'REGULATORY FORMATION DISTR IBUTION 'S EM (BIDS)

AGCBSSION NBR 8212210037 DOC ~ DATE 82/12/14 NOTARIZED~, NO ¹ FAOIL:50 '275 Diablo Oanyon Nuclear ipower .'Plantr 'Uni~t ii Pacific Ga 05000275 BYNAME.50»323 Diablo Canyon Nuclear 'Power Planti 'Unit 2r Pacific Ga 05000323 AUTH AUTHOR AFFILIATION InteriorrDept.of r National;Park Ser vice '~RE~CIP ~ NAME RECIPIENT AFFILIA'TIOP KERRIGANiJBD<, .NRC No Detailed, Affiliation Given 'SUBJEQT! Provides Natl Register of Historic, Places eligibility notification of tplant Archeological Si,te 'SLO 2,

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.EXTERNAL! AGRS 6 I6 LPDR 03 '2 2 NATL LAB '21 5 i5 NRC,PDR 02' 1 NSI~C -05 1 1 NTIS ,1 1

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." R Jiw 3 lc~hh I f j I wl JINNI s„W» IWR II,', ~+7 Os >/y r 0 I United States Department of the Interior 0 Jp NATIONALPARK SERVICE WASHINGTON, D.C. 20240

m assr.v REFEa vo: g/0 OEC I'4 l982

The Director of the National Park Service is pleased to inform you of our determination pursuant to the National Historic Preservation Act, as amended, and Executive Order 11593 in response to your request for a determination of eligibilityfor inclusion in the National Register of Historic Places. Our determination appears on the enclosed material.

As you know, your request for our professional judgment constitutes a part of the Federal planning process. We urge that this information be integrated into the National Environmental Policy Act analysis and the analysis required under section 4 (f) of the. Department of Transpor tation Act, if this is a transportation project, to bring about the best possible progr am decisions.

This determination does not serve in any manner as a veto to uses of property, with or without Federal participation or assistance. The responsibility for program planning concerning properties eligible for the National Register lies with the agency or block grant recipient after the Advisory Council on Historic Preservation has had an opportunity to comment. F

We are pleased to be of assistance. in the consideration of historic resources in the planning pr ocess.

Attachment

82i22i0037 82i2i4 I PDR ADQCK 05000275 P PDR yV DETERMINATlON OF ELIGIBIUTY NOTIFICATION National Register of Historic Places National Park Service

Name of property: Diablo Canyon Archeological Site OSLO-2

Location: San Luis Obispo County State: CA / Request submitted by: NRC/J'anis D. Kez~gan

Date received: 11 1 82 Additional information received:

Opinion of the State Historic Preservation Officer:

El E I ig ib le CINot Eligible C]No Response Comments:

The Secretary of the Interior has determined that this property is:

KIEligible Applicable criteria: D CI Not Eligible

Comments: This pzopestp is a smtticomponent stzatified site»n th aP'gott 4 feet at midden. The ear liest ho~son is consistently dated by C—and Obsidian hydvation at 9320 B.P. The hunting period (middle) hobson is dated at 5100-7520 B.P. and the Eatest hobson the chumash is dated at 930 B.P. This site is Eikely to yield important information on a v~ety of anthropological and history'ical questions and is probabEy pa>'t of the previously listed Rancho Canada de '-Eos osos y pechos y 2slay az'cheoEogicaE cks tx'Oct »

CI D ocum entation in su fficient (Please see accompanying sheet explaining additional materials required)

e e of the National Register

WASO-28 Date: N

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Dr. Dames g. Davis State Geologist Division of Hines and NinthGeology'416 Street Sacramento~ California 95814 Dear Jim:

VTe appreci.ate your keeping us. informed about investigations Qf a, possible extension of the San Kigue&to fault recently conducted, by your staff. Your actions in bringing this investigation to our attention early and your close communi.cation with as during the investigation permitted appropriate actions to be taken. Similarly, ~our actions in bringing to our attention apparent offsets in the sea'cliff north of the Diablo Canyon Nuclear Power Plant permitted the staff to make an early assessmcnt of these features. Pe also appreciate the assistance of George Cleveland and Dave Wagner during our investigation of the apparent offsets on May 4, 1978. Documentation of our evaluation is in preparation. Uith best regards. Sincerely,

Original Sig edby >.C. Steps J. Carl Stepp, Chief Geosciences Branch Division cif'Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation bcc: H. Denton W. Gammill R. Hofmann J. Stepp P. Grew

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17 Rp <6 Oil QD Hr. James F. Devine U. S. Geological Survey Itail Stop 905 National Center South Lake Drive Reston, Virginia ,22092 'ear Jim:

You are requested to review and comment on appendix DLL-11 of amendment 50 which you have, and section 2 of enclosed amendment 52 of the report entitled "Seismic Evaluation for Postulated 7.5M Hosgri Earthquake" submitted by the Pacific Gas 6 Electric Company. We are expecting within two weeks a revised study fiom PCM that will address, among other things, apportioning earthquake probabilities among the various faults according to their recent movement rates. You will be requested to include this in your review, also.

Sincerely, = D RIBUTION: ANTRAL FILE NRR RDG GB RDG J. Carl Stepp, Chief DSE RDG .Ceosciences Branch Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation Enclosure: As stated

bcc: W. Gammill J. Stepp R. Hofmann T. Cardone

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~ T Eh. James P. Devine U.S. Geological Suxvey %lail Stop 905 National Center - South Lake Drive Reston, Virginia 22092

Dear Jim:

I recently transmitted to you by my letter dated January 26, 1977, two documents pertaining to Diablo Canyon Nuclear Power Plant site! l. A letter dated November 19, 1976, fram James Qeocaris; 2. A letter dated November 3, 1976, fram Prof. James H. Brune.

The ACRS Subcommittee on the Diablo Canyon site requested our written responses to these twa letters, Hy letter of January 26 asked you to review-the two lett~ra as expeditiously as posHble and provide your comments ta us. X also asked you to provide an estimate of the amount of time that would be required for you to respond. To date I have had no response from you.

X wauld appreciate yaur response as soon as possible so that we may provide the informatian that the ACRS Subcommittee requested. Please let me know a timetable within wh1ch you expect your revMv of these items will be completed. Sincerely yours, Original S!gnad 4Y L.N. HsIisr J. Carl Stepp, Chief Geosciences Branch Div1sion of Site Safety and Environmental Analysis

cc: H. Denton DISTRIBUTION: Q. Gaaunill Docket File 50-323 D. Allison NRR Rdg. DSE Rdg. GB Rd.

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BURNAMBW Stepp:1m WGammill 5/Q/77 ~5/ /77

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Mr James Pi Devine UiS ~ Geological Survey liail Stop 905 National Center South Lake Drive Reston> Virginia 22092

Dear Jim:

This is to request that the UiS. Geological Survey review the attached docunents pertaining to the Diablo Canyon Nuclear Power Plant Sita>

Letter dated 19 November> 1976 from James Geocaris Letter dated 3 November> 1976 from-Prof+ James Ni Brune

The Geocaris letter concerns the possible length of the Hosgri faulti Qe realize that you have already addressed this problem in your past letters to uso However~ we desire your advisee on whether Mri Geocaris is introducing new material and wish pou to address his questions specificallyi Dri Brune's letter concerns a possible transient high accelera- tion pulse which might be caused by rapture propagation along the Hosgri faulti Several references given by Dri Brune over the telephone are also enclosed to assist in your evaluation of the safety consequences and reasonableness of his hypothesisi

Since the ACRS subcommittee has requested our written responses to these two letters, we ask that the review be made as ex- peditiously as possibleo Please give me an estimate of the amount of time your review will requirei Sincerely> OTlgiOai Signed Q~J >„C. Steps J i Carl Stepp, Chief Geology/Seismology Branch Division of Site Safety and Environmental Analysis 2.7S Enclosures: As stated CoNs II+ 5

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ccrc 1s/o encl: RS Boyd RS DoYoung Js Panzazella P» Shuttle@orth " v/enc1.! w0 Qammill JS Stepp R, Ho&ann RS IfcHullen PSJ0 Williams

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g 1 For frlEMO ROUTE SLIP See me about this. For concurrence. action. form hKC-9S (Rev. hfay 14, 1947) hKCM 0240 Note and return. For slcnature. For Information. ! TO (Name and unit) INIBALS REMARKS I

DATE you this morning.

TO (Name enid unit)

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Vi.c~ 4r.. P» /'.N.%.d,l ++~ 'Thomas G. Mccreless cv-~ .r ~.'g f'.: g . g~". „, gD . 634-1374 11/11/76 cC'.~ .~)3 USE OTHER SIDE FOR ADDITIONALREMARKS CPO r tell 0 - its-455

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I ~ INSTITUTE OF GEOPHYSICS AND ~ ~ 5XXMMKKXNQMII'A t. ~ . PLANETARY PI.IYSICS JOLLA, CALII'oRNIA xx')et 92093 LAJQLLA LABQRAToRIEs A"025 3 November 1976

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Executive Director Advisory Cmmission on Reactor Safeguards Nuclear Regulatory Commission llashington, D. C. 20550

ATTENTION: ltort La Barkan

This letter is written at the request .of.l1r. JaPIes Geocaris, and its purpose is to explain the phenome'non of high frequency eneroy focussing by a propagating earthquake rupture and its possible relevance to the Diablo Canyon nuclear power plant.

The ph nomenon of focussing of high frequency energv by a propagatin source is well known in physics. An'elementary example is the high frequenc of sound heard from an approaching train as compared" to the relatively lowe frequency heard when tne train is receding. Benioff used the principle to explain asymmetry in the intensity of shaking froml t..e kern County, California earthquake of 1952. I'numerous o.her seismoIogists have since. used it to explain similar amplitude asyozIetries., In simplest terms, it is focussing of a narrow beam of high frequency energy in the direction of rupture.

The simplest theoretical representations of the phenomenon suggest that very high accelerations, several times the acceleration of gravity, migl be produced in a narrow beam (+ 5') in the direction of a propagating earth- quake rupture under certain special conditions. Unfortunately, at this time it is not possible to determine to what ex'tent these conditions can occur in actual earthouakes. The phenomenon has been verified and studied to a limited extent in laboratory models zlId in numerical computer models, but again, it is not possible as yet to verify that the relevant conditions in these models occur in natural earthquakes.

There is good evidence that for many earthquakes amplitudes at relatively lar e distances have been increased several fold by rupture focussing. For near- ierd strong motion of importance in structural design the data is too liII:ited to be certain of the importance of the phenomenon,

N. La Barkan Page -2- 3 Hovember 1976 but several recent strong motion records, including'he Pacoima Dam record of the San 'Fernando earthquake (tl = 6.4, a = 1.25g) and the Nelindy Ranch record of the Bear Valley earthquake of September 4, 1972 (H = 4.7, a = .69g) may have been affected by rupture focussing.

From elementary considerations, it is apparent that rupture focussing , could be of great importance in designing and siting critical structures {such as nuclear power plants) near active faults. On the other hand, it is possible that some presently unkhown factors might prevent the phenomenon from being as dang'erous as first appears from these elementary considerations

In the case of the Diablo Canyon nuclear reactor, given the assump- tions that the San Simeon- system is a continuous active fault coming within 5 km of the Diablo Canyon nu !ear power plant, focussing by rupture propagation ~m~orthwest to soutneast) could lead to anomolous high accelerations, possibly greater than 2g. At the present time it is not possible to say what the probability of such high accelerations is. Many of the factors necessary for estimating the probability are being inten-. sTvely studied and should be much better understood in a Pear or two.

JAMES H. SRUHE h Professor of .4eophysics JNB/nar cc: J. Geocaris

~ ~ VI~ I a4< I ~ I a@ sal)VIII C9 Biography

Born .

November 23, 1934 Modesto, California Education

Ph.D. (Geophysics), Columbia Universi y 1961. B.S. (Geophysical inginee ing), University of Nevada, 1956. Professional Experience

Associate Director7 nst" ute o". Geophysics anc Planeta~ Phys. cs, Univer. of Cali orn'a, San "'ego, 1"73- 1976. Chairman, Geologica~ Resea c.". D''sion, Sc 'pps ".nsti=u:e o= Oceanogra '.::. Professor of Geopnysics, Un:ve sity of Cal'forn'a, Sa.. Diego, '«69- Associate Professor of Geophysicss Cali=o"nia "nsti " e cf Te .. logy 1965-1969; = erv'sor, = is-...o~ an- ==a"-=c-.. (===". =': he== -;.- Adjunct Associate Professor of Geology, Columbia iniversity, 1964.- Geophysicist, U. S. Coast anc Gecdetic =u.vey, 196~. Research Scientist; Columbia Un:versity, 195S-1963. -Zxplora~ion ?esearch, Chevron G'1 Company, '95?. Exploration Geophysics, .Chevron Oil Company, 1956. Honors

President,- Seismological Society o Amer=ca, 1970. Vice P esident, Seismological Society o" Amer'ca, '969. oar of Di ectors, Seismological Socie —;- of Americas '967-1972. Grove Karl Gilbe t Award in Seism'c Geolo-y '967. Nomina.ed New vora'cademy o Sc'ences,', 1966, men-e . 970 . Fellow, American Geo nysical Union, 1967. ~ . First recipient of J. B. Nacelwa..e Award by A.G.U., 962. Arthu . Day Awa d (Foreign Co-op. Research) 1 72 Professional ae;-..bershios Geolog'cal Society of Ame ica Seismologic=l.Societ~s of America

4 American Geophys'cal Union Nationa .-e"earch Council Scholarshi s and Fello':Ishi s University Fellowship in Geophysics, Columbia Univers" ty, 1957. Higgins Fe'owship, Columbia Un ve . ity, 1956. Hax Flei chman, University o. Nerada, two years. Jones-Hoover Scholarship, Uni'ers'ty of Nevada, one year. Committees National Research Council, Seismologica'ociety of America. .repre"entative, 1967-1970 . NAS-NAE Committee Advi"ory to Envi."'onmental Science 'Services Administration, 1970-1973. IRH y Majraphy 'James beil Brune Page Two

Comnittees (cont)

Panel on Solid Earth Geophysics, Ifational Committee Advisory to ESSA, National Research Council, 1960. Panel on Seismology, 'fAS-bAE Committee on the Alaska earthauake, 1965. Governor's Earthquake Council, 1971. Panel on St ong-Ifotion Seismology, sfational Academy of Scien es, 1971-1974. Committee on Seismology, IIAS-HPC, 1971-1973.

Research

Seismology; Earth structure; Ea thcuake source mecha-..=sm; Tectonics; Heat flow; Explosions as seismic sources; Seisnic wave dispers'on; Free oscillations of the Earth; Uorrzl mode and ray theory; Seismic noise; Hiero-. earthauakes. ~ ~ Listed

I American:fen of Science "Nho's h"no in the Nest

s

6/74

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Decenber 8, 1976

James Geocaris, Esq. Brent Rushforth, Esq. Center for Law in the Public Interest Center for Law in the Public Interest 10203 Santa Monica Drive « 10203 Santa Honica Drive Los Angeles, California 90067 Los Angeles, California 90067 fedos. In the Hatter of Pacific Gas and Electric Company (Diablo Cany'on Nuclear Power Plant, Units 1 and 2) Docket Hos. 50-275 O.L. and 50-323 O.L.

'.-.;."';,,': This is'n .response to your'etter of November 19, 1976 suggesting th ': —-'"need for.further consideration of the possibility of a Hosgri-Sa --'."'„" .:.. Gregoria fault link up. As you are aware, the USGS report of April 29, :.'':.":;=" '..;"; ~ .-.',.==...-.'. 1976; did consider all the available information bearing on this question...-':.,";.:-:.: '":.'-,:-: A;Specifically, it was assumed that the Hosgri fau'1t connected with faults ....'..-;-:.:„-',-'~', ~ ~ ~ ~ ~ ~ '.v ~i

".-';";.";-'...The NRC. and its consultant, the USGS, are presently reviewing the inf'or- -,:;":;""mation presented at an earlier n eting of tho Los Angeles Basin Geo-:: ~ '.'.=.-',:,:.'; logical.Society M determine whether any substantial'ew information .':, '.." ':-;"';;,:: exists which would have an effect on the seismic design of Diablo Canyon. ~ ~

":::.':,"t In the meantime, we": would welcome any new infonaation whfch has not";..;'":-;.-":;"-.".:.-.',;—,'.-.';.-'„."'.". -=:--,:,-'='::.,previously been furnished to'he USGS; .- Hr.::Tour tellotte and; I, woold -"--;:.:-::;;-„',:.-,:;,.-. -::~-;-"-be milling to«meet with you"to.discuss this:.matter.further'hi)e.vte,«,'!ik.'-..-='-:='".'':.,:.i',,'. , =;.-:--',-":are:-.in San'Luis Obispo;;for:the environmental hearings"..„:"-,-:

"Counsel for NRC Staff DR/LPDR ,„,::,:;„.::Formal. Files cc: Elizabeth S. Bowers, Esq. Dr MHliam E. ' orr>ccrc Hartin '.'rthur C. Gehr,'sq.'" ~ .-.:,-.'..'"; ". '.. " Philip A. Crane, Jr., Esq. ..Atomic Safety and Licensing ',. 'rs. -Elizabeth Apfelberg .... " Appeal Board Andrew J. Skaff, Esq. ', .... Atomic Safety and Licensing ,'- " Hs; Raye F1eming .'.-...... : Board Pane1 .:.,';, .;;--:.-,-:. p.";„ Nr. Frederick Eissler . ..'"'' .:. Docketing and Service Section ',.'.:„"-.':: -., ': Hr. Gordon Silver rs. an ra 1 ver OfLD « N r ...He 'EG.1iara 2 CornwelL. Tel ephone oncurrence '«« ~ ', c D;-Davis SVRMANcnn Nr. Paul C. ynlnntlne hy Denni ' Allison Yal'e I-. 'Con .J. TourteU.at e n, Es'q. « '««. «8 4 .«««

Distribution 0'ocket File LWR-1 File D. Allison E, Hylton

DEC g 0 )F6 Docket Nos.: 50-275, 50-323

I HEHORA,"tOUtd FOR: John F. Stolz, Chief, Light Mater Peactors Branch fto. 1

FROtl:, 0. Allison, Project ttanager, Light Mater Reactors Branch Ho. 1

S|JBJECT: DIABLO CANYON SEISHIC DESIGt< BASIS

The intervenors'ttorney has in itten to the ACRS and the staff questioning whether the magnitude 7.5 earthquake on the Hosgri fault is a sufficient design basis for Diablo Canyon in light of the possible connections of this fault with other faults to the North. The ACRS has requested that Me pro- vide response fron U.S.G.S. Copies of this correspondence are enclosed.

Jim Devine at U.S.G.S. has been working .on an answer for ateut 3 weeks now and will provide a response soon. This subject was discussed in the U.S.G.S. report concerning Diablo Canyon. 'In its rapport the U.S.G.S. assumed that these postulated connections are real and dismissed any conseauen need to use an earthquake larger than magnitude 7.5,due to the nature of the result- ing fault system. The U.S.G.S. is checking to determine exactly what was done at the recent seminar in Los Ange'les before responding. Onwinal S>gned By Dennis P. Allisan Dennis P. Allison, Prospect Panager Light Mater Reactors Branch tto, l Division of Prospect ttanagoment Enclosure: as stated cc: B. Pusche E. Case R. Boyd P,. DeYoung D. Yassallo .. R. Heineman J. Knight I. Sitweil Y. Kapur H. Denton I Gami 1 1 J. C. Stepp R. Hogan J. Tourtellotte . 0. Davis os r>crW

OUR,'%Able ~ DATE~ T 4 y~y,R ALOD ~4 ~o UNITED STATES :.-..'i, hagi'.;"; NUCLEAR REGULATORY CQMIVllSSIQN ADVISORY COMMITTEE ON SAFEGUAROS o "g' REACTOR +~GATI WASHlNGTON, D. C. 20555

Hovember 29~, 1976

D, Allison

POTENTIAL LENGTH OF THE HOSGRZ FAULT NEAR THE DIABLO CANYON SITE \ Attached is a copy of a letter to the ACRS from the Center for Law in the Public Interest'which points out, that some respected geologists have again, recentLy, expressed the view that the Hosgri fault could link with other fauLts forming a system about 300 miles long

The Diablo Canyon Subcommittee Chairman has requested that we obtain comments from you and U S. Geological Survey on the significance of this information and its impact og the postulated magnitude 7.5 earthquake occurring on the Hosgri fault.

J+ Cw McKxnley, ief Prospect Review anch No Attachafent: Center for Law Ltr dtd Li/19/76

cc: B Rusche E, Case R Boyd R, DeYoung R Heineman H. Denton W, Garmill Ci Stepp D, Okrent

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Advisory Corr~ittee on Reactor Safeguards ~ Nuclear Regulatory Comzaission ~ washington, D.C. 20555

Pear Sir: ~ p ' Re are attorneys for several Xntervenors in the ~ Dj.ablo Canyon Nuclear Generating Station operatinct license hearings. tie are sure you are a -are that the Diablo Caryon matter is now before nur Advisory Committee on Reactor Safeguards'. Your Committee is fccusint3'on the seismic hazarQs .posed hy the Hosgri fault which runs 2-1/2 miles offshore from the plant site. 5 En our investigations regarding seismic hazards at Diablo Canyon,'nformation that could affect the niag- nitudc of an earthquake at the plant site has cone to our attention that.-the Committee has not considcrec7o Mvisory yet .'t, present, your Cori.-.,ittee is evaluating the seisric hn"ards posed by a fault approximately 100 @tiles in length kno' .. as thc liosgri. Recently, rcspccted qcologists work:ing on Calf'ior»ia faulting hove e~:prc-s d t'.ic v'"w t'.tat t'ie llo gri links uli to anothftr nort>ll:c t.crly trcnclittg cckstct3 .fault,. tllc Soll Grei Ori.o p to for:ll dl'lc 300 )'ill c long fatilt s"st.clil ru»n'ing fxc:;..> Poi»t Concl, pcitin (tl c sout!ica:-.t: cr~T uf t:!ic. 1ln."gri ";nuit) eric] libel.mini~ .i>itlt t'.>t. san A-.Qrc't: faltlt nn: t;lt. 1'. tnci5 co ( tll . nor t.tl"c 1: lie) 0 C t:llc 'n t, c;c)rio "nuit.) . 1'clr cyazplcf 1'rdf'.".; .ne 1 )i Si1»L'r, Chairaan ot'hc 'lc.;iartr,:cttt of (-:cology at thc.. tttiivcrsitp of Cctj.iform:tia at„. ~ «tnta Ct u:., «gprc>ts:-,c d tile vx5:i.i'n 0 pre'tt.'.ltttloti tc5 tl:c Lo>c tl<;clcs ltllin cico)oq j<.'al Sc)c:ic'I.'}'tl NctvL'tltltclr,. )tt7t't tha(. :hc lln."imari hnd.5an (Jrccgot.io;lrc~ joinccl 'l:l OnL~ fault. As wc uncover::tancl, it thc.llo.'lett'j attcl B,t'tl Grcic;orio lrc.'llotll wt.ll ttiapllc

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un«r t»nty»e in an area of a fcw doyen miic near Point Suy on'he Central California coa t. Apparently,, if this area was better mapped 'hy geological surveying expeditions, the linkage of the two faults coulQ bc morc convincingly established or refuted; He be3.ieve that, the Advisory Committee shoulQ knoM

whether the Hosgri, is a 100 or a 300 mile long 'efinitively gaul't bofors it settles upon an estinate of earthguahe mag- : nitude and other aspects oi the seismic evaluat'ion for the Diablo Canyon nuclear. plant. We believe that it would bc

' most inappropriate for the AQvisory Committee to continue ~ their analysis on. the basis of a 100 m3.1e long fault without ~ examining the views of thc severa3. reputable geologists who ar'e familiar wit:h the relevant. data and believe that the '.fault to be 300 miles long. Pe urge you to consult geologists and DSGS ( . in the universities ho.are fami3.iar with Central '.* ~ California coastal faulting 'to determine the state of know- : . ~ ledge regarding the possib"c San Gregorio-Hosgri linkage and, . especially, what new surveys feasibly could he underta.;cn in the near futUre to establish or refute the'xistence oX the. .link.-

~ 0 I II Xn your investigation of this matter;~ ve~ ur(3e you especially to seek: out viewers of reputable,. independent geoloc;i ts. Throughout the historv'f the siting anQ con- struction of the Diablo Canyon plant,;independent'cientists . have 'ounded the warnin(3s about offshore 'faulting that helve ~ prov(;n true, only to be i(3nored by the Nuc:lear Regulatory Co~xi .sion and Pacific Gas and I:lcctric .Comp:lny. For example, during the const':ruction licensiniv'hase, gcolni„.ist Robert Curry, i'!lo recently ha done worl on the geo3ogical di,a.ter tlM Teton Dam, 3 arned Ches Cor".",i:si Qn and u"i1 ity compo!ly al>out offshor(.' au3.ting ?3llt thi8 omPii!i&ioll riever or(EGl'e(3 "urvcys for fault" unitclr tllc occ.an rior c;i(l t.lr utility take off..l>o'rc surv(v.',. Nore rcccnt1}, Clarence !"133. Ch .ar.'n .n- of tllc ('cnloqv Dc:~;»-t-r,;c»t at tll: Univor:»jty of C'l3.ifornia at Lo" ~ ~ e ~ a All(3('.3 .- l~ubli-'l:tl a dcf in i t:ivc:1'r t:.l.i:3 c 1n (in(.c (3 ir«eiii'::cr 26, '976 f'i'~) /el 3 Yolu!.l: 1') t) pp ~ 3.2g ).-129>l j 8c L. tl (1 fsiil('3s'.,l l't(.'(3\ll 1- ~ ~ tol y Cuil:li:(sion l;.o(il() «QJ;no(i'3c()c!Q h L 1('j>(late"t 41 ttn Lil>31( thol~ t.llc "".n:(:iry 19 I) s clpo)-t: .')y oi l ci:~1!>'ul>'!tl')lo!it:f: '> f t,hr a. xi st (in('i A f. s.! i(l 3.() 0 mile lollg ?to;: J 1 .i faul t. (i'a:1 tron 4'c'ru::t thc. A()vi."o)".y Commit telo will i:on(?ui.f: a thol ougll invr..'lti .at:ion of. tile potential lac':()1 i-.'lan Gl'< (ill ko lilll lg .w t.h p]()!)ily attclltinn t;n t.llc vi('.wl: oC l(>)>utall)(l ini)('})('ni)ent Soj i. nt.i ~LS a;1 lp(ill sin tll('t;aff O t t;ho t)ui ~ )'( Bcqulatciry CQ'ilillj.:1:lion. )le 1Ioul() apl>l cciat.r. henri»(~ .1(i'.» you e I b r ~ ~ ~ ~ ~~.J ~ 0 ~

' hr. Dade M. Noeller ~ 3m 19 November l976 regarding your plans for such an inve'tigation at your earliest convenience. Yours sincerely,

Brent t4. Rushforth r~~Pyfg. '~~~Kg~ James Geocaris 'Cco '

~ r 7 Dale. Bridenbaugh'. Phillip Crane, Jr. Richard Hubbard Ninor 'regory .Dr. David Okrent James Tourtellotte 0

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FOR LAW (tO~O OS (ItuSr((S tN THE PUBLlc INTEREST LC(tAL S(A(l IOtOS 4AHTA HOHICA bOLILCVAIIO t~ ~ 'rctpt H 'ENTER ?W0 trrr ~ I fp4~lo (~ I th( JO rr 4 ~ (+5 JIPTH FLOOIt CIAtnf rr m L m ~ 0 $4(HI H AqQHPIlll A tHCwlS MPst 'I J 5t~fr 5uQINS LO5 AHOCLCb CALIFOAHIAOOOd7 @HI 4 hl+Y5 ii~ A lips vlrclr L 5(JIAlttQ Srr(ltt lr IlltvIPItrt I@PAIL H SAM ZCLCJIIQIrclQISI ~ r ~ ~ ~ $ $ ~ 1 SLII&$EAHS'ng&g t'I 4 ~@PI 5IADv 3(W JAQK StbtUw ~ al tISPid > StttH(~ aOaOHiS(4iintr O(aC(l( St(*uit L u04LL (4~t( ~QM rrLRa~ glJO4i Ir Irrkrrt45(tt tAtrrOS u WSAt $ LM~LL ML(t~ e&5IHG IELLOWS rr(trr(ltrrQLt(tt QlPV4~ (~It h4A 0 IQQ(L 5 Q(QQAA5 JAPI C (CI~( 19 November 1976 ~ 4 F05(tits

Mr. James Tourtellotte'r. Dow Davis Office of Executive Legal Director BETH 042 U.S. Nuclear Regulatory Commission Hashingtonr D C ~ 20555 Gentlemen: A few days ago one of us talked with Hr. Dais regarding new information on the fault running 2-1/2 miles offshore 'from the Diablo Canyon plant site. Several reputable geologists who have done extensive work on the California coastal faulting now believe that the Hosgri fault links up to'he San Gxegorio fault to form a massive 300 mile long , fault system that, in turn, runs into the San Andreas. fault north of San Francisco. Several of the geologists who holi . this belief ax~ now reporting their views publicly. For example, Professor Eli Silver, Chairman of the Department of Geology at the Univexsity of California at .Santa Cruz, reported s is view earlier this month at a pxogram sponsored by the Lo". Angeles Basin Geological Society that the Hosgri- and San G: gorio formed a single fault system. Ne realize that some of the Nuclear Regulatory Commissio..'s consultants at U.S.G.S. do not share the views of Silver and others regarding the connection of the Hosgr3. and San GxQgorio. However, we beleive this divergence oZ scientific opinion over a matter that could affect. the mag- nitude of i credible earthquake at the Diablo plant, site should:"e :esolved so that, the Commission's seismic analysis proceeds rta a realistic basis. Re do not think the seismic anal>"-i >r Diablo Canyon should proceed upon a fundamental assay"'. the length of the f=ult and the potential magnitu:;e 5f an earthquake on the fault< with which several . reputable ~cientists disagree. v 4 0 A '

I Hr.'8ames Tourtellotte .8'K,~os Davis '

Xn light of this new information, we would like to me t with you and the Diablo Canyon project manager, Mr. Dennis Allison, to discuss this matter of the Hosgri-San Grego io link. Ne are interested especially in discussing geologic surveys of the possible site of the Hosgri-San Gregorio linkage around Point Sur that might confirm or refute the connection of the two faults. lf such surveys are feasible, we believe that it. is the regulatory responsi- bility of the Nuclear Regulatory Commission to undertake then be=ore the Diablo plant is licensecl. Frankly, gentlemen, our investigation of the history of this case has left us most unimpressed with the regulatory zeal of the Comaission. Your decision not to require surveys for offsho e faulting during the construction license phase and your apparent foot-dragging in confirming the work oZ Hoskins and Griffins is incomprehensible to us. He txust- that p with operating licensing of the Diablo plant imminent your evalu tion of the potential Hosgri-San Gregorio linkage will be more thorough and prompt. Yours sincerely, (.]8 l)e<)lA Brent N. Rushforth

~ ~ James Ceocaris Cce Dale 3ridenbaugh Phillip Crane, Jx. Rich ".d Hubbaxd Grege ~ Minor ~\ ~ gUN 14 876

Hr. James F Devine U. S. Geological Survey Nail Stop 908 - National Center South Lake Drive Reston, Virginia 22092 Dear Jim:

Enclosed for your information and comment is a "Preliminary Draft of Design Spectra for Diablo Canyon Reactor Facility," by M. M. Newmark. I understand'that this report will be submitted to the ACRS prior to the June 25-26 meeting. Therefore, I would appreci- ate any comments or views which you might have on the report by June 16, 1976. Sincerely, O-ig,nai Signed by W.P.Gammill

P. Gananill,'illiam Assistant Director for Site Technology Division of Site Safety and. . Environmental Analysis Office of Nuclear Reactor Regulation Enclosure: As stated

DISTRIBUTION: Docket File (50-275) NRR Rdg DSE Rdg VPG Rdg

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CILETTEB QNOTORIZED PROP INPUT FORM NUMBER OF COPIES RECEIVED « RIORIGINAL RlUNC LASS IF I ED one signed OCOPV DESCRIPTION ENCLOSURE Lgr trans the following: GeOlogy & Seismo1'ogy Review'...... (l cy encl rec'dg

PLAl& NAlP.: Diablo Canyon l & 2 'Mi

SAl«ETY ACTION/INFORMATION ENVIRO 5-3-76 ASSIGNED AD: ASSIGNED AD : BRANCH CHXEF: BRANCH CHXEF ~

PROJECT MANAGER; PROJECTASST'OR MANAGER ; LIC. SST.: Qo o LIC~

INTERNALDISTRIBUTION ~ ZEHS NRC PDR MKIK «S ERNST I'&E BENAROYA BALLARD SPANGLER GOSSXCK & STAFF ENGINEER N IPPOLXTO SITE TECH SE KNIGHT OPERATING REACTORS GAMMILL 2; SIHWEIL STELLO STEPP PA!JLICKI HULMAN OPERATXNG TECH L'ROJECT MANAGEMENT REACTOR SAFETY HISENHUT SITE ANALYSIS BOYD ROSS SHAO VOLI2IER P, COLLINS NOVAK BAER BUNCH HOUSTON ROSZTOCZY SCHWENCHR J, COLLINS PETERSON CHECK GRIMES KREGER MELTZ HELTEMES AT & X SITE SAFETY & E SKOVHOLT SALTZMAN ANALYSXS RUTBERG DENTON & MULLE EXTERNAL OISTR IBUTION CONTROL NUMBER BROOKHAVEN NATL LAB LPDR' /-vlsO ~ o NATL LAB TXC RFG V-IE ULRIKSON(ORNL) NS LA PDR ASLB CONSULTANTS op II ~ ~ ~ 4 ~ ~ ~ ~ ~gNT Og ~ / 0 United States Department of the Interior 0 GEOLOGICAL SURVEY RESTON, VIRGINIA 22092 File Regulatory Docket

q APR 39 1976 lz g ~@- cF "7~/

Mr. Benard C. Rusche Director of the Office of Nuclear Reactor Regulation 8 U.S. Nuclear Regulatory Corloission Washington, D.C. 20555

Dear Mr. Rusche:

Transmitted herewith, in response to your request, is a review of the geologic'and seismologic data relevant to the Di lo Canyon Nuclear Station, Units 1 and 2 (NRC'Docket Nos.' and 50-323 OL).'ower

This review was prepared by F. A. McKeown and J. F. Devine of the U.S. Geological Survey. Mr. McKeown was assisted by Holly Wagner, David McCulloch and Robert Yerkes in the preparation of portions of this review; Mr. Devine was assisted by Robert Page and Wayne Thatcher in the preparation of portions of this review.

We have.no objection to your making this review par t of the public record. Sincerely yours,

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APR 28 f976

tie. leonard. C; Rusche O)rector of tha office of Hucleat', Reactor Regulation U,S. Nuclear Regu'latorg Comafss)on 'Mashington, D.C. 20565

Dear t~lri

Rusche'ransnitted herewith, in response to. gout request, fs a revf@< of the. geologic and seismologic data relevant 'ta the Mablo Canyon Nuclear Peter Station, Units l and 2 {RK Cocket. bios. 50-276 OL and 59-323 QL).

This review i~as. prepared by IF:. A..tlckeoyn and'. F. Devine of the lj.S. Geological Survey. V~r. NCKeo':m @as assisted bg golly Wagner, Qav)d VxCB)och and Robert Yerkes 5q the preparation of portions of this reyiei. Hr. Devine t;Ias assisted bj Robert Page and Hayne Thatcher 4n the, preparation of portions of this rev)eu.

Ue have- no. objection to your mak)ng Sids revue;I part of the public record. 'inceralg yours,

Enclosure

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Geology and Seismology

This is a review of the geological and seismological information

contained in Amendments 31, 32, 34, 37 and 40 of the Final Safety Analysis

Report (FSAR) foi the Diablo Canyon nuclear power plant site. The review

also includes a discussion of questions concerning the size of an earthquake

to be expected on offshore fault zones raised by some California scientists since review of the amendments.

The amendments were prepared by the Pacific Gas and Electric

Company (PGSE) in response to a request in a letter dated February 12,

1975, from the Nuclear Regulatory Commission (NRC). for certain additional information relevant to design basis earthquake issues, which have been the principal problems requiring additional earth sciences information and analyses. To support assertions in the FSAR through Amendments ll, 19, and 20, five requests for information (referred to as questions in the Amendments) were made.

2.17. Provide additional discussion and arguments for determining the maximum earthquake that can be expected on faults of various ranks within the San Andreas system. Relate the discussion to historic seismicity. 2.18. Provide additional documentation, including seismic reflection profiles, on the intersection of the Hosgri fault zone with the Transverse Range faults. Include geologic maps southward of those provided in the FSAR showing the structural relation- ships of the Transverse faults and structures having a nor th- west trend. I ~ p ~

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I 2.19. Provide additional documentation, including seismic profiles, on the northern reaches of the Hosgri fault zone. Include a fuller development of your views on the structural relationship of the Hosgri fault to the San Simeon fault.

2.20. Provide additional information on the location of the 1927 event, together with its probable mechanism. Discuss probable relationships of this event to the geologic structure in the region.

2.21. Provide your evaluation of the maximum credible earthquake on the Hosgri fault zone. Assuming this event occurs along the segment of the Hosgri fault zone nearest the site, evaluate its response spectrum at the site and compare it with the> design response spectrum.

The response in the FSAR to the questions has provided considerable additional geologic and seismologic information and analyses. Many uncertainties in the data and interpretations still exist. Among the most important of these are: (1) the location and mechanism of the 1927 earthquake, (2) the exact relation of the Hosgri fault zone to faults in the Transverse Range system and the San Simeon fault, (3) the continuity of some faults, (4) the relative amounts of dip-slip and strike-slip movement on the Hosgri fault zone, (5) the sense of displace- ment on parts of the Hosgri zone, (6) identification and correlation of acoustical units, and (7) kinematic relations among different fault zones.

In addition to these uncertainties, some information shown on the profiles is not shown on the maps and vice versa, and some profile data are not included that are important to evaluate the extension or character of some faults. Because geologic maps developed from seismic reflection profiles are based upon much interpretation that may differ among several interpreters, it was necessary for the purposes of our 0 IC

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Ig review to make independent interpretations of the seismic profiles.

These independent interpretations are somewhat different than the

interpretations presented in Amendments 31 and 32. The major differences are brief'ly described in appropriate sections of this review.

Although some changes in, and additions to, geologic and seismologic

details have been made in Amendments 31, 32, 34', 37 and 40 compared with

previous data in the FSAR, no major changes can be made in our conclu-

sions that were stated in the review of the FSAR, and Amendments 11,

19, and 20, which was transmitted to the NRC from the Director of the

United States Geological Survey by letter of January 28, 1975. The

pertinent statement in our previous conclusions was as follows:

"Earthquakes along the EBZ presumably would not be as large as expected on the San Andreas/ fault, however, from the information presently at hand we can find no evidence that would preclude the occurrence of an

earthquake as large as events characteristic of subparallel strike-

slip faults, which bound basins, such as the Santa Naria, in the San

Andreas system and which do not transect structural provinces." The

size of an earthquake on faults that bound basins was not specified in this conclusion. For reasons stated in subsequent parts of this review, however, the magnitude of the design basis earthquake for

~ the Diablo Canyon nuclear reactor site should be about 7.5 and

located on the Hosgri fault zone. This is based principally on

the fact that the November 4, 1927, earthquake had a maanitude of

1As defined in the FSAR, EBZ refers to the East Boundary fault zone, which is the Hosgri fault zone. " I "I ~ pv v t If'I f g%gtv Q (~

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ih 7.3 and that the best estimates of its location indicate that it could have occurred on the Hosgri fault. Furthermore, the range in magnitude is compatible with the largest recorded or estimated magnitudes of earthquakes that have occurred on subsidiary faults in the San Andreas system.

Selected comments important to an evaluation of the amendments are outlined below.

Amendment 31

NRC guestion 2.18

On figures 8 and 9 relative displacement on the Hosgri fault between Point Buchon and Point Sal is shown to be down on the east.

On figure 10 relative displacement on the southern extension of the

Hosgri fault south of Point Sal is down on the west, which is compatible with the argument that the Hosgri fault is the east boundary of a portion of the Santa Maria Basin. Changes in direction of relative movement, however, are very suggestive of lateral displacement, which may have occurred after development of the basin and bounding faults.

On page 9, reference is made t'o figure 11 as evidence that no scarp-forming seismic events have occurred on the southernmost part of the Hosgri fault since prior to the Wisconsinan stage of the Pleistocene. It is true that no offset of the ocean floor is evident on figure ll. However, close inspection of figure 11 shows offset of the post-Wisconsinan unconformity when sighting along it or placing a straightedge along the mapped trace. Also, faulting of the post-

Wisconsinan sediments cannot be precluded because a change in acoustical hl }

r signature is evident across an upward projection of the fault shown

in figure ll. The change in the acoustical signature of unit A2 across the fault is quite clear and may be evidence of lateral movement on the fault.

It is not clear from the profiles in figures 13a and 13b that the disturbed zones in them that are inferred to represent the liest Hosgri fault are the same. At least three additional faults can be inter- preted in the profile of figure 13b. Also a disturbed zone appears to be between stations 133 and 136 in the profile of line 13a. Kelez,

Bartlett, and Polaris survey lines crisscross this area and evidence from them to support or negate the suggested correlation of disturbed zones is not apparent.

An independent interpretation of the seismic profiles in the offshore area from about Point Sal to about five miles south of Point Arguello indicates that the Hosgri fault extends at least five miles south of Point Arguello and does not turn eastward as suggested in

Amendment 31.

Although the Lompoc fault zone appears to have offset the sea floor, and may, therefore, be considered capable of movement again, its length of only about eight miles as inferred by the applicant appears to be incompatible with a magnitude 7.3 earthquake. An independent interpretation of the seismic profiles in the area of the Lompoc fault differs from that of the applicant in that it shows that the Lompoc fault zone is about 20 miles long; the longest single fault in the zone is about 15 miles in length. Furthermore, the displacement

is interpreted to be dip slip or possibly oblique slip; rather than

reverse slip as suggested by the applicant.

NRC guestion 2.19

As noted in the previous section, the sense of displacement on

the southern part of the Hosgri fault is up on the west side, figure 1 (N), and therefore is not compatible with its being primarily related

to basin development. However, an alternative interpretation suggests

the displacement on the Hosgri fault in figure 1 to be down on the west.

Figure 1 (N) has three buried faults not shown on Plate I. This

leads to questions concerning the interpretation of some of the data in the report.

Another instance of faults shown in profile but not on a map is

seen from comparison of figure 4 (N) and Plate I. The correlation of

faults between Lines 16 and 12 (figures 3 (N) and 4 (N)) is questionable.

A profile along Line 14 would help. Also, an interpretation of Line 10

should be included.

Although the straight coast line between Cambria and Point Estero

'suggests that the extension of the San Simeon fault is just offshore;

data are lacking to prove this. None of the data presented in Amendment

31 preclude the San Simeon fault from intersecting the Hosgri fault offshore between Cambria and Point Estero. The two faults even as

shown on Plate II (N) are less than 2.5 miles apart and could very well

be tectonically coupled to each other by an en echelon or anastomosing series of faults which is characteristic of faults in the coast ranges.

Such coupling of the Hosgri and San Simeon faults is supported by C J

'p - "l '( WQ interpretation of stratigraphic sections recently reported by Hall (1975).

He infers that "...the San Simeon and Hosgri faults are part of the

same system,..." and that 80 km or more of right slip has occurred

along the system during the last 5 to 13 million years.

Figures 7a (N) and 7b (N) are very puzzling. They show an inflection

in the sea floor over the Hosgri fault and a drastic change in the thickness and acoustical signature of unit A2, assuming A2's correlative with A2. In addition to vertical displacement, lateral displacement, which is not mentioned, could be interpreted from these profiles.

However, the basis for separating A2'rom A3 is not apparent. Similarly, it is not apparent why unit A', east of the fault, is terminated. It appears to continue to the east edge of these profiles.

On figure lla (N) the A2 unit east of the fault at station 119. is correlated with the Monterey formation (p. 8, NRC guestion 2.19,

Amendment 31), but the signature of the A2 unit west of this fault is completely different. This inferred lithologic change, as elsewhere, suggests lateral displacement.

NRC guestion 2.20

On page 10 it is reasoned that both the Hosgri and West Hosgri faults can be eliminated as sources of the 1927 earthquake because neither the sea floor nor the post-Wisconsinan unconformity are offset in the epicentral area of the earthquake. This reasoning is not satisfactory because typically surface rupturing of a fault is discon- tinuous, and offset may not be detected if the displacement had a I )

I'1 I/* large lateral component. Furthermore, as stated on page 4 of this

review, the base of post-Wisconsinan sediments is offset, and a fault in the sediments cannot be precluded in figure ll. The evidence, therefore, to eliminate the Hosgri fault as the source of the 1927

earthquake is inadequate. As previously stated, the length of the

Lompoc fault appears to be incompatible with the magnitude of the 1927 earthquake.

Figure 1 shows that segments of the Hosgri fault zone, the Lompoc

fault, Purisima fault, and Lion's Head fault occur within the error circle of Gawthrop and error ellipse of Engdahl for the 1927 earthquake. However, all of the faults are outside of the area designated by„Smith as the "inferred distribution of aftershock sequence of the 1927 earthquake." The 1927 earthquake, therefore, cannot be unequivocally located on any one of these faults. The Hosgri fault, however, is closer to the center of the estimate of error than the other faults and, therefore, must be considered as a possible fault on which to locate the earthquake.

Amendment 32

NRC Question 2.17

Although this section contains descriptions and explanations of the "kinematics of structural behavior in the south-central California region..." contemporary seismic activity is not fully explained. Also, we do not agree with some statements given as fact. For example, on page 2 it is stated as fact that the 1927 H.7.3 earthquake occurred on the Lompoc fault. This is not fact but a highly controversial f b, II assumption. Item 2 on page 2 of this amendment indicates that the

Lompoc and San Andreas are the only faults in the southern Coast Ranges

that "reflect substantial late quaternary surface deformation." As

defined on page 3 of this amendment, "substantial" clearly includes the

San Simeon fault, which as stated on page 7 of this review may be

coupled with the Hosgri fault. The attempt to explain the large

magnitude by using the logic that. the Lompoc fault is in a transition

zone between the Coast Ranges and Western Transverse Ranges applies to other faults in the zone including the southern part of the Hosgri fault.

Amendment 34

NRC guestion 2.21

The maximum credible earthquake of 6 1/4 - 6 1/2 on the Hosgri fault zone used in this section to derive peak site ground acceleration

is unacceptable because as stated previously the 1927 earthquake with a magnitude of 7.3 cannot be precluded from having occurred on the

Hosgri fault. Although we believe that the 1927 earthquake should be used to estimate the safe shutdown earthquake, fault length-magnitude relationships have also been considered. The uncertainties in these relationships and the assumptions involved in the use of them are well known.

Nevertheless, we may consider that the Hosgri fault is about 90 miles

(144 km) long, or even greater if it is coextensive with the San

Simeon fault. The part of this total length that may rupture during an earthquake is highly conjectural, particularly in view of the complex tectonic style of the faults in question. However, using a reasonable 4' ~ J

10

factor for continuous rupture along a discontinuous zone of deformation,

in our judgment, it is prudent to consider magnitude 7 as a possible

minimum magnitude based on this criterion above, exclusive of the

consideration of the 1927 earthquake.

Recen'tly some earth scientists in California have discussed the

possibility that the Hosgri fault zone not only may intersect or be

coextensive with the San Simeon fault, but that the San Simeon fault

may connect with the San Gregorio fault, presumably in the vicinity of

ttonterey Bay. It is argued that these three faults could comprise a

system that may make it capable of generating a magnitude 8 earthquake. Available data, although incomplete, do not substantiate this inferred \ system of faults in the sense that it is a long linear fault along which major movements are occurring and, therefore, is. capable of a

magnitude 8 or larger earthquake. It is well known that earthquakes with instrumentally measured magnitudes of 8+ generally occur along major discontinuities that may

be either subduction zones or transform faults. In western, North, America

the only such discontinuity recognized is the .

Not only is there no record of a magnitude 8 earthquake on the offshore system, but significant differences in tectonic style exist between

that system and the San Andreas fault, which strongly suggest that the great length of rupturing associated with magnitude 8 earthquakes on strike-slip faults would not occur. These differences are outlined below:

11

(1) As stated previously, an interpretation that the San Simeon intersects the Hosgri fault zone offshore between Cambria and Point

Estero cannot be precluded. Such an intersection would permit a nearly straight line continuation of the Hosgri zone. However, interpretations by Hoskins and Griffiths, the applicant, and Wagner all show continuation of the Hosgri zone or branches of it north of any postulated intersection.

If the San Simeon fault does not intersect the Hosgri zone, then they are en echelon to each other as original(y interpreted by Hoskins and Griffiths.

The tectonic style of this area, therefore, is one of branching or en echelon faults.

(2) Data on the relationship of the San Simeon fault to the San Gregorio fault have not been provided by the applicant nor were they requested. The Hosgri fault zone is comprised of many discontinuous, anastomosing, and en echelon faults as interpreted by both Wagner and

McCulloch, and the applicant. Relationships between HSS zones appear to be similar to the style of faulting in the coast ranges: an anastomosing, en echelon pattern unlike that of the San Andreas fault

Offshore faults north of Point Piedro Blancas do not form a single continuous fault. Greene and others (1973) show the San Gregorio fault connecting with the onshore Palo Colorado fault northeast of the Sur- Nacimiento fault zone. Furthermore, the San Simeon fault if projected northwest immediately offshore is truncated by the Sur-Nacimiento zone

(Crowell, 1975). These relationships appear to preclude any similarity to the continuous style of the San Andreas fault. "~ 12

(3) The Hosgri zone and the San Simeon fault are considered in this review as part of the San Andreas system of faults. This interpretation is made because (a) of evidence of lateral movement along the Hosgri fault zone and the San Simeon fault, (b) these faults like coast range faults are subparallel to the San Andreas fault, and (c) the regional stress field responsible for the plate boundary movements concentrated along the San Andreas fault may reasonably be expected to cause lateral movement on subparallel faults. Nuch geologic and seismologic evidence, however, shows that the major plate boundary movements are occurring on the San Andreas fault. Speculation that the major movements now occurring on the San Andreas fault should transfer tens of miles to another part of the system, which is discontinuous and nonlinear, within a few decades or perhaps several hundred years cannot be supported with available geologic evidence.

(4) The Hosgri fault zone and San Simeon fault are recognized as the eastern boundaries of offshore basins with large vertical displace- ments. The evidence for this is compelling, and the presence of the companies. In our review we basins is reason fori exploration by oil have not disputed this evidence, but argued that the displacement on these basin-bounding faults in the current stress regime may have a large component of lateral displacement should an earthquake occur on them. These faults apparently do not form crustal plate boundaries which suggest that both their length and depth are not of the order of plate boundary faults and probably would not support earthquakes as large as those that occur along crustal plate boundary faults.

13

The suggestion that the Hosgri-San Simeon-San Gregorio faults

comprise a system capable of a magnitude 8 earthquake is a legitimate

and serious question, which has been considered since discovery of the

Hosgri fault zone by Hoskins and Griffiths (1971). It is our current

judgment, however, based upon the data in the fSAR, data in the literature,

,.some work in progress within the USGS, present concepts of earthquake s /source areas along the west coast of the U.S., and the arguments given, above that such faults have not been demonstrated to be capable of generating magnitude 8+ earthquakes.

In essence the Hosgri, San Simeon, and San Gregorio faults, even

if par ts of a common zone of deformation, have the dominant characteristics

of subsidiary faults within the San Andreas system. Such subsidiary

faults have no record of or estimate of earthquakes larger than magnitude 7.5

on them.

Conclusions

Although the FSAR includes a considerable amount of new information

and analysis, the only change that can be made in the original conclusions

transmitted to the NRC on January 28, 1975, is to be more specific in

our estimate of the design basis earthquake. This is based upon the following facts and judgments.

1. The Hosgri fault zone is more than 90 miles long and may even 1 be tectonically coupled to the San Simeon fault as they are within 2.5 miles of each other and both form parts of the eastern boundary of the Santa Maria basin. f 14

2. Narked changes in thickness and signature of acoustical units across the Hosgri fault zone in several profiles indicates evidence of lateral slip. This was noted in our review of January 28, 1975, but such changes are even more abundant in the profiles of Amendment 31. Right lateral movement is reported for the San Simeon fault. These data suggest that displacements on the Hosgri fault are related to the highly active San Andreas plate-boundary system.

3. The length of the Lompoc fault appears incompatible with the magnitude of the 1927 earthquake.

4. The Hosgri fault is closer to the center of the estimates of error of both Engdahl and Gawthrop than any other fault. It is therefore a possible source of the 1927 earthquake. 5. guestionable evidence related to vertical displacement on the Hosgri fault in the epicentral area of the 1927 earthquakes does not eliminate it as a source. Surface rupture is generally discontinuous, and if lateral slip occurred, it probably would not be detected. Offset of the base of post-llisconsinan sediments and probable faulting of them is evidence of post-Pleistocene movement.

For the above reasons and discussions given in the review, we conclude that the 1927 earthquake could have occurred on the Hosgri fault and that a similar earthquake with a magnitude of about 7.5 could occur in the future anywhere along the Hosgri fault.-- ) J

J j V

15

6. We recognize the suggestion that the Hdsgri, San Simeon, and 'i San Gregorio faults may comprise a system capable of magnitude 8 earthquakes. It is our judgment,.~however, that these faults are sub-

sidiary faults within the San Andreas system and such faults have not

been demonstrated to be capable of magnitude 8+ earthquakes.

7. We repeat our opinion that, for sites within 10 km of the

surface expression of a fault, the description of maximum earthquake

ground motion by means of a single acceleration value may not be an appropriate representation.

Consequently, we feel that an appropriate earthquake for this

site should be described in terms of near-fault horizontal ground motion.

A technique for such a description is presented in the Geological

Survey Circular 672 entitled "Ground Motion Values for Use in the Seismic Design of the Trans-Alaska Pipeline System" (Ref. 4). It is

our intention that the ground motion values as exemplified by Table 2

"Near-fault horizontal ground motion" of Ref. (4) for magnitude 7.5 be

used to form the basis of a description of the earthquake postulated

to have the potential for occurring on the Hosgri fault at a point

nearest to the Diablo Canyon site subject to the conditions placed

on these values in Ref. 4. The earthquake so described should be used

in the derivation of an effective engineering acceleration for input into the process leading to the seismic design analysis. 'v. ~

U 16

It is intended, also, that this potential earthquake be considered in addition to all earthquakes considered previously by the applicant during the construction permit review process.

References

Bonilla, M. G., and J. M. Buchanan (1970), Interim report on worldwide historic surface faulting: U.S. Geol. Survey, open-file report no. 1611.

Engdahl, E. R. (1975), Teleseismic locatiop of the 1927 Lompoc earthquake:

TERA Technical Report, Berkeley, Calif.

Greene, H. G., Lee, H. H. K., McCulloch, D.S., and Brabb, E. E., 1973,

Fault Map of the Monterey Bay Region: U.S. Geol. Survey Mis. Map

MF-518.

Hall, C. A. (1975), San Simeon-Hosgri fault system, coastal California:

Economic and environmental implications: Science, 190, p. 1291-1293.

Hosgins, E. G. and Griffith, J. R., 1971, Hydrocarbon Potential of

Northern and Central California Offshore: . Am. Assoc. of Pet.

Geo. Men. 15, p. 212-228.

Page, R. A., D. M. Boore, I/. B. Joyner and H. W. Coulter (1972), Ground motion values for use in the seismic design of the Trans-Alaska Pipeline System: U.S. Geol. Survey Circular 672.

San Andreas Fault in edited by John C. Crowell: California Division of Mines and Geology Special Report 118, 1975. ~ g ~

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ENCLOSVBE 'ESCBIPTION i 3'4'of.the Ltr trans the following: Review of Amdt 31, 32,, & FSAR...... 'ith regard to seismology..;.in draft form.....

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1TEM REC"D IN DISTRIBUTION SECTION 2"17-76

PLANT l@lK: Diablo Canyon 1 & 2

SAFETY FOR ACTION/INFORMATION HNVXRO 2-17-76 ehf ASSIGNED '~ no ASSXGNED AD : 14ANCFI CiiXEP: P. V BRANCH CHIEF : PROJECT ~~ANAGHR; PRO JL'CT 11ANAGER: LXC ~ ASST. Q~) ~urn ~~ LXC

ASST'NTEIINAI DISTRIBUTION REG "7y~s'r;U$ SAEKX 1 HIGURCLZECH 1"XLL'&H JLDDKAH XHDHSr.o HRNST ~CIIPOZMl4 BHNAROYA ~I/»LT.ARD Q~iQ IA+hgS SPANGLER GOSSXCK & STAFF ENGXLIE~ER NG XPPOLXTO SXTE TL7CH Xj'gE UACC KNXGHT OPERATXNG REACTORS GAM1XLL S XIIINEXL STELLO STEPP i'ji PAMLXCliX IIULYiAN Ii~+-M OPERATING T"CH PROJECT MANAGE}IHNT RHACTOR SAPETY EXSHNIIUT SITE ANALXSXS BOYD ROSS SFIAO VOLLIFER P. COLLINS NOU/ K BAHR BUNiCH HOUSTOil ROSZTOCZY SC1NENCHR J. COLLXNS PETHPSON C}IHCIi GRXHHS IiREGER MELTZ IIELTHMHS SITE SAI'I'.TY & ENVIR SKOV}IOLT SAT.TZI!AN ANALYSIS RUTBHRG Di',NTON & [email protected] EX IEII."JAI.DISTRIBU1ION CONTROL NUMBER T.PDR '~BE ~i~+])~Pc NATL I.hB BIYOOKIIAVI'",N NATI'AB TXC RHG, V"XE ULIGKSON(ORNL) NPgC LA »DR CONS UI.TAI

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1 gA. Oc 'v 6 ~ Q 'States Department of the Interior I l0 United l 0 GEOLOGICAL SURVEY R ESTON, VIRGINIA 22092 MLQ +

January 12, 1976; 8 GC5 nb

Mr. William P. Gammill Chief, Site Analysis Branch ,Division of Technical of Nuclear ReactorReview'ffice Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dear Bill:

Enclosed is a revised draft review of the Amendments 31, 32 and 34 of the FSAR for the Pacific Gas and Electric Company's Diablo Canyon site, Units 1=and 2, San Luis Obispo County, California, Docket Nos. 50-275 and 50-323. This review was prepared by Frank A. McKeown, who reviewed the geology, and James F. Devine, who reviewed the seismology. Mr. McKeown,was. assisted by Holly Wagner, David McCulloch,'and Robert Ye'rkes; Mr. Devine was assisted by Robert Page and Wayne Thatcher. Sincerely yours,

Fred N. Houser Deputy Chief Office of Environmental Geology I% Enclosure +c

Oi s OgUTIOy

'Z m R 4'+7 Ip)6.1916 ~ \

~ p ~ Draft Rcvgcw F. A. HcK~ (Geology) J. F. Dev%8 (Seismology) Diablo Canyon FSAR Amendments 31, 32 and 34 January 12, 1976

PACIlIC GAS AND ELECTRIC COMPANY DIABLO CANYON SITE, UNITS 1 AND 2 SAN LUIS OBISPO COUN~TY; CALIFORHIA AEC DOCIKT HOS. 50-275 AND 50-323

Geology and Seismology / This is a review of the geological and seismological information / contained in Amehdmcnts 31, 32, and 34 of,the Final Safety Analysis

Report (1SAR) fdr the Diablo Canyon nuclear power plant site. Amendment 37, conta'ining important discussion of the ground respons'e pertinent

was received in early November and too J.ate to be consideredto'eismicity, in this review. The amendments were prepared by the Pacific Gas and

Electric Company (PG&E) iri response to a request in a letter dat d

February 12, 1975, from the Nuclear Regulatory Commission (NRC) for certain additional information relevant to design basis earthquake

C issues, which have been the principal problems requiring additional earth sciences information and analyses. To support assertions in the I FSAR 'through Amendments,ll, 19 and 20, five requests for information

(referred to as'uestions in the'Amendments) were made.

2. 17. Provide additional discussion and arguments for determining thc maximum earthquake that can be expected on faults of various ~anks within the San A»drcas system. Relate the discussion to historic scismi:city. 2. 18. Provide additional documentation, including seismic .reflection profiles, on .the intcrs'ection of thc )losgri'ault "onc with thc Yransvcrsc Range faults. Include geologic maps south~ ard of thgsc provided in the l:SAR showing thc structural relation- ships of thc Transvcrsc faults and structures having a northwest trend. H

1 ~ ~ ~ I

1 ~

2. 19. Provide.additional documentation, including seismic profiles, on thc northern rcachcs of thc Ilos'gri fault zone. Include a fuller dcvclopmcnt of your views 'on, the structural relationship af thc llosgri fault to thc San Simeon fault.

2. 20. Provide additional informat'ion on thc location of the 1927 event, togcthcr with its probablc mccha»ism. " Discuss probable relationships of this cvcnt 'to thc geologic structure in the region. / 'I 2.21. Provide your evaluation of the maximum credible earthquake on the.llosgri'ault zone. Assuming this event occurs along the of thc Ilosgri fault zone nearest the site, evaluate 'egment its response spectrum at the site and compare it with the design response spectrum.

The 're'sponse in the PSAR 'to the questions has provided considerable

additional geologic'nd seismologic information and analyses.

However, unaiubiguous answers to the questions haVe not been achieved. Hany uncertainties in the data .and interpretations still exist. Among the most important of these. are: l) the location, and mechanism:of'he 1927 earthquake, 2), the exact relation of the

Ilosgri fault zone to faults in the Transverse Range system and the

San Simeon fault, 3) the continuity of some faults, 4) the relative I amounts of dip-slip and strike-slip movemcnt on, the Ifosgri fault;one, 5) the sense of displacement on parts of the Hosgri zone, 6)

identification and correlation of acoustical u'nits, and 7) kinematic

relations among different fault zones.

In addition to these uncertainties, some information shown on the

2 profiles is not shown on the maps and yi'ce versa, and some profile" data are not included that are important to evaluate the extension or

character of some faults. Because geologic maps developed from seismic ~ ~ ~ ~ reflection profiles are based upon much interpretation that may differ

among, several interpreters, it was necessary for the purposes of our

review to, pa/qq independent interpretations of the se'ismic profiles~.

These independent interpretations are somewhat different than the

~ . interpretations presented in Amendments 31 and 32. The major / differences are briefly described in appropriate sections of this review.

1, Although soee changes in, and additions to, geologic and seismologic

details have been made in Amendments 31, 32, and 34 compared,wi.'th

previous data in the FSAR, no major changes .,can be made in our. conclu-

sions that were stated in the review of the 'FSAR, and Amendments

11, 19, and 20, which was transmitted to the FRC from the Director

of the United States Geological Survey by letter of January 28, 1975.

The pertinent statement in oor previous conclusions was as follows:

"Earthquakes along the .EBZ presumably would no't be as large as expected on. the San Andreas however, from the information fault, / 1 presently at'hand we can find no evidence that would preclude the / / occurrence of an earthquake as large as events characteristic'of / subparallel strike. slip faults, which bound basins, such as, the Santa

h/aria, in the San Andre'as system and which do nnt'ransect structural

~ provinces." The size of an earthquake on. faults t:hat bound basins \ was not. specified in this conclusion. For reasons'stated in subsequent

As defined in the FSAR, EBZ refers to the East Boundary fault zone, which is the Hosgri fault .zone. I ~ ~

1 ~

~ ~

parts of this review, however, the magnitude of the design basis

for'j>c Diablo Canyon nuclear reactor siteI'art)aqua);c should be jp thc range of 7.0 to 7.5 and located on the Ilosgri. fault "onc. This

is based principally o'n thc fact that the Ãovcmbcr'4, 1927, earthquake had a magnitude'f 7. 3 and that thc best, estimates of its location indicate tha't i6 could have occurred on the Hosgri fault.

Selected comments important to--an evaluation of Amendments 31, 32, and 34 are outlined below.

Amendment 31

NRC Question 2.18

On figures 8 and 9 relative displacement on the Hosgri fault

between Point Buchon and Poiht Sal is'hown t'o be do~m on the east.

On figure 10 relative displacement on the southern 'extension of. the

Hosgri fault south of Point Sal is down on the west, which is compatible

with .the argument „that the Hosgri fault is the east boundary of a pcrtion

of the Santa )laria Basin. „Changes 'n direction of'elative movement 1 however, are very'suggestive of lateral displacement, which may have occurrred after develop'ment. of the basin and bounding faults.

On page 9, reference is made to fi'g.. 11 as evidence that no scarp-forming seismic events have occurred on the southernmost part of the l)osgri. fault since prior to the h'iscon'sinan stage of the PIcistoccne. It is true that no offset of thc ocean floor is cvidcnt \ ~ ~ on fig. 11. )!owcvcr, close inspection of fig. 11 shows offset of

unconformity when sig)>ting along it'r placing a thc'ost-4'isconsinan 4 ~

1' I ~ I

~ ~

straightedge along the mapped trace. ~ Also, faulting of the post-

LBsconsinan sediments cannot be precluded because a change in acoutical

signatqyq iq, qyi4qnt across an upward projection of the fault phoyp in figure ll. The change in'he acoustical s'ignature of unit A2

across the faul't is quite clear and may be evidence of lateral

movement on the fault.

It is not, c)ear fr'om the profiles in figures 13a and 13b that the 'disturbed zoned'in them that are inferred to represent the Hest llosgri

fault are the same. At least, three additional faults can be inter-.

preted in the-profile of figure 13b. Also a disturbed zone appears

to be between stations 133 and 136 in the profile of line 13a. Kelez, Bartlett, and Polaris survey'inis criss-.cross this area and

additional evidence from them to support or,n*egate the suggested

correlation of disturb'ed zones should be described.

An i.ndependent.interpretation of the seismic profiles in the offshore..area from about Point Sal to about five miles south of I Point Arguello-indicates that the,Hosgri fault extends at least five

miles south of Point Arguello and does not turn eastward as suggested

in Amendment 31.

Although the Lompoc fault, zone appears to have offset the sea

floor, and may therefore be'onsidered cayable of movement again, its- length of only about eight miles as inferred by the applicant appears

to be incompatible with' magnitude 7.3 earthquake. An independent ihterpretation of the seismic profiles in the area of the 'Lompoc foul't di'ffers from that of the applicant in that it shows that the Lompoc

4) fault zone.is about twenty miles long; the longest single fault in the zone is about fiftee'n miles in length. Furthermore, the displacement is interpreted to be dip slip or possibly oblique slip,'ather than reverse slap aa suggested by,the applicant.

'

NRC guestion 2.19

As not'ed in the previous section the sense of'displacement on

the southern part of the Hosgri fault is up on the:wes't side, figure ' 1 (N), and therpfore is not compatible with its being primarily

related to basin development. However, an alternative interpretation

suggests the displacement on the Hosgri fault in figure 1 to be de on the west.

Figure 1 (N) has three buried faults not shown on Plate I. This

leads to questions concerning the interpretation of some of the data in the report. Another instance of faults shown-in profile but not on a map is

seen from comparison of fig. 4 (N) and Plate X. The correlation of

faults between Lines,16 and 12 (figs. 3 (N) and 4 (N)) is questionable.

A profile along Line 14 would help. Also; an interpretation of, Line 10 should be included.

Although t:he straight coast line between Cambria and Point Estero suggests that thc extension of the San Simeon fault is just offshore; data arc lacking to prove this. None of the data prcscnted in

Amcndmcnt 31'reclude the San Simeon fault from intersecting the ftosgri fault offshore between Cambria and Poiht Estcro. The two

faults even as shown on Plate II (N) are less than 2.5" miles .apart. I ~ and could very well be tectonically coupled to each other. by an en echelon I or anastomosing 'series of faults which is characteristic of fauJ.tp gp pQq coast ranges. Guch coupling of the Hosgri'nd San Simeon faults is supported by interpretation of stratigraphic sections recently reported by '1iall ~ (1975).

He infers that. "—-the San Simeon and Hosgri faults are part of the same I system, —-" and', that 80 km or more of right 'slip has occurred along the system during the last 5 to 13 million years.

Figs. 7a (N) and 7b (N) are very puzzling. They show an inflection in the seafloor over the Hosgri fault, and a drastic change in the thickness and acoustical signature of unit A2, assuming A2's correlative with A2. In addition to vertical displacement, lateral disp'lacement, which is not mentioned, could be interpreted from these profiles. However, the basis for separating A2'rom A3 is not apparent. Similarly it is not apparent why unit A', east of the fault, is terminated. It appears to continue to the east edge of these profiles.

On figure. lla (N) the A2 unit east of the fault at station 119 is

I correlated with the Honterey formation (p. 8, NRC Question 2.19, amend. 31),

P P but the signature of the A2 unit west of 'this fault is completely different. This inferred .lithologic change, as. elsewhere, suggests lateral displacer;.ent. i 0 W

NRC Question 2.20

On page 10 it is reasoned that both the Hosgri and West flosyrj. faults can be eliminated as sources of the 1927 earthquake because neither the sea floor nor, the post-Wisconsinan unconformity are offset in the epicentral area of the earthquake.. This reasoning is not satis-

factory because'typically surface rupturing of a fault is discontinuous, 'I and offset may no't be detected if the displacement had a large lateral I component. Furthermore, as stated on page 4 of this review, the base

of post-Wisconsinan sediments is offset, and a fault in the sediments

cannot be precluded in figure 11. The evidence, therefore, to eliminate

the Hosgri fault as the source of the 1927 earthquake is inadequate.

As previously stated, the length of the Lompoc fault shown by the applicant

appears to be incompatible with the magnitude'f the 1927 earthquake. / Figure 1='shows that segments of the Hosgri fault zone, the Lompoc

fault,, Purisima fault, and Lion's Head fault occur within the error circle of Cawthrop and error el'lipse of Engdahg for the 1927 earthquake. However, all of the faults are outside of the area designated by Smith as the "inferred distribution of aftershock sequence of the 1927

earthquake." The 1927 earthquake, therefore, cannot be: unequivocally

located on any one of these faults. The Hosgri fault, however, is closer to the center of the estimate 'of error than the other faults and,

therefore, must" be considere'd as a possible fault on which to 1'ocate the earthquake.

Amendment 32

NRC Question 2.17

Although this section contains descriptions and explanations of

9 the "kinematics of structural behavior in the south-central California region —-" con'temporary seismic activity is not fully explained. Also, we do not agree with some statements given. as fact. For, example, oy page g it is stated as fact that the 1927 M.7.3 earthquake o'ccurred on the Lompoc fault. This is not fact but a highly controversial'ssumption. Item 2 on page 2 of this amendment indicates that the Lompoc and San Andreas are the

1') only faults in the southern Coast Ranges that "reflect. substantial late

Quaternary surface deformation." As defined on, page 3 of this amendment,

"substantial" clear'y, includes the San Simeon fault, whiCh as stated on page 7 of this review may be coupled with the Hosgri- fault. The attempt to explain the large magnitude by using the logic that the Lompoc fault is in a transition zone between the Coast Ranges and Western Transverse

Ranges applies to other faults in the zone including the southern part of the Hosgri fault.

Amendment 34

NRC Question 2.21

The masimum credible earthquake of 6 1/4 - 6 1/2 on the Hosgri

fault zone used in this section to derive peak site ground acceleration is unacceptable because as stated previously the 1927 earthquake with a magnitude of 7.3 cannot be precluded from having occurred on the

Hosgri fault. Although we believe that the'927 earthquake should be used to estimate the safe shutdown earthquake, fault

length-magnitude'elationships have also been considered. The uncertainties in these 0

I ' v 0 ~ ~ V relationships and the,.assumptions involved to use them are well

known. Nevertheless we may consider that the Hosgri fault is about 90 miles (144 km) 3.ong, or even greater if't is coextensive with the

San Simeon fault.- The part of this total length that may rupture during= an

earthquake is highly conjectural, but we assume that one third of the fault.

will rupture, which is about 48 km. This assumed 3,ength is supported somewhat if the range in S-P times for the aftershocks of the 1927

earthquake are considered. The range in times calculates to about 45 km . as shown hy Engdahl (1975). The fault length-magnitude. curve for

strike-slip faults '(Bonilla and Buchanan, 1970, fig. 3) shows magnitude 7 for a 45 km rupture. In our judgment it is prudent to consider this as a possible minimum magnitude, exclusive of the consideration of the 1927 earthquake. 'Conclusions l Although the FSAR includes a considerable amount of new informa-

tion and analysis, the only change that can be made in the original

conclusions transmitted to the NRC on January 28, 1975, is to be more t -specific in our estimate of the design basis earthquake. This is based

upon the following facts and judgments.

1. The Hosgri fault zone is more than 90 miles long and may even

tectonically coupled to %he San Simeon fault as they are within. 2.5 miles of'a'ch other and both form parts of the eastern b'oundary of the Santa Maria basin. 0 S ~

~, e

'

2. irked changes in thickness and signature of acoustical units

across the 11osgri fault zone, in several profiles indicates evidence of

lateral slip. 1'his was noted in our review of January 28,-1975, but pucj1

. changes are even mope abundant in thc profiles of Ancndment 31. 'Right:

lateral movcmcnt is. reported for thc San Simeon fault. Thcsc data / suggest that displaccmcnts on the Hosgri fault are rclatcd to thc

C highly active San Ppdreas plate-boundary s>stem.

3. Thc length! of the Lompoc fault appears incompatible with the

magnitude of the 1927 earthquake. 0 4. The Hosgri fault is closer to the center of the estimates of

error of 'both Engdahl and Gawthrop than any other fault., It is 'there-.

' fore a possible source of the 1927 earthquake.

'I 5. Equivocal evidence related to vertical displacement .on the Hosgri

fault in the epicentral area of'the 1927 earthquake does not eliminate it as a source. Surface rupture is generally discontinuous', and if lateral slip occurred, it probably would not be detected. Offset of the base of post-Misconsinan sediments and probable faulting of- them is

evidence of. post-Pleistocene movement.

For, the above reasons and discussions'iven in the review, we

conclude that the 1927 earthquake could" have occurred on the 1losgri I fault and that a similar earthquake with a magnitude in the range of X 7.0 — 7.5 could o'ccur in the future'anywhere'long'he 11osgri fault. 1

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6. We repeat our opinion that, for, sites 'within lQ km of the surface expression',of a fault, the description of'aximum earthquagp giougd

motion or design motion by means of a single acceleration value and a

standard response spectrum may not be an appropriate representation

for design purposes. Consequently; we feel that it is appropriate that we describe the r Safe Shutdown earthquake for this site in terms of near-fault horizontal S ground motion.. The technique for such a description is presented in the

Geological Survey Circular 672 entitled "Ground Motion ValueS for Use in the Seismic Design the Trans-Alaska System" (Ref. of Pipeline 4). '

It is our intention that the ground motion values as shown in Table 2

"Near-fault horizontal ground motion" of Ref. (4) for magnitude 7.0

and 7;5 be used as a description of the earthquake postulated to have

the potential for occurring on the Hosgri fault at a point nearest to the

Diablo Canyon site.

4 The conditions placed on these values as described in Ref. (4) p. 3-l3 also apply in this case, e.g. "They characterize free-field ground motion,..."

The design values of motion should be derived by modifying the ground motion values to implicikely allow for non-linear energy absorbing mechanisms in the vibratory response of the structure and,.their application to

appropriate response spectra as specified in Ref. (4) p.p. 2 and 3 and

appendix B. It is intended, also, that this potential earthquake be .considered in addition to all earthquakes considered previously by .the applicant during the construction permit review process. ( 'W

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r, References Cited

Bonilla, M. G., and J. M. Buchanan (1970) Interim report on worldwide histoqgc surface faulting: U. S. Geol. Survey,'pen file report no. 1611.

Engdahl, E. R; (1975), Teleseismic 1'ocation of the 1927 Lompoc earthquake: r TERA Technical Report, Berkeley, Calif.

J Hall, C. A. (1975), San Simeon-Hosgri fault system, coastal 'California:

Economic and:environmental implications: Science, 190, p. 1291-1293.

Page, R. A., D. M. Boore, W. B. Joyner and H. W. Coulter (1972), Ground motion values for use in the seismic design of the Trans-Alaska Pipeline System: U. S. Geol. Survey Circular 672. p Distribution Nos. 50-275 NRC PDR Docket 2 0 875 50-323 N0y Local PDR and Docket File LWR 1-3 File WPGammill Mr. Robert Morris JOsloond U. S. Geological Survey JCStepp RBMcMullen Engineering Geology Branch Denver Fedexal Center TJHirons Colorado 30225 DPAllison Denver, VKB.lson Dear Mr. Morris: , RHofmann Enclosed for your review are two reports referenced in Section 2.5 of the Diablo Canyon FSAR. The reports are entitled (1) "Teleseismic Location . ofI the 1927 Lompoc Earthquake," and (2) "Aftershocks of the 1927 Lompoc Earthquake."

The applicant has also submitted, as proprietary information, a report entitled "Western Geophysical Company and Shell Oil Company Proprietary Seismic Reflection Data from the Offshore Region between Point Estero and Point Arguello: Basic Data, Xnterpretive Data and Discussion." A copy of the letter transmitting. the above report is enclosed.

Xn addition, we e~ect the applicant to submit additional pxoprietary and non-proprietary information in response to our request for additional information dated November 14, 1975. A copy of our Novembex 14, 1975 letter is enclosed. Questions 2.22, 2.23, 2.24 and 2.g5 pertain directly to your area of review; The other two questions pertain to structural engineering aspects of the Diablo Canyon design.

We will provide thc pertinent non-proprietary responses for your review when they are received. We will also make the proprietary infornation available for your review, and we will contact you regarding the detailed arrangements. Sincerely,

Orlglnal ffgncd J)y Olan Parr Olan D. Parr, Chief Light Water Reactors Prospect Branch 1-3 Division of Reactor Licensing

Enclosures & ccs: See page 2

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cc- Mr. Prank McKeown (1) U. S. Geological Survey Engineering Geology 3ranch Denver Pederal Center Denver, Colorado 30225

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@75 NOY >g i975 Mr: James P. Devine U. S. Geological Survey National Center, Mail Stop 908 Reston, Virginia 22092 Dear Mr. Devine:

Enclosed for your use is a copy of the following:

"Western Geophysical Company and Shell Oil Company Proprietary Seismic Reflection Data from the Offshore Region between Point Estero and Point Arquello'asic Data, Interpretive Data and Discussion."-

Please notify us of receiving this information submitted by Pacific Gas and Electric Company for Diablo-Canyon Units 1&2 by returning a copy of this letter. The Proprietary Information (Copy No.6 under control No.'3031) should also be returned for final disposition, when of no further-use.

'illiamP. Gammill, Chief Site Analysis Branch Division of Technical Review Office of Nuclear Reactor Regulation cc: w/o Encl. v6ocket Pile J. Stepp R. Hofmann J. Osloond c K" Distribution NRC PDR Dockot Nos. 50-275 NOV 0 6 575 Local PDR and 50-323 Docket Pile (2) LWR 1-3 Pile HPGammill (w/o encl) JOsloond (w/o encl) Mr. Robert Morris JCStepp U. S. Geological Survey RBMcNullen Engineering Geology Branch TJHirons Denver Federal Center'enver, DPAllison Colorado 30225 VKWilson (w/extra cys) I RHofmann Dear Hr. 1'forris: 'Enclosed for your review are three copies of Amendment 37 to the Diablo Canyon PSAR. This amendment supplements Amendmcnts 31, 32 and 34 which were forwarded to you in August and September. Amendment 37 completes the applicant's responses to our formal requests for additional information.

Ue do expect the applicant to provide us, next week, with copies of certain reports referenced in the FSAR and certain seismic profiles. These are items we have requested by telephone. Some of them will be submitted as pzoprietary information. Me will make these items available for your review and will contact you regarding the detaQ.ed arrangements when the items are received. Sincerely, Orieiual Signed by, Olan parr Olan D. Parr, Chief Light Mater Reactors Pro)set Branch 1-3 Division of Reactor Licensing Enclosure: Amendment 37 to,the Diablo Canyon PSAR (3) cc w/encl: Hr. Prank McKeown 0) U. S. Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 30225

5k e James Pe Devine V) Department of the Xnterior U. S. Geological Survey Center Hai Stop OPFlcs 3So th -Lake..priv '------...... -...... RL'LKL.1-...3. ..RL:LMR 1-...3.. SURMAMsp'onal 22092 ton, Virg DPA1lison mt -'---ODParr,... „... Ll/...... /.75...... 11./ ...... /..Z5.... Porxa hEC-318 (Re@. 9-3 3) hZCM 0240 4 u. s; oovssvMsNv ssiNviwo osricss sore.see-see \

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Ir t 0 I Distribution = NRC PDR Docket Hos. 50-275 NOV,O 1975 Loc 1 PDR and 50-323 5 r ocket File (2) LWR 1-3 File WPGammill (w/o encl) JOsloond (w/o encl) Mr. Robert Morris JCStepp U. S. Geological Survey RBMcMullen EngineerIng Geology Branch TJHirons Denver Federal DPAllison Canter'enver, Colorado 30225 VHWilson (w/extra cys) RHofmann Dear Hr. Morris: Enclosed for'our review are three copies of Amandmant 37 to the Diablo Canyon FSAR. This amendment supplements Amandmants 31, 32 and 34 which were forwarded to you in August and September. Amendment 37 completes the applicant's responses to our formal requests for additional information.

Wa do expect the applicant to provide'us,next week, with copies of certain reports referenced in tha PSAR and certain seismic profiles. These are items we have requested by te1aphone. Some of them willbe submitted as proprietary information. We will make these items available for your ravIew and will contact you regarding the detailed arrangements when the Items are received. Sincerely, Original Signed by, Olan Parr .Olan D. Parr, Chief Light Water Reactors 'ro)act Branch 1-3 Division of Reactor Licensing Enclosure: Amendment 37 to the Mablo Canyon PSAR (3) cc w/encl: Mr. Frank McKeown 0) U. S. Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 30225 Mr. James P. Devine (a) Q@AIJ'II/741 '/ , Department of the Wterior 1 U. S. Geolo ical Surve Ha ional Center Mail Stop 9 -3 1-3 orrIcc3S th-Lake-Driv RL:L! —RL:LWR'-C»-/l --- '" 4URNAMc3Re ton, Virgin 22092 DPA1 ison:mt 'DParr

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Docket No 0-27 j323 NP 3 ~ ~9~> Mr. Robert M ris U. S. Geological Survey Building 25 Denver Federal Center Denver, Colorado 80225 SU~~i. AMENDMENT TO DXABLO CANYON REPORT The following docuIImnt material,staining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving or not receiving the subject material by returning a copy of this letter or phone (301) —492 —7258.

PSAR Volumes

Amendment No. To PSAR Dated

Amendment No. To Environ. Rpt. Dated

PSAR Volumes

Amendment No; 34 To PS'ated 9/16/75

Other: Amendment sent around 9/19/75

Hi3.liam R. Gammill, Chief &i

1 Distribution SEP 1 8 1975 NRC PDR Local PDR Docket gable~ LWR, 1T3 Fille Docket Nos -275 WPGammill GIll JCStepp RBMcMullen TJHirons Mr. James Morris DPAllison . U. S. Geological Survey VHWilson Engineering Geology Branch RHoffman Denver Federal Center JOsloond DGIIver, Colorado 30225

Dear ?fr. Morxis:

Enclosed fox'oux''eview aro three copies of Amendment 34 to the Diablo Canyon FSAR. This amendment supplements Amendmcnts 31 and 32 which wex'e forwarded to you. this past Augusti These 3 amendments include most of the geology and seismology information which we e~ect the applicant to submit. The balance of this information should be submitted by October 15, 1975. SincerelyP

Original Signed by, 0. D, Parr

Olan. D Parr, Chief Light Mater Reactors Project Branch 1-3 Division of Reactor Licensing Enclosure: Amendment 34 to the Diablo Canyon FSAR (3) cc w/encl I g/& Mr. Frank McKcown (1) U.ST Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 30225

Mr. JG es Z. Devine (2) Department of the Xntcrior U. S. Geological Survey ~tional Center, Mail Stop 908 South Lake Drive Reston, Vir inia 22092

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Doc'et No. 50 275/323 Hr. Robert H. I'1orris AUG 8 a tg76 U.S. Geological Survey Bl dg. 25 Denver Federal Center Denver, Colorado 80225

SUKrzcT: Amen'dment (32) to Diablo Canyon 182 Re P ort Tne following document material pertaining to review of the subject nuclear facility is being transmitted separately for your infoxmation. Please notify our branch of receiving'.,or not x'eceiving the subject material by returning a copy of this letter or phone (30l) —492 — 7258.

PSAR Volumes

Amen@vent No. To PSAR Dated Amenchnent No. To Environ. Rpt. Dated

PSAR Volumes

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Docket No. 50 275/323 Dr. Carl Wentworth MG aa pig U.S.G.S. 345 Hiddlefield Rd henlo Park, California 94025 r Amendment (32} to Diablo Canyon 182 Report Tne following docznent material pertaining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving-'or not receiving the subject material by returning a copy of this letter or phone (301) —492 —7258.

PSAR Volumes

Amendment No. To PSAR Dated

AmendInent No. To Environ. Bpt. Dated

FSAR Volumes

' Amendment No. 32 To FSAR Dated 8-2Q"'75 (Rec 8-22-75) Other-. Amdt. sent. about 8-22-75

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555

No 50 275/323

Nr. Stan R. Brockman AUG 2 2 >975 U.S. Geol o'gi cal Survey Building 25 (D3) Den.ver Federal Center Denver, Colorado 80225 SUmrer: Amendment (32) to Diablo Canuon 182 Report The following document material pertaining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving'r not receiving t¹ subject material by returning a copy of this letter or phone (301) —492 —7258.

PSAR Volumes

Amendment No. To PSAR Dated Am~~ent No. To Environ. Rpt. Dated

FSAR Volumes

Amendment No. 32 To PSAR Dated 8-20-75 Rec ' 8-22-75 Other- Amdt. Sent. About 8-22-75

tt. P. Gammi11,Chi e f Site Analysis Branch Division of Technical Review Office of. Nuclear Reactor Regulation : Docket o fmann J. Osloond

jtII) u~rrco s rArrs NUCLEAR REGULATORY COMMISSION 'L'VASHING'rON, D. C. 20655

Do ket No. 50-275/323 Nr. Robert H. Norris U.S. Geological Survey AU6 „" l;~7~ B]dg. 25 Denver Federal Center Denver, Colorado 80225 SU'~CT- Amendment (31) to Diablo Canyon lF2 Report A The following doctmmt material pertaining to review of the subject nuclear facility is b ing transmitted s parately for your information. Please notify our branch of receiving'or not receiving the subject material by returning a copy of this letter or phone (301) —492 —7258.

PSAR Volum s

,Amendment No. To PSAR Dated Amendment No. To Environ. Rpt. Dated PS'olumes Amendment No. 31 To @SAR»t~ 8-18-75 (Rec'd 8-'19-,75) Other:

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M. P. Gammi 1 1,Clii ef Site Analysis 13ranch Division of Technical Review , Office of Nuclear Reactor Regulation cket Fi e R. HcNu cn J. Osloond 4 UNITEO STATES NUCLCAB BEGUI ATOBY COMMISSION L'YASHINGTON, D. C. 20SSS

Docket No 50-275/323 R. Nr. Stan. Brockman MG 1975 U.S. Geoloical Survey 3 1 Building 25 (D3) Denver Federal Center Denver, Colorado 80225 Amendment (31) to Diablo Canyon 182 Report The following document material pertaining to review of the subject nuclear facility is b ing transmitted separately for your information. Please notify our branch of receiving or not receiving the subject material by returning a copy of this letter or phone (30l) — 492 — 7258.

PSAR Volumes

Amenchnent No. To PS'ated Amendment No. To Environ. Rpt. Dated

FSAR Volumes

dment No; 31 To PS'ated 8-18-75 Rec'. 8-19-75 Other: Amdt. sent about 8-21-75

ll. P.,ammi 1 l,Chi ef Site Analysis Branch Division of Technical Review Office of Nuclear Reactor Regulation cc- Docket File Hofmann J. Osloond

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Do L,et No. 50„275]323 Dr. Carl lien tl>orth AUG 3 U.S.G.S. 1 345 Middlefield Rd Menlo Park, California 94025 197'~~-

Amendment (31) to Diablo'.Canyon 152.'Report The following docum nt material pertaining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving'..or not receiving the subject material by returning a copy of this letter or phone (301) —492 — 7258.

PSAR Volumes

Amendment No. To PSAR Dated Amendment No. To Environ. Hpt. Dated

PSAR Volumes

Amendment No. 31 To CESAR Dated 8-,18-75 (Rec' 8-19-75$ Other: Amdt. sent around 8-21-75

t<.P. Gammill,Chief Site Analysis Branch Division of Technical Review Office of Nuclear Reactor Regulation

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4 l~ Distribution NRC PDR AUG 2 0 1975 Local PDR Docket File (2) LWR 1-3 File WPGammill JCStepp Docket hos. 50"275 RBMcMullen and 50-323 TJHirons DPAllison VHMilson RHoffman Mr. James Morris U. S. Geological Survey Engineering Geology Branch JOsloond'ear Denver Federal Center Denver, Colorado 30225 Mr. Morris: Enclosed for your review are three copies of Amendment 32 to the Diablo Canyon FSAR. This amendment supplements Amendment 31 which was forwarded to you on August 18, 1975. These amendments include most of the geology and seismology information which wa expect the applicant to submit at. this time. Sincerely,

Original Signed bg, pinn PRIT Olan D. Parr, Chief Light Water Reactors Pro3ect Branch 1-3 Division of Reactor Licensing Enclosures Amandmant 32 to the Diablo Canyon PSAR (3) .

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Distribution Docket File AUG 3O t975 NRC PDR Local PDR LVR 1-3 File WPGammill JCStepp Docket Nos 50-275 RBMcMullen aad 50-323 TJHir'ons DPAllison VHWilson RHoffman Mr. James F. Devine JOsloond Department of the Interior U. S. Geological Center, HailSurvey'ational Stop -908 South Lake'Drive Reston, Virginia 22092 3)ear Mr. Devine'. Enclosed for your review are two copies of Amendment 32 to the Diablo Canyon FSAR. This amondmoat supplements Amendment 31 which was forwarded to you on August 18, 1975. These amendments include most of the geology and seismology information which we expect the applicant to submit at this time. It is currently estimated that the remainder willbe submitted 'at the end of this month. Sincerely, Driginnl Signed by Own Parr Olan D. Parr,. Chief Light Mater Reactors Pro)ect Branch 1-3 Division of Reactor Licensing Enclosure: Amendment 32 to the Diablo Canyon FSAR (2)

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Dear Mr. McKeown: ! Enclosed for your review is a copy of Amendment 32 to the Diablo Canyon PSAR This amendment supplements Amendment 31 which was forwarded to you on August 18, 1975. These amendments contain most of the geology and seismology information which we expect the applicant to submit at'this time't is cux'rcntly estimated that the remainder will be submitted at the end of'this month. Sincerely, Original Signed by Oian Parr Olan D. Parr, Chief ~ Light Water Reactors Pro)ect Branch 1-3 Division of Reactor Licensing 'nclosure: Amendment 32 to the Diablo Canyon FSAR

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and 50-323 'JHirons DPAllison VHWilson RHoffman Mr. James Morris JOsloond U. S. Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 30225 Dear Mr. Ehrris: Enclosed for your roviev are three copies of Amendment 31 to the Diablo Canyon FSAR. This amendment contains most of the additional information regarding geology and seismology of the Mablo Canyon site which ve mpect the applicant to submit at this time. It is currently estimated that the remainder will be submitted at the end of this monthd Sincerely,

Original Signed by, Olan Parr

Olan D. Parr, Chief Light Water Reactors Prospect Branch 1-3 of Reactor Licensing'ivision Enclosures Amendment 31 to the Diablo Canyon FSAR (3)

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Dear Hr. NcKeown: Enclosed for your review is n copy of Amendment 3l to the Mablo Canyon FSAR. This amendment contains most of the additional information regarding geology and seismology of the Diablo Canyon site which ~e expect the applicant to submit at this time. It is currently estimated that the remainder Mllbe submitted at the end of this month.

Sincex'ely, ~

Original Signed by, Olan Parr Olan D. Parr, Chief Light Water Reactors Pro)ect Branch 1-3 Division of Reactor Licensing E Enclosure: Amendment 31 to Diablo Canyon FSAR

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Original Signad ipy Olan Parr Olan D. Parr, Chief Light Rater Reactors Pro)ect Branch 1-3 Division of Reactor Licensing Enclosure: Amendment 31 to the Diablo Canyon FSAR (2)

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Docket No. 50-275|'323 Dr. Carl Ment<'ts 182 Report The following domzn~nt material pertaining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving'r not receiving the subject material by returning a copy of this letter or phone (301) — 492 —7258.

PSAR Volumes

Amenknent No. To PSAR Dated

Amendment No. To Environ. Rot. Dated

FSAR Volumes Amendment No. To FSAR Dated —~HI—~ Amdt. n b

W. P. Gammi 1 1, Chi ef Site Analysis Branch Division of Technical Review Office of Nuclear Reactor Regulation cc: Docket File R..Hc u en R. Hofrgqnn J. Osloong

Villi'EO STATES NUCLEAR REGULATORY COViMISSiOM VJAS&lliVGTON,O. C. 20655

DxJ;et tx~o 50-275/323 AUG Hr. Stan R. Brockman 4 )g7g U.S. Geological Surey Building 25 (D3) Denver Federal Center Denver, Colorado 80225 -Amendment (30) to Diablo Canyon Units 152 Report

The following document material pertaining to review of the subject nuclear facility is being transmitted separately for your inforroation. please notify our branch of receiving'or not receiving the subject material by returning a copy of this letter or phone (301) — 492 —7258.

PSAR Volum s

Zmena&nt info. . To PSAR Dated Amerrhnent No. To Environ. Rpt. Dated

PSAR Volun™s

Amendment No. 30 To FSAR Dated 7-31-75 '(Rec ' 8-1-75) Other: Amdt. Sent About 8-4-75

H.P. Gammill, Ch,ief Site Analysis Brahch Division of Technical Review Office of Nuclear Reactor Regulation cc: Do-cke-i: Fi 1 e Hofmann, J. Osloond

UNITED STATES NUCLEAR REGULATORY COMiBISSION WASHINGTON, D. C. 20555

Docket No. 50-275/323 Hr. Robert H. Nor< is U.S. Geoloical Survey AUG 4 U7~ Bl dg. 25. Denver Federal Center Denver, Colorado 80225 Amendment (30) to Diablo Canyon Units 152 Report The following docIrnent material pertaining to revieI7 of the subject nuclear facility is being transmitted seoarately for your information. Please notify our branch of receiving',or not receiving the subject material by returr6ng a copy of this letter or phone (30l) — 492 — 7258. 'I PSAR Volumes

Amen@nent No. To PSAR Dated Amendment No. To Environ. Bpt. Dated

FSAR Volumes

Amendment No. 30 To FSAR Dated 7-31-75 (Rec' 8-1-75) Other: Amdt. Sent About 8-4-75

Site Analysis Branch Division of Technical BevieI< Office of Nuclear Reactor Regulation cc: Docket Fi1 e cu en

. J. Osloond e 0 f e~~

P Ig 4 +75 DXSTRIBUTXON:, ~ocket Pile NRR-RDG SAB Mr. P. A. HcZeown U,S. Geological Survey Building 25 (D-1) Denver Federal Center Denver, Colorado 80225 Dear Prank:

Enclosed are summaries of our meeting with PG & E on Pebruary 7 and the ACRS subcommittee meeting on Diablo Canyon. l apologise for not having gotten these to you sooner.

J. C. Stepp, Section Leader Seismology & Geology Section Site Analysis Branch, TR

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ROM: US Dept of In"erior DATE OF DOC DATE REC'D LTR TWX RPT OTHE R Reston, Va 22092 1-28-75 1-28-75 H W Corille TO: ORIG CC OTHER NN Gen. Gossick one signed 0 CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO: 0-2 323 D ESC R IPTION: ENCLOSURES: Ltr trans the following: Review of the geologic 6 seismologic data....

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PLANT NAME: Diablo Canyon 1 P 2 FOR ACTION/INFORMATION BUTLER (L) SCHWENCER (L) ZIEMANN(L) REGAN (E) W/ Copies W/ Copies W/ Copies W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L) W/ Copies W/ Copies W/ Copies W/ Copies PARR (L) VASSALLO (L) KNIGHTON (E) SPELS W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNQBLOOD (E) W/ Copies W/ Copies W/ Copies 9/gtoPies Pg/illC~ INTERNAL DISTR I BUTION REG FILE TECH REVIEW BENTON LIC ASST A/T IND ~SCHROEDER GR IMES R. DIGGS (L) B RAITMAN rOGC, ROOM PN506A MACCARY GAMMILL H. GEARIN (L) SALTZMAN ~@{MglNLQSTAF F KNIGHT KASTNER E. GOULBOURNE (L) ABEL CASE PAW LICK I BALLARD P. KREUTZER (E) G I AMBUSSO SHAO SPANGLER J. LEE (L) PLANS BOYD STE LLO M. MAIGRET (L) MCDONALD MOORE(L) HOUSTON ENVIRO S. REED (E) CHAPMAN ~DEYOUNG (L) NOVAK MULLER M. SERVICE (L) DUBE (Ltr) SKOVHOLT (L) ROSS >vapo, DICKER S. SHEPPARD (L) E. COUPE GOLLER (L) (Ltr) IPPOLITO KNIGHTON M. SLATER (E) PETERSON P. COLLINS TEDESCO YOUNGSLOOD H. SMITH (L) D. THOMPSON (2) DENISE LONG REGAN S. TEETS (L) KLECKER REG OPR LAI NAS PROJECT LDR G. WILLIAMS(E) EISENHUT FILE 5 REGION (3) BENAROYA V. WILSON (L) WIGG I NTON MOR R IS VOLLMER HAR LESS STEELE EXTERNAL DISTRIBUTION

1 —LOCAL 0$ C~ PDR~~es R-SAN/LA 1 —TIC (ABERNATHY) (1)(2)(10) —NATIONALLABS ~~ PD 1 — NAT LAB 1 —NSI C (BUCHANAN) 1 —W. PENNINGTON, Rm E-201 GT BROOKHAVEN — — 1 —G. ULRIKSON, ORNL 1 ASLB 1 CONSULTANTS — 1 —Newton Anderson NEWMARK/BLUME/AGBABIAN 1 AGMED (RUTH GUSSMAN) B-127 GT 1 —ACRS HOLDING/SENT Rm 1 —R. D. MUELLER, Rm E-201 GT 1

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U.S. ATOIIIO EHEROY COIIIIISSIOR 1976 General L. V. Gossick Rtylal~ JAN 38 Nuclear Regulatory Commission Ilail Scclha Washington, D.C. 20545. 0 zr 9 Dear General Gossick:

Transmitted herewith, in response to a request by your staff, is a review of the geologic and seismologic data relevant to the Diablo Canyon Site, Units 1 and 2 (AEC Docket Nos. 50-275'nd 50-323 .

This review was prepared by F. A. MCKeown and James F. Devine of the U.S. Geological Survey.

We have no objection to your making this review part of the public record.

! Sincerely yours,

irector Enclosure

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Let's Clean Up America For Our 200th Birthday V

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~ V ~ V Pacific Gas and Electric Company Diablo Canyon Site, Units 1 and 2 San Luis Obispo County, California AEC Docket Nos. 50-275 and 50-323

This is a final review of the geological and pertinent seismological data in the. Final Safety Analysis Report'(FSAR) and Amendments'l, 19, and

20 for the Diablo Canyon nuclear power plant site, Units 1 and 2. A preliminary review dated January 23, 1974, of the FSAR was transmitted to the Atomic Energy Commission by E. H. Baltz on Harch 28, 1974.

The principal considerati'on in the preliminary review was that it did not provide information to evaluate adequately an offshore fault or structural zone that had been reported in the literature (Hoskins and Griffiths, 1971) since review of the Preliminary Safety Analysis Report

(PSAR). Since the preliminary review of the FSAR the applicant and its consultants have conducted extensive geophysical surveys and made geological analyses of them to determine the offshore geology, most of which is presented in Appendix 0 of Amendment 19. Prior to the applicant's surveys the U.S. Geological Survey on behalf of the U.S. Atomic Energy Coomission had made a geophysical survey of a large part of the offshore structural zone. This information (Wagner, 1974) was open filed to the public in September 1974 and the applicant has used it extensively in Amendment 19, This final review therefore is directed mostly to evaluation of the data in Amendment 19, although all parts of the FSAR were reviewed. No field examin tion of the site was made in conjunction with review of the FSAR.

The FSAR and its amendments contain a reasonably accurate description and evaluation of a large amount of geophysical and geological data. The geologic maps (Plates III and IV, Amendment 19) offshore of the southcentral c- 1 8

1 6

California coast agree in general with the offshore geologic map of

Wagner (1974). In detail however the maps differ at many places. For

example, the trends, location, and number of faults in Estero Bay shown on

Plate IV differ from those shown in Plate I of. Wagner. A synopsis of the geology on Plates I, II, III, and IY is that the offshore Santa Haria

basin is bounded on the east and west by major fault zones. Further, both fault zones are recognized as capable within criteria of the Atomic

Energy Commission. The easternmost fault zone, called the East Boundary

zone (EBZ) by the applicant and called the Hosgri fault zone (HFZ) -by Wagner (1974), is of primary importance because it passes within four miles of the site and is about 90 miles long. /As will be outlined in another part of the review, we do not concur with the applicant's conclusion that

the current structural environment of both the off'shore and onshore areas

is dominated by vertical movements. We do concur with the applicant that the faults exposed in excavation for the site and,in the cliffs near the-

site apparently are not capable within AEC criteria. However, the age (80,000-120,000 years before present) of the youngest terrace materials was inferred by long-distance correlation of terraces (p. 2.5-33). We

accept the correlation as probable but an absolute age determination would be highly desirable. As these faults and foundation conditions have been amply documented and have not appeared to present problems that could not be managed by engineering practices, they are not discussed in this review.

Re ional Geolo The applicant's description of the regional tectonic features given in Amendment 20, (p. 2.5-7 through 2.5-13f) is quite adequate. In brief the C ) ~ I

~ 1 plant site is located in the South Coast Ranges structural'rovince which

is characterized by northwest trending structural and geomorphic features.

The applicant lists five major structural features (fault zones) in the

region around the site (p. 2.5-9, Amend. 20). These are the San Andreas,

Rinconada-San Marcos-Jolon,'ur-Nacimiento, Santa Lucia Bank and San

Simeon faults at distances of 45, 25, 18, 28, and 18 miles from the site

respectively (Table A, Amend. 19). All of these faults are considered

capable by the applicant (p. 2.50-64, 65, Amend 19). The East Boundary

fault zone at 2.5 to 4 miles from the site,is not listed as a major structural feature although it bounds the offshore Santa-f1aria basin as the Santa Lucia Bank fault does and is commensurate in size with the Santa

Lucia Bank fault. We consider the East Boundary fault zone a major structural feature.

Jn the vicinity of- the site, that is the Estero Bay-San Luis Range area, three principal fault zones. are discussed in addition to the East

Boundary fault zone (p. 2.5-13c through 13f, Amend. 20).. These are. the

West Huasna, Edna,,and San Miguelito faults at distances of 11, 4.5, and '2.5 miles from the site, respectively. Nearly all faults trend northwesterly. Highly deformed Mesozoic and Cenozoic rocks occur between the faults.

The available data do not indicate that any of these faults are

capable according to AEC criteria. The trend of the Edna fault when projected to the northwest suggests that it could possibly intersect the

EBZ in Estero Bay. The location and discontinuous style of faults mapped

in Estero Bay however by both the applicant (Plate IY Amend 19) and Wagner (1974, Plate I) do not confirm. intersection of the Edna fault with

the EBZ. As the EBZ is larger and closer to the site, consideration of

the Edna fault as a source of earthquakes is of less importance 1" ~ ~

~ 1 1 East Boundary Fault Zone

As indicated previously in this review'and by the applicant

(2.5D-9, Amend. 19) the East Boundary fault zone has been the structural feature of most interest and importance. Nearly all of the extensive geophysical explorati'ons conducted and analyzed during .the past year or so since the FSAR was first issued have been directed especially to defining this zone and its geologic relationship to contiguous features such as the

Santa Maria basin, structures in the San Luis Range, and the Transverse

Range structures projected, from the southeast. The importance of the EBZ and need to investigate it thoroughly was evident from the facts that it is less than four miles from the site, is more than 90 miles in length, and appears to have minor seismic activity associated with it. The applicant has made a commendable effort to define and explain the zone.

We concur. with the applicant's description of the EBZ and his conclu- sion that it, is a faulted zone of inflection between the offshore Santa

Maria Basin and the uplifted Coast Ranges'(p. 2.5D-37 through 2.5D-42, and

2.5D-98, Amend. 19). It appears therefore that the zone once was more closely related to the vertical tectonics associated with basin development than to transcurrent tectonics associated with plate boundaries. As recognized by the applicant, the'BZ may also be a "---part of the San

Andreas continental margin transform fault system---" (p. 2.5D-41, .Amend.19).. Such northwest trending fault zones as the''EBZ, both offshore and onshore, have been considered by others (for example, Hamilton and Myers, 1966, p. 522 and figure 2, Atwater, 1970, p. 3525) to be part of a system of faults with right lateral movement. The applicant presents considerable data and arguments to support the concept"---that the current tectonic 1 l, ~ environment in the southern Coast Ranges and .adjacent offshore region

is dominated by vertical movements associated with general uplift of the ranges." (p. 2.5D-63, Amend. 19). It is clear from the offshore seismic

reflection profiles in Appendix A as well as mapping onshore that vertical

separations of as much as several thousand feet occur in Pliocene and . older strata. Evidence of lateral separation is,less'clear, probably

because lateral separation can rarely be demonstrated uriequivocally. The

applicant concluded however that as much .as several thousand feet of lateral

displacement may have occurred on the EBZ throughout.its history (p; 2;SD-41,

Amend. 19). Evidence of lateral slip on the EBZ has been given by Wagner

(1974, figure 13, p. 7). Similar evidepce is apparent in figure 5A

(Appendix A) and,sections B-B',, and D-D'late VII,.where marked changes in

thickness of acoustical units occur across faults and reverse sense of

movemen't on the same fault is shown. Also, the San Simeon fault, which is considered the eastern boundary of the northern part of the Santa t1aria basin is reported to have about 1500 feet. of lateral. displacement.

Incomplete fault plane solutions (Smith, 1974) are. used .by, the applicant in

an attempt to demonstrate the dominance of vertical movements. All three solutions given by, Smith however'ave signifi'cant later'al components to the inferred fault mechanism. Additional seismological evidence that Coast

Range faults currently have lateral movement on.-them is given'y Greene

and others (1973, Sheet 2). These authors show on Sheet 2 predominant right-lateral movement in fault plane solutions of'arthquakes in Yonterey

Bay near projections of northwest trending Coast Range faults..

As (1) nearly all of the evidence of lateral movement is in the youngest rocks, some of which may be Post-Misconsinan (Wagner, 1974, p. 13) C I ~

I 1 ~ and'(2) the mechanism of current earthquakes has a significant component

of lateral movement, vertical movements may now be a subordinate component

on faults in the EBZ as well as other major faults in southcentral coastal Cal iforni a. Conclusions

We conclude from the evidence in the FSAR and literature that large

vertical displacements occurred in the EBZ, mostly during the late Miocene

and -Pliocene when the offshore Santa Maria basin was most actively developing.

Most current tectonic activity however -is causing as. much or more lateral=

as vertical displacement on northwest trending faults in the Coast Ranges

and offshore region. Both the East Boundary zone and Santa Lucia Bank

fault zone may have a first order genetic relation to the Santa Maria basin

and consequently are not regional in the sense that they do not transect

structural provinces such as the Transverse Ranges as the San Andreas

fault does. They should be considered inextricably involved, however, with the strike-slip fault mechanics of plate boundary motions that are

currently concentrated along the San Andreas fault. Earthquakes along

the EBZ presumably would not be as large as expected on the San Andreas

fault; however, from the information presently at hand we can find no

evidence that would preclude the occurrence of an earthquake as large as events characteristic of subparallel strike slip faults, which bound

basins, such as the Santa Maria, in the San Andreas system and which do not.transect structural provinces. 7 C

S ~ I ~ ~ ~ ~

~ 1 ~ ~ ~ ~ V V V

The portions of the Final Safety Analysis Report and Amendments ll, 19, 20 of the report entitled "Analysis of Offshore Seismicity in the Vicinity of the Diablo Canyon. Nuclear Power Plant" and"--

the Pacific Gas and Electric Company letter dated December 27, 1974, concerning seismic response and its enclosures have been reviewed.

The seismological aspects of this site were previously investigated

by the applicant and a review was prepared by the Seismological Division of the Coast and Geodetic Survey (since changed in organiza- P

tion in the National Oceanic and Atmospheric Administration) dated . September 21, 1967.

As evidenced by the previous discussion of the Geology, a large

amount of new data has been developed offshore from the plant site.

The; interpretation of these. data, as previously discussed, necessitate

the placing of a moderate to large earthquake on either the East

Boundary Zone or the Santa Lucia Bank faults. The applicant, in

Amendment 20, has addressed the significance of this interpretation

and has indicated a "potential for large earthquakes involving faulting over distances in the order of tens of miles: Seismic activity at this level can occur'along offshore faults in the Santa Lucia Bank region (the likely source of the Magnitude 7.3 earthquake

of 1927)...." Elsewhere in the FSAR is stated "The East Boundary

zone is considered to be seismically active...." ~ Our opinion, is I based on these statements and the current necessity of considering

these two structures as having similar seismic potential.

Due to the lack of instrumental data from sites within 10 km

of the surface expression of a fault, it is difficult to describe the ~ ~

~ ~ ~ maximum acceleration, or velocity that would be recorded in this

nearby zone. In addition, the correlation of any'of these parameters

with damage is suspect in the near zones. On the other hand, there

are numerous incidents of structures, extremely close to the fault

undergoing movement and experiencing earthquakes, that experienced

little or no damage. Also, it is apparent that the maximum peak acceleration does not continue to climb as one approaches closer to

and reaches the fault break or as one postulates larger and larger

earthquakes at 'a given point on the fault.

The efforts by the applicant to consider the effects of earthquakes on existing records of strong motion from sites near to the earthquake fault in terms of the frequency content of the response spectra

are worthwhile. However, a question of transferability still remains

> (the .size of the event. in one case and the distance in another). Nevertheless," this analysis when used to match peaks of the- spectra

(nearby and more distant sources) to the response of critical com-

ponents is in our opinion an important technique for assessing

potential damage.

However, in conclusion, we believe that with the limit.of the

present information as to the interpretation of the relationship of the, East Boundary fault to the Santa Lucia Bank fault, an earthquake similar to the November 4, 1927, event but occurring along the East

Boundary Zone or the Santa Lucia Bank fault zone represents the maximum earthquake that is likely to occur near to the site. This event is in addition to the maximum earthquakes considered in the Construction Permit evaluation and subsequent hearings and reviews. As long

8 'I ~ ~ t; 4

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~ ~ 'as this interpretation remains valid, it is our opinion that the

design value of 0.5 g used as a zero period acceleration in the development of the appropriate response spectra is inadequate. References

Atwater, Tanya, 1970, Implications of plate'tectonics for the Cenozoic

tectonic evolution of western North America: Geol. Soc. America

Bull., v. 81, p. 3513-3536.

Greene, H. G. and others,,1973, Faults and earthquakes in the Monterey

Bay region, California: U.S. Geol. Survey map MF-518.

Hamilton, ll. and Myers, M. B., 1966, Cenozoic tectonics'f the liestern

United States: Reviews of Geophysics, V. 4, no. 4, p. 509-549. Hoskins, E. G., and Griffiths, J. R., 1971, Hydrocarbon potential of

Northern and Central California offshore: Am. Assoc. Petroleum

Geologists Memoir 15, p. 212-228. Smith, S.=-ll.; -'1974, Analysis of Offshore Seismicity .in the vicinity

of the Diablo Canyon Nuclear Power Plant. Report to Pacific Gas

and Electric Company.

llagner, H. C., 1974, Marine geology between Cape San Martin and Pt. Sal

South-Central California Offshore: U.S. Geol. Survey open file report 74-252. r k %I

~ ~ k gal.''" < ~ Cy. UNITED STATES JPf') p ]915 ATOivlIC ENERGY COiMiVIISSION WASHINGTON, D.C. 20545 rr~ 0 '4tCg 0>-

Docket No 50-275/323 ~..F: A. Y~eown U. S. Geological Survey Building 25 (D-1) Denver Federal Center Denver, Colorado 80225 Subject: Diablo Canyon Suhnittal on.Requested Seismic Response

The following document material pertaining to review of the subject nuclear facility is enclosed for your informatiu«. Please notify our branch of receiving or not receiving the subject materiel by returning a copy of this letter or phone (301-973-7258).

PSAR Volumes

Amendment, No. To PSAR Dated'o

Amendment No. Environ. Rpt. Dated

FSAR Volumes

AR ndment No. To PSAR Dated Other: Subject plant information received 12/30/74 on seismic res ' ical Design Class I structures and nxnponents — usin modified input r and damping values in MC Reg. Guide 1.61.

W. P. GaInnill, Chief Site Analysis Branch Directorate of Licensing

'nclosure: As Stated cc- w/o Encl. Docket File J. Stepp J. Osloond 0 I JAB 7 1975 ~gI,IIGI r UiN!TEO STATES ATOMIC ENERGY COMMiSSION

.pb WASHINGTON, D.C. 20545 r„ zo~ '~1tgI 0I--.

Docket No. 50-275/323 Mr.. James Devine Hail Stop 905 U. S. Geological Survey National Center Reston, Virginia 22092 Subject: Diablo Canyon Suhnittal on Recpested Seismic Response

The following document material pertaining to review of the subject nuclear facility is enclosed for your information. t't 'Please notify our branch of receiving or not receiving the subject material by returning a copy of this letter or phone (301-973-7258).

PSAR Volumes

Amendment No. To PSAR Dated''

Amendment No. To Environ. Rpt. Dated

FSAR Volumes

Amendment No. To PSAR Dated Other: Sub'ect lant informatio response of typical Design Class I structures and ccmponents —using mxLified in ut res nse tra 'd

N. P. Gamrnill, Chief Site Analysis Branch Directorate of Licensing Enclosure: As Stated

cc: sv/o Encl. Docket File + J. Stepp J. Osloond

UNITED STATES

ATOMIC ENERGY COMMISSI i WASHINGTON, D.C 20S45 ea g rd ~~III DEC 81 $74 Docket No. 50-275/323 Dr. Carl Vent@orth USGS 345 Middlefield Road Menlo Park, California 94025

Subject: DIABLO CANYON FINAL SAFETY ANALYSIS REPORT AND AMENDMENTS

The following document material pertaining to review of the subject nuclear facility is being transmitted separately for your information. Please notify our branch of receiving or not receiving the subject material by returning a copy of this letter or Phone (301-973-7258).

PSAR Volumes

Amendment No. To PEAR Dated

Amendemt No. To Environ. Rpt Da.ted

FSAR Volumes

Amendment No. 1-22To FSAR Dated l .Other: Subject material sent about 12/31/74, as requested by Mr. Fred Houser.

Site Analysis Branch Directorate of Licensing. cc. ocket File F. Houser R. McMullen J. Stepp J. Osloond 0 gg%Cl

~+) UN1TED STATES 0 ATOMIC ENERGY COMMlSSlON WASHINGTON, D.C. 20545 0 ~~fES DEC 3 g 1974 Docket No. 50-275/323 ~ + Dr. Carl Wentworth USGS 345 Middlefield Road Menlo Park, California 94025

Subject: TEKNEKRON, INC. REPORT FOR DIABLO CANYON PLANT

C The following document material pertaining to review of the subject nuclear facility is enclosed for your information. Please notify our branch of receiving or not re'ceiving the subject material by returning a copy of this letter or phone (301-973-7258).

PSAR Volumes--

Amendment No. To PSAR Dated''

Amendment No. To Environ. Rpt. Dated

FSAR Volumes

Amendment No. To FSAR Dated

Other: Report entitled "Anal sis of Offshoie S ?

Diab'lo Canyon Nuclear Pow'er Plant" b Stewart" S

W. P. Gammill, Chief Site Analysis Branch Directorate of Licensing Enclosure: As Stated cc: w/ encl. acket File F. Houser R. McMullen J. Stepp J. Osloend ~ g ' NRC FORM 195 - - V.S. NUCLEAR REGULATORY COMIt"MION DOCKET NUMBER ,„'2i'ISI .o I z t$ FILE NUMB B DISTRIBUTION FoR PART 50 DOCI(ET A1ATERIAL NRC COrI N cl / +w n FROM: DATE OF DOCUMENT Hr Gammill US Dept'pf Interior 12-24-75 Reston, Va DATE RECEIVED F N Houser 12

O'LETTER LINOTOR IZE D PROP INPUT FORM NUMBER OF COVIEStRECEIVED ABORIGINAL ISVr CLASsIFIED II$ICOP Y /)onr ~ h I DESCRIPTION ENCLOSURE

Ltr trans the following: Draft review of Amdts 31, 52, & 34 of the FSAR .....with regard to geology'.....

ITEN REC"D FOR DXST IN DISTRIBUTION SECTION 2-17-76.

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'lABLO CANYON 1 & 2

SAFETY FOR ACTION/INFORMATION 7-7b ehf ASSXGNED AD; n ASSXGNED AD : BTlANCH CHIEF: BRANCH CHIEF ~ PROJECTASST'NVXROIIANAGER: PROJECT IIANAGER: LXC~ LIC~ ASST, $ .

INTERNALD IST R I BUT ION G FILE N~STEHS RO ~ ~ E ST X&E ~MRQEDZR. BENAROYA A+LARD ~D LA+ SPANGLER GOSSXCK & STAFF ENGINEER N IPPOLITO $ SITE TECH GAMMILL CAgr. KNIGHT OPERATXNG REACTORS INTEGER IMIR SXINEXL STELLO STEPP PAW ICKX HULMAN LI 3 OPERATXNG TECH PROJECT MANAGEMENT REACTOR SAFETY EXSENHUT SITE ANALYSIS BOYD ROSS SHAO VOLLIIER P, COLLXNS NOVAK BARR BUNCH HOUSTOii ROSZTOCZY SCHIPENCER J, COLLXNS PETERSON CIIECK GRXHHS NELTZ HELTEIIES AT & I SITE SAFETY & ENVIR SKOVHOLT SALTZHAN ANALYSIS RUTBERG DENTON & I~iULLER EXTLIENALOISTRIBUTION CONTROL NUMBER LPDR ScC,~~~~pu NATL LAB BROOKI VEN NATL LAB TIC REG V-XE ULRIKSON(ORNL) N~SC LA PDR ASLB CONSULTANTS ~CD QSEI, r NBC FORM ISS (2-76) tg

~ ~ ~ ~ ~ United Sta.tea epartment oE the Interior GEOLOGICAL SURVEY WV~ pP RESTOb/, VIRGINIA 2209'2 W~) e"

December 24, 1975

' ~EGg/ -. w 9ECE

Enclosed is a draft review of the Amendments 31, 32 and 34 of the -'FSAR for the Pacific Gas and Electric Company's Diablo Canyon site, Units 1 and 2, San Luis Obispo County, California, Docket Nos. 50-275 and 50-323. This review was prepared by Frank A., HcKeown, who reviewed the geology,.and James F. Devine, who reviewed the seismology., Hr. HcKeown was assisted by Holly Vagnex, David HcCulloch, and Robert Yerkes; Hr. Devine was assisted by Robert Page and Wayne Thatcher.

Me are transmitting this draft to provide a basis for discussions at our planned meeting in Bethesda on December 30. Sincexely yours, T --E- u< Fred N. Housex Deputy Chief Office of Environmental Geology Enclosure

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(9g I ~ ~ 1 ~ F. A. HcKeown (Geology), J. F. Dgiine (Seismology)'iablo ~yon . ~ ~ FSAR Amendments 3l, 32 and 34 I

~ ~

PACXFXC GAS AND ELECTRXC COHPANY DIABLO CR~TYON SITE, UNXTS 1 AND 2 SAN LUXS OBISPO COUNTY, CALIFORNIA AEC DOCKET NOS. 50-275 KID.50-323

'Geology and Seismology

i'his is a xeview of the geological and seismological information contained in Amendments'31, 32, and 34 of the Final Safety Analy'sis

Report (FSAR) for the Diablo Canyon nuclear power plant site. Amendment 37, containing important discussion of the ground response pertinent to

seismicity, was received in eaxly November and too late to he considered

in this review. The amendments were prepared by the Pacific Gas and

Electric Company (PGRE) .in response to a request in a letter dated February 12, 1975, from the Nuclear Regulatory Coa~ission (NRC),fox t ~

, 'k certain additional iriformation relevant to design basis earthquake

' issues, which have been the principal problems requixing additional i eaxth sciences information and analyses. To support assertions in the FSAR thxough Amendments ll, 19 an'd 20, five'equests for information (referred to as questions in the Amendments) were made. "

2.17. Prov'ide additional discussion and arguments for determining the maximum earthquake that can be expected on faults of various ranks within the San hndreas system. Relate the discussion to historic seismicity. 2.18. Provide. additional documentation, including seismic x'cflcction 'rofi'les, on the intcrs'ection of the flosgri fault.zoic with 'thc Transverse Range faults. Include geologic maps south«ard of those provided in the FSAR showing the structural relation- ships of the Transverse faults and structures having a northwest trend. 4 ~ p Provide additional documentation, including seismic profiles, on the northern roaches of thc i!osgri'ault zone. Include a fuller dcvclopmcnt of >our views on thc structural relationship of the 1!osgri Sault to thc San Simeon fault.

2. 20. Provide additional information on the location of .tho 1927 event, together with its probablo mechanism. Discuss probable relationships of this cvcnt to thc geologic structure in the region.

2.21. Provide your evaluation of the maximum credible earthquake on thc.l!osgri fault zone. Assuming this event occurs along the segment of the Flosgri fault zone nearest thc site, evaluate its'esponse spectrum at the site and compare it with thc design xesponso spectrum.

The response in the CESAR 'to the questions has provided considerable

additional geologic and seismologic information and analyses.

However, unambiguous answers to the questions haVe not been achieved. Hany uncertainties in the data and interpretations still exist. Among the most important of these are: l) the loc tion and mechanism of the 1927 earthquake, 2) the exact'relation of the

"Elosgri fault zone to faults in the Transverse Range s)stem and the 'San Simeon fault, 3) the continuity of some faults, 4) the relative amounts of dip-slip and strike-slip movement on the ifosgri fault ."one, 5) the sense of displacement on parts of the ilosgri zone, 6) identification and correlation of acoustical units, and 7) kinematic relations among different fault zones.

In addition to these uncertainties, some information'hown on the

I profiles is not shown on the maps and vice versa, and some profile data are not included that are important to evaluate the extension or character of some faults. Because geologic maps developed from seismic % ~ ' ~ ~ r reflection pxofiles are based upon much interpretation that may differ among several intexpxeters, it was necessary fox the purposes of our review to make independent interpretations of the seismic profiles. These independent interpretations are somewhat different tnan the

interpretations presented in Amendments 31 and 32. The major differences axe briefly described in appropxiate sections of this review.

Although some changes in, and additions to, geologic and seismol'ogic

details have been made in Amendments 31, 32, and 34 compared with

px'evious data .in the FSAR, no major changes can be made in our conclu-

that were stated in the review of the FSAR, and Amendments 'ions

11, 19, and. 20, which was transmitted to the NRC from the Director

of the United States Geological Survey by letter.,of January 28, 1975.

The pertinent statement in our previous conclusions was as follows:

"Earthquakes along the EBZ presumably would not be as large as expected on the San Andreas fault, however, from the information

presently at hand we can find no evidence that would preclude the occurrence of an earthquake as large as events characteristic of subparallel strike slip faults, which bound basins, such as the Santa

V . hfaria, in the San Andreas system and which do not transect structural, provinces." The size of an earthquake on faults tha't bound basins s'as not specified in this conclusion. For reasons stated in subsequent

1 As defined in the FSAR, EBZ refers to the East Boundary fault zone, which is the Hosgxi fault zone. \ ~

C

~ V A% parts of this review, however, the magnitude of the design basis

caxthquake for the Diablo Canyon nuclear reactor site should be in

the range of 7. 0 to 7.S and located on the Ilosgri fault "one. This is based principally on the fact that-the Ni'ovcmbcr 4, 1927, earthquake

'ad a magnitude of 7.3 and that the best estimates of its location indicate that it could have occurred on the Elosgri fault. e Selected comments important to an evaluation of Amendments 31,

32, and 34 are outlined below.

Amendment 31

ITIC Question 2.18

On figures 8 and 9 relative displacement on 'the Elosgri fault

between Point Buchon and Point Sa" is sho~ to be down. on the east.

On figure 10 relative displacement on, the southern extension of the Hosgri fault south of Point Sal is down on the west, which is compatible. with the argument that the Hosgri fault is the east boundary of a portion;

of the Santa Haria Basin. Changes in direction of relative movement,

C howevei, are very suggestive of lateral displacement, which may have occurrred after development of the basin and bounding faults..

On page 9,. reference is made ~o fig. 11 as evidence that no scarp-formxng seismic events have occurred on the southernmost part of the Ilosgxi fault since prior to the Nisconsinan stage of the Pleistocene. It is true that no offset of the ocean floor is evident on fig. 11. IIowcver, close inspection of fig. 11 shows offset of the post-h'isconsinan unconformity when sighting along it or placing a

h le J~ 5

"''straightedge along the m ped trace. Also, faulting of .ie post-

Wisconsinan sediments cannot be precluded because a change in acoutical

signature is evident across an upward projection of the fault shown.

in figure ll. The change in the acoustical signature of unit A2

across the fault is quite clear and may be evidence of lateral

movement on the fault. a Xt is not clear from the profiles in figures 13a and 13b that the disturbed zones in them that are inferred to represent the liest EIosgxi fault axe the same. At least three additional faults can be inter-,

pxeted in the profile of figure 13b. Also a disturbed zone appeaxs

to be between stations 133 and 136 in the profile of line 13a.

Kelez, Bartlett, and Polaris survey'ines criss-cross this area and

additional evidence from them to support or negate the suggested

~ ~ ~ correlation of disturbed zones should be demonstrated. An independent interpretation of the seismic profiles in the offshore area from about Point Sal to about five miles south of Point Arguello indicates that the Hosgri fault extends at least five miles south of Point Arguello and does not turn eastward as suggested in Amendment 31.

Although the Lompoc fault zone appears to have offset the sea Hoor, and may therefore be considered capable of movement again, its length of only about eight'miles as inferred by the applicant appears

to be incompatible with a magnitude 7.3 earthquake. An independent ! interpretation. of the'seismic profiles in the area of the Lompoc fault differs from that of the applicant, in that it shows that the Lompoc l 4

~ V We 'ault zone is about twenty-miles long; the longest single fault in .the zone is. about fifteen miles in length. lbrthexmore, the displace- ment is dip slip or possibly oblique slip, xathex than reverse slip as suggested by the applicant.

NRC Question 2.19

As noted in the previous section the sense of.displacement on

the southern part of the Hosgxi fault is up on the 'west side, figure

1 (H), and therefoxe is not compatible with its being primari.ly xelated, to basin development. However, an alternative interpretation

suggests the displacement on the Elosgri fault in figure 1 to be do~ on the west.

Figure 1 (H) has three buried faults not shown on Plate.X. 'his

leads to questions concerning the interpretation of some of the data in the report.

instance of4'nother faults shown in profile but not on a map is

seen from comparison of fig. 4 (H) and Plate X. The correlation of

faults between -Lines 16 and 12 (figs. 3 (H) and 4 (H)) is questionable. I A.profi.le along Line 14 would help. Also, an interpretation of Line 10 should be included. Although the straight coast line between Cambria and Point Estero- suggests that thc extension of the San Simeon fau1t is just offshore; data are lacking to prove this. Hone of'the data presented in

Amcndmcn't 31 preclude the San Simeon fault from intersecting the Hosgri fault offshore between Cambria and Point Estero. The two

faults even as shown on Plate II (N) are less than 2.5 miles apart. ~ V 0i ~ ~

and could very »ell be tectonically coupled to each other by an en echelon or anastomosing series of faults which is characteristic of faults in the coast ranges.

Figs.'a (N) and 7b (N) are very puzzling. They show an inflection

in the seafloor over the Hosgri fault, and a drastic change in the

thickness and acoustical signature of unit A2, assuming A2's correlative with A2. ln addition to vertical dis}placement, lateral displacement, »hich is not mentioned, could be interpreted from these r profiles. However, the basis for separating A2'rom A3 is not apparent. Similarly it is not apparent why unit A,.east of the fault, is terminated. It appears to continue to the east'dge of .these pxofiles.

On figure lla (N) the A2 unit east of the fault at station 119 is

correlated with the Monterey formation (p. 8, NRC Question 2.19,

amend. 31), but the signature of the A2 unit west of this fault is completely different. This lithologic change, as elsewhere, suggests lateral displacement.

NRC Question 2.20

and Nest Hosgri On page 10 it is reasoned that both the Hosgri faults can be eliminated as sources of the 1927 earthquake because neither the sea floor nor the post-Nisconsinan unconformity are offset in the epicentral area of. the earthquake. This reasoning is not satis- factory because typically surface rupturing of a fault is discontinuous,

and offset may not be detected if the displacement had a large lateral

component. Furthermore, as stated on page 4 of this review, the base of post-Misconsinan sediments is offset, and a fault in the sediments I ~ ~ g

cannot be precluded in figure ll. The evidence, therefore, to eliminate the Hosgri fault. as the source of the= 1927 earthquake is inadequate.

As previously stated, the length of the Lompoc fault shown by the applicant

appears to be incompatible with the magnitude of the 1927 earthquake.

Figure 1 shows that segments of the Hosgri fault zone, the Lompoc

fault, Purisima fault, and Lion's Head fault occur within the error

circle of Gawthrop and error ellipse of Engdahl for the 1927 earthquake.

However, all of the faults are outside of the area designated by Smith

as the "inferred distribution of aftershock sequence of the 1927

earthquake." The 1927 earthquake, 'therefore, cannot be unequivocally located on any one of these faults. The Hosgri fault, however, is

closer to the center of the estimate of error than the other faults and, therefor'e, must be considered as a possible fault on which to locate the earthquake.

Amendment 32

NRC Question 2.17

Although-this section contains descriptions and explanations of the "—kinematics of structural behavior in the south-central California region —-" contemporary seismic activity is -not fully explained. Also, we do not agree with some statements given as fact. For example, on page 2 it is stated as fact that the 1927 H.7.3

earthquake occurred on the Lompoc fault. This is not fact but a

highly controversial. assumption. Item 2 on page 2 of this

amendment indicates that the Lompoc and San Andreas are the V ~ '1 ~ only. faults in the southern Coast Ranges that "reflect substantial

late quaternary surface deformation." As defined on page 3 of this

amendment,."substantial" clearly includes thc San Simeon fault, which

as stated on page 6 of this review may bc coupled with thc- Hosgri fault.

The attempt to explain the large magnitude by using the logic that the

Lompoc'fault is in a transition zone between thc Coast Ranges ~nd

Western Transverse Ranges applies to other faults in the zone including

~ the southern part of thc Hosgri fault.

Amcndmcnt 34

NRC Question 2.21

The maximum credible earthquake of 6 1/4 - 6 1/2 on the Hosgri

fault zone used in this section to derive pea}; site ground acceleration

is unacceptable because as stated previously the 1927 carthqual;e with 'a magnitude of 7.3 cannot be precluded from having occurred on 'the Hosgri fault.

Cdnclusions

Although the FSAR includes a considerable amount of new informa-

tion and analysis, the only change that can be made in the

original conclusions transmitted to the NRC on January 28, 197S, is to be more specific in our estimate of the design basis earthquake. This is based upon the following facts and judgments.

1. The Hosgri fault zone i's niore than 90 miles long and may even be tectonically coupled to the. San Simeon fault as they arc within 2.5 I 4 t J

~ EI

~ 8 wan ~

', 10

,'+ miles of each other and both form parts of the eastern boundary of the

~ Santa.Feria basin.

2. Marked changes in thickness and signature of acoustical units across the Ho'sgxi fault zone in several profiles indicates evidence of

lateral slip. This was noted in our review of January 28, 1975, but such

. changes are even more abundant in the profiles of Amendment 31. Right

lateral movemcnt is reported for thc San Simeon fault. These data suggest that displacemcnts on thc Hosgri fault are related to thc

highly active San Andrcas plate-boundary system.

3. The length of the Lompoc fault appeaxs incompatible with the.

magnitude of the 1927 earthquake.

4. The Hosgri. fault is closer to the center of the estimates of

error of.'both Engdahl and Gawthrop than any other fault. Xt is there- fore a possible source of the 1927 earthquake. 5. Equivocal evidence related to vertical displacement on the Hosgri fault in the epicentral area of the 1927'arthquake does not eliminate I 'it as a source. Surface fupture is generally discontinuous, and if lateral slip occurred, it probably would not be detected. Offset of the base of post-8'isconsinan sediments and probable faulting of them is evidence of post-Pleistocene movement.

For the above reasons and discussions given in the review, we t conclude that the 1927 earthquake could have occurred on the Hosgri

fault and that a similar earthquake with a magnitude in the range of 7.0 — 7.5 could occur in the future anywhere along the Hosgri fault. C

'.Il ~ CP1 o

11

6. Me repeat our opinion that, for sites within 10 km of the surface

expression of a fault, the description of maximum earthquake ground

motion by means of a single acceleration value and a standard response

ll spectrum may not be an appropriate representation of the ground motion

for design purposes. However, if a single acceleration value is to be designated by extension of the existing strong motion data base, the

0.5 g acceleration offered by. the applicant is .inadequate for representing .

a magnitude 7.0 to 7.5 earthquake at a point on the 1losgri fault nearest

the plant site when used in conjunction with a conventional analysis.

The appropriate value should be developed in association. with a response spectrum taking into account the proximity of the fault, site conditions

and the estimated larger earthquake than the magnitude 6 1/3 — 6.1/2 used

by the applicant in these studies. ~ ~ ~ W ~

f ' o Ic:AIL 'TOMIC Eiw RGY COPdM lkerM'al VJASHlYGTOih. D.C. «3545

gee a < Docks t .'o: 50 275/323

,I Mr. Fred A.,Houser Department of the Interior U. S. Geological Survey National Ctr, Mail Stop 908 12901 Suniise Valley Drive Reston; Virginia 22092 Amendment (19) To Diablo Canyon Report I'

e

P The following document. material pertaining to reviewer of the subject nuclear facility is being transmitted separately for your information.

~ ~

PSAR Uolumes

Anendeeat No,. Ta PSAR Dated Dated, "AmendsOTHER'S nt No. To Environ. Rpt. PSAR Volumes

Amendment Ho. 19 To CESAR Dated.ll/1 74 Reed. I Two more cpys. of amdt. sent about 12/10/74 as you requested.

'M. P. Gammi3,1, Chief

Swl.e''.nalys3-s Br -'c ~ DL.L e.c to etc 0 I.icensin~q

cc:~o cke t F ile J ~ Stepp R. McMullen J. Os'oond

Distribution: Docket File LNR 1-3 Reading DEC. O~ 1974 LNR 1-3 File AEC PDR Docket Nos. 50-275 Local PDR and 50-323 NPGammill JCStepp, RE4Mullen TJHirons DPAllison VEfilson m'. Frank McKeown RHoffman U. S. Geological Survey ODParr Ehgineering Geology Branch Denver Federal Center Denver, Colorado 80225

Dear hk. McXeosrn: Copies of a report entitled, "Analysis of Offshore Seismicity in the Yicinityof the Diablo Canyon Nmlear Power Plant," were sent to you and Mr. Stan Brochnan separately on December 3, 1974. This report is referenced in Appendix 2.5D subnitted in Amendment 19 to the Diablo Canyon Final Safety Analysis Report (FSAR), and in Section 2.5.6, submitted in Amendment 20 to the FSAR.

Amendments.19 and 20 to the FSAR were sent to you with my letters of november 1, 1974 and Rnrenber 4, 1974. As mentioned, in those letters, we would appreciate receiving your evaluation of the geology and. seismology submittals by January 3, 1975. Sincerely,

Original Signed by O. D. Parr Olan D. Parr, Cid.ef Light Water Reactors Project Branch 1-3 Directorate of Licensing

cc: See page 2

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Hr. Robert 1L Yarris U. S. Geological Slavey Building 25, Federal Center Denver, Golorado 80225

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Docket i:o =" 50-275/323

Mr.- Stan Brockman . U.S..ideological Survey Building 25 (D3) Denver Federal Center Colorado 80225'enver,

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I h Sub ject: Amendment .(-20) to Diablo Canyon Repo'rt.

2 The -folloving document. material per'taining Fto revx,em: o f the. subject nuclear facility is b e ing transmitted. I E ' separately for your information 'I I

'

F= PSAR Volumes AhhonIiooot No. To PSXR DaOoB

Amendment No. To Environ. Rpt. Dated. ' J\ PSAK Volumes 'Nov. Amendm nt Ho. - To ~ PSAK, Dated. 8i,1974 !- h E - -1974 'I oTHER: Amdt.. s ent approx. Hov. 13, r

F M. P..Gammill, Chief-- Site s'naalysLs '- Bxcnchh Direc torate of Licensing

Docket File R. McMullen cc: R. Hofmann J. Osloond

UNITED S:A TM i>) IC Kid iwG C COMMISSION VJASHINQTOIY. Q.Ci 235 5

~ :.> - . ~ ~ -: vi Docket i o. 50-275/323 Hr. Robert '. ltorris U'.S. Geol ogi cal Survey-"- B) dg. 25, Federal Center Denver,. Colorado - 80225

t t

I

Subject: - Amendment-..(20) to Diablo Canyon Report ',-. 'I *

Il I The following document. materi to'eview al pertaining ' of - tha subject nuclear fac" lity is,. b e ing transmit ted n separately for your .informati ll =

PSAR Volumes / Amendment No. To PSAR Dated i P Amendm nt Ho. To Environ. Rp t. Dated 0 II

CESAR Volumes I '20 -. -..'"".--.' Amendment Ho. To CESAR, Dated.- .1,974 i '- o E R.Amdt. se nt '-approx. Nov. 13,- 1974

P Gammill, Chief. Sate ~-nalysx,s E-cn"~ Directo- te of Licensing

Docket File R. HcNullen R. Hofmann J. Osloond

Distribution'ocket Fi1 LWR 1-3 Reading LWR 1-3 File ABC PDR Docket Nos. 50-275 Local PDR and 50-323 NOlJ'4 l974 WPGammill JCStepp RBMcMullen

rr TJHirons, . DPAllison Mr. Prank McKeown VHWi1son U. S. Geological Survey Engineering G'eology Branch Denver Federal Center Denver, Colorado 80225

Dear Mr. NcKeovm:

- Enclosed for your review is, a copy of Amendment 20 to the Diablo Canyon PSAR, This amendment contains revised material for Section 2.5 of the Diablo Canyon Pinal Safety Analysis Report.

As mentioned in our letter of November 1, 1974, we would appreciate receiving your evaluation of the geology and seismology submitt'als by January 3, 1975.- Sincerely,

O«84ai 8igaad by Clan Pa27

Olan D. Parr, Chief Light Water Reactors Project, Branch 1-3 Directorate of Licensing Enclosure: 20'mendment to, , Diablo Canyon„FSAR

OffICE~ L:LWR 1~ L:QlQg-3 SURNAME~ TJHironQt1s ODParr /74. OAT@~ 11/g 11/g,f/74 orm ABC 3!8 IRev. 9.53) AECM 0240 OP@ Cdd Id dl40d S 44d d'70 j +~K g jet ~.n i „'1 «'4 '» k f .«~~»'.)f»('K« .K t» * \, *,„ . Kt

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Enclosed for your review are 2 copies of Amendment 20 to the Diablo Canyon FSAR. This amendment contains revised material for Section 2.5 of the Final Safety Analysis Report.

As mentioned in our letter of November 1, 1974, we would appreciate receiving your evaluation of the geology and seismology submittals by January 3, 1975.

F Sincerely,

Origin'.I -" oR-'S bX O],En PQIT Gian D. Parr, Chief Light Water Reactors Project Branch 1-3 Directorate of Licensing Enclosure: ,- Amendment 20 to', Diablo Canyon FSAR

LWR OFCICS~ L: L:L1% 1-3

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Enclosed for your review are 3 copies of Amendment 20 to the Diablo Canyon FSAR. This amendment contains revised material for Section 2.5 of the Diablo Canyon Final Safety Analysis Roport. As mentioned in our letter of November I, 1974, 've would appreciate xeceiving your evaluation of the geology and seismology submittals by January 3, l975. ,Sincorely,

Original Signa/ Parr by'lan Olan D. Parr, Chief Light Water Reactors Pro)ect Branch 1-3 Directorate of Licensing .Enclosure: Amendment 20 to -Diabl'o Canyon 'FSAR

L:LNR L'LWR 1-3 '%~

SURNAME~ TJHiro . ls ODParr 11/~g/74 0AQE+ ll/yy/74 Form ABC3fN IRov. 9-53) AECM 0840 oprr c44 10 or45&l 44o ohio It tl ~ ~ I >

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Enclosed for your review aro 2 copies of Amendment 19 to the Diablo Canyon FSAR. This amendment contains PG5E's geology-seismology report and, in particular, a discussion of the offshore faults in the vicinity of the Diablo Canyon site. In order to maintain our licensing review schedule for Diablo Canyon, we would appreciate receiving your evaluation of this report by January 3, 1975. Yours truly,

Ortglnal Signed by O. D. Parr Olan D. Parr, Chiof Light Mater Reactors Pro)oct Branch 1-3 Directorate of Licensing Enclosuro: Amendment 19 to Diablo Canyon FSAR (2)

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' -Distribution: Docket Fil'e LNR 1-3 Reading LNR 1-3 File AEC PDR Local PDR Docket Nos. 50-275 N01t 0 1 1974 and 50-323 NPGammill JCStepp RBMCMullen TJHirons Mr. Frank McKeown DAllison VHNilson U. S. Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 80225

Dear Mr. McKeown:

Enclosed for your review is a copy of Amendment 19 to the Diablo Canyon FSAR. This amendment contains PG5E's geology-seismology report, and in particular, a discussion of the offshore faults in the vicinity of the Diablo Canyon site. In order to maintain our licensing review schedule for Diablo Canyon, we would appreciate receiving your evaluation of this report by January 3, 1975. Yours truly,

'priglnal Signed bg p. D. parr Olan D. Parr, Chief Light Nater Reactors Project Branch 1-,3 Directorate of Licensing Enclosure: Amendment 19 to Diablo Canyon FSAR

OFFICE~ A."l'NR.'l-;3 L:PJIQ 1-,3...

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'1 ~ '/4IU ip 444 4>44>~AX > Distribution: Docket File AEC PDR Local PDR Docket Nos. 50«275 Noy 0 1 1974 WPGammill. and 50-323 .JCStepp RBMCMullen DAlljson TJHirons Mr. Fred Houser LWR 1-3 RekHing Department of the Interior LWR 1-3 File V. S. Geological Survey/ VHWilson National Center, hiail Stop 908 12201 Sunrise Valley Drive Reston, Virginia 22092

Dear htr. Houser:

Enclosed for your review are 3 copies of Amendment 19 to the Diablo Canyon FSAR. This amendment contains PG4E's geology-seismology report and, in particular, a discussion of the offshore faults in the vicinity of the Diablo Canyon site. In order to maintain our licensing review schedule for Diablo Canyon, we would appreciate receiving your evaluation of this report by Januaxy 3, 1975. Yours truly,

Original Signed by, 0. D. Parr Olan D. Parr, Chief Light Water Reactors Project Branch 1-3 Directorate of Licensing Enclosure: Amendment 19 to Diablo Canyon FSAR (3)

OFFIC23F L: LWR 1-3 L:LWR 1-3

SURNAMSW ison:pga OS)a~a

DATE~ 1///74 11/g /74

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CONSULTANT

PRPi!: DATE OF DOC DATE REC'D. LTR TWX . RPT OTh" R United States -Department of the Xn erior Res ton, Virginiaj'22092 Elmer H. Baltz~ 7'-22-74 '-26-74 TO: ORXG CC 'TH:"R SENT AEC PDR XHOLD SENT LOCAL PDR XHOLD Mr. Gammill 1 signed CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET ANO:

0-275/323 DESCRIPTION: ENCLOSURES: Ltr trans the following: (1) Track Chart (2) Copy of Inshore Ends of Seismic Reflection DIST PER J. I:OS~LOOND Profiles 1'0 to- 24. 4/h"ii!NV)Ndi'=~~L')Ugg'.=LI4 9 NOTE: AEC & LEAL PDR COPIES SENT TO R, GRAHAM $g FOR DIST go':tltot ( 1 cy ea encl rec-'d) Rej j,'e

PLANT N>~ -'iablo Canyon Units 1 & 2 'FOR ACTXO:t/I:i=0~~ATION 7-29-7

BUTLER (L) SCHWENCER (L) ZXEMANN (L) REGAN (E) W/ CYS W/ CYS W/ CYS W/ CYS CLARK (L) STOLZ (L) DICKER (E) GAMMILL W/ CYS W/ CYS W/ .CYS W/ 2CYS ~ ~ I ~ ~ ~,PARR(L)g/WILSON VERA)~ALA.lG AAJ AN SLALOM'I 'i f I W/3 CYS W/ CYS W/ CYS W/ CYS KNXEL (L) PURPLE (r.) YOUNGBLOOD (E) W/ CYS W/ CYS W/ CYS W/ CYS

INTERNAL DISTRIBUTION REG FILE'ECH REVIEW BENTON LXC ASST A/T XND GRIMES DIGGS (L) BRAITliAN ~CGC ~SCHROEDER GAlMILL GEARIN (L) . SALTZM>20 ~NTZXNG/STAFF i~rACCARY KASTNER GOULBOURNE (L) B, HURT CASE KNIGHT BALLARD KREUTZER (E) GXAl'fBUSSO PAWLXCKI SPANGLER r.EE (L) PLANS BOYD SHAO MAIGRET (1,) MCDONALD iMOORE (L)(LWR-2)'TELLO ENVIRO REED (E) CHAPi~fAN ~EYOUNG (L)(LIiR-1) HOUSTON MULLER SERVICE (L) DUBE w/input . SKOVHOLT (L) NOVAK DICKER SHEPPARD (L) ED COUPE GOLLER (L) ROSS KNIGHTON SLATER (E) PE COLLINS'PPOLITO YOUNGBLOOD SMITH (L) D. THOMPSON (2) DENISE TEDESCO REGAN TEETS (L) KLECKER REG OPR LONG - PROJECT MGR WILLIAMS (E) EISENHUT FILE & REGION (3) LAINAS WILSON (L) ~HIRONS(2t) MORRIS BENAROYA BLESS STEELE VOLLMER EXTERNAL DISTR1BUTION - LOCAL PDR San Luis Obis o, Cal. (HOLD) TIC (ABERNATHY) (1) (2) (10) -NATIONAL LABS . ~1-PDR-SAX/MlPCC8 1 - NSXC " - (BUCHANAN) 1-ASLBP(L/W Bldg, Rm 529) -BROOKHAVEN N T LAB ASLB 1-W, PEiNNINGTON) RmI E-201 GT 1-G ~ ULRIKSON) ORNL - P, R. BAVIS 1-B&M SWINEBROAD Bm E«201 GT „1-AGMED (RUTH GUSSMAN) 16 " ACRS HOLDING 1-CONSULTANTS Rm B-127 GT

ANEWiMK/BLUE'rE/AGBABZAN 1-RD. ~ ."IUELLER) Rm F-309 A \ +Q) I ~ t 4+1 ~'r~g~w p ~() ' File CY, ~0- 75 ~ gg7 50,-323 r Q $0 United States Department of the Interior Vl 0 GEOLOGICAL SURVEY RESTON, VIRGINIA 22092 July 22, 1974

Mr. William P. Gammill, Chief JUL.26 1974c Site Analysis Branch U.S. ATOMIC ENtkbY CQMI'AISSION Directorate of Licensing Regulatory U.S. Atomic'nergy. Commission Mail hction Washington, D.C. Gv Dear Mr. Gammill: Per our telephone conversation today, enclosed for your information is a copy of a track chart and a copy of the inshore ends of seismic . reflection profiles 10 to 24 and that were obtained by the Geological Survey aboard the USNS Bartlett in 1972. These profiles supplement later profiles made by the Survey in November, 1973 aboard the R/V Kelez as part of our AEC-sponsored project on California offshore geology and geophysics, and the Bartlett profiles are being used in our review of geologic conditions offshore from Diablo Canyon. Sincerely yours,

Elmer H. Baltz Deputy Chief for Engineering Geology Office of Environmental Geology Enclosures

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3 ~ 3 Uh'ITED STATES ATOivliC ENERGY COIM)MISS~~ V/ASH INC . ON, Q.C. 20545 July 3, 1974

Docke" No. 50- 5/323

Hr. V. V. ~~Ji ckey US Geological Survey Old Security Bank Building Boulder, Colorado 80225

Sno j ec t '- A~END~KNT (11) TO DlABLO CANYON REPORTS

The folio«ing document material pertaining to reuse;.z of the subject nuclear facility is being transmitted ~ separately for your information.

P SAR Volumes

Amendment No. To PSAR Dated Amend-,ent No. 'o Environ. Rpt. Dated FSAR 'Volumes

A-.end-..;en t Zo, 1 -To FSAR Dated 6/24/74 (Reed. 6/28/74

OTy.ER: Amdt. sent approx. 7/2/74.

f illiam P. Gammill, Chief Si te Anal': sis Branch Direc tor. te of Licensing

cc: 'cket File R. ifc~iiullen J. Osloond

ATOMIC ENERGY COMMISSION 'VMS) lli46 7ON, D.C. 205-'5 r July 3, 1974 t/AttS Tit~ Docke t No. 5W275/323

Hr. Fred N. Houser US Geological Survey Engineering Geology Branch Denver Federal Center Denver, Colorado 80225 I l

ec Sub j t:,AMENDMENT (11) TQ D~LQ C~QN REPORTS

Tne following document material pertaining,'to review of "the subject nuclear facility is being transmitted 'separately for your information.

PSAR Volumes

emendmant Ro. To PRAR Dated Amendment No. To Environ. Rpt. Dated

FSAR Volumes

Amendment No. 11 To FSAR Dated 6/24 74 Reed. 6 28

0 THE R: Amdt. sent approx. 7/2/74.

William P. Gammill, Chief Site Analysis Branch Director..te of Licensing

cc:~ockat Pile R. McMullen J. Osloond J 4 AEC DI IBUTION POR PART 50 DOCEPT MA AL W (TEMPORARY FORM) CONTROL NO: 2801

FILE: CONSULTANT

FROM DATE OF DOC DATE REC'D LTR MEMO OTHER United States Department of the Interior Reston, Va. 22092 Elmer H. Baltz 3»28-74 4-2-74

TO s ORIG CC OTHER SENT AEC PDR SENT LOCAL PDR Mr. Gammill 1 signed CLASS UNCLASS PROP INFO INPUT NO S REC'D DOCKET

NO'ESCRXPTXON: ENCLOSURES: Ltr trans the following: Prelimioar Review of aspects of geologic data presented in the ~ FSAR for the Diablo kX;I" IPI.IRK'o No'f Romoi/o

PLANT NAME e Diablo Canyon Units 1 6 2

FOR ACTION/INFORMATION 4-3-74 BUTLER(L) SCHWENCER(L) ZIEMANN(L) REGAN (E) W/ Copies W/ Copies W/ Copies W/ .Copies CLARK(L) STOLZ(L) DICKER(E) W. PE GAMMXLL W/ Copies W/ Copies W/ Copies W/ 2 Copies ,GOLLER(L) VASSALLO(L): . KNIGHTON(E) " I W/ Copies W/ Copies W/ Copies W/ Copies KNIEL(L) SCHEMEL(L) YOUNGBLOOD(E) W/ Copies W/ Copies W/ Copies W/ Copies

INTERNAL DISTRIBUTION G FILE TECH REVIEW BENTON A/T IND AE >HENDRIE GRIMES LXC ASST BRAIIMAN OGC, ROOM P-506A BN SCHROEDER GRfMILL DIGGS (L) S ALLAN B, HURT MUNTZING/STAFF MACCARY KASTNER GEARIN (L) CASE KNIGHT BALLARD GOULBOURNE (L) PLANE GIAMBUSSO PAWLICKI SPANGLER LEE (L) MCDONALD BOYD SHAO MAIGRET (L) DUBE w/Inpu t MOORE (L) (BWR) STELLO ENVIRO REED (E) INFO DEYOUNG(L) (PWR) HOUSTON MULLER SERVICE (L) C. MILES SKOVHOLT (L) NOVAK DICKER SHEPPARD (L) B, KXNG P, COLLINS ROSS KNIGHTON SLATER (E) DENXSE IPPOLITO YOUNGBLOOD SMITH (L) REG OPR TEDESCO REGAN TEETS (L) PILE G REGION(3) LONG PROJECT LDR WADE (E) MORRIS LAINAS WILLIAMS STEELE BENAROYA HARLESS (L)(E)'ILSON VOLIkfER- EXTERNAL DISTRIBUTION 1 - LOCAL PDR 1 - DTIE(ABERNATHY) (1) (2X 10).NATIONAL LAB' 1"PDR-SAN/LA/NY 1 « NSIC(BUCHANAN) 1-ASLBP(E/N Bldg,gm 529) 1-GERALD LELLOUCHE 1 - ASLB(YORE '-W PENNINGTONB Rm E 201 GT BROOKHAVEN NAT. LAB 1-CONSULTANT'S 1"AGMED(Ruth Gussroan) 16 - CYS ACRS HOLDING NEWARK/BLUME/AGBABIAN RM- B-127, GT. 1-GERALD ULRXKSON...ORNL 1-RD..lfULLERWeF-309 GT Pp I

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0 ~ '„>»>,'"x/ AoguT>>tory'V United S'tates Department of the Interior~ 0 GEOLOGICAL SURVEY -KASNNQT4N;-BG--2024Q- Reston, Va. 22092 March 28, 1

NOCRggy 50-323 UR~Q'PRE Mr. William P. Gamnd.lip Chief egypt Site Analysis 3ranch 5 Directorate of Licensing Office of Regulation U. S. Atomic Energy Commission ! Washington, D. C. 20545 ~(>

Dear Mr. Gamnd.ll: Enclosed for your information is a preliminary review of aspects of geologic data presented in the PSAR for the Diablo Canyon Nuclear power plant site, units 1 and 2, California (AEC Docket Nos. 50-275 and 50 +3) o As you know, Mr. H. C. Wagner of our Office of Marine Geology is preparing a review of offshore geophysical data collected by the Geological Survey and by the applicant. We expect this review to be completed shortly. Sincerely yours,

Elmer H. Baltz Deputy Chief for Engineering Geology Office of Environmental Geology Enclosure l

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Preliminary Review Diablo Canyon, Calif. F. A. McKeown January 23, 1974

Pacific Gas and Electric Company Diablo Canyon site, Units 1 and 2 San Luis Obispo County, California ~ AEC-Docket Nos. 50-275 and= 50-323-

Geology

A preliminary review of the geological and seismological data

presented in the Final Safety Analysis Report (FSAR) for the Diablo

Canyon nuclear power plant site, Units 1 and 2, indicates the need I

for additional information. The report appears to have included ~

.data and discussions of nearly all geologic and seismologic.features

pertinent to the safe operation of the plant. One feature, however, for which adequate information is not provided is an offshore fault

or structural zone which has been recognized since presentation and

review of the Preliminary Safety. Analysis-Report (PSAR).

The-principal geologic and seismologic features of importance to the site are small faults near or within the site area and large

faults along which large earthquakes may occur several miles from

the site. The occurrence of small faults that do not cut terrace

deposits near and within .parts of the plant site is documented and explained in sufficient detail to accept them as noncapable faults

within the definition of AEC criteria for capable faults,. The

proposed four maximum earthquakes (pages 2.5-12 and -13) that could 4

affect the site are reasonable'. However, since these four possible

earthquakes were proposed by Benioff and Smith (1967), a fault or

structurally disturbed zone with a length of 90 miles or more that

passes within 7 or 8 miles offshore of the site has been interpreted by Hoskins and Griffi'ths, (1971).

Th'is structural'one i's discussed on pages 2.5-10, -ll, and '- -67 of the FSAR. As stated by the applicant on page 2.5-67 "Ava'ilable data. for the reported offshore structural zone are not conclusive

for determining its extent, continuity, and state of activity." The applicant's descriptions of the, zone are taken from the work of Hoskins -and Griffiths who show it as a fault. Their interpretations of the displacements along the zone, which the applicant presumably

accepts, do not indicate that the sea floor or Holocene deposits have I been offset. The basic data upon which the interpretations have been made, however, are not presented by either the applicant or Hoskins" an'd Griffiths. Seismic activity along and in the vicinity of the zone's shown in figures 2".5-3 and 2.5-3A and discussed on page 2.5-67 in the FSAR. It is probable that the accuracy of the 'locations of the earthquake epicenters shown in the figures is too poor to relate them conclusively to the zone; conversely, they cannot be disassociated from the zone. The question of whether the zone is a fault or contains faults that are capable within the

definition of AEC criteria is therefore unresolved.

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Because of the apparent length and proximity of the offshore zone to the site, consideration of the zone as another possible

source of a maximum earthquake in addition to the four propcsed

by the applicant may be necessary. Until definitive information is presented to demonstrate otherwise, prudence requires that the zone. be'onsidered capable.

References

Benioff, H., and Smith, S. W., 1967, Seismic evaluation of the

Diablo Canyon site, Diablo Canyon, Unit 1: PSAR Docket'o.

( 50-275, and Diablo Canyon Unit 2,: PSAR Docket No. 50-323.

Hoskins, E. G., and Griffiths, J. R., 1971, Hydrocarbon potential

of northern and central California offshore, in Cram, I. H., ed., Future petroleum provinces of the United States —their

geology and potential: Am. Assoc. Petroleum Geologists Mem. 15, v. 1,, p. 212-218. ~ + ~

c,'( de.' >

4 'I j 4 r

I January 28,,1974

50-275/323 Pr 6 0 Michey

US Geological Survey'ld Security Banh, Building Boulder, Colorado 80302

Subject. ~HDHEHT HO 2 TO .DIABLO CAHYOH RSAR

The following documents concerning our of the subject facility x@gg~~~~gg~g~ havereviewerKeen sent separately

Notice of Receipt of Application.

Draft Environmental Statement, dated

Final Environmental Statement, dated

Safety Evaluation, or Supplement No., dated

Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Vol. 2 Amendment No. to Application/SAR, dated l/lS/74

Construction Permit No. CPPR- , dated

Facility Operating License No. DPR- , dated

Technical Specifications, or Change No. , dated

Other:

Directorate of Licensing Site Analysis Branch R' %fi5%%fFs: IUXliam Gammill, hief ~MFd

. Docket, Rile R McHullen J Stepp ~ 8 Don OFFICE e

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Docket No. 50-2Z5/323 Hr. Pzed H. Rouser US GeoIogica1 Survey Engineering Geology Branch Denver Pedeza1 Center Denver, CoIorado 80225

Subject: AHEHDMEHX HO 2 TO DXASLO CAHYOH PShR

The following documents concerning our review of the subject facility

Notice of Receipt of Application.

Draft Environmental Statement, dated

Final Environmental Statement, dated

Safety Evaluation, or Supplement No., dated Notice of Hearing on Application for Construction Permit.

Notice of Consideration of issuance of Facility Operating License.

Application and Safety Analysis Report, Vol. g Amendment No. to Application/SAR, dated

Construction Permit No. CPPR- , dated

Facility Operating License No. DPR- , dated

Technical Specifications, or Change No. , dated

Other:

Directorate of Licensing Site Analysis Branc MI%ian P Gammill» Chief

cc: Docket Pike Ro HcHnllen J. Ste J., Oaloond OFFICE A

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, 71r. Howard. H. Valdron U. S. Geolog1cal Survey Engineering Geology Branch Denver Federal Center Denver~ Colorado 80225 Dear Nr. caldron:

For your information, T enclose a copy of' Safety Evaluation dateC January 23, 1968, prepared. by the Division of Reactor Licensing in the matter of Pac1f1c Gas and. Electric Conpany Diablo Canyon Nuclear Power Plant.

Comments prepared. by the U. S. Geological Survey are attached, as-Appendix D to th1s report.

Sincerely +ours p Original signed by Robert L.~ Tedesco'

Roger S. Boyd.~ Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosnre: As stateC above

cc: Nr. Ihdght M. Lemmon

OFFICE > —4RL—--- -— DFYmu h SURNAME > HSteele 2/7/68 2/ / DATE I Porm AC-318 (Bee. 043) MLS.GOVKRNNKNTPRINTINC OAXKa I~2 I4~ F p

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1h'. Dwight N. Lemzen Assistant Chief Geologist U. S. Geologicil Survey U. S. Department of the Xnterior Room 4214~ GSA 3uilding Washington, D. C. 20242

Dear Nr. Lenunon: For your information, I enclose a copy of a Safety Evaluation dated. January 23, 1968, prepared. by the Division of Reactor Licensing in the matter of Pacific Gas and. Electric Company IKablo Canyon Ijtuclear Power Plant.

Comments prepared by the U. S. Geological Survey are attached. as AppeIRlQc D to this reporto Sincerely yours,

Qriginai signed by Robert.'.~ Tedesco

oger S.~ 3oyd., Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure: As stated. above,

RP/DRL RP3-5/DRL OFFlCE > Hstecle/cLK DFKnu SURNAME p

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14r. William N. $Bd.te, Chief Division of River Basin Studies Bureau of Sport Fisheries and. Wildlife U. S. Department of the interior Uashington~ D. C. 20240

Dear Nr. Mhite-- For your information, I enclose a copy of a Safety Evaluation dated. January 23, 1968, prepared, by the Division of Reactor Licensing M the matter of Pacific Gas and, Electric Company Diablo Canyon Nuclear Pover Plant.

Comments prepared. by the Fish aud. LlildlifeService are attached, as Appendices Q«l and. 6-2 to this report. Sincerely yours~

I I;,'I„„ii SIgned by 'gilbert L. Tedesco Roger S. Boyd,, Assistant erector for Reactor Prospects Division of Reactor Licensing Enclosure: As stated. above

OFFICE p IqJIIRZ, RPB-"),/

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Nr. Ihight M. Lemmon Assistant Chief Geologist U. S. Geological Survey U. S. Department of the Xnteriox, Room 4212, GSA Building Mashington, D. C. 20242

Dear th. Lemmon: This supplements our letter to you dated. October 25, 1967 concerning the Pacific Gas and Electric Company's Euclear Plant at the Diablo Canyon Site.

Two copies of POCK Co's letter date4 December 14~ 1967 transmitting revised Page 2 to Amendment Eo. 5 to the application for license are attached, for your use. Sincerely yours~

Roger S. Boycl, Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure:

Page'evised. 2 to Amendment Zo. 5 (2)

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Mr. Harold. L, Price - Director of Regulations JAN 3 ]968 U. S, Atomic Energy Commission Washington, D. C, 20545 Dear Mr. Price:

This is in response to Mr. Boyd's letters of July 31, and. August ll, 1967, transmitting Amendments Nos. 1, 2, and 3 to the Preliminary Safety Analysis Report of the application by the Pacific Gas and Electric Company for a construction permit for the proposed. Diablo Canyon Nuclear Power plant, San Luis Obispo County, California, Docket No. 50»275.

The Service has reviewed, Amendments Nos. 1, 2, and. 3 and. has the following comments on the proposed environmental monitoring program contained. in Amendment No. 1 and on the cooling water intake str'ucture contained in Amendment No. 3:

The proposed environmental monitoring program generally conforms to the recanmendations in our June 23 letter to the Commission; however, the applicant's proposal does not include collection and examination of water and, sediment samples which we recommended. and. consider a necessary part of'he monitoring program. Fish and. wildlife resources would be insured. of more adequate protec- tion from radiological hazards with implementation of the monitoring program along with,other proposed safeguards, provided. that water and. sediment samples are included in the program and. that initial liquid waste discharge limits are adjusted if considered. necessary. Specifications for the cooling water intake structure contained in Amendment No. 3 do not include adequate information for an analysis of possible effects on fish and, wildlife. The bar racks and traveling screens designed primarily to keep debris 'ut of the system could. serve the additional purpose of minimi- zing harm to fish and. Qlg+P'e provided that intake velocities were not limiting. Being'ognizant"of.".t1ie'>CommissionIs opinion that its regulatory authority does not apply to other than radiological hazards, we recommend th'aC"the Commission urge the Pacific Gas and Electric Company to consult with the Fish and. Wildlife Service and..the Resources Agency of California in establishing final design criteria for the intake structure. 4 hhg 4(7 ~

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03hl3338 The opportunity for presenting our views on these amendments is appreciated.. t Sincere+ yours,

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Mr. Dwight M. T.emmon Assistant Chief Geologist U. S. Geological Survey " U. S. Department of the Xnterior Room 4214, GSA Building Uashington, D. C. 20242

Dear Iir. Lemmon:

Two copies of Amendment No. 5 to the Pacific Gas and Blectric Company's facility license application are enclosed for your use. In addition to certain financial data, the amendment contains the Fourth Supplement, to the Preliminary Safety Analysis Report for the proposed nuclear plant at the appli- cant's Diablo Canyon site Sincerely yours,

01iginal signed by, H, Steele ger S. Boyd, Assistant Director for Reactor Prospects Division of Reactor Licensing Bnclosure: Amendment Ho. 5 (2 cys)

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Mr. Harold. T ~ Price Director of Regulation U. S. Atomic Energy Commission 4915 St. Elmo Avenue Bethesda~ Maryland. 20545 Dear Mr. Price: Transmitted. herewith in response to the request of Mr. Edson G. Case dated. February 6~ 1967, i.s a review of the geologic and. hydrologic aspects of the license application of the Pacific Gas and. Electri.c Company, Diablo Canyon Nuclear Plant Site.

This review prepared. by Henry V. Coulter and. Eric L. Meyer of the Geological Survey has been discussed with members of your staff and. we have no objections to your making it a part of the public record,. Sincerely yours,

Acti'n8 Director Enclosures

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Hydrology

The site is on the shore of the Pacific Ocean in San Luis Obispo County, near the mouth of Diablo Canyon Creek. The reactor is to be located. on a terrace on the left 'bank of the Creek at a grade altitude

of 85 feet above mean sea level. Cooling water is to be obtained. from

an intake at the ocean south of the reactor and. discharged. about 1,200 feet north of the intake. A spit of land. extends about 1,000 feet into

the ocean between the intake and. discharge points. The reactor location would. not be affected. by floods of Diablo

Canyon Creek, the only deve3oped. drainage nearby. The switchyard., however, is shown as occupying a part of the canyon where it could. be affected. by flooding. There are no reports of ground water developments in the vicinity of the site. Xt does not appear that the reactor would. affect fresh- water resources of the area.

~ Geology

The analysis of the geology of the Diablo Canyon Nuclear Plant Site

presented, in A.E.C. Docket No. 50-275 and. supplements was reviewed and,

compared. with the available literature, and. the exploratory trenches. at the site were examined. on August 14-15,- 1966. The analysis appears to be carefully derived, and. to present an adequate appraisal of those aspects of the geology which would. be pertinent to an engineering evaluation of the site. l fe 4 Ife I f ke

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~~A~ +V' (gJ 5 )WVAWAg A v 1lVll September 19, 1967 Dis tribution: pi~! Supplemental Docket Eo 50-275 r~ DRL Reading RPB P2 Reading Orig: HSteele (2) R. S. Boyd OGC J. F. Newell Hr. Lfelvin A. Honson Branch of Permits Division of River Basin Studies Bureau of Sport Fisheries and Uildlife U. S. Department of the Xntcrior Lfashington, D. C. 20240 Dear kh. jonson:

Xn accordance vith x'ecently established procedures, the Atomic Energy Commission has forvarded to the Pacific Cas and Electric Company a copy of the U. S. Pish and Uildlife Report containing comEIents .and recommendations on both radiological and non- radiological effects of the proposed operation of a nuclear power reactor at the applicant's Diablo Canyon site located in San Luis Obispo County, California.

A copy of Dr. Morris'etter of September 15, 1967, .to Che appli- cant is enclosed for your information. You vill note that copies of the September '15th letter, together Wth the Pish and Uildlife Report have been sent to the appxopriate state and local officials in California. Sincerely yours, Orit;ideal simed by: Roger 8. Boyd

Roger S.,Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing Enclosure: AEC ltr. to PGGZ dtd. 9/15/67

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Hr. Dwight H. Lemmon Assistant Chief Geologist U. S. Geological Survey U. S. Department of the Xnterior Room 4214, GSA Building lfashington, D. C. 20242

Dear Hr. Lemmon:

A copy of the Third Supplement to the Preliminary Safety Analysis Report fox the nuclear reactor which Pacific Gas and Electx'ic Company proposes to construct and operate at its Diablo Canyon Site is enclosed for youx use. The supplement contains additional technical data in the form of answers to questions x'aised'y the Commission. Sincerely yours,

Original signed by K Steele

Roger S.~ Boyd,~ Assistant Director for Reactor Pro)ects Division of Reactor Licensing Enclosure: Third Suppl. to PSAR (Diablo Canyon Site)

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Hr. lie'1vin A. Honson Branch of Permits Division of River Basin Studies Bureau of .Sport Fisheries and Uildlife U. S. Department of the Xnterior Uashington, D. C. 20240 Dear Ur. Ifonson:

A Copy of the Third Supplement to the Preliminary Safety Analysis Report for the nuclear reactor which Pacific Gas

, and Electric Company proposes to construct and operate at its Diablo Canyon Site is enclosed for your use. The supplement contains additional technical data in the form of answers to questions raised by the Commission. Sincerely yours,

signed by H.~ Steele 'riginal k

Roger S.~ Boyd, Assistant Dixector fox Reactor Pro)ects Division of Reactor Licensing Enclosure: ! Third Suppl. to PELE (Diablo Canyon Site)

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kh'. Melvin A. jonson Branch of Permits Division of River Easin Studies Bureau of Spoxt Fisheries .and Wildlife Q. S. Department of the Xnterior Uashington, D. C. 20240

Dear Eir jonson:

Copies of Amendments Hos. 1 and 2 to Pacific Gas and Electric Company's facility license application are enclosed for your use.

The amendments consist of the First and Second Supplerents to the Preliminary Safety Analysis Report for the proposed Diablo Canyon nuclear reactor, and contain additional technical data requested by the Commission. Sincerely youxs,

Original signed by H. Steele Roger S. Boyd, Assistant Director for Reactor Pro)acts Division of Reactor Licensing Enclosuxes: As stated above

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Ih'. QUight H. Lemmon

Assistant Chief Geologist'. S. Geological, Survey U. S. Department of the Xnterior Rom 4214, GSA Building Hashington, Q. C. 20242

Dear 5!r. Lemmon:

Copies of Amendments Nos. 1 and R to Pacific Gas and Electric Cenpany's facility license application are enclosed for your useo

The amendments consist of the First and Second Supplements to the Preliminary Safety Analysis Report for tho proposed Diablo Canyon nuclear reactor, and contain additional technical data, requested by the ComEIission. Sincerely yours,

Original signed by H. Steele Rogex'. Boyd, Assistant Directox for Reactox Pro)acts Division of Reactor Licensing Enclosures: As stated above

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Mr. Harold L. Price JUN 2 3 1967 Director of Regulations U. S. Atomic Energy Comnd.ssion Washingtonp D. C. 205II5

Dear Mr. Price: This is in reply to Mr. Zdson G.. Case's letter of February 6, 1967~ requesting our comments on the application of the Pacific Gas and Electric Company for license for its proposed. Diablo Canyon Nuclear Power Plant, San Luis Obispo County, California, Docket No. 50-275..

The prospect would be located adjacent to the Pacific Ocean on the California coast about 12 ndles west southwest of San Luis Obispo, California. A pressurized water reactor, designed, for an initia1 output of 3~250 thermal megawatts, and an approximate net electrical output of 1,060 megawatts would be used, as a power source.

A radioactive waste disposal system and, other facilities required for a complete and operable nuclear power plant would, be provided. Gaseous wastes would be vented to the atmosphere, and liquid wastes would be discharged to the Pacific Ocean via the condenser cooling water. Condenser cooling water would be pumped from the Pacific Ocean through traveling water screens and returned to the ocean at the water's edge in Diablo Cove. 5 Detailed design criteria far the cooling water system have not been finalized at this time.

The applicant plans to initiate a radiological survey of the area about two years before plant operation. Details of this program have not been completed, but special emphasis willbe placed on the edible marine species which are present in Diablo Cove.

The applicant has contracted for ecological studies of the marine env'tronment, and the Resources Agency of Ca1ifornia has made similar investigations. The results indicate that existing flora and fauna are a highly diversified mixture of warmwater and cold« water forms. These studies will be continued in order t'o adequately descxibe seasonal changes. Special emphasis will be placed on seaweed, which appears to be the chief source of organic activity.

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The area adjacent to the plant site is a small part of the larger coastal fishing grounds extending from slightly north of Point Buchon south to Point San ~s. Fish species present in the area include white sea bass, ungood~ greenling, sanddab, cabezon~ black rockfish and yellow rockfish. Shellfishes present include red, aba1one which is the most important and. black abalone, flat abalone~ and threaded abalone.

i'he application indicates that the release of radioactive wastes would not exceed maximum permissible limits prescribed in Title 10~ Part 20, of the Code of'Federal Regulations. Although these limits refer to maximum leve1s of radioactivity that can occur in drinking water for man without resulting in any known harmful effects, operation within the limits may not always guarantee that fish and. wildlifewill be protected from adverse effects. If the concentration 9n the xeceiving water were the only consideration, ma>cbuum p~ssible lindts would be adequate criteria for determining the safe rate of discharge.. However~ radioisotopes of many elements are concentrated,'and, stored by organisms that require these elements for their normal metabolic

Some organisms concentrate and store radioisotopes 'ctivities. of elements not normally required but which are chemically simU.ar to elements essential for metabolism. In both cases, the radionuclides are transferred from one organism to another through various levels of the food chain gust as are the, nonradioactive elements. These transfers may result in further concentration of radionuclides and a wide dispersion from the prospect area particularly by migratory fish, msmauQ.s, and, birds. In view of the shove, we believe that pre- and post-operational radiological surveys should be conducted by the applicant and include studies of the effects of radionuclides on se1ected organisms which require the waste elements or siud3.ar elements for metabolic activities. These surveys should be planned, in cooperation with the Fish and Wildlife Service~ the Federal Water Pollution Control Administration~ and the Resour'ces Agency of California If the post«operationa1 surveys establish that the release of radioactive effluent at leve1s permitted under Title 10, Part 20, Code of Feder81 Regulation's, results in haimful.concentrations of radioactivity in fish and wildlife~ the data from the'adiological survey should serve as a guide to x'educe the discharge of radioactivity to acceptable levels The sport and, commercial fisheries in the prospect area are valuable public resources and should.'be protected from radioactive contami- nation. Therefore~ it is recommended that the Pacific Gas and ELectric Company be required to: t ~

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1. Cooperate with the Fish and Mld1ife Service, the Federal Mater Pollution Contx ol Administration, The Resources Agency of California~ and other interested state 'agencies in developing plans for radiological surveys. 2. Conduct or arxange for the conduct of preoperational ~ radiological surveys of selected, organisms'hat concentxate and, stoxe radioactive isotopes, snd of the environment including water and, sediment samples. These surveys should be conducted. by scientists. knowledgeable in the fish and wildlife field. 3. Prepare a xeport of the pre-operational radiological survey and provide five copies to the Secretary of the Interior for evaluation prior to project, operation.

Conduct radiological surveys~ similar to those specified in xecommendation 2 above, analyze the data, and prepare and submit reports every three months during the first year of reactor operation and, evexy six months thereafter or until it has been conclusively demonstrated that no significant adverse conditions exi.st. Submit five copies of these reports to the Secretary of the Interior for distxibution to the appropriate State and Federal agencies for evaluation. Reduce the discharge of radioactive wastes to acceptable levels, ifthe post-operational surveys establish that the release of radioactive effluent at levels permitted'under Title 10~ Part 20~ Code of Fed.eral Regulations, results in hara~ concentra- tions of radioactivity in fish and wildlife. Me understand that it is the Comnd.ssion's opinion that its regulatory authority over nuclear power plants involves only those hazards associated with radioactive materials. Me have recommended, in past applications that before the permit is issued~ thermal pollution and othex detrimental effects to fish and wildlife which may result from plant construction and operation be called to the attention of the applicant., In this case, we believe that the applicant is aware of these pxoblems. 'The company has signed an agreement with the Resources Agency of California to conduct studies which would identify harmful effects resulting from other than radiological causes~ and to mitigate losses ifthey occur. However, we recommend that the following .observations be brought to the attention of the applicant. W

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I ~ J, V )IV( I II'l .Vkl, W I "vr«jr-.,; Company engineers and consultants have made studies relating to temperature effects near the cooling vater outfall from the proposed nuclear plant. As a result of these studies, the following area temperature predictions wexe made: An area, enclosed by an isotherm 18o F. above ambient will not exceed 1/8 of an acre and wiU. be within 150, feet from the point of discharge; an isotherm 10o F. above ambient vould enclose an area 2.0 aires 50 percent of the time and 4.2 acres 20 percent of the time within 300 feet of the outfal3. and vould not extend than 15 feet below the surface; an isotherm 4o P. above 'ore ambient vould enclose an area of 15 acres 80 percent of the time, 32 acres 50 percent of the time, and 82 acres 20 percent of the time and vould, not extend more than 10 feet 'belov the surface.

Because Diablo Cove is an area where varmwater and cold.-vater forms of a diversity of marine organisms intermingle, even a small temperature increase, could x'esult in an ecological imba1ance by eliminating the more sensitive cold-water forms. Mhether this vould prove harmful to the sport and commercial fisheries in adjacent'atex could only be determined by pre-operational and post-operational ecological studies. These studies should be in coopexation with the Fish and 8'ildlife Service and the'lanned Resources Agency of California. If the ecological studies establish that the heated effluent results in changes that are significantly detrimental to ff.sh and wildlife, as determined by the Pish and wildlife Service or the Resources Agency of California, corrective measures to reduce the temperature of the effluent should be taken. Further, that if fish and vildlife losses occurs compensation for such losses would be the responsibility of the applicant.

Another problem vhich could adversely affect fish and, wildlife is the cooling water intake. Xt is anticipated that large volumes of ocean vater vould. be circulated through the plant with the intake at the water's edge. Various marine organisms would 'be drawn into the intake and destroyed unless a suitable screening device vere provided. The pre-operational ecological studies should. include a survey of the marine organisms present in the area of the intake in order to define their numbers and relative importance. In addition, a suitable intake screen should be provided. The Pish,and MQ.dlife Service and the Resources Agency of California should be consulted in designing the intake screen. In view of the Administration's policy to maintain, protect, and improve the quality of our environment, and, most particularly the water and air media, 'we request that the Commission urge the Pacific Gas and Electric Company to: ~ 0 ~ ~ 1 ~ 1

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4 lJ ~ 41 ~ 1. Cooperate with the Pish and Wildlife Service and the Resource's Agency of.California and other interested state agencies in developing plans for ecology,c'al surveys; initiate these'urveys at least two"years before reactor operation; and continue them on a xegular basis during'operation or. uritil it has been 'onclusively demonstrated that no'ignificant adverse conditions exist. 2. Neet with personnel of the Pish and Wildlife Service and the Resources Agency of California at frequent intervals to discuss new plans and to evaluate results of existing surveys.

3. Nake such modifications in prospect structure and operation as may be determined necessary as a result of the surveys. Provide a screening device at the cooling water intake~ the specifications of which would be deter- mined in cooperation with the Pish and Wildlife Service and the Resources Agency of California. Provide compensation for any losses of fi'sh that may occur as a result of constructionand'Q.dlife orcyeration of the project.

The opportunity for presenting our views on this prospect is appreciated. Sincerely yours,

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lt ll l'Ã AZ htlf'L9:1, Distribution:~ suyp1.~ ~CCtlIIC CI J. Newell D. Muller H. Tedesco I C. kh'. DIdaht M, LaIauuxa Long AeI3iatIMtIt Chief Qaoloaio4 H. Xreland U<8. Geoloaias3. Survey U. 8. Department of the Xnterior STaohingtoe, 9, C. 80248 War 3h'. Lemon) Several applications''for reactor construction permits or operating licenses are currently being reviewed by you. To aid you in scheduling work on these various projects and to help in assuring that we receive your reports in time to send to the ACRS for its review of particular applications we have compiled a list of anticipated deadlines for receiving consultant reports on the various projects. Xn each case wp would like to receive your report during the first week of the month before the project is considered by the ACRS. Considering this, the contemplated schedule for your sending reports to us is as follows'..

1, Duke Po~er Company (Oconee 1 8c 2) - May

2. Vermont Yankee (Vermont Yankee) - May

3. Public Service of Colorado (Ft. St. Vrain) - June

II. PG8:E (Diablo Canyon

5. Philadelphia Electric (Peach Bottom 2 8c 3) - July

6. Virginia Electric (Surry 1 8: 2) - August 7. Jersey Central (Oyster Creek) - August 8. Public Service of N.J. (Burlington) - October

Some of these project deadlines will likely slip from time to time. Therefore, I would expect to send you revised listings on a periodic basis. Sincerely yours,

OIIynal sIgned by RolleI S. Boyd

Roger S. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing D I th 4 /67 .. 0 0 C

gQRCI gOy l~ UNITED STATES suppl. CCE v~, ATOMIC ENERGY COMMISSION DHL Hea ing WASHINGTON. D.C. 20545 AD/HP Heading Orig: H. S. Boyd 0 bcc: P. A. Morris ~)4II5 OI Monson.'istribution:S. Levine J. Mewell Mr. Melvin A. Konson D. Muller Branch of Permits H. Tedesco Division River of Basin Studies C. Long'. Bureau of Sports Fisheries 8I 7H.ldlife Ireland. U. S. Department of the Interior llashington, D. C. 20240

Dear Mr.

Several applications for reactor construction permits or operating licenses are currently being reviewed by you. To aid you in scheduling wo on these various projects and to help in assuring that we receive your r ports in time to send to the ACRS for its review of particular applicati ns we have compiled a list of anticipated deadlines for receiving consults t reports on the various projects. Xn each case we would like to receive your report during the first week of the month bef'ore the project is considered by the ACRS. Considering this, the contemplated schedule f'r your sending reports to us is as follows: go- >G'y~ l. Duke Power Company (Oconee l 8 2) - May ~ 2, Vermont Yankee (Vermont Yankee) - May 3. Public Service of Colorado (Ft. St. Vrain) - June

4, PG8cE (Diablo Can on - June -'xg S

5. Philadelphia Electric (Peach Bottom 2 5 3) - July

6. Virginia Electric (Surry 1 % 2) - August 7. Jersey Central (Oyster Creek) - August 8. Public Service of'.J. (Burlington) - October

Some of these project deadlines will likely slip from time to time. Therefore, I would expect, to send you revised listings on a periodic basis. Sincerely yours,

Roger S. Boyd, Assistant Director f'r Reactor Projects Division of Reactor Licensing D H . h 4/l8 . 0 (

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f' DisSuppli.:~™tribution: DRL Rdg. '&PRSB,Rdg. Docket Ho. 50-2?5 Orig: HSteele (2) FEB 6 1967 E. G. Case R. S. Boyd K. Hoodard J. F. Newell

%h'. Melvin A. Honson, Branch of Permits, Division of River Basin Studies Bureau of Sport Pis er e d . d U. S. Department of the Interior Uashingtons D. C. 20242 Deax'r jonson:

Xn accordance uith the understandings uhich mere reflected in Secretaxy Udall's letter of Inarch 20, 1964 to Chairman Seaborg, I am forwarding herewith Volumes I and II of the Preliminary Safety Analysis Report filed by Pacific Gas and Electxic Company for the proposed constxuction and operation of a pres- surized mater nuclear reactor at its Diablo Canyon site Ln San Luis Obispo County, California. The proposed reactor is designed for initial operation at 3250 thermal, megawatts. and Late would appreciate xec'eiving a xeport frcrn the Pish 7711dlifa Service concerning those features of the proposed reactor operation vhich xIight have radiological effects on fish and shellfish.

On the basis of our tentative schedule fox'his pro)ect, it mould. be desirable to have your repoxt available fox'ur use by Apx'il 15s 1967 Sincerely yours,

SgsllC~ d bye E Q Qg80 Edson G. Case, Deputy Director Division of Reactox Licensing

Enclosures: As stated above

OFFICE Ip DRL

SURNAMED ..HSteele/d).. Bag @BC .. DATE > 67 ..?l /67 Po~ hZC-318 (IIov.M) V. a corasNc~r rplenro orncs 10-Osrol-3 ;«f05'0l fPf4, 8 e;2'I gh I

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gh Dwight H Lemon Assistant Chief Ceologist U. S. Geological Survey U. S. Department of the Xnterior Room 4214, CSA Building Washington,. D. C. 20242

Deax Hr. Lemmen:

Xn accordance with the understandings which were reflected by Secretary Udall's letter of March 20, 196$ to Chairman Seabox'g, X am forwarding herewith Yolumes X and XX of the Pxeliminary Safety Analysis Repox't filed by Pacific Cas and Electric Company for the px'oposed construction and .opex'ation of a pres- surized water nuclear xeactor at its Diablo Canyon site in San Luis Obispo County, California. Preliminary information relating to the Diablo Canyon site was transmitted to you with our letter of October 7, 1966.

Ue auld appreciate receiving the results of a review by the Geological Survey of those geological and hydrological features of the proposed reactor location which may have a bearing upon our evaluation of the suitability of the proposed site.

On the basis of our tentative schedule fox this pro/act, it would be desirable to have your report available fox our use by April 15, 1967. Sincerely yours,

Original signed by F G. Case Edson C. Case5 Deputy Director Division of Reactox Licensing

Enclosures: As stated above

OFFICE IN ML... 5

SURNAME IN HSteegefd] RSB yd E ase

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1hax Hr Xenxe: Gu'etter of Cckcbex"g, X/66 txnusud.ted to ~ux'STice a pmllnfnmy zeyart", prepared by Pacific Gas and Electric Coayaxgr cn its yropased Diablo Canyon Site Zne1qaed aro tvo colored photograph T hich ahouM lm in"Orted Xn the envelope Xn Apymd1x 3 of that zap orb .

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Boyd'cn 00 Case, A-sistcnt Mrectox'd@via %en of Reactor Xicensiag Zacloauxes e Photcgnnyhs

Distribution Su@pl. Prospect Ro. Olp) DHG Reading EhPRSB Reading bcc: E. G. Case P. dorian J. Reve Il R. 9. Boyd

omcE > REcPRSB: DHL

RSB SURNAME > 1 lO/1 lO/I~/66 DATE > Ponn AEC-318 (Rev. 043) 0, t, Cetttlllltet ttlttlte Ottltt 10-02201-0 r Jr ( 0 1 e

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Distribution Suppl. rog. No. 419) DHL Heading HM'HSB Reading bcc: E. G. Case P. Norisn OCT 7 Ess, Z.,Newell H. S. Boyd )7h Mr. Dwight M. Lemmon Assistant Chief Geologist U. S. Geological Survey Room 4214, GSA 33uilding Washington, D. C.

Dear Mr. Lemmon: In accordance with the understandings which were reflected in Secretary U'ds11's letter of'arch 20, 1964~ I sm forwarding herewith a request for a preliminary site revi~ew submitted by the Pacific Gas and Electric Company. This review involves the siting of the Company's proposed nuclear power plant at its site near Diablo Canyon, California. As you willpote, this site is quite near the Csyucos Site previously reviewed by the Geologics3. Survey.

We would appreciate receiving, by early November 1966, a dxaft report of the results of a preliminary review by the Geological Survey of those geologica1 and hydrological features of the pxoposed reactor location which msy have a bearing upon our evaluation of the suitability of the proposed site. Please note that the information contained in the enclosure should not be released or discussed publicly at this time. Sincerely youlsp

Original signed bg E. G. Case

Zdson G. Case, Assistant Director Division of Reactor Licensing k Enclosure: Preliminary Site Rpt.

OFFlCE P HgcPHS DHT HSB ase SURNAME >

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and Coast 6 Geodetic Survey concerning four sites

proposed by the California Department of Water TO (Name a unit) I'IALS REMARKS Resources, Copies of these drafts have been pre- Dr, Mann viously transmitted to the ACRS and should be made final for review of the Committee at its July meeting. TO (Name and unit) REMARKS Subject to any comments you may have, I plan to Dr, Doan DATE request the Surveys to officially transmit these reports in their present form Tuesday, July 5. FROM arne and unit)

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DEPARTMENT OF THE INTERIOR

s ' DRAFT Geological Survey May 26, 1966 Coulter San Luis Obispo County, California Cayucos Site g-p7A General j

The Cayucos site is underlain by rocks of the Franciscan formation r which contains many intrusive serpentine bodies. The difference in physical properties between the Franciscan rocks and the serpentines and within the serpentine bodies themselves between massive serpentine and alter'ed and sheared serpentine is great. This dissimilarity in physical properties, primarily

shearing strength, exercises a strong geologic control on slope stability and foundation conditions in terrain underlain by Franciscan rocks. There are no topographic indications of major landslide problems within the site area. Minor slope stability probelms related to cut-slope development during construction can be anticipated. Faults

'etailed mapping which would give diagnostic evidence concerning the presence or absence of large faults at or near the site is not availaHa and their existence there certainly cannot be precluded. High-angle shear zones

with gouge development up to several feet in width are common. Such shear I zones are. characteristic in Franciscan rocks and are generally considered to

relate to a geologically remote, not recent, period of tectonism. The

active Nacimiento fault is located approximately 10 miles north-r'eismically east of the site. The nearest point to the site on the San Andreas fault is

40 miles, and the Santa Ynez and Big Pine faults pass within -,'pproximately

90 miles of the site. An undetermined number of offshore faults whose exact

positions and trends are unknown have been postulated in the area approxi- mately 75 miles southwest of the site.

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The Cayucos site is located within a zone of active seismicity. In

I the period 1934 to 1962, 14 earthquakes with epicentral locations within

20 miles of the site have been recorded. Of these 14 earthquakes, seven

had a Richter magnitude between 4.0 and 4.3 and the remainder were less than

4.0. Within the zone between 30 and 40 miles from the site three epicentral locations with Richter magnitudes of 6.0 and 6.5 have been recorded. The highest intensity assigned to the Cayucos area was VII H.M. associated with the earthquake of November 1927 with a Richter magnitude of 7.3 and an

epicentral location 55 miles west of Point Arguello. Problems fecause of the complex stratigraphy, the general lack of continuous mappable lithologic units, and the intricacies of localized shearing and attendant structures, the recognition of ma)or throughgoing structural features in Franciscan terrain is difficult. Detailed regional mapping

and structural analysis will be required to provide diagnostic evidence that

may prove or disprove the existence of ma)or faults south»west of the Nacimiento fault in the vicinity of the Cayucos site. Massive serpentine is relatively stable in steep or vertical cuts whereas cut slopes in sheared serpentine are potentially unstable on slopes. greater than 1:l. Insofar as bearing capacity under foundations is concerned, the i shearing strength of massive serpentine is relatively high but decreases with increasing proportions of shearing and alteration. Veins of soft altered I material in hard serpentine may present special problems, Hence, for 'adequate l 'I

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geologic evaluation of the Cayucos site accurate delineation of the distri- bution of serpentine bodies and of the degree of shearing and alteration

within the bodies is required. Such delineation can best be pxovided by detailed geologic mapping combined with an adequate sampling and testing program designed to provide sufficient information on the physical properties of the various lithologic units undexlying the site to formulate adequate slope and foundation design criteria. r e E

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P' UNITED STATES r- ~ ~ t DEPARTMENT OF THE INTERI Geological Survey DRAFT: May 1966 Coulter Ventura County, California Sycamore Canyon Site General

The Sycamore Canyon site lies adjacent to the beach on the south flank

of the Santa Monica Mountains. The site is underlain by a complexly folded,

faulted and sheared sequence of Miocene sedimentary and intrusive igneous

rocks. There is topographic evidence in Sycamore Canyon, beyond the limits of the site, of landslides in geologic environments similar to those existing within the site. Faults

Three faults with large-scale stratigraphic displacement, the Sycamore Canyon fault, the Baudette fault sand the Serrano fault, and several subsi- diary faults of lesser displacement have been recognized within the site

area. Diagnostic evidence as to whether or not any of these faults displace

Pleistocene and/or Recent deposits is not available. The active San Gabriel fault lies 26 miles northeast of the site. The nearest point to the site

on the Santa Ynez fault is 32 miles north; the Newport-Inglewood fault 36 miles east; the San Andreas fault 46 miles northeast; the Big Pine fault

45 miles north; the Garlock fault 52 miles north; and the White Wolf fault

56 miles north. An undetermined number of offshore faults whose exact positions and trends are unknown have been postulated in the Santa Barbara channel south of the site.

The Sycamore Canyon site is located within a zone of active seismicity.

Xn the period 1934 to 1962, 39 earthquakes with magnitudes of 3.0 to 3.9 4 8/

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E Il'k and epicentral locations within a radius of 20 miles of the site, have been recorded. Six of these earthquakes have epicentral locations less than

5 miles offshore from the site. There are three additional earthquakes with magnitudes of 4.1, 4.7, and 4.7 with epicentral locations within 5.5 and

6 miles respectively of the site. No maximum intensity records are available for the Sycamore Canyon area.

Problems

The following geologic problems are involved in the consideration of

the Sycamore Canyon site.

1. The site is within the zone of intersection of several faults, the date of the latest movement on which has not been, and perhaps here for dearth of diagnostic stratigraphic criteria cannot be, established. 2. There is evidence of serious slope stability problems in the

Sycamore Canyon area which may be found to affect either the site itself or the natural drainage system through the site. 3. The site is located in a zone of active seismicity the relation- ship of which to the faults through the site has not been established.

'FAIT 5 1 sa ~ ~ ~ UNITED STATES

DEPAR'Q1ENT OF THE INTERIOR

DRAFT: ?fay 1966 Geological Survey Coulter Ventura County, California

Oxnard Site General

The Oxnard site is underlain by at least 1,800 feet'of unconsolidated,

saturated, predominantly fine-grained alluvium. The maximum elevation within

the site is 10 feet above sea level and the relief is low. The general seaward

slope offshore from the site is gentle, approximately 40 feet per mile;

however, 1 mile west of the site this gentle slope is dissected by the steep

declivity at the head of the Hueneme submarine canyon. Insofar as slope stability is concerned, this relationship imposes steep gradient rather than gentle gradient controls on the submarine topography. Faults

Recognition of faults in an actively aggrading alluvial sequence of this type is virtually impossible without extremely detailed subsurface exploration. The nearest recognized seismically active faults, the Santa Ynez and Big Pine,

are located approximately 30 miles north of the site. The nearest point to

the site on the San Andreas fault is approximately 50 miles northeast. An undetermined number of offshore faults whose exact positions and trends are unknown have been postulated in the Santa Barbara channel south of the site.

The Oxnard site is located within a zone of active seismicity. In the

period 1934 to 1962, 54 earthquakes with epicentral locations within a

20-mile radius of the site have been recorded. Of these 54 earthquakes,

four had a Richter magnitude of 4.0 to 4.7 and the remainder were less than

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l 4.0. Since 1769, six large earthquakes with estimated or recorded magni-

tudes of 6.0 or greater have occurred within a 60-mile radius of the site. The highest intensity assigned to the Oxnard area was VEI H.bf. associated with Kern County earthquake of 1952 with a Richter magnitude of 7.7 and an epicentral location along the White Wolf fault approximately 75 miles north of the site.

Problems

During the Alaskan earthquake of 1964, extensive surface rupture, massive

liquefaction flow slides on relatively gentle slopes and differential compac- tion were observed to have taken place in thick saturated alluvial sections similar to that underlying the Oxnard site. These effects were observed at epicentral distances ranging from 30 to more than 100 miles.

The potentially unfavorable dynamic response characteristic of the alluvium at the Oxnard site combined with the steep gradient controls resulting

from the location immediately offshore of the Hueneme submarine canyon suggests

the gikelihood that comparable effects resulting from a major earthquake centered on any one of the active faults, located within 100 miles of the

Oxnard site may be anticipated. C 1

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l ~ UNITED STATES ~ ~

DEPARTMENT OF THE:INTERIOR DRAFT: May 1966 Cculter Geological Survey Tehachapi Site General

The proposed plant site is located on the southeast edge of the

San Joaquin Valley approximately 17 miles south of Arvin and ll miles north of Gorman. The site is underlain by silty sandstones of the Tejon formation of Eocene age which dip northwesterly at moderate to steep angles. The rocks of the Tejon formation are described as being weak when wet and slightly stronger when dry. Boring data indicate artesian groundwater conditions in the vicinity of the site and "suggest that serious hydrostatic uplift pressures may be encountered at foundation grade." Faults

Five major seismically active faults showing evidence of recent primary surface rupture occur within a 20 mile radius of the site. Many additional faults with less prominent surface expression but with possibly equal or even greater potential effect on the site lie within this area. Evidence of a flowing spring and juxtaposed divergent'edding attitudes along the gully entering the plant site at the southeast corner suggest the presence of a fault traversing the site from southeast to northwest.

Hater supply for the plant is to be taken from the aqueduct. To the extent that a continuous supply of water represents an operating requirement for the plant, consideration must be given to possible disruption of flow through the aqueduct in those many localities where the line crosses major fault zones between the Tehachapi Site and the ultimate source of water to the east. 1

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'roblems In addition to the high regional seismicity of the area the following problems at the Tehachapi Site must be considered:

Poor foundation conditions on weak, saturated, silty sandstone with potential hydrostatic uplift pressures at foundation grade. 2. Complexly faulted bedrock adjacent to and perhaps beneath the site. 3. Possible interruption of plant water supply by disruption of the

aqueduct throughout a broad zone of seismically active terrain east of the site. ~~ e DRAFC

REPORT ON THE SEISMICITY OF THE CAYUCOS,

OXNARD SYCAMORE CANYON AND TEHACHAPX CALIFORNIA

AREA

In response to the request of the Division of Reactor Licensing of the

Atomic Energy Commission, the Seismology Division of the Coast and Geodetic

Survey has prepared this report on the seismicity of Cayucos, Oxnard, Sycamore

Canyon, and Tehachapi,California, and their environs.

The fault nearest Cayucos is the Nacimiento fault which is inland and trends northwest-southeast parallel to the, coast at a distance of about 8 miles from the site. The San Andreas has roughly the same orientation and is approximately 42 miles from the site at its nearest point. Historically, Cayucos has experienced macroseismic disturbance from at least sixteen earthquakes registering intensities above Modified Mercalli III. The strongest recorded intensity was MM VII caused by the earthquake of November 4, 1927, which occurred off Point Arguello about

75 miles from the site and had a magnitude of 7.5. This produced a maximum acceleration of 0.13g. On February 23, 1931, a small earthquake occurred in the immediate vicinity of Cayucos, a result of which a'aximum intensity of V was produced.

Oxnard is in an area that is underlain by deep alluvial deposits and evidence of surface faulting is not readily detectable. However, to the north and east are a number of poorly defined faults of the transcurrent system prevalent in this region. The site is approximately 25 miles from the Santa Ynez fault and 50 miles from San Andreas fault. It has been subjected to seismic disturbances of MM intensity III at least 35 times during historic;,times. lg

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Intensity VII is the highest experienced and occurred on three occasions. The first on January 9, 1857, as the result of an earthquake near Port Tejon,

distance, 50 miles; the second caused by a small nearby earthquake on December 14,

1912; and the third on July 21, 1952, as a result of the Kern County earthquake which was 55 miles dis tant and had a magnitude of 7. 7.

The Sycamore Canyon site is located at a distance of about 26 miles from the

San Gabriel fault, 32 miles from the Santa Ynez fault and 36 miles west of the

Newport-Inglewood fault. The nearest point on the San Andreas fault is 46 miles to the northeast. It has been subjected to seismic disturbances of intensity III

or more at least 42 times since 1769. A maximum intensity of VI was recorded as

a result of 13 earthquakes ranging in distance from 10 to 210 miles.

The Tehachapi site is very near the juncture of the San Andreas fault and the faults of the transcurrent system of southern California. It lies between two

seismically active faults, the White Wolf, 11 miles to the northeast and the

Garlock, 5 miles to the southeast and at a distance of 9 miles from San Andreas which lies to the southwest. It is an area of very high seismic activity. The most notable earthquake to occur here was the Kern County earthquake of July 21, 1952. It had a Richter magnitude of 7.7 and a maximum intensity of XI at a point near Bealville, 26 miles from the site which would have subjected the latter to an intensity of VIII and an acceleration of .27g.

Using the criterion of the effect of a magnitude 8.0 earthquake on the nearest point of the San Andreas fault to each site the following effects are postulated: Cayucos, intensity VIII, acceleration 0.27g; Oxnard, intensity VII, acceleration 0.13g; Sycamore Canyon, intensity VII+ acceleration 0.23g. The intensity given II

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'I "3- above for Oxnard refers to bedrock; however, the site is situated on 1800 ft of alluvial material so that the acceleration could be as much as 3.5 times higher.

To evaluate further this estimated acceleration at Oxnard, a seismic measurement of the ground amplification factor is recommended.

With regard to Tehachapi a magnitude 8 shock occurring at the nearest point on the San Andreas fault would cause an intensity at the site of X+ and a maximum acceleration of .70g. If the complex nature of the fault structure near the intersection of the Garlock and the San Andreas faults is taken into consideration,

there is a high degree of probability that a shock of magnitude 8 could occur within 5 miles of the site in which case it would be subjected to intensity XI and a maximum acceleration of .9g.

An excellent example of the earthquake forces encountered in this region is given in descriptions of the Kern County earthquake damage near Bealville in

U. S. Earthquakes, 1952, page 17 and the publication "Earthquakes in Kern County, California during 1952," (see reference).

Another factor for consideration in evaluating the coastal areas as a reactor site is the possibility of damage. For the most part, a tsunami is generated by a submarine earthquake or an earthquake located close to coastal areas although only a small percentage of earthquakes of this type have been known to generate measurable water waves. The vertical displacement of submarine blocks of the earth's crust is the most commonly accepted explanation of the cause of these waves. Since it has been observed on land that great earthquakes have caused uplifts of 30-50 feet and affected crustal blocks hundreds of miles long and up to a hundred miles wide, it is easy to conceive of such a crustal movement under the ocean generating huge water waves. Slides along the coasts are also I 4

thought to be possible sources of and great earthquakes originating on

the sides of deep oceanic troughs may cause huge masses of unconsolidated material lh to slide into the depths, displacing a great amount of water. It has been sug-

gested also that there is a possible coupling mechanism between tsunamis and

large surface waves with periods over a minute. Historically, these waves have

had amplitudes considerably less than those transmitted directly from the sources.

Along the coast of California there is no well established source areas for

the generation of tsunamis. On December 21, 1812, there was a strong submarine

earthquake (possibly 7 1/4-7 1/2 magnitude) off the southern California coast

which reportedly generated a tsunami that reached land elevations of 50 feet at Gaviota, 30-35 feet at Santa Barbara, etc. However, it has not been possible to

definitely substantiate these heights. So employing the results of Iida's work

for estimating tsunami wave heights along the Japanese coast and realizing the fault movements along the California coasts are mostly strike-slip, it is

estimated that tsunami run up (flooding) caused by locally generated tsunamis

would not be more than approximately 30 feet. For tsunamis generated by distant

sources such as Japan, Aleutians and the extension of the San Andreas fault off

the west coast the tsunami run up at these sites would be approximately 30 feet

above mean lower low water.

In summary, the Survey believes that within the lifetime of facilities located 'I at the above sites and on rock, accelerations in the period range of 0.3 to 0.6

seconds should be taken into account in the designs as follows: Cayucos, 0.27g; Oxnard, 0.13g and as much as 3.5 times greater if on approximately 1800'f alluvium; Sycamore Canyon, 0.23g and Tehachapi 0.9g. For tsunami run up from distant severe marine earthquakes, the coastal sites should be protected to a

vertical height of 30 feet above mean lower low water. This 30 feet level is ~ ~

1

t l also adequate protection for any tsunami generated by local earthquakes along the coas t of southern California.

U. S. Coast and Geodetic Survey Mashington, D. C.

May 24, 1966 4 REFERENCES

"United States Earthquakes, 1952," Leonard M. Murphy and William K. Cloud, U. S. Department of Commerce, Coast and Geodetic Survey, Serial No. 773, 1954. "Earthquakes in Kern County, California during 1952," California Department of Natural Resources, Divis ion of Mines Bulletin 171, 1955. I g 4

4

I

Jy

C Iiqximum Dist;ance--Tntensity Date E icentral Area lntensitv (Iiiles) (I~i) C Cavueos Oxnard Sycamore Te'nachaoi

1769 July 28 Los Angeles region VZ|:|:-TX 05 v 40 v

1812 D c 21 Off Coast of So. Calif 110 lv 45 VX>: 75 Vj: 1852 Oct 26 San Simeon 135 T-XX% 1852 Nov 27-30 Ventura County 120 30 V 35 V 1855 July lo Los Angeles County 165 50 V 6 1857 Jan 9 Fort Tejon 115 V 50 Vii. 70 Vl (X)

1870 Jan 3 Bakersfield V 30 Xll- Xv": 1872 Impar 26 Owens Valley X-XZ 175 IV 170 lv 170 Xv 115

'883 Sept; 5 Ventur a V-Vl 120 = 10 V 35 XTT. 11T~ 1885 Apr 7 Bakersfield 30 1890 July 20 Bakersfield 3o (zv 1892 Feb 23 Baja California IX-X 250 X|:T. 210 V-VT VXX-XXU. S.

1893 Apr 0 Los Angeles region 711T-XX 160 1XT. 35 Vi 35 Vl 1896 Aug 17 Hanford lo5 (Tv) 1899 July 22 San Bernadino County VXXX loo zan 8o vz 1899 Dec 25 San Jacinto 130 V ~ y 4 ~ ~

II

1

* I l"

~ < 5 4

Iiaximum Distance --Intensity . Date E icentral Area Intensity (in.les) -= (i'i) e

~Ca eos Oxnard Sycamore Tehachaoi 1902 July 27 Santa Barbara County VlXT 6o xv (2 similar af tershocks July 31) 1902 Dec 12 Los Alamos 6o llew 1903 Jan 7 Baker sfield 30 XV' 1905 Mar 18 Bakers field 30 T.v':

1905 Dec 23 Bakersfield 30 zv+~ 1906 Apr 18 San Prancisco 28o (v) 1908 Sep 0 Bakersfield (2 shocks) 30

xvi'8o 1910 Nay 6 Near Bishop (zxz) 1912 Dec 10 Oxnard Nax. 25 V-VX 1915 Jan ll Los Alamos 6o xv 1915 Nay'8 Southern Sierra Nevada 8S (zvQ 1916 Oct 22 Tejon Pass 5 (v:t) 1918 i»a 6 Santa Vionica (V-Vl) 15 v 1918 Apr 21 Riverside County, lian 6.8 TX 125 zv 100 v-vx 1918 Nov 19 Santa iionica Bay 1919 Jan 25 Tejon Pass v 1919 Feb 16 South of i'Iaricopa 30 ZV~ J 4

4 e $

C

E I'!aximum Distance--Xntens" ty e Date Z icentral Area (Ijiles) (IZj)

e Cayucoa Oxnard Sycamore Tabac'. adi

1920 June 21 Xnglewood VXXX

1922 Ijar 10 Cholame Valley, I~!ag 6~ 100 XV:":

1925 June- 29 Santa Barbara, Idaho 6.3 1926 Jun 30 Kern River Canyon 3O-.( 1927 Jul 8 Bakersfield XV 30 1927 Nov 4 Off Pt. Arguello, Nag 7.5 XX-X 75 VXX 135 V-VX 155 XXX I

1930 Jan 15 34.2N., 116.931, Nag. 5.2 VXX(2) 100 V XXX-'933 1930 Aug 30 33. 9N., 118. 6tt, " 5. 2 VXX 40 XXX 10 VlX 1931 Feb 23 Templeton, Parkfield, Ivjax, Cayucos

ajar 10 33.6N., 118.0U, Ijap 6.3 XX 80 VX 50 VX 110 (XV) " 1933 Oct 2- 33. 8N., 118. 1I'J, 5. 4 40 (V) " 1934 June 7 35. 9N. > 120. 5)12 6. 0 VXXX(2) 40 V 135 (XV) 110 (XXX) 1935 Jan 23 35.5N., 119.2N, 40 (XXX) 1940 Oct 10 33.8N., 118.4U, Il 15 V

1l 1941 June 30 34. 4N., 119. 6N~ 5 9 100 V 30 VX 1941 Sep 14 37. 6N., 118. 7V, I 185 (XXX) IV+

f> I'!Q.X3.MQBl D~ stance --Intens'y Date Z icentral Area Intense t ~ (ii» es) (iiii)

Cayucos Oxnard ~S camo"e Tehac'haoi

1941 Sep 21 34. 9N. ~ 118. 9",i, iiag 5 5 ~i

1941 Oct 21 33. 8N., 118. 2)1, 5 . UII 55 XV 00 v " -1941 Nov 1LI. 33. BN., 118. 2ti, 5. 5 UII-VIII 40 V " 1942 Oct 21 33. ON., 116. Otl, 6. 5 VII 190 jV=

" 19M June 18 33. 9N., 118. 23t, 4. 0 VI(2) 50 IIl " 1946 Mar 15 35. 7N., 118. 1H, 6. 3 VIII 125 U 120 V 70 U " 1947 Apr 10 35. ON., 116. 6tr, 6. iI VII 165 V 16O V 1948 Feb lo 36. 1N., 118. 8H, 4.6 VI 80( III) 1948 Apr 16 34. ON., 119. Ot'l, Il 10 VI " 1948 Dec 0- 33.9N., 116.@,l, 6.5 VII 155 VI 140 UI ll / 1949 Aug 27 3~. 5N., 120. 5H, g 9 70 I-III 75 90 " 1950 Feb 25 34. 6N., 119. 1$'1, 4. 7 VX 40 VZ 1951 Dec 25 32.8N., 118.4V, 5.9 VI 100 V 85 v 1952 July 21 35. ON., 119. ON, 77 X~ 110 VI 55 UII 65 VI 10 VIII (180 a tershocks; n.ag. 410 and over,, recorded at Pasadena fron July 21 to September 26; 6 aftershocks o 5.0 and over on the 21st). 4 Iiaximum D~ s~ance--Xn~ens'y 0 E ~ "cent al Area Xntens='t (iu. es) (> !) gal t

~Ca ucos Oxnarn Syctmove Tehacha o~ ~ 1952 July 25 East; of Caliente (2 30 lv-:: shocccs) 1952 Jul 28 Near B ar lioun~a3.n 20 XV': 1952 Jul 31 North of Calien~e 20 Xil""

1952.Aug 22 35.3N., 118. 9't, Via@ 5.8 70 TV 80 iv 15 v II 1952 Aug -23 34. 5N., 118. 231, 0 6o I 5 v " 1952 Nov 21 35.8N., 121. 2t~, 6. o 35 ~ 140 xv 1954 Jan 12 0N. ol'1, 35. ~ 119. 5 9 55 V 65 v ll VX 1954 Jan 27 35. 1N., 118.6W, 20 V 1954 <~far 19 33. 3N., 116. 2il, 18o T.v 170 xv

1954 iiay 23 35. 0N., 119. OH, 5.1 10 XV Dec II 1954 16 39e 3Ne p 1 18r 2tl> 7 0 285(xv) 35o(xv) 35o(:v) 310(:zx) II 1955 Aug 7 35.4N., 118. 6V, go (zt- II 1955 Nov 21 35.4N., 118.7V, 4I 25 (~v) " 1956 Feb 9 31. 8N., 115. 9N, 6. 8 VENT.-XX 245 xv 260 |:v (m-U.s. ) " 1957 Jan 29 35. 9N. ~ 122. U'1, 4. 9 75 XV

1957 Liar 18 34. 1N. ~ 119. 2Y~ Ko vz C 4 k

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L'maximum . Dis tance --intens ity E icentral Area intensity = (liiles) '!Hi)

~Ca ucos 0-:oarQ Svca.,o s ~zena c.'1a oi 1958 July 13 30. 4N., 119. 5':!, -i~~ag >k. 7 25 V 40 XV

1959 Sept 30 3~. 0N., 120. 6~:.',

1l 1961 Jan 28 35.8N., 118. oiI, 70 (ZV) II 1961 Nov 14 34; 9N., 119. 011,

II 1963 Feb 28 34. 9N., 119: 01'1, 5 0 7 V

lntens'y at Site: ~aEstimated using Gutenberg-r"ichter lnt. vs Distance

( ) Estimated from nearby reports ~'

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J NRC DISTRIBUTIO)N FOR PART 50 DOCKET I"IATERIAL (TEMPORARY FOR(Vi) ~ CONTROL NO:

'J.~N'ept

of Commerce DATE OF DOC DATE R EC'D LTR TWX RPT OTHER Silver Springs, 'Md 4-10-75 4-22-75 I Van Der Hoven TO: ORIG CC OTHER SENT AEC PDR XX Mr Schroder one signed SENT LOCAL PDR CLASS UiUCLASS PROP INFO INPUT NO CYS REC'D D . NO: XXXXXX 1 ~ 50-27 23

DESCRIPTION: ENCLOSUR ES:

Ltr re our 1-23-75 ltr....trans the following''omments on the FSAR for Diablo Canyon 1&2

~ ~ ~ ~ ~ ~ ~ ~

PLANT NAME Diablo Canyon 1 & 2

FOR ACTIOiN/li'wFORii)iATION 4-23-75 ehf BUTLER (L) SCH',YENCER (L) IEMANN (L) REGAN (E) IV/ Copies W/ Copies W/ Copies W/ Copies CLARK (L) STOLZ (L) DICKER (E) LEAR (L) W/ Copies W/ Copies W/ Copies W/ Copies PARR {L) VASSALLO {L) KNIGHTOiU (E) SPB'JS-- ~ V<~/3:opies W/ Copies W/ Copies 'W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOO (E) LPI I W/ Copies W/ Copies W/ Copies W/ Copies INTERNALDISTRIBUTION R G TECH REVIEW ~ DENTOiU LIC ASST A/T IND ~ PDR SCHROEDER G R I iViES R. DIGGS (L) BRAITiviAN ~ OGC, ROOMi P.GOGA ~ieiACCARY GAI.'iMI LL(2) H GEARIN (L) SA LTZ)V(AN ~ GOSSICK/STAF F KNIGHT KASTNER E. GOULBOURNE (L) MELTZ CASE PAW LICK I BALLARD P. KfIEUTZER (E) GIAMBUSSO SHAO SPANGLER J. LEE (L) P LAX'S BOYD STELLO M. MiAIGRET (L) iVICDO(UALD MOORE (L) HOUSTON ENVIRO S. REED (E) CHAPivlAN DEYOUNG (I.) NOVAK MULLER M. SERVICE (L) DUBE (Ltr) SKOVHOLT (L) ROSS DICKER S. SI.IEPPARD (L) E. COUP".. GOLLER (L) (Ltr) IPPOLITO KNIGHTOiU M. SLATER {E) PETE RSOi~l . P. COLLINS TEDESCO YOUNG B LOOD H. SIVilTH (L) HARTF I E LD (2) DEN( IS E J. COLLINS RFGAN S. TEETS (L) KLECKER RLG OPR LAIiNAS PROJECT LDR G. WILLIAMS(E). E ISE iNHUT g[$Q@~iL.GIGA (2) BEN)AROYA V. WILSON {L) . WIGGINTON VOLLMiER HAR LESS R, INGRAiM (L) STEELE EXTERNAL DISTRIBUTI N

— ( ~1 I OCAL PORE J.v i S D b( s Po— 1 —T!C {ABEIiNATHY) (1) (2) (10) —NATIONALLABS —PD R.SAN/LA/NY I KT LAB 1 —NSIC (BUCHANAN) 1 —W. PENNP.:GTON, Rm E-201 GT .1 BROOi

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~ ~ ~ ~ ~ 4 ~ 4 O.S. DEPARTMENT OF COMMERCE IQational Oceanic and Atmospheric Administration ENVIRONMENTAL RESEARCH LABORATORIES Silver Spring, Maryland 20910

April 10, 1975,

R32

Mr. Frank Schroeder, Acting Director Division of Technical Review United States Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Schroeder:

This refers to the letter of January 23, 1975 from William P. Gammill, Chief, Site Analysis Branch, Division of Technical Review requesting comments on the following:

Diablo Canyon 1 and 2 Pacific Gas and Electric Company Final Safety Analysis Report Amendment No. 24 dtd. 1/15/75

These comments are attached. Sincerely,

Isaac Van der Hoven Air Resources Laboratories Attachment cc: E.H. Markee, Site Analysis Br., USNRC 'L L I

~ I 5

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sr Comments; on,„.

Diablo Canyon Site Units 1 and 2 Pacific Gas and Electric Company Final Safety Analysis Report Amendment 24,dated January. 15, 1975

Prepared by Air Resources Laboratories National Oceanic and Atmospheric Administration

April, 10, 1975

Using the latest available data of wind speed and dir ection (May 1973 through April 1974) at the 25-ft. level and corresponding temperature differences between 25 and 250 ft ,- we have calculated that for a ground level release there is a probability that a relative concentration of 1.8 x 3 10 sec m will be exceeded 5X of the time at a distance of 800 m downwind. The atmospheric stability was categorized according to the temperature gradient criter ia listed in AEC Safety Guide 1.23. The release time was assumed to be from 0-2 hours.

For the long-term annual release a ground source was assumed. This is in

. contrast to the 70-m release height assumed by the applicant (p. 2.3-24). Figure 1.2-22 shows the top of the tallest vent duct to be about 32 m above grade, while the adjacent reactor containment building is about 67 m in height above grade. We would thus assume that the vent release would be caught in the building wake. We calculate from the 25-ft. wind data that the highest annual average relative concentration gill be yt the 800-m o site boundary towards the NW at a value of .2 x 10 sec m ~. ~4 ~i

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f' DIPZRIBUTXO7

Supp'RL Reading RPB-g Reading Orig: HSteele (2) R. S. Boyd. F. Docket Eo. 50-27, 1968 J. Nevell

Iir. Leonard Hurpby Chief~ Seismology M.vision U. S. Coast 5 Geod,etic Survey ESSA - washington Science Center RocIDd.lie~ I'Iaryleml 20852

Dear 1h. Hurphy:

For your information, X enclose a copy of a Safety Evaluation dated. January 23, 1968, prepared by the Division of Reactor Licensing in the netter of Pacific Gas and Electric Company Diablo Canyon nuclear Pomr Plant.

Comments prepared by the U. S. Coast 8i Geodetic Survey are attached as Appendix E to thio report. Sincereiy"yours, I Origlnrl simed by Robert L. Tedesco I Roger S. Boyd, Assistant Director for Reactor Prospects ~ Division of Reactor Xicensing Enclosure: As stated. above

OFFICE Q ~/ RPB->/ HSteele/ s DFKnuth SURNAME W 2/7/68 -a(Z/68 DATE > Po~ AEC 318 (Rev. 943) 4%29 VS.COYQNllQtfPRINIINCOfvÃXs I~1 a

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Hr. LeonarIi Murphy Chi'ef, Seismology Division '. S. Coast 8o GeocLetic Survey ESSA - Uashington Science Center Rockville, Maryland. 20852

I Dear Ih. Murphy: This supplements our letter to you dated. October 25, 1967 concerning the Pacific Gas and. Electric Company's Qxclear Plant at, the Diablo Canyon Site.

A copy of PRZ Co's lettex dated. December 14, 1967 transmitting revise4 Page 2 to Amendment Fo. 5 to the application for license is attached, for your use. Sincerely yours~

oger S. Boyd, Assistant Director for Reactox Prospects Division of Reactor Id.censing Enclosure: Revised. Page 2 to Amendment No. '5

OFFICE > ..IGNI~ FWK&Z&8/d.s SURNAME W /68 DATE+ ....I...1/~/68/ 1/ VA.COVERNNENTPRINTINO OFFICE: I~2 le%29 7 h >. Ll'W ~

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* Distribution: Supplemental. DRL Reading October 25, 1967 RPB-2 Reading

Orig: HSteele (2)'. Docket Ho. 50-275 S. Boyd Tech. Reviewer J. F. Newell

Mr. Leonard Murphy Chief, Seismology Division Coast 6 Geodetic Survey ESSA, - LTashington Science Center Rockville, Maryland 20850 Dear M'r. Murphy:

A. copy, of Amendment No. 5 to the Pacific Gas and Electric facility license application is enclosed for your'ompany's use. Xn addition to certain financial data, the amendment contains the Fourth Supplement to the'Preliminary Safety Analysis Report for the proposed nuclear plant, at the applicant's Diablo Canyon site. Sincerely yours,

Original signed b7 l K Steels Roger S. Boyd, Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure: Amendment No. 5

OFFICE P ----DRL:

SURNAME > -.HSteeke dj--- 10/25/67 DATE W (Box'. Porm AEC-318 043) V S. GOVERNMENT PRl NRNG OfflCE ) 1~214<29 I - I .4

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DATE OF DOCUMENTs DATF..., %D I' NOs '''~Is-'s 'f~ j LTR.. MEMOs REPOR s I OTHERs

TOs ORIG.) Cci OTHERs Harold Price 0 k ro duced ee raced ACTION NECESSARY Q CONCURRENCE Q DATE ANSWEREDs NO ACTION NECESSARY ~ COMMENT BYs C IF.s POST OFFICE FILE CODEs

REG. NOs soczm so-zrs (Sea. Omz) DESCRIPTIONs IMvss Be Unclsssslfied) REFERRED TO DATE RECEIVED BY DATE ",Etre transp

($0 coyieg mc>8)

TInepoxt (tm-page) an nm Seiaaicitg Oe The Fsuclear PLant At Bm N.aMo @agan Site, California>" dELted 9-18-67 Qx'e M)rrie

Distribution)) 't-suppLL5 fQ.e SRovholt

U. S. ATOMIC ENERGY COMMISSION Q4)L CQNTRQL FQRQ FORM AEGG26S (840) 'kU, S. GOVERNMENT PRINTING OFFICE: l957-259-553

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I ~ ' gH Ot U.S. DEPARTMENT OF COMMERCE ENVIRONMENTALSCIENCE SERVICES ADMINISTRATION 4p o P COAST AND GEODETIC SURVEY O>ORs Oi + MD. 20852 'OCKVILLE,

September 21, 1967

IN REPLY REFER TO'23

cod ~

Mr. Har old L. Price Director of Regulations U. S. At;omic Energy Commission Washington, D. C. 20545 Dear Mr. Price: Xn accordance with your request, we are forwarding 10 copies of our report; on t;he seismicit;y of Diablo Can- yon, San Luis Obispo County, California. The Coast and Geodet;ic Survey has reviewed and evaluated t;he informat;ion on the seismicity of t;he area presented by She applicant; in their "Preliminary Safety Anal- ysis Report," and find 8ha8 i4 is sat;isfactory wit;h respect; to both dist;anh and nearby earthquakes. We have also included a si;ai;ement; aboui; t;he t;sunami run- up aC t;he sit;e. Xf we may be of furt;her assistance t;o you, please do not; hesit;at;e Co contact; us. Sincerely yours,

~

~ e C.~ Tison, ~ ear Admiral, U E SA Director Enclosure r a

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~a.. REPORT ON THE SEISMICITY OF THE

NUCLEAR PLANT AT THE DIABLO CANYON SITE, CALIFORNIA

At the request of the Division of Reactor Licensing of

%1 the Atomic Energy Commission, the Seismology Division of ,~ a.v the Coast and Geodetic Survey has evaluated the seismicity of the area around the proposed reactor site in Diablo Can- yon, San Luis Obispo County, California, and has reviewed, the similar. analysis'made by the applicant in the Prelimi- nary Safety Analysis Report of the Nuclear Plant at the n Diablo Canyon Site, Pacific Gas and Electric Company. The applicant's seismicity report,is complete for both nearby K and distant earthquakes which,may have affected the proposed site. The study of sources of the potential maximum earth- quakes along the San Andreas Fault, the Nacimiento Fault, the Santa Ynez Fault and the San Andreas aftershocks west of this fault includes not only a, review of 'the historical earthquakes but a discussion of those parameters related to the earthquake frequency spectrum as fault length, depth of fp focus, slip and duration of strong shaking. Eased upon the r eview of the seismic history and r e- lated earthquake frequency spectrum data and the related geologic considerations, the Coast and Geodetic Survey agrees with the applicants statement of 0.20 g at the site and on 1

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rock for She predicted 'maximum ground accelerations of She design earthquake and twice this value, 0.40 g on rock for

R II safe shut-down conditions. We believe this value (0.40 g) would provide an adequate basis for designing proi;ect;ion against She loss of functions of components importanC 8o safety. For tsunami runup aC this site we recommend ahab it be protected 8o a vertical height of 30 feet above mean lower low water.

U. S. Coast and Geodetic Survey Rockville, Maryland 20852 September 18, 1967 ~ y/

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') ~ Distribution: Suppl. DRL Reading~ RPB 2 Reading AUG 11 1967- Orig: HSteele (2) 50-275 R. S. Boyd Docket Ro. Tech. Reviewer J. P. Newell

lfr. Leonard Efurphy Seismology Division'hief, U. S. Coast and Ceodetic Survey ESSA - Uashington Science Center Rockville, maryland 20852 Dear Hr. Murphy:

A copy of the Third Supplement to the preliminary Safety Analysis Report for the nuclear reactor, which Pacific Gas and Electric Company proposes to construct and operate at its Diablo Canyon Site is enclosed for your use.

The supplement contains additional technical data in the form of answers to questions raised by the

Commission'incerely yours,

Original signed by H.~ Steele

Roger S.~ Boyd, Assistant Director for Reactor Prp)acts Division of Reactor T.icensing Enclosure: Third Supple to PSAR (Diablo 'anyon Site)

OFFICE W DRL:RP

SURkAME ~ HSteele/5 8/10/67 DATE > Form ABC-318 (Bev. !hO) US. GOVERNMENTpeINTINC GEEIEE ~ 1~21 ~ e22 I I

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Hr. Leonard Hurphy Chief, Seismology Division Coast and Ceodetic Survey ESSA - Hashington Science Center Rockville, Heryland 20852 Dear 11r. Hurphy:

Copies of Amendments"Nos ~ 1 and 2 to Pacific Cas and Electx'ic Company's facility license application ax'e enclosed for your use.

The amendments consist of the First and Second Supplements to the Preliminary Safety Analysis Report for the proposed Diablo Canyon nuclear reactor~ and contain additional technical data requested by the Comission. Sincerely yours,

Original signed by H. Steele Roger S. Boyd, Assistant Director fox Reactor 'Pro)ects Division of Reactor Licensing Knclosures: As stated above

TIRT.~ '9 T2 OFFICE W

SURNAME W .....HS.te.eLel~.. 7/31/67 DATE > poem AEC 318 (IIov.043) U.S. COVFRN kfHT ((Rl NT IN(> CFFICF 1~2 I1W20 $',xj. .'aoZ0 Lsd'i «3'ai Q "* QIqqu8 3rribos8 ill.G aalbsog R QCH (S) oLooaBH:i1s«0 byoi .8 «ovoLvo8 .RooT LJo779N ~ l ~ L II, ~ >wkl6 '.wr ~ w se A .. "s c' ' Distribution: ~cc'Lcr UNITED STATES Suppl ~= ~O ATOMIC ENERGY COMMISSION DRK Heading 0 WASHINGTON. D.C. 20545 AD/HP Heading ~S Orang. H. S. BoyIi ,o i+ bcc: P. A. Morris or4IIc CI APR I 8 I967 8. Levine J. Newell D. Muller 1IIr~ XOcN&rd Murphy H. Tedesco Chief, Seismology Division C. Long Coast 5 Geodetic Survey H. Ireland ESSA - Vashington Science Center Hockville, Maryland 20850

Dear Mr. Murphy:

Several applications for reactor construction permits or operating licenses are currently being reviewed by you. To aid you in scheduling work on these various projects and to help in assuring that we receive your reports in time to send to the AORS for its review of particular applications we have compiled a list of anticipated deadlines for receiving consultant reports on the various projects. Tn each case we would like to receive your report during the first week of the month bef'ore the project is considered by the ACRS. Considering this, the contemplated schedule for your sending reports to us is as follows:

l. Duke Power Company (Oconee 1 k 2) - May 2. Vermont Yankee (Vermont Yankee) - May // Q- 3. Public Service of Colorado (Ft. St. Vrain) - June g

4. PQ8:E (Diablo Can - June Q 3-'7 5. Philadelphia Electric (Peach Bottom 2 gc 3) - July j

6. Virginia ELectric {Surry 1 gc 2) - August 7. Jersey Central (Oyster Creek) - August ).I g 8. Public Service of N.J. (Burlington) - October ) Yi- I-/+

Some of these project deadlines will likely slip from time to time. Therefore, l would expect to send you revised listings on a periodic basis. Sincerely yours,

OrIgmal sIgIIed by; Roger S. Boyd

Roger S. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing d:th II/17/67 N

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P Distribution: Suppl.+ DRL Rdg. RSPRSB Rdg. Orig: HSteele (2) Docket No. 50-275 E. G. Case FEB 6 1967 R. S. Boyd K. Voodard JJ F. Newell

Hx. Leonard Hurphy Chief, Seismology Division

ESSA - tfashington Science Center Rochville, kfaryland 20852 Deax't. Hurphy: In accordance vith the understandings which vere reflected in Chairman Seaboxg's letter of October 3, 1963 to Admixal Karo,. X am forvarding herevith Volumes X and XX of the Px'eliminary Safety Analysis Report filed by Pacific Gas and Electric Company for the proposed construction and operation of a pressurised vater nuclear reactor at its Diablo Canyon. site in San Luis Obispo County, California. Preliminary ipformation relating to the Diablo Canyon 1966. site was transmitted. to you vith our letter of October 7,

Ue would appreciate x'eceiving the results of a review by the Coast and Geodetic Survey concerning seismological charactexistics of the proposed x'eactor location which may have'a bearing upon our evaluation of the suitability of the proposed site. vould On the basis of oux tentative schedule for this project, it be desixable to have your repoxt available for our use by April 15, 1967. Sincexely youxs,

Original sisncd bX E. Q. Case

Edson G. Case, Deputy Director Division of Reactor Licensing

Enclosuxesx A,s stated above

OFFICE > ..DRL

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C'ap OCT 1 2 1S66

Mr. Xecnard. Murphy Chief~ Seism1ogy Mvision U S Coast &, Geodetic Survey ZSBA - UI:&in@ton Science Center BMg. Ho. 1i Rn. C-23 RcchvQle, Thailand 2023$ Dear I.h', Murphy: Cur lettex of October 7, Io|~6 transacted to your office c preliminary report prepared by Pacific t'as and Electric CcnIpany on its proposed XCablo Canyon Site, Zaclcsed are t0o colored photographs which shcuM be inserted in the envelope in Appendix 3 of that report. Sincerely yours>

OIIginai signed iIy Roger S. Boyd

son 6. Case~ Assistant Director Division of'eactor Licensing Zuclosures. 2 Photcgraphs

Distribution 9) XBI'eading R&PRSB Beading bcc: Z. G. Case X'. Iforian O'. Resell R. S. Boyd

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Leonard Murphy Chief', Seismology Division U. S. Coast 8c, Ge odet ic Survey ESSA - Mashington Sc ience Center o - %7s Bldg. No. 1 ~ Rm. C-23 Roclor1lle, Nary1and 20235 Dear Mr. Murphy:

ln accordance with the understandings which were reflected in Chairman Seaborg's letter of October 3~ 1963 to Admiral, Karo~ I am forwarding herewith a request for a prel9mfaary site review submitted by the Pacific Gas and Electric Company., Tbis review involves the siting of the Company's proposed nuclear power plant at its site near Diab3.o Canyon~ California. As you wi11 note~ this s ite is quite near the Cayucos Site previously reviewed by. the Coast 5 Geodetic Survey. Ve would appreciate receiving, by early November 1966, a draft report of the results of' prelindaary review by the Coast 5 Geodetic Survey concerning seismological characteristics of the proposed reactor 1ocati on whhach may have a 'bearing upon our evaluation of the suit ability of the proposed site . Please note that the informat ion con- tained in the enclosure should not be released or discussed publicly at this time. Sincere~

yours'riginal signed by p. G, Case Zdson G. Case, Assistant Director Division of Reactor Licensing

'nclosure:. Prel iminary Site Rpt.

WS3L, DRL DFFICE t R RS god: t SURNAME >

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WV1S 197~ Docket No 50-275/323 Dr. Isaac Van der Hoven, Chief r, :.-,Air Resources Environmektal Laboratory . National Oceanic & Atmospheric Administration 8060 13th Street Silver Spring, dryland 20910 SUB'~- A~KND~<~T (27) TO DIABLO CANYON 1 & 2 REPORT " 9I fll 2tt Mj 1 facility is being tranmlitted separately for your infozration. Please notify our branch of receiving-or not receiving the subject material '~ — by retund~ a copy of this letter or phone (301) 492 —7258.

N PSM Voluzes

Ar~~t No. To PSAR Dab 8 5-2-75 (Rec'd 5/6/75) nt No To Environ. Rpt. Dated

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William P. Gammi3.1, Chief . Site Ana1ysis Branch Division of Technical Review Office of Nuclear Ebmctor Ebagulatian Cc: Docket File J. Fairobent J. Osloond

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MAR 28 1S74

Do ol> Eo. 50-275/323

Dr. Xssac Yan dcr Hoven, Chief Air Resources Environmeutal Laboratory National Oceanic 6 Atmospheric AdnLxdstration 8060 - 13th Street Silver Spriag, Kmyland 20910 Dear Dr. Van der Hovcn: Your assistance is requested in evaluating the meteorological analysis of diffusion characteristics as presented by the applicant for the Diablo Canyon Station. The Final Safety Anal''sis Reports have been submitted as part of the operating license application for tvo units in San Luis Obispo County> California.

Voluke one (I) of the PSAR arith amendments 1 and 2 frere sent. to you separately (3/27/74).

> Xn or'der to complate our position input scheduled for 3/29/74, 'our evaluation results are needed as ~lose to that date as posoipleo DZSTqkunON: Sincerely, Docket File L-Rdg L-S)J3 L>m/SS Qilliam P Cammf.ll, Chief > cc: 'QHrons Site Analysis Branch Et&rkee Directorate of Licensing Josloond

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)h. Donald. H. Pack, Acting Director Air Resources Laboratory Environmental Science Services Administration 8060 - 13th Street Silver Spring, Maryland. 20910

Dear Mr. Pack: For your information, I enclose a copy of a Safety Evaluation dated. January 23, 1968, prepared. by the Division of Reactor Licensing in the matter of Pacific Gas and, Electric Company Diablo Canyon nuclear Power Plant.

Cmments prepared by ESSA are attached. as Appendices C-1 anal C-2 to this report. Sincerely yours,

Original eigne< bf Robert L~ Tedesco ~

Roger S.~ Boyd, Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure: As stateC above

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TO Peter A.'orris, Director Division of Reactor Licensing SEP 1 1967

PROM ~ It.i Milton Shaw, Director Division of Reactor Development & Technology hhI ) h (V SUBJECT SAFETY ANALYSIS REPORTS 0 r~

RDT !NS:5258

II r t 1 preference is made to the letters of July 25, 1967 and August 18, 1967, August ll, 1967, and August, 17, 1967, from the Division of Reactor Licensing, to the Environmental Science Services Administration refluesting comments on the following safety analysis reports respectively- ") I Zion Station Units 1 and 2 Commonwealth Edison Company Preliminary Safety Analysis Report I Volumes I and II dated July 12, 1967 I and Amendment No. 1 dated August 15, 1967 Diablo Canyon Site ~ Pacific Gas and Electric Company Preliminary Safety Analysis Report '',) Third Supplement dated July 31, 1967 Easton Nuclear Station h Niagara Mohawk Power Corporation Preliminary Safety Analysis Report Volume I, dated August 1, 1967 Review by the Environmental Meteorology Branch, Air Resources Laboratory, ESSA, has now been completed and their comments are attached. Attachments: Three Sets of Comments (Orig. 6r 1 cy.) t r ~ rt, „ h )s C; if I ,r pi hh il th I CI f i) "1 'rtI 1 rhine r~ ri tt r h f I -.r 1 I I!tI

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Diablo Canyon Site Pacific Gas and Electric Company Preliminary Safety Analysis Report O' "TP'~'WC""""Y('f'1 Third Supplement dated July 31, 1967 I'~v HAIL c'x ill ct&~ VMCTloil Prepared by Environmental Meteorology Branch Institute for Atmospheric Sciences Environmental Science Services Administration August 28, 1967

In regard to question VII.G.5, it is obvious from the comparison made by the applicant that there is very little difference beyond the first 300 meters between using a virtual point source or a volumetric source technique to account for added building-induced diffusion. It should be pointed out that both techniques are an empirical means to account for a phenomena which is not clearly understood but which is observed. For comparative purposes it is interesting to note the ratio between concentrations without accounting for building turbulence and the volumetric approach. The table below shows the Diablo Canyon calculations compared to recent field tests at the National Reactor Testing Station conducted under inversion conditions and moderate wind speeds (u = 6.3 m/sec).

II Distance (meters) Diablo Can on EBR-II Tests

100 3.5 200 4.2 300 9.8 400 6.2 3.9 600 3 ~ 2 700 3.2 800 2 ' 1000 2 ' Extrapolating the results, one would conclude that an, added dilution factor of 2.8 is reasonable at the site boundary of 800 m. I ~ re

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Hr. Donald 'H. Pack, Acting Director Air Resources Laboratory Environmental Science Services Administration 8060 - 13th Street Silver Spring, Maryland 20910 Dear Hr. Pack:

A copy of the Third Supplement to the Preliminary Safety Analysis Report for the nuclear:reactor which Pacific Gas and Electric Company proposes to construct and operate at its Diablo Canyon Site is enclosed for your, use.

The supplement contains additional technical data in the form of answers to questions raised by the Commission. Sincerely yours,

Original signed by P.~ Steele

Roger S.~ Boyd, Assistant Director Xor Reactor Pro)acts Division of Reactor Licensing Enclosure: Third Suppl. to PSAR (Diablo Canyon 'Site)

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Mr; Donald H." Pack, Acting Director Air Resources Laboratory Enviroxmenta1 Science

Services'dministration 8060 -'3th Stx'eet Silver Spring, Maryland 20910 Deax'er. Pack

Copies of Amendments Mos. 1 and 2 to Pacific Cas and Electric Company's facility license application are enclosed for your use.

The amendments consist of the First and Second Supplements to the Preliminary Safety Analysis Report for the proposed Diablo Canyon nuclear reactor, and contain additional technical data requested by the Commission. Sincerely youx's, Original signed by g. Steele

Roger S. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing Enclosures: As stated above

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' h thht Pr(p U. S. DEPARTMENT OF COMMERCE ENVIRONMENTALSCIENCE SERVICES ADMINISTRATION Silver Spring, Maryland 20910 April 25, 1967 'frqtff pt +

INSTITUTES FOR ENVIRONMENTAL RESEARCH INSTITUTE FOR EARTH SCIENCES IN REPLY REFER TO: INSTITUTE FOR OCEANOGRAPHY R323 INSTITUTE FOR ATMOSPfIEIIIC SCIENCES h INSTITUTE f OR TELECOMMUNICATION SCIENCES ANO AERONOMY OFFICE OF ADMINISTRATIVE f SUPPOIIT SERVICES

Mr. Roger S. Boyd Assistant Director for Reactor Projects Division of Reactor Licensing m75 U. S. Atomic Energy Commission Washington, D. C. 20545

~,( Dear Mr. Boyd, "I In reply to your letter of April 18, 1967 regarding the current list of reactor license applications now being reviewed by us, all but two now being reviewed have been completed and comments forwarded to you through the Division of Reactor Development and Technology. Our list with the date that the comments were forwarded is as follows:

l. Oconee 1 and 2, 12/21/66; 2. Vermont Yankee, 12/13/66. 3. Pt. St. Vrain, 1/18/67.

4. Diablo Canyon, 3/20/67.'. Peach Bottom 2 and 3 (Being Reviewed). 6. Surry 1 and 2 (Being Reviewed). 7. Oyster Creek, 4/11/,67. 8. Burlington, 3/6/67. r

I If there is any discrepancy please let us know as soon as possible. ( l Yours truly,

r / (rr fag()("P( '( g ( g Donald HE Pack, Acting Director Air Resources Laboratory Institute for Atmospheric Sciences h CC: Dr. I. Van,der Hoven, EMB,ARL

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Distribution: ~glcr pp4, 4g UNITED STATES Suppl.'RL OM IC ENERGY COMMISSION Rea ing « AD/HP Heading 0 WASHINGTON. D.C. 20545 Orig: R. S. Boyd d APR 1 8 f967 bcc: P. A. Morris r4rrs 0< S. Levine J. Hewell Mri Donall H. Pack D. Muller Acting Director R. Tedesco Air Resources Laboratory C. Long Env9.ronmental Science Services Administration R. Ireland 13th Street '060 I Silver Sprina, Maryland 20/10 Q 0 m/$ Dear Nr. Pack! Several applications for reactor construction permits or operating licenses are currently being reviewed by you. To aid you in scheduling work on these various projects and to help in assuring that we receive your reports in time to send to the ACRS for its review of particular applications we have compiled a list of anticipated deadlines for receiving consultant reports on the various projects. In each case we would like to receive your report during the first week of the month before the project is considered by the ACRS. Considering this, the contemplated schedule for your sending reports to us is as follows:

1. Duke Power Company (Oconee 1 &: 2) - May 4 2. Vermont Yankee (Vermont Yankee) - May

3. Public Service of Colorado (Ft. St. Vrain) - June

4. PG&cE (Diablo C ) - June

5. Philadelphia Electric (Peach Bottom 2 &: 3) - July I 6. Virginia Electric (Surry 1 8'4 2) - August

7. Jersey Central (Oyster Creek) - August 8. Public Service of N.J. (Burlington) - October

Some of these project deadlines will likely slip from time to time. Therefore, I would expect to send you revised listings on a periodic basis. Sincerely yours,

Original signed by: Roper S. Boyd

Roger S. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing

B yd: h I 1 /67

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I HAZARDS SUHHARY REPORT

RDT:NS:S117

Reference is made to the letter of February 6, 1967, from the Division of Reactor Licensing to the Environmental Science Services Administration requesting comments on the following safety analysis report:

Diablo Canyon Site Pacific Gas and Electric Company Preliminary Safety Analysis Report Volumes I and II dated January"18~ 1967 Review by the Environmental Meteorology 3ranch, Air Resources Laboratory, ESSA, has now been completed and by copy of this memorandum, we are transmitting their comments to Mr. P. A. Morris,. Director, DRL. cc: P. A, Morris, Director, DRL, w/attach, (Orig. & 1 Cy.)W.—~~ iW r %fp ., ~ 0- % &la ,1

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Diablo Canyon Site Pacific Gas and Electric Company Preliminary Safety Analysis Report Volumes I and II dated January 18, 1967

Prepared by Environmental Meteorology Branch Institute for Atmospheric Sciences March 20, 1967

As discussed in our comments on October 19, 1966, the important features of the transport and diffusion climate of the Diablo Canyon site are the high frequency of onshore winds from the west and northwest, the persistent occurrence of a marine inversion at about a height of 1000 to 2000 feet above sea level and the rough mountainous terrain rising to a height of over 1000 feet within a distance of 3000 feet from the shoreline. While at first glance the semi-permanent existence of a marine inversion would suggest poor dilution conditions, it is necessary to consider that good dilution usually exists under the inversion lid during the daytime onshore flow. Thus, an effluent released at the site near the ground would probably undergo considerable mixing in the first mile or so before being restri.cted in the vertical by the inversion aloft, The stabilizing effect of air trajectories over a smooth, cold water surface before reaching the site is rapidily changed to an unstable effect within a few hundred feet of travel over rough and heated inland terrain.

The diffusion parameters used to calculate, the site dispersion factors (Table 2-4) are conservative. A ground source is assumed as well as inversion conditions (Pasquill F) with a wind speed of 1 m/sec for periods up to 24 hours. No credit is taken for the meandering of the wind direction over a 24 hour period, The adjust- ment to take into account building - induced turbulence amounts to a factor of 4 at the site boundary of 800m, which is reasonable. It is noted that a comprehensive on-site meteorological program is planned including a meteorological tower at the reactor site and on the 914-ft on-site hill's well as surface measurements at four other locations and a series of smoke and fluorescent particle tracer tests.

In summary, no, unusual meteorological aspects are anticipated with regard to the safety analysis of the Diablo Canyon site. The assumption of a ground level source, low wind speed, inversion conditions and a constant mean wind direction over a 24-hour period is quite conservative. ;i tt ~

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( '1 Dis tribution; Supp]., +~'46 DRL Rdg. R&PRSB Rdg. HSteele Docket lfo. 50 275 Orig: (2) E. G. Case R. S. Boyd FFB 6 1967 K. Woodard J. P. Nevell

Hr. Donald H. Pack Aix Resoux'ces Laboratory Environnental Science Services Administration 8060.13th Street Silver Spring, Maryland 20910 Xlear th Pack:

Enclosed are Volumes I and XX of the Preliminary'afety Analysis Report filed by Pacific Cns and Electx'ic Cmapany for the proposed construction and operation of a pressurised water nucleax reactor at its Diablo Canyon site in San Luis Obispo County, California. The px'oposed reactor is designed for initial operation at 3250 theaanl megawatts.

Ue auld appreciate xeceiving a report fry the Aix Resources Laboratory, ESSA, on tho aeteozological aspects of the proposed xeactor location T1hich aight have a beaxing upon our safety reVieTFe

On the basis of our tentative schedule for this project, it could be desirable to have your report available for our use by April 15, 1967. Sincexely

yours,'riginnl signod be E. G. Cnsc Mson C. Case, Deputy Directox Division of Reactor Licensing Enclosures: As stated above

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Edson G. Assistant yp . Case, Director DATE: October Division of Reactor Licensing 21p 1966

FRpM . Harold Bernard., Acting Chief Environmental h Sanitary Engineering Br., RDT

SQQJECT HAZARDS SUMMARY REPORT

RDT: NS

Reference is made to your letter of October 7, 1966, to the Environmental Science Services Administration requesting comments on the following: Preliminary Site Report Diablo Canyon San Luis Obispo County, California Dated September $0, 1966

The comments of the Environmental Meteorological Research Branch, ARL, are attached.. Attachments: Comments (orig. h 1 cy. )

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1 Comments on Preliminary Site Report Diablo Canyon San Luis Obispo County, California Dated September 30, 1966

Prepared by

Environmental Meteorology Branch Institute for Atmospheric Sciences October 19, 1966

Two 'important aspects of atmospheric 'transport and diffusion at the Diablo Canyon site along the California coast are the prevailing flow from the west under a persistent low-level temperature inversion and the rough, mountainous terrain landward. As a consequence, because of a prevailing upwind overwater trajectory with inversion conditions which extend through an average depth of 1000 feet, initial diffusion from the proposed reactor site will be poor. However, as the air travels inland, a rapid transition takes place such'hat,- as Edinger f 1] points out from observations, "this surface based inversion is replaced by an actively convective~ slightly superadiabatic layer several hundreds of feet in depth by the time the air has passed only two or, three miles inland".This is generally typical of overwater to overland trajectories but the effect is intensified along this portion of the California c'oast because of rugged terrain and intensive surface heatingi The Diablo site especially, with 1000 ft terrain at the eastern boundary and peaks rising to almost 2000 feet within three miles, will experien'ce this effect, Thus, an important question to be answered is the extent of the'ransition zone from slow'o rapid dilution. The applicant seems well aware of this situation as evidenced by the planned meteorological investigations at 'the site, including measurements on a 100 ft tower on top of the 914 ft hill overlooking the site from the east. Special situations which also should be investigated include flow parallel to the coastline where presumably the forces which tend to break up the inversion would not be as effective as is the case with inland trajectories, Also, 'the actual trajectory,.of'ir which starts from the reactor site in a direction should be determined. For example, nighttime drainage 'eaward flow down Diablo Canyon might possibly travel seaward for only a short , dstance before being affected by the prevailing'esterly flow. This type of flow was observed by Pack and Angell $ 2] at Corral Canyon along the Malibu Coast.

In summary, the Diablo Canyon site is liable to, experience relatively high on5ite effluent concentrations as a result of the rapid downward mixing of initially stable, elevated plumes. Beyond the site boundary at a distance of about a mile, the transition from slow to rapid diffusion will be complete Special cases such as flow parallel to the coast and seaward from the canyon should be considered." E T *

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I.l] Edinger~ J, G,, 1961: "Variability of Low Level Thermal Stratification Over Coastal Terrain in Southern California", University of California, Los Angeles, Weather Bureau Contract CWB»9666, 65 pp.

I 2] Pack, D. H. and Angell, D. K., 1963: "A Preliminary Study of Air Trajectories in the Los Angeles Basin as Derived from Tetroon Flights", Mo thl Weather Review, Vol ~ 91, No 10-12, pp. 583-604. ~ ~ ~ ~ cw'~ ~'I ~ 0 ~ ~

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Ih. Xozsm B., Pack Acting 3ixeetor Air Resources Xeboratory BnrLx~te1 Science Services AfaiatstrtLtian 8060 13th Street SQver Spring, %upland 20glo Ibm'r Xhch: Our Retaker cd; Ceto'her f, ISN transvaal to pour o&ice e yreli&naxy report. yrcSIared "by Pacific Cas,'and ZLectrie Cempany m its XIxcyased 13iabIo Cmgrcn Site Shielded me two colored photcgrayhs eMch ahouht he inserted in the enve1,o~ in Appendix 3 cC'hat aport.

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r) L Mr. Donald H. Pack Acting Director Air Resources Laboratory Environmental Science Services Administration 8060 13th Street Silver Spring, Maryland 20910 Dear Mr. Pack: Enclosed herewith is a request for a preliminary site review submitted by the Pacific Gas and ELectric Company. This review involves the siting of the Company's proposed nuclear power plant at its site near Dia>lo Canyon, California. As you wil3. note, this site is quite near the Cayucos Site previously reviewed by'our group.

4'e would appreciate receiving, by early November 1966, a report of the results of a preliminary review by the Air Resources Laboratory on the meteorological aspects of the proposed reactor locationi which may have a bearing upon our evaluation of the suitability of the proposed site. Please note that the information contained in the enclosure should not be released or discussed publicly at this time. Sincerely yours,

Original signed lIy , E. G, Case

Zdson G., Case~ Assistant Director Division, of Reactor Licensing Enclosure: Preliminary Site Rpt. Distribution: "'9) DRZ Reading R8PRSB Read iTIg bcc: E. G. Case P. NoriMI ewell

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Docket Nos. 50-275 Im 50-323 Dr. Nathan N. Hewmark Consulting Engineerfhng Services 1211 Civil Engineering Building University of Illinois Urbana, Illinois 61801

Dear Dr. Newmark:

Enclosed fs a final draft of our response to the Diablo Canyon Intervenors'pril, 1977 seismic interrogatories. He need to have you review these answers to ascertain that we have correctly characterized your positions on Diablo Canyon seismicity and structures, and also to ascertain whether your views on this matter are fn accord with those of the Staff. Since the replies are already overdue, we would appreciate your expediting your review of the document.

1 Me are also desirous of meeting with you and Dr. Hall at the earliest possible date to review interfaces of your testimony with that of the Staff and the

I am informed .that the NRC Contracts Branch is in the process of working on your contract. Sincerely,

L. Dow Davis Counsel for NRC Staff Enclosure cc (w/o encl.): Dennis Allison Carl Stepp

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SUBJECT.'REVIB< OF GRAFT RESPONSES TO INTERROGATORIES 3 AND 4, DIABLO CANYON UNITS 1 AND 2 (SEB:306, 1111)

Dear Dr. Hewmark:

!Je have recently received two interrogatories pertaining to the Diablo Canyon Units 1 and 2 application, which are related to the seismic re- evaluation of the plant. Enclosed please find two (2) copies of our draft responses to the interrogatories for your review. Your prompt review of the draft responses and your technical comments are hereby requested no later than tiay,6, 1977.

He are also sending you a paper titled, "Assessment of Seismic Wave Effects on Soil-Structure Interaction" prepared by D. L. Bernreuter of Lawrence Livermre Laboratory for your review and coments. The conclusions reached in this paper may be brought into future ACRS deliberations and hearings.

David C. Jeng, Section A Leader Structural Enaineering Broach Division of Systems Safety Office of Nuclear Reactor Regulation Enclosuresr As Stated

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4 FII IIV RESPONSE TO INTERROGATORY NO. 3

Interro ator No. 3 What reductions in the response spectra for the various buildings of the DCNGS, due to the large foundations of these buildings, constitute proper, conservative values for evaluating the seismic safety of the DCNGS? Please state each and every fact upon which you base this contention.

RESPONSE

It has frequently been observed that structures on large foundations appear to respond with less intensity to earthquakes than do smaller structures and more specifically, than does free- field instrumentation. Several researchers, e.g., Yamahara in 1970, N. Ambraseys in 1975 and R. Scanlan in 1976 (Refs. I thr u 3) have attempted to provide a rational explanation for this observed behavior. These references give, in general, a relation- ship between the average acceleration over the area of the foundations as a function of the relative foundation width compared to the predominent wave length of earthquake input motion.

The NRC staff believes that the following reduction in response spectra for DCNGS structures should be allowed to realistically account for the above described observation:

' Af= Ao where Af = reduced acceleration for foundation

A = acceleration for free field d R= 1- 5 but not less than 0.67 R = response spectra reduction factor = < seismic wave transit time providing a measure of the extent of acceleration averaging effect applicable to the foundation r This reduction factor "R" for DCNGS structures is eatablished based on studies of the spectrum amplification factors obtained from the recorded Pacoima Dam response spectra. The lower limit on R (i.e., 0.67) is kept purposely high for adequate conservatism in the application of this concept to DCNGS structures, in view of the small amount of data upon which the concept is based.

More rigorous discussion of the technical bases for the above described concept is provided in Appendix C, Supplement No. 5 to the Safety Evaluation of the Diablo Canyon Nuclear Power Station, Units No. 1 and 2 (Ref. 4.).

Consistent with the concept of a wave motion of earthquake deformation, there are torsions and tiltings of a building foundation. The torsional effects are accounted for by assuming an eccentricity of horizontal seismic force of 7A of the width of the structures. The tilting effects are judged minimal and neglected in the analysis.

REFERENCES

1. Y. Yamahara, "Ground Motions during Earthquakes and the Input Loss of Earthquake Power to an Excitation of Buildings, Soils and Foundations," Vol 10, No. 2, 1970, pp. 145-161, Tokyo.

2. N. Ambraseys, "Characteristics of Strong Ground Mtion in the Near Field of Small Magnitude Earthquakes," Invited Lecture, Fifth Conference, European Committee for Earth- quake Engineering, Istanbul, September 1975.

3. R. H. Scanlan, "Seismic i!ave Effects on Soil-Structure Interaction," Earthquake Engineering and Structural Dynamics, Vol. 4, 1976, pp. 379-388.

4. N. Newmark, "A Rationale for Development of Design Spectra for Diablo Canyon Reactor Facility," September 1976.

I DRAFT pf

RESPONSE TO DCNGS INTERROGATORY NO. 4

N .4

What value for structural damping for DCNGS do you contend constitutes a proper, conservative value for use in evaluating the seismic safety

of DCNGS? Please state each and every fact upon which you base this contention.

RESPONSE

The damping mechanisms to which structures, systems and components

are subjected, are mainly of two kinds. One is material damping which corresponds to the internal or hysteretic energy dissipation

within the structural material at the microscopic level. The other is system damping which is related to the energy dissipation at macroscopic level, such as, non-linear effects due to concrete

cracking, plastic hinge formation, gap chattering, and interface forces at structural joints, supports, fasteners, etc.

The NRC'taff believes that the structural damping values of Regulatory

Guide 1.61 (Ref. I) are appropriate and conservative values for use

in evaluation of the seismic safety of DCNGS.

According to the Regulatory Guide 1.61, the maximum critical damping values used for the seismic analysis of equipment and large diameter piping is limited to 3% of critical, while the damping values for

-2- DRAFT reinforced concrete structures is 7X of critical for the safe shutdown earthquake (SSE). The technical justification for selection of the 3X damping value for nuclear steam supply systems, equipment and piping at the SSE level was originally based upon judgment of experienced experts such as Or. N. Newmark (Ref. 2). Recent on-site low amplitude damping tests have, however, verified the appropriateness of this selection. Figure 1 (Refs. 3, 4, 5, 6, 7) shows a plot of damping values as a percent of critical damping and the excited level of the primary coolant loop equipment of several plants. The curve shown is an approximate fit of the test data obtained. The data were obtained from forced exci tation tests (via use of vibration generators) and measured earthquake responses of plant systems and components. These values are for low amplitudes of excitation

(generally judged to be less than OBE level). For larger amplitudes of excitation (SSE level), the damping would increase considerably.

As can be seen from Fig. 1, the selection of 3 to 4/ damping value for NSS components and large diameter piping is considered to be conservative.

From Figure 1, it is seen that observed damping values increase with increasing response amplitudes. This same trend is also shown in

Figure 2, (Ref. 8), which is the results of a survey of several buildings in the Los Angeles area subject to the San Fernando Earthquake.

The recommended 7C of critical damping at the SSE excitation level for reinforced concrete structures was also established primarily on the basis of engineering judgment combined with very limited test data available during the late Sixties to early Seventies.

However, since the publication of Regulatory Guide 1.61 in 1973, considerable experimental damping data at low to medium excitation amplitude levels have been generated. Table 1 (Refs. 8 thru 16) is the results of a survey of these more recent data which provide supportive evidences for the selected 7X damping value applicable to reinforced concrete structures subjected to SSE level motions.

It is noted that the damping values specified in Regulatory Guide 1.61 are, in general, applicable to seismic design of all nuclear plants. For the DCNGS which was originally designed for a safe shutdown earthquake of 0.40g, the damping values of Category I structures systems and components are likely to be greater in the event of a postulated safe shutdown earthquake of the order of 0.75g, resulting from the presence of the nearby Hosgri fault. This is due to the fact that the strain levels of the structures, systems and components are likely to be higher than those strain levels the plants are originally designed for. However, for conservatism, this likely increase 'in damoino values is disregarded and the values of \ 4- DRAFT

Regulatory Guide 1.61 are used in seismic analysis of the DCNGS.

As demonstrated in the above discussions, the selection of the

damping values used for the analysis of the DCNGS is based on the

results of many experimental investigations as well as engineering judgments of experts in the field of earthquake engineering. lie

believe that these damping values are adequate and when used in

conjunction with the NRC staff approved seismic design criteria, should yield conservative results f'r the evaluation of seismic

design adequacy of the DCNGS.

REFERENCES

1. NRC Regulatory Guide 1.61, "Damping Values for Seismic Design of Nuclear Power Plants," Published October 1973.

2. N. Newmark, et al, "Seismic Design Spectra for Nuclear Power Plants," Journal of the Power Division, ASCE, Vol. 99, Nov. 1973, pp. 287-303. 3. Ibanez, P., et. al., "San Onofre Nuclear Genreating Station Vibration Tests," UCLA-'ENG-7073, August 1970. 4. Matthiesen, R.B., et. al., "San Onofre Nuclear Generating Station Supplementary Vibration Tests," UCLA-ENG-7095, December 1970.

5. Smith, C.B., et. al., "Response of San Onofre Nuclear Generating Station to Earthquakes," UCLA-ENG-7151, July 1971.

6. EGCR Blast Test Project Group, "BLAST (Interim Report)", UCLA- ENG-7081, October 1970. 7. Smith, C.B., and Matthiesen, R.B., "Forced Vibration Tests of the Experimental Gas-Cooled Reactor (EGCR)," UCLA Report No. 69-42, August 1969.

8. G. C. Hart, M. Lew and R. DiJulio, Jr., "High-Rise Building Response: Damping and Period Nonlinearities," Fifth World Conference on Earthquake Engineering, Rome 1973.

9. P. Jennings, et. al., "HystemticResponse of a Nine-Story Reinforced Concrete Building," Earth uake En ineerin and Structural D namics, Vol. 3, 1974. 10. N.M. Newmark, "Seismic Response of Reactor Facility Components," ASME First National Congress on Pressure Vessels and Piping, San Francisco, CA, May 1971.

11. J.A. Blume, "Summary of Current Seismic Design Criteria for Nuclear Reactor Facilities," September 1967.

12. A. Morrone, "Damping Values of Nuclear Power Components," Westinghouse Corporation, WCAP - 7921.

13. J. Blume, "The Motion and Damping of Buildings Relative to Seismic Response Spectra", Bulletin of the Seismic Societ of America, Vol. 60, No. 1, pp. 231-259, Feb. 1970.

14. G. Hart, et. al., "Damping in Nuclear Reactors", Fifth World Conference on Earthquake Engineering, Rome 1973. 15. Havil and, et. al., "A Study of the Uncertanties in the Funda- mental Translational Periods and Damping Values for Real Buildings," MIT Publication No. R76-12, February 1976. 16. Carpenter, et. al., "Structural Walls in Earthquake Resistance Structures, Experimental Program," Portland Cement Association, August 1975.

O San Onofre Steam Generator — S. Fernando Earthquake San Onofre Steam Generator — Vibration Generators H Indian Point No. 2 Steam Generator 8 Oak Ridge EGCR Steam Generator X San Onofre Pressurizer — Vibration Generators b San Onofre Pump — Vibration Generators V Indian Point No. 2 Coolant Pump

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1. ItiTRQOUCT IOl<

. It is normallyop assumed in the seismic analysis of structures that the free-field motion

u:.I! ch l s us,'u as iAput i s the same f>. a Ig } no'n «> on a g i vega I eve I bc npa «h th~ s oun«, i . 'ofl

mat. This represents a sim lif''.,p i ica.ion, as no all particles oi soil describe tne sa.-..e motion simultaneously. As the foundation mat of the structure is rigid in the horizontal direction, it will tend to avere age the ground motion. Abandoning the assumptionion'rib'sendof the ~= ""> ~ 'p'' 'y '. inp.. a.ion .-.av iaad to a redo"-io~«as re'e«s i'Isg at i onamot ' ' "' .-e - - =oundation ma: wiil experience as .h oispgacement components.. will.'i cancel each other to a r',certain extent. This is of consid erable the design of nuclear power interest for plants which are very stiff, large structures. To investigate these effects, the extremely complex phenomenon of the passage of a seismic wave has to be sin',plifi'ed considerably, Typically, the basemat is assumed to be ri'g'id anand th soil is represented by simple soi'I springs, e.gap Scanlan [1] shows that averaging a passing compressive wave for which the directioni ec ions o f wave propagation and seismic retion coincide results in a different effective "single-point" earthquake, which shakes the structure in the classical manner used for seismic analysis. tfewmai k [2j and Yamahara [3] use slightly. different approaches to derive at the same basic results as Scanlan. Both Newmark and Yamahara present some data to support their basic, results. Becauseecause of the potential importance of wave passage and the fact that a number of simplification must be introduced into the analysis it wou ld be use fu 1 to determine if the phenomenon actually exists. It is the purposeu of this paper to determine if wave passage effects can be determined from the simplified analyses currently used. 2. REVIEW OF BASIC THEORY AND RESULTS A number of slightly different approaches have been used to develop thee basicasic theoreory.. n [ is e most .complete and reasonably typical. Hence, his model and results can be used to identify the main simplifying assumptions common to most models and to obtain an order of magnitude estimate of the reduction of the free-field around motion projectedc e by the theory.

In Scanlan's [[1JJ modelel, the basemat is represented by a rectangular rigid foundation , . resting on top of the soil and connected to the soil by a continuously distributed set of soil springs. The seismic input is'pa lie d at the base of the soil springs'and is assumed to be of the form

u(t) = A Cos m t + p 7 n n n C s where a

h„cos (u„s + p„) = FourSer expansion of surface accelerogran

C = appropriate wave train velocity.

~or perfumed under the auspSces of the U.S. Enernergy Researchn & Development Administration under contract tlo. W-7405-Eng-48

y ' The term u x/C in eq. (1) approximates the fact that the wave train is traveling across the site. Scanlan considers two cases: the 'first case is when the soil particle motion is in i " ~ .i.on as t.. wave ls :r..v .ling ~rr 'he so"ond :s wnen the so! pa:".'cle motion is transverse to the direction oi the»ave motion. Scanlan shows that tne traveling wave can be replaced by an averaged time history applied simultaneously at the base of the soil springs. Scanlan found that for both cases that

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L = foundation dimension

A plot of K /A is shown on Fi'gureu e 1, The important thing to note from Figure 1 is that ~ n n the theory predicts that the net effect of the traveling wave is to effectively reduce the "higher frequencies." High frequencies in this case are defined relative to the average traveling wave train velocity and the foundation dimension L. In addition, Scanlan found that a torsional motion wou ld be exes te d even in syametric structures. This torsional motion is generally not included in typical soil structure ' interaction anal ysis. For the syneetnc case, there is of course,.'no torsional motions induced when the same motion is input at every point under the, structure. Thus, it is not possible to come up with an expression conpletely equivalent to eq. (2). However, Scanlan shows that tot siona'1 behavior is very similar. I 3. CHOICE OF AH APPROPRIATE MAVE VELOCITY

It is seen from eq. (2) and Figure 1 that the assumed wave train velocity is an extremely important parameter. If the important part of the ground motion is from surface waves, then the appropriate average velocity can be obtained. However, in the'reasonably near field of an earthquake, a number of complex arrivals give rise to the strong motion Thus, many of the arrivals recorded at two nearby instruments would be associated with the high apparent wave velocities of the lower layers, Oecause strong motion instruments are typically triggered at some threshold level, little data exists from actual earthquakes which can be used to estimate the wave velocities ' associated with the strong motion. Considerabl e da ta exis s from underground nuclear ' explosions which can be used t make reasonable estimates of the apparent wave train velocity, Tamura et al. [4] and Tsuchida et al, [5] published results obtained from two

-3- d ifferent arrays of accelerometers located on soft alluvial nround. For both arrays the apparent wave velocity was computed by obtaining the time lags from a cross-correlation of

the records reco."ded at the various instrumentss, Tamura. ~»I... . [».[' es;imated a wave velocity " " o naa,"iy ".'.;.ec as the trave velocity T""c"idaJV ~ ~ et a' [dg obb aire~ a so".ennuii gc = ".r variation in their results in that the wave velocity varied between 2.6 to 5.3 km/sec. lt should be noted that these velocities are much larger than the wave velocities of the near sureacd layers. /Cry siml .al resul is al e obtI i'n ~dd ii da~a obtained trom un~ergroun'Uc aar expl"'sions. son> is used. 'n th~s case, the recording arrays have a co+non time base. A number of different sets of data were examined and all gave similar results as obtained for the available earth- quake data - namely the apparent wave velocity of the traveling wave train is much higher than, the wave velocities of the near surface layers. 4. AHALYSIS OF AVAILABLEDATA A number of assumptions were made in the various analyses of the wave passage effect, such as, Scanlan's model. The validity of many of these assumptions are difficult to , determine. This suggests that it would be useful to assess the overall effect of wave passage on the response of structures. This can be done byy qua I s ta t >ve Iy comparing the overall response of structures to real traveling waves to that predicted qualitatively by equation (2) to determine if it is important. There are at leaeas t two ways tto dod this. First, the most ide'al case is to comparec m a free-field measurement with a measurement obtained in a building. Because so few cases where this is possible exist, we must also use a second method of comparing the response of an accelerometer located at the basemat of various groups of nearby buildings i~1th different basemat areas. By comparing these to the theory, we should be able to determine if the effect is important. One of the few useful cases is the comparison between the recording in the parking lot and in the Holly>cod storage building during the San Fernando earthquake. Hewmark [2] used this example as evidence for wave passage effects. Figure 2 gives a plot of the ratio of the Four>er Spectral amplitude of the parking lot motion divided by the motion recorded in the basement of the Hollywood storage building Hewmwmar k I 2] was a bl e to predict the differ- ence between the two spectra by using a wave velocity of 0.6 km/sec The value of wave -velocity used by Hewmark is very low as compared with the experimentally obtained wave velocities discussed above. 'f Although few additional cases exist of strong motion recorded both in buildings and nearby in the free-field, there are a number of cases where groups of buildings with different basemat areas have recorded data. lieie can uses eq. ((2)) tto obtainb an estimate of the effect various basemat areas. Figure 3 ilIustrates the averaging as a function of. frequency that would be expected for an average wave velocity of C -" 0.6 km/sec and 3 km/ sec for structures of effective length of 100'nd 300'. The ratio of the Fourier coefficients of the effective time histories for the two different structures is shown. From this figure, we see that the choice of C is very important. 'If, as indicated in Section 3, the appropriate wave velocity is that of the deeper layers (>3 km/sec) then wave passage is not very important, On the other hand, if the value of C used by Hewmark is appropriate, then wave passage effects should be important and observable. Figure 4 shows the location of a group of buildings in the Los Angeles area used in this study, as well as, the basemat areas for these buildings. Figure 5 shows the ratio of 0 -4- the 2"'amped relative velocity spectral amplitude of each building to that of the largest .- basemat t.th 3411 Milshire Building3. There are only slight differences between the two l' l d a'tc.. 5i'e, Of'lj ho ~lvolo>e o ..hoe C a:a i; .,s".on» b'cavsei j we are pr!T"";'y intere":ed in +he overall trend of the data rather than the fine structure of the spectral ratio. The 2'am'amp nd spectra was chosen to smooth out sonic of the violent fluctuations observed in the Fourier spectra and simp'.. 1'fi y interpretation. '' i.ll t,.'.",e t:qhl n fre;uencvt. 'ue u' end, sqteater..' +hen....3 Hz} w> lotttd ox ec'--.; " on e asis 0 Figure 3 --

changein the ratio is betvieen 1 and 3 Hz. However, the response shown on Figure 5 is consistent viith the choice ofo a higher wave velocity for frequencies greater than 3 Hz.. The

3411 Hilshire Building seems to have filtered the ground motion between 1 and 3 Hz as compared to the other buildings. 5. DISCUSSION AND CONClUSIONS'pace limitations preclude the presentation of othero er similarsemi ar data. E.g.,E. a record was obtained in a 14-stor-s ory buildiuilding within 2 km of the Hollywood storagee building.u ng. Thisis spectras ectra was very similarr too thata recorded in the parking lot at the Hollywood storage building and showed no evidence of averaging. Data obtainnd>ne a t th e Humboldt Bay Nuclear Power Plant showed a considerable difference between the free-field and that recorded in the refueling building. Seed, et al. f6] were ablee touo accountacc for this difference [for frequencies greater than 3 Hz] by a soil stru cture interaction analysis neglecting any wave passage effects. The main conclusions that can be reached from this , is'h a t we nee d to actually measure 0 ~ the wave velocity to associate with the traveling wave. Thee avaiav '1 a bl e data seems to suggest a tis velocity is, much larger than the wave velocity of the near surface layers. In addition, comparisons with theor y arere mixedmi in that some some cases appear to support the theory and others do not. But any iinterpretation is difficult because the wave velocity is unknown and has such an important effect onn thee p henomenon. It appears we are seeing many complex effects that clearl y cannot'be lumped together in a simple averaging scheme.

6. ACKHOHLEDGHENTS This study was partly funded by the Nuclear Regulatory Cotamission.

WOTlCE "This report was pre pared S an aeeOunt Or s'vnrk e yt e nhed States Government. Neither e nite tates nor the UnitedU States Energy Research 4 Dc,vcloevelopmcnt Administration, nor any eir employees, nor an'ry o their contractors. ors, or their cm ployce s, makes any

completeness or usefulness of an i a aratus, ~ rod uctct or process disclosed y or sen s t at its use would not privately.owned ru:hts." infringe'4R r eference to a company or product name does not imply approval or recommendation of th d e niversity of California or the U.S. Energy Research &, Development Administration to thee exc Iusion of otheis that may be suitable."

References f' ~ i' S-.~ ic lave E-fec s on Soil-Structure inter'c'' . e I quiche bing .n ~~r...g a,ic S., c., a l 0jna...>c,, ~ (1 «Io) I p 379- 68

[2] Newark, H. H;, Hall, M. J, andd i"organ,Ho J. R., Comparison of Building Responses and ree ie d Notion in Earthquakes," Proc. of the 6th World Conferencee on Ear thqua ke Enrineering, Vol. 3, (1977), 3-01-06.

I [3 j d..Brat 3, h., G.(' cun t".0 ions Our ing Ear;h(",eke and .'Apu Loss of earthquake Power to an Excitation of Buildings," Soils and Foundations, ~'ol. 10 (19?0), pp 145-161.

Tamura, Hoguchi, and Kato, "Earth uake Ob r [4] C., T., K., " on the Surface of Alluvial Soft Groundou , Proc.Pro of the 6th World Conference on Earth-

[5] Tsuchida, H., Kurata, E., and Hayashi', S. , "Qbservation of Earthquake Response of Ground a an er ica Seismometer Arrays," Proc. of 6th Earthquake Engineering, Vol. 2, (1977 ), 2-173-2-17 [[63j S eed, H. B., Valera; J., Tsai, C. F., and Lysmerr. J .. So>1-Structure Interact>on u ay in the Ferndale Earthquake .of June 7, 1975," resentation to the ACRS Seismic Subcommittee lheeting, February 7-9, 1977, Bethesda,ND.

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0. 0.1 10,0 rGG 0 EREQUva rY UZ 0 Mr. Paul Morton Room 642 28 Civic. Center Plaza Santa Ana, California 92701

Dear Hr. Morton:

At the request of Perry Amimoto, I am forwarding copies of various reports relating to the Diablo Canyon Nuclear Power Station.

Enclosed is a copy of the Commission's Pinal Environmental Statement, with Addendum, and our Safety Evaluation Report with Supplements 1-4. He are in the process of locating other related documents and they will be sent to you in the near future. Sincerely,

~ J. C. Stepp, Chief ology and Seismology Branch Division of Site Safety and Environmental Analysis Enclosures: As stated

DIST: DOCKET FILES~(50-275, 50-373) NRR Reading GSB Reading DSE Reading GWilliams JStepp C.

OPPICE~ ST

SURNAME3F3P'SE„.GWILLIAHS.,w 6/24/76 DATE Form AEC.318 >(EST. 9 33) hECbt 0240 0 U. S; OOVERNMENT PRINTINO OPPICEI 1014 SES 1SS lki t V <3 ll k

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rem ~,5 1 pJ 2Iir. Don Bernreuter Lawrence Livermore Labs P. 0. Box 808 3~5 Livermore, California 94550

Dear Don:

Enclosed is a Preliminary Draft of the report "Design Spectrum for Diablo Canyon Plant Facility", prepared by Dr. Newmark. I am sending this to you for your information, but if you have comments l would appreciate your giving me a call. Uith best regards.

Sincerely, I

J. C. Stepp, Chief Geology and Seismology Branch Distribution: Division of Site Safety and Central File GSB Rdg Environmental Analysis NRR Rdg DSE Rdg Enclosure: As stated i"

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DATC~ Form ARC-318 (RcT. 9.33) hZCM 0240 4 U, 4 4OVCRHMCNT rRIHTIN4 OrrICCI IC74 421 ICC e

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Hr. Ted Beeston California Energy Commission 111 Howe Avenue Sacramento, California 95825 Dear lir. Beeston: Pursuant to your request, enclosed, please find the most recent USGS "status of review" reports on the Diablo Canyon 'A 1 Nuclear Power Plant site. Those reports represent review of I ,I the latest studies conducted by utility. lk h) Sincerely,

J. C. Stepp, Chief Geology and Seismology Branch Division of Site Safety and Environmental Analysis Enclosure: As stated cc: w/enclosure Q. Gammill 0. Parr D. Allison

DISTRIBUTION: CENTRAL FILE NRR RDG GSB RDG DSE RDG

OPPICC3P DSE:GS

eURNAMC~ p JCStep :sb

DATC~ 4/20/76 Im hBC.318 (Rer. 9.33) hBCM 0240 0 v e'ovcRNMcNT pRINTINo opplccl Ip74 ecaIee ' 'I

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Dr. N.,N. Hewmark Consulting Engineering Services 1211 Civil Engineering Building Urbana, Illinois 61801

Dear Dr. Newmark:

Attached for your information is a copy of an internal memo I issued containing the minutes of the meeting we had on April 12, 1976, con- cerning the seismic design of Diablo Canyon. Please note Item (5) wherein it was noted that the applicant will be requested to submit a report including the final analysis of the plant seismic capabilities. You will be requested to review his findings and your report to us will essentially be an evaluation of the applicant's report.

I will let you know how things develop in the near future. In the meantime, if you have any comments on the attached minutes, please let me know.

Isa S. Sihweil Structural Engineering Branch Division of Systems Safety Office of Nuclear Reactor Regulation Enclosure

w/o en. bcc: R. Heineman H. Denton R. Maccary R. DeYoung D. Allison

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OPPICd~ DHiNBZ7M7...... ISihweil~ p dVAHAMCW < DATd+ 04/gg/76 POrm hEC.318 (Rdt. 9-S5) AECM 0240 Q U, d, OOVCIIHMCNTPAINTIHO OPPICEI 1074 ~ 520 Idd O'El 9 'R "'~" . ~

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. R. E. Heineman,.Director, Di'vision of Systems Safety, NRR R. R. Maccary, Assistant Director for Engineering,'HRU: ision -of Systems Safety, NRR —.- !

M'' MEETING BETWEEN SEB STAFF AND N NEWMARK CONSULTING ENGINEERING SERVICES CONCERNING DIABLO CANYON, APRIL 12, 1976. '! !

!'efe'rence: "Seismic Wave Effects On Soil Structure Interaction" by R..H. Scanlan,.3rd SMIRT Conference, 1975. !

The SEB met with N. M. Newmark Consulting Engineering Services at the Dulles Airport- Holiday Inn to discuss seismic design requirements for the Diablo Canyon Nuclear Power Plant on April 12, 1976. Representatives from the Division of Project Management and the Office of Executive .Legal Director attended.. A list of attendees is attached. ! Professor Newmark made a presentation on his proposal for the seismic , analysis of the Diablo'Canyon site'which treated modifications and redu'ctions of design response- spectra and considerations relating to ~ ,* . and At the'equest of the SEB, ratios were ' tiTting torsion. ductility ~ also discussed. After several exchanges of views'the following con- . " clusions were agreed upon:

S The. applicant will be. asked to specify a magnitude 7.'5 earthquake ~ '. .at.-the'.HOSGRI fault with horizontal spectra -normalized .to 0.75g. Regu1ato'qy'uide'.60'spectral shapes may be used. Use of the HOSGRI. spectral shape will require- further justification since it is. believed 'that the HOSGRI spectral "shape was developed for lower magnitude earth- . . quakes. ' ~ ~ ~ ! 2. . A. reduction. in both h'orizontal and ver'tical respon'se spectra will be permitted depending on- the actual equivalent length of individual . ~ .".'uildings. This reduction recognizes that ground motions are not synchronized under structures durin'g earthquakes. In other words, different points in the foundation base slab will not,experience ~ :. = .the ma'ximum.free field ground. motion at the. same time. .The equiv- alent length of each individual structure |Iill-be. equal to the square 'root of the building. base slab area. The magnitude of the reduction factor shall be determined as the average of the value from the theoretical procedure given by Scanlan (see Reference) for a h'armonic wave and the value determined using the Pacoima Dam record obtained'in the 1971 San Fernando earthquake. The harmonic

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wave in the Scanlan procedure will be assumed to have a -".frequency of 7 hertz.

3. Where such reduction in response spectra is used, the applicant will be asked to appropriately account for additional tilting and torsion which may result from the nonsynchronized earth- quake motions considered in item 2, above. In reevaluating the capability of the plant structure, systems and components, inelastic behavior may be relied upon to absorb the ground motion energy. Where such a behavior is relied upon, a ductility ratio not exceeding 1.2 may be used in determining seismic loads and motions. For each particular structure where this ductility is relied upon, the applicant will be asked to provide justification and bases for assuring that the increased strains and deformations will not affect the safety functions of the plant systems and structures. This ductility ratio is permitted by the SEB staff for near-field earthquakes, such as those associated with the HOSGRI fault, which tend to have shorter durations of strong motion. It is recognized that for short duration earthquakes, the use of elastic response spectra tends.to produce overly conservative results.

It was also decided that the analytical work required to develop individual response spectra for the various plant buildings will be performed by the applicant and a report will be requested thereafter. The SEB staff and Dr. Newmark will review this report and only thereafter will finalize the SER for release.

- The above procedure is a departure from currently imposed requirements. Items 2 and 3 taken together are felt to be an optional and acceptable. description of the seismic event which could lead to reduced seismic loads in'ome elements and increased loads elsewhere. Item=4 is of criteria which will produce a reduced, yet acceptable,a'relaxation 'argin of'safety. A technical base exists for permitting the reduced safety margin as indicated in item 4.

.lQ >(Hi>~3< Isa S. Sihweil, Chief Structural Engineering Branch Division of Systems Safety

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MEETING BETWEEN SEB STAFF AND N. M. NEMMARK CONSULTING ENGINEERING SERVICES CONCERNING DIABLO CANYON, APRIL 12, 1976;

N. M. Newmark N. M. Newmark Consul ting Engineering Services W. J. Hall N. M. Newmark Consulting Engineering Services D. P. Allison NRC/DPM .0. D. Parr NRC/Or M L. D. Davis NRC/Office of Executive 'Legal Director '. J. Grossman NRC/Office of Executive Legal Director I. Sihweil NRC/DSS geng NRC/DSS K Kapur NRC/DSS F.. Schauer NRC/DSS P. Kuo NRC/DSS J. O'rien NRC/DSS

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Dr. Nathan Newmark Consulting Engineering Service 1211 Civil Engineering Building University of Illinois Urbana, Illinois In the Natter of Pacific Gas and Electric Company (Diablo Canyon Nuclear w Plant, Unit Nos. 1 and 2) Docket Nos. -275 0. . and 50-323 O.L.

Dear Dr. Newmark:

Enclosed for your information is a copy of our reply to Scenic Shoreline's motion to establish a seismic committee for the Diablo Canyon Plant. Also included is a draft of the contentions being raised by the Diablo Canyon Intervenors. Page 5 of that document contains the contentions about geology and seismology. 4 I hope that these documents will help put the upcoming hearings into a better context for you. Sincerely,

L. Dow Davis Counsel for NRC Staff

Enclosures as stated

DISTRIBUTION LIST: Davis Teurtellotte Shapar Engelhardt Grossman OELD Reading Formal Files Reg. Cent PDR/LPDR

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Dr. N. M. Newmark g. L5 Consul ting Engineering Ser vices 1211 Civil Engineering Building Urbana, Il 1 inoi s 61801

Dear Dr. Newmark:

A meeting was held on April 20, 1976, between the NRC staff and PG8E. Dr. John Blume who is a consultant=-to PGEE was'also present.

Me presented to PG&E the position'we 'Jointly developed on the seismic f 0~i|1 C, 1i d 1 f Ap 12th meeting sent to you with my letter dated April 20, 1976. Both 'we , PGSE and Dr. Blume were in general agreement with the approach developed, although they indicated more time is needed to assess its impact on the plant. Dr. Blume also indicated that, in addition to the Scanlan methodology and the information obtained from the Pacoima Dam record, he would like to use the approach developed by Yamahara. The Yamahara paper is attached for your information. Me did not object to Dr. Blume's suggestion since we believe the Yamahara paper to be not significantly different from the Scanlan paper. Regarding the ductility ratio of 1.2 which we decided we can'ive with, PG8E indicated that they would like to use higher ratios. Me explained that it will be very difficult to defend the use of a ductility ratio higher than 1,2, particularly for seismic Category I structures. For non-Category I structures, however, such as the Turbine Building and the Intake Structure, we said we may consider higher ductility ratios.

To minimize actual seismic reanalysis and reevaluation efforts, PGEE indicated that they will attempt to utilize the ductility ratio directly in justifying a reduction in the input response spectra., Together with the reduction in the peak effective acceleration depending on the size, of'individual buildings, they hope to develop spectra lower than-the HOSGRI spectra normalized to 0.5g.

Dr. Blume gave us a preliminary advance copy of his latest paper "Allowable Stresses and Earthquake Performance", a copy of which is attached. A final version of this paper will also be included in a future Amendment to the Diablo Canyon application. The applicant plans to use this paper to qualitatively justify the adequacy, of the plant design in future hearings we ~

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on this plant. We told the applicant and Dr. Blume that we will begin a formal review of this paper. You are accordingly requestedd to review the paper for its technical content and provide us with your comments by May 10, 1976. The review of this paper is con- sidered a part of your effort on the Diablo Canyon plant and any time spent on its review may be, charged to the Diablo Canyon account.

I am planning to closely monitor PGSH's efforts and I will keep you informed of any developments that may occur. P'lease let me know if you have any questions.

Isa S. Sihweil Structural Engineering Branch Division of Systems Safety Office of Vuclear Reactor Regulation

Enclosures: As stated

cc w/o encl: R. Heineman H. Denton R. Haccary R. DeYoung D. Allison, K. Kapur

x27 DSS:SEB I I 0PPICC3P'UIINA pf ISihweil MC Knur

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lk Mrs. Richard Devine 1030 Farrell Road Grover City, California 93433 Dear Mrs. Devine: Your recent letter to the Nuclear Regulatory Commission expressed your concern about the safety of the Diablo Canyon Nuclear Power Plant in view of its nearness to a fault.

The Diablo Canyon plant is extremely well designed and constructed to resist earthquakes. Construction permits were issued in 1968 and 1970 for Units 1 and 2, respectively, at the Diablo Canyon site. Based on the investigations conducted at that'ime the plants were designed to withstand the following earthquakes:

(1) A great earthquake of magnitude 8.5 along the San Andreas fault 48 miles from the plant.

(2) A ma)or earthquake of magnitude 7.25 along the Nacimiento fault 20 miles from the plant. (3) A ma)or earthquake of magnitude 7.5 along the offshore extension of the Santa Ynez fault 50 miles from the plant. r (4) An aftershock of magnitude 6 '5 not associated with a known fault 6 miles from the plant.

Effects on the Diablo CanyIIIn Units of an earthquake centered on the offshor'e fault about 3 1/2 miles from the site are being analyzed in detail by PG&E at our request. The NRd ."staff and consultants are independently evaluating potential shaking at the plant site that could be caused by an earthquake on the fault. Our evaluations will then be reviewed by the Advisory Committee on Reactor Safeguards. Following that review the Atomic Safety and Licensing Board will hold public hearings and make,a decision concerning an operating 1icenSe for the plants. The plant must be shown to be safe before an operating license will be granted. E

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I hope that this is responsive to your concerns about the safety of the Diablo Canyon Nuclear Power Plant.'lease contact my office if you have further questions. Sincerely,

,',.;~no~ Ipn~db), tl 9 OC1IIIcn Harold R. Denton, Director Division of. Site Safety and Environmental Analysis Office of Nuclear Reactor Regulation

DISTRIBUTION: CENTRAL FILE NRR RDG GSB RDG J. Stepp B. Rusche E. Case L. Hulman W. Gammill D. Muller H. Denton R. Boyd W. Regan G. Knighton B. Youngblood M.'roff D. Eisenhut J. Yore E. Hughes D. Allison 0. Parr (NRR II726)

DSE D E B DSE 0FFICS~ OELD H -gQ- SURHAMSW nn:s t p ton 3 3 31/'6 I/A)76 j//76 76 3l...L'.f,.l7 6.

Form hZC-318 (Rsr. 9.H) hKCM 0240 Q V, S, OOVSRNMSNT FRINTIHS OFFIC I IOSA ~ S2d Idd ~ ~

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)97'et No ( 0-27 323 Mr. Stanley R~B ockman 'ranch of Seismicity 6 Risk Analysis Stop 968, Box 52046 Denver Federal Center Denver, Colorado 80225 SUE~- AMENDMENT TO DIABLO CANYON REPORT The following document material p~ining to review of the subject nuclear facility is being trananitteQ separately for your information. Please notify our branch of receiving'r not receiving the subject material by returning a copy of this letter or phone (301) —492 — 7258.

PSAR Volum s

Amendment No. To PSAR DateQ

Amendment No. To Environ. Rpt. DateQ

FSAR Volumes ."" Amendment No: 3'o PSAR DateQ 9/16/75 Other: Amendment sent around 9/19/75.

Hi liam P. gammill, Chief Sate AnaJysz.s Branch Division of Technical Review Office of Nuclear Reactor Regulation cc: c et File R. Hofmann J. Osloond

1

January '28, 1934

Docket No. 50 275/323 Hr John H. Bird QS Army Eng Mst. Los Angeles Corps of Engrs - 300 H Los Angeles Los Angeles, Ca1ifornia 90012

Subject: GEOLOGXC AHD STABXLXTY XHFORHATXOH IH AHEHDHEHT HOo 2 TO DIABLO CAHYOH FIHAL SAFETY AHALYSXS REPORT

E The following documents concerning our review of the subject facility xeextmmaittnddhr2:yuarttI~mlima have been sent separately for your use in review of this site Cl Notice of Receipt of Application.

Draft Environmental Statement, dated

U Final Environmental Statement, dated Safety Evaluation, or Supplement No., 'dated Notice of Hearing on Application for Construction Permit.

Notice of Consideration of Issuance of Facility Operating License.

Application and Safety Analysis Report, Vol. g Amendment No. to Application/SAR, dated

Construction Permit No. CPPR- , dated

Facility Operating License No. DPR- , dated

Technical Specifications, or Change No. , dated

Other:

Directorate of Licensing Site Analysis Bx'anch EIl %%5i%5@ william PE Cammill~ C ief ~ XXÃKQiMX

cc: Docket File Ro HeHullen J Osloond

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1 'DESTRXBUTlOi Docket Pile 50-361 6+0-362 50-275 K 50-323 L:Rdg L:AD/SS 7 1924 .. L:SAB

Station', Corps of Dr. Bob Whalen, Waterways Experiment Engineers'i-San Hwang, Tetxa Tech Hartin Vitousek, University of Hsiang Pang, University of Delavaxe N. R. 'wallace, Bechtel inc.'. Orville T. lagoon, Corps of Engineers R. Weggel, University of California Q. EKllex', National Oceanic 6 Atmospheric Admi'nistration B. Wilson,.Consultant George Carayannis, U.S. Army Coastal Engineexing. Research Ce'nter

AEC STAPP BACKGRO12lD HATE'GAL. ON TSUHAHIS Enclosed for your use are background material developed by the staff and their consultants relating to tsunamis for the San Onofre and Diablo Canyon sites. This information is in a form of excerpts from Safety Evaluation Reports on the sub)ect nuclear pover plant sites and a copy of staff summary analysis as Zollcrrs: (l} Safety Evaluation of the San Onofre Nuclear Generating Station Units 2 and 3; dated October 1972. (2) Staff Summary on Local Ts~ Potential, San Onofxe Huclear Generating Station Units 2 and 3; dated June 1973.

(3) Sugary'azards Analysis of the San Onofxe Nuclear Generating Station Unit 1; dated November 1963. (4) Safety Evaluation for the Diablo Canyon Nuclear Power Plant Unit 1; dated January'.968. (3) Safety Evaluation of the Diablo Canyon Nuclear Pawer Plant Unit 2; dated November 1969.

L. G. HuLmn, Senior Hydraulic Engineer Site Analysis Branch Directoxate of Licensing Enclosures (5): As stated

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I PA PA% Ill N ~ 4@tl ~ 44'S ~ l%7CI 1„ r~ AEC DIS~T.BUTION FOR PART 50 DOCKET MA 'L (TEMPORARY FORM) CONTROL NO: 4947

FILE: CONSULTANT FROM: DATE OF DOC DATE REC'D LTR NEMO RPT OTHER Dept of the Army Washington, D. CD 20314 5-31-74 6-4-74 H. B. Willis TO: ORIG CC OTHER SENT AEC PDR W. P, Gammill 1 signed SENT LOCAL PDR

CLASS UNCLASS PROP INFO INPUT NO C S REC'D DOCKET NO: XXX 50-2 /323

DESCRIPTION: ENCLOSURES: Ltr trans the following: Review Comments on Cut Slope at Diablo Canyon Power Plant

ACKNOWLEDGED DO NOT REMOVE PLANT NAT1E: Diablo Canyon Units 1 & 2 ( 1 cy rec'd )

FOR ACTION/INFORMATXON - -74 GC BUTLER(L) SCEMENCER(L) ZIEMANN(L) REGAN(E) W/ Copies W/ Copies W/ Copies / Copies CLARK(L) STOLZ (L) DICKER(E) P. Gamnill W/ Copies W/ Copies W/ Copies W/ 2Copies PARR(L) VASSALLO(L) KNIGHTON(E) " TT I T.T I n~ T.T I n TT I n ~ ~ T Ie T vv2 avv ~ ~ T vvgk,% v ~ e I vVyavv KNIEL{L) PURPLE (L) YOUNGBLOOD(E) W/ Copies W/ Copies W/ Copies W/ Copies

INTERNAL DISTRIBUTION G FXL TECH REVXEW ENTON" A/T XND AEC PDR HENDRIE GRIMES 'XC ASST BRAI'ItfAN ROOM P-506A OGC, VSCHROEDER GAMMILL DIGGS (L) SALTZHAN HUNTZXNG/STAFF ? 1ACCARY B. HURT KASTNER GEARXN (L) CASE KNXGHT BALLARD GOULBOURNE (L) PLANS GIAHBUSSO PAWLICKI SPANGLER LEE (L) MCDONALD BOYD SHAO MAXGRET (L) DUBE w/Input MOORE (L) (BWR) STELLO ENVIRO REED (E) DEYOUNG (L) (PWR) HOUSTON MULLER SERVICE (L) INFO MILES SKOVHOLT (L) NOVAK DXCKER SHEPPARD (L) CD GOLLER(L) ROSS KNIGHTON SLATER (E) KLECKER P, COLLINS IPPOLITO YOUNGBLOOD SMITH (L) EXSENHUT DENISE TEDESCO REGAN TEETS (L) AOR FILE REG OPR LONG PROJECT LDR WADE (E) FILE & REGION(3) LAINAS WILLIAMS (E) DE THOMPSON (2) NORRIS BENAROYA HARLESS WILSON (L) VOLTE R EXTERNAL DISTRIBUTION 1- LOCAL PDR v TXC (ABERNATHY) (1)(2X 10)'NATIONAL LAB'S 1-PDR-SAN/LA/NY 1- NSIC{BUCHANAN) 1-ASLBP(E/N BldB,1tm 529) 1-GERALD LELLOUCHE 1- ASLB . 1-W. PENNXNGTON, Rm E-201 GT BROOKHAVEN NAT. LAB P, R DAVIS (AEROJET NUCLEAR) 1-CONSULTANT'S 1 ACHED(Ruth Gu~sman)

16- CYS ACRS HOLDING NEWARK/BLUME/AGBABIAN . RM-B-127, GT- 1-GERALD ULRXKSON...ORNL 1 "RD..MULLER..F-309 GT 'T 1-B & H SWXNEBROAD Rm E-201 r

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I ATTENTION OFa- DAEN CWE»S 480-g yg 31 May 1974

~ . 50- 323

Mr. William P. Gammill Chief, Site Analysis Branch Directorate of Licensing Regulation US Atomic Energy Commission

D.C. 20545 'ashington, S JUN4 1974'.S. ACMIC EIIRRQI CDMIllSSlDll RoSolaooTr Mall SIIIIOE

Dear Mr. Gammill:

Your, request for review of the Stability Evaluation of the Power Plant ,Cut Slope of FSAR at Diablo Canyon Site, San Luis Obispo County, Cali- fornia has been completed by our Los Angeles District. Their review comments are inclosed. If you have questions on their comments, it is suggested .that you contact Mr. Fuquay, Los Angeles District, Area Code 213, 688-5470. Sincerely yours,

1 Incl HOMER B, WILLIS As stated Chief, Engineering Division Directorate of Civil Works

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REPLY TO ) ATTENTIONOP) ) DARN C|IE S 31 May 1974

kh. William P. „Gammill Chief, Site Analysis Branch Directorate of Licensing 'Regulation

US Atomic Energy Commission . Washington, D.C., 205''+5

Dear'r. Gammill: Your request for revim of the Stability Evaluation of the Po~Ier'lant Cut Slope of PSAR at. Diablo Canyon Site, San Luis Obispo County, Cali fornia hss been 'completed by our Los Angeles District. Their review comments are inclosed. If you have questions on, their comments, it is suggested that you contact Mr. Puquay, Los Angeles District, Area Code 213, 688 5470+ Sincerely yours,

1 Incl HOMER 3+ WILLIS As stated Chief, Engineering Division Directorate of Civil Works 0 3Q t > )

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SPLED "F 14 March 1974

SUBJECT: Technical Assistance to Atomic Energy Commission, Diablo Canyon Site:

IS'ivision Engineer South Pacific Division ATTN: SPDED-G

1. Reference is made to letter, DAEN-CWE-S, dated 16 October 1973 and 2d Xnd, SPLED-F dated 10 December,1973, subject as above.

2. The data has been received and the review has been made. The comments are attached.

FOR THE DXSTRXCT ENGXNEER:

1 Xncl GARTH A FUQUAY as Chief, Engineering Division ~ ~

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i SPDED-G (14 Mar 74) 1st Xnd SUBJECT: Technical Assistance to Atomic Energy Commission, Diablo Canyon Site

DA, South Pacific Division, Corps of Engineers, 630 Sansome Street Room 1216, San Francisco, California 94111 '7 March 1974 TO: ADA (DAEN-CWE-S) WASH DC 20314 l., As explained in 2d Indorsement of references cited in paragraph 1 of basic, the review comments could not be furnished in the time frame originally requested.. Submittal of all data is now completed and the review comments are inclosed.

2. Two meetings were held with representatives of LAD,, AEC, the power plant owner and his consulting soils engineering company. The last meeting, held 22 February 1974, was.also attended by a representative of SPD and at that meeting the site was (inspected.and the owner and soils consultant answered all questions with regard to their analyses of the slope-stability. The AEC representatives were informally advised at that time of the LAD findings as enumerated by in paragraphs 11-14 of the inclosed review comments.

FOR"'THE DIVISION ENGXNEER:

1 Incl JOHN W. QGERHART nc 'hief, Engineering Division ~y ~ ~

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REVIEW 'COMMENTS

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CUT SLOPE AT DIABLO CANYON POWER PLANT

MARCH 1974 I '

REVIEW COMMENTS ON CUT SLOPE AT DIABLO'CANYON POWER PLANT

1, The Pacific Gas and Electric Company's Amendment No. 2 to Final Safety Analysis Report for Units 1 and 2 at Diablo Canyon Site, San Luis Obispo County, California was received by Los Angeles District on 4 February 1974. As requested by 1st Ind to letter DAEN-CWE-S, dated 16 October 1973, a review has been made of Appendix 2.5c, Stability Evaluation Power Plant Cut Slope of Final Safety Analysis Report.

2. At the request of Atomic Energy Commission on 7 September 1973 the applicant, PG 6 E, had been required to provide basic data and analyses to substantiate the stability of the existing cut slope east of Units 1 and 2 ~ The following data was requested:

a. Static and dynamic engineering properties of the soils and rock underlying the slope, based on results of complete field and laboratory test data.

b, Actual properties and the assumptions for soils and rock used in the stability analyses. c. Description and discussions of stability analyses.

E 3 ~ In order to provide adequate assurance of slope stability the AEC also requested the following:

a, Perform static and dynamic stability analysis, using an acceptable method of analysis,

b. Provide and discuss the failure criteria, the failure modes, and the range of computed factors of safety.

4. The need for the above data and analyses was verified by the LAD at the meeting held on 25 October 1973 '

~ On 21 and 22 February after a preliminary review of the report a meeting and site inspection was held with personnel from ( Q LAD, the AEC, the applicant and.the applicant's Architect»Engineer Harding-Lawson and Associates, The following are comments on the inspection, and review of the investigation, testing, design values and stability analyses for the subject cut slope. «A

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INVESTIGATION AND ANALYSIS

6 ~ The surficial conditions of the slope appears to be satisfactory', The exposed soils on the face of the cut are mostly slope wash consisting of black silty clay and sandy clay. In the lower portion of the slope, colluvium consisting of sandy to gravelly clay underlies the slope wash materials The basal soil unit is represented by ancient marine beach deposits of silty sand and gravel which rest directly on wave cut terraces. The underlying bedrock consists of a tuffaceous to silty sandstone and siltstone, In the upper part of the slope a shallow layer of silty clay overlies the bedrock, The lower portion of the slope has been excavated to about 1 vertical on 2 horizontal. The upper portion of the slope was cut to approximately 1 on 3 ~

7 ~ To explore the subsurface conditions the A-E has drilled 12 test holes varying in depth from 30 to 120 feet, and excavated 8 test pits to depths ranging up to 12 feet, Disturbed and undisturbed samples representative of the soil overburden were obtained for classification and detailed static and cyclic loading tests. Core samples of the rock were tested to deter- mine the shear strength and permeability of the bedrock.

8 ~ From the results of the investigations and laboratory tests it was

concluded that the cut slope consists of four predominant materials'he surficial soils'lope wash, usually less than 10 feet thick, are medium stiff to stiff silty clay containing occasional small rock frag- ments and organic debris, The colluvium, or sandy gravelly clay under- lying the slope wash varies up to 50 feet in thickness. The colluvium is underlain by terrace deposits of silty sand and gravel in the lower portion of the slope. These marine-deposited materials range from 5 feet to a maximum of 17 feet thick in the area investigated, The rock unit underlying the alluvium consists of a tan to brown sandstone and occasional siltstone which is highly weathered from about 5 to 10 feet below the bedrock surface. The bedding planes in the rock generally strike east-west and dips to the north, The dip varies from ver'y steep south of Unit 2 to nearly horizontal in the .center of the slope area.

A review of the data in the Final Safety Analysis Report pertaining to the structural features, and field inspection at the site indicates a few minor fault zones were observed in excavations in the bedrock and other larger and more continuous faults were observed within the mapped areas. None of these faults extend upward into the overlying Quaternary deposits. Information obtained from the U. ST Geological Survey on their study of fault systems in the offshore area has not revealed any recent or active fault trace that would affect the selection of the maximum size earthquakes to be expected during the life of the pro)ect,

Free ground water was not encountered during the exploration performed in the slope area. There was seepage water present in the excavation W ~ «

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9 ~ The selected static and dynamic strength parameters including unit weights were based on results of laboratory tests and field geophysical survey.

10, The Modified Bishop's Method was used to analyze the static stability of the slope, The seismic response of the slope was; analyzed by finite element methods using a computer program developed at the University of California at Berkeley by Lysmer, Udaka, Seed and Hwang, The deformation analysis was based on determination of yield acceleration and the resulting amount of movement when the yield value ds exceeded, The magnitude of horizontal displacement is a function of the shear strength of the materials along the arc analyzed, Curves were developed relating laboratory direct shear data and displacement. In the seismic and deformation analyses the magnitude of acceleration and frequency scales of the designated earthquake were doubled.

EVALUATION

11 'he amount of exploration and sampling has been sufficient to determine the type of materials and cross section of the slope, The testing of representative samples is consistent with the practice of the Corps of Engineers, The selected static and dynamic strength parameters are repre- sentative values of the various materials on the slope based on results of laboratory static direct and triaxial shear tests, and field geophysical survey and laboratory dynamic triaxial shear test results. 12 'sing the adopted unit weights and strengths, checks were made by LAD of the pseudo-static analyses for critical failure surfaces presented in plates 12 and 13 of the Final Safety Analysis Report. The checks were done manually and by computer, In all cases checked, the safety factor was verified. The minimum computed yield acceleration was 0.56 ~ Yield acceleration is defined as the applied seismic coefficient times gravity at which movement would start. The failure plane for the minimum yield acceleration would be within the soil overburden. 13 'he methodology used in the 'dynamic.-analyses is consistent with the latest State-of-the-Art techniques and the results are conservative, It was reported that throughout the course of the investigation, testing and analyses Dr. H, B, Seed was periodically consulted for the dynamic and displacement analyses, A review of the report "Stability Evaluation, Power Plant Cut Slope" by Dr. H. B, Seed has been included in Final Safety Analysis Report, ~ ~

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14. The calculated maximum displacement of 10 inches, resulting from the selected double design earthquake should not cause damage to struc- tures located near the toe of the cut. However, provisions should be made to insure that the condition of the material on the slope is not altered particularly by saturation due to poor surface drainage, C

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?Ir. G. F. firsig, General Manager western Exploration and Production Regional Exploration Shell OQ. Company P. 0. Box 576 Houston, Texas 77001 Dear Mr. Pirsig:

You wexe refexxed to us by Mr. Robert Quitsau of your company, as one who might be able to assist us to obtain or observe Shell geophysical data. The data may help us detexmino safety related seismic engi- neering requirements fox the Diablo Canyon Nuclear generating station.

The data or prepared cross sections we wish to observe are within the area offshore from Point Conception to San Simeon, California. More specifically we are particularly concerned with the location of the fault (about 3 l/2 miles offshore) depicted by lIoslcins and Griffiths, 1973 Bull. $'APG, opposite Point Buchon near San Louis Obispo, California; the possible intersection of that fault, and the Santa Lucia Bank fault (about 27 miles 'offshore), with possible offshore extensions of transverse range faults from Point Arguello south to the Channel, Islands; and the possible continuation towards shore of the Hoskins and Griffiths'eature near San Simeon.

The approximate boundaries of these areas are1

1. Lat. 35 08'30" to 35 lj'30" 120 50'o 120

56'ong 2. Lat. 34 to 34 120 30'o 121 30', 40'. 50'ong. Lat. 35 30'o 35 Long. 121 to 121 17'

sketch map of the area is enclosed.

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,I I We are particularly interested in faulting in bedrock, probably belav X0,000 feet. However, in the absence of deep data, near surface sparker profiling would also be helpful. Any assistance you can provide would be greatly appreciated.

We could visit you on or about the 10th of March. Please advise us if this is convenient for you. Sincerely,

Rcnner B. Hofmann, Seismologist Site Analysis Branch Division of Technical R&iev Office of Nuclear Reactor Regulation (391) 492-9972

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'.'Ianuscrip'C received, llay 4r 19r0, s Geologist, Shell Oil Company. lVe are grateful to SheIJ Oil Company for per- mission to pubIish thLS article and for the great amount of geological and geophysical data provided, as welt as for tho drafdng and clerical help. 4g,

/ DISTRIBUTION: Docket Ho. 50-275/323 L:Docket,pile L Rdg L:SAB L:AD(/SS b cc: THirrons . — LPM lir. E. L. Dodson, Chief ACardone Soil Hechanics Branch JOsloond DAEN-CME-S U.S. Army Corps of Engineers Porrestal Building Washington, D.C. 20314 Dear Hr. Dodson: The assistance of your branch in evaluating slope stability aspects associated vith the Diablo Canyon Site is requested. This site located in San Luis Obispo County, California, vill have tvo units and Pinal, Safety Analysis Reports QPSAR)'re being submitted, for evaluation vith the app3 ication for an operating licensing. Enclosed are acceptance review comments (tvo copies) on the PSAR by our branch geologists for your information. The Geologic and Seismic Section (2.5) of Chapter 2.0 from the Diablo Canyon PSAR is also enclosed for'our further dis- tribution., The scheduled review dates vill be sent vhen established. Reimbursement for evaluation assistance should be charged to contract AT(49-24)-0037. Sincerely,

william P. Gammill, Chief Site Analysis Branch Directorate of Licensing Enclosures: As stated

L: SAB SAB OFFICE P L:

JOsloo N SURNAME > d:ba Pe. ill DATE > 10/3/73 10/ 3 /73 10~/ /73 Form hEC-318 (Rdv. 9-33) hECht 0240 ohio old—1d SNdd ( dl~r8

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Dr, Nathan M Newmark bcc: D Bierly, DR Consulting Engineering Services J. L~ Smith, DC 1114 Civil Engineering Building R. Conaway, OC University of Illinois Urbane, Illinois 61801

Dear Dr Newmark:

Contract No. AT(49-5)-2667

Nathan M, Newmark Consulting Engineering Services is hereby requested, pursuant to the conditions of Contract No. AT(~49-5)»2667, to initiate the following services for the Commission concerning the post-construc- tion permit surveillance for the Pacific Gas and Electric Company's Diablo Canyon, Unit 1 and Uisconsin )Kchigan Power Company's Point Beach, Units 1 and 2~

To review and evaluate the facility design to determine if the structural design criteria previously agreed to during the construction permit review have been properly implemented pursuant to Article I, paragraph (a) (4) of the contxact,

Reporting Requf.rements! Preparation of a report on (1) above pursuant to Article I~ pax'agraph (a) of the contract. All costs shall be itemized and requests for reimbursement shall be submitted, pursuant to Article III of the contxact Any potential conflicts of interest shall be reported pursuant to Article I, paragraph (d) of the contract

Monetary Ceiling: $ 208000

Period of Performance: MAR '7 1969 through June 30, 1969

Other Applicable Requirements: None

OFFICE >

SURNAME >

. DATE>

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Dro Nathan H. Newmark ss MAR V

This constitutes a Mork Directive pursuant to Article X, paragraph (b) of Contract No. AT(49-5)-2667 ~ Sincerely,

Peter A. Harris ~ Director Division of Reactor Licensing (Authorised Representative for the Contracting Officer)

DRL:CgCTB OG DRL ADRT DRL.DIR OFFICE > DeYo Da%ison/sp "7ZP~- Le e MAQ.— SURNAME > Dube 2/26/69 2/~g/69 2/~469 /69 $/ /69 DATE i J

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l, V 'r~ Nathan M~ Newmark bcct D. Bierly, DR Consulting Engineering Services Ji L~ Smfth~ DC KV V 1114 Civil Engineering Buildfng R. Consway, OC University of Illinois Urbsna~ Illinois 61801

v 4 Dear Dr, Newmarkt ,, ~ Contract No AT(49-5)-2667

Nathan M, Newmark Consulting Engineering Services is hereby requested~ pursuant to the conditions of Contract No, AT!(49-5)«2667~ to initiate the following services for the'Commission concerning the post construe tion permit surveill'ance for the Pacific Gas, and Electric Company's Diablo Canyon~ Unit 1 and Qisconsiri Michigan Power Company's Point Beach~ Units 1 and 2i To-review and evaluate the facility design to determine if the structural design criteria previously agreed to durfng thy construction permit review have peen properly, implemented pursuant to Article I~ paragraph (a) (4) of the contract,. 4 Reporting Requirementst Preparation of a report on (1) above ,pursuant to Article I, paragraph (a) of the contract+ All casts shall be

ftemiied and requests for reimbursement:, „ shall be vsubAftted~ pursuant to Article IXX of the contract Any potential conflicts 'of interest shall be reported pursuant to Article Is paragraph (d) of the contract .

4 Monetary Ceilfngt $20~000 ~ Period of Performancet MAR 7 1969, through June" 30~ 1969, Other Applicable Raquirementst 't None II iI II 4 II Ii

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This constitutes a Mork Directive purouant to Article Xq paragraph (b) of Contract No ~ AT(49~5) ~ 2667'incerely ', E

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Dr. Nathan N. Zemaxk 2114 Civil Engineering ItuiMing 'University of Xllinois Urbana, Xllinois 61801

Dear Dx. Esmark:

For your information, X enclose a copy of a Safety Evaluation dateC January 23, .1968, prepared. by the Division of Reactor Licensing in the matter of Pacific Gas snd, Electric Company Diablo, Canyon Nuclear gower Plant.

She report prepared'y Eemnark ant EQ1 is attached. as Appendix P to the safety evaluation. Sincerely yours~

Original signed bIt Robert L. fedesco Roger 8. Xhyd., Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure- As stated. above

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Dr. Nathan N. Newark ll14 Civil Engineering Bui1ding University of Xllino9.s Urbana, Xllinois 61801 Dear Dr. Neman:

A copy of Pacific Gas and Electric Company's 1etter dated December 14, 1967, transmitting revised Page 2 to Amendment Ho. 5 to the application for license~ is enclosed for your use. The revised page refers to the Diablo Canyon Nuclear Unit. Sincerely yours~

oger S. Boyd~ Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure: As stated above

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REG. NOI QGCKETt 90 275 (SUPH ~ CAKY) DESCRIPTIONE IMEEst 80 Uncfosslficd) REFERRED TO DATE RECEIVED SY DATE Xtr reference@ Seo- Boyd«8 f 16 68 TQQQQGto 0 o o ooand harG5gg tranELO 66 foHRwB@s ~~ P PQXQ ENCLOSURESI ( «d) Info Res t assort to thCL me Reaetatoxy Staff cntit1ed "Adequacy Rf the StmetLTral criteria. for th Oiamo Canjjm Site 1Vaelear Mant«" dated, l2 67«hy Famer MC BQQooo ~ SeYceag Distri LLt cna Rr i~luPyio Ale Cgo (XRPrOCTE Xo Co>mar ( c) Cy untQ Rhino 4 malurn ping

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C Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D.C, 20545

Re: Diablo Canyon Report - Docket No. 50-2'/5 ' C Dear Dr. Morris:

In accordance with the request from Roger S. Boyd, dated 16 January 1968, we have reviewed the report to the AEC Regulatory Staff dated December 1967, prepared by Dr. Hall and myself, and compared the copy with the draft prepared by us. One minor point is,.called to your attention. At the bottom of the first paragraph on page 7, the original draft and notes (from the dnd of the first complete paragraph on page 8 of the original draft) indicates that a sentence should be added as follows:

"On this basis, we concur in the design approach adopted."

However, this added statement may not be important, and I believe that the typed copy of the report reflects our views and is in accord with our draft. Therefore I am signing it on page ll and returning a copy to you. I am also returning the amended draft copy, which is marked for Troy Conner.

Thank you for your cooperation. Sincerely yours, ~ ~~a

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~ ~ REPORT TO AEC REGVLATCBY STAFF

ADEQUACY OF TEE STRUCTURAL CRITERIA FCB

THE DIABLO CANYON SITE NUCLEAR PLANT

Pack.fic Gas, an4 Electric Company

(Docket $0-275)

by

N. M. Newmark

W. 'J. Hall

December, 1967 C

~ ~ s ADEQUACY OP THE STRUCTURAL CRITERIA FOR

THE DIABLO CANYON SITE NUCLEAR PLANT by

N. M. Newmark and, W. J. Hall

INTRODUCTION

This report concerns the adequacy of the containment structures and.

components, reactor piping and. reactor internals, for the Diablo Canyon Site

Nuclear Plant, for which application for a.construction permit and. operating t

license has been made to the U. S. Atomic Energy Commission (Docket No. $0-27))

by the Pacific Gas and. Electric Company. The facility is to be located. in San Luis Obispo County, California, 12 miles west southwest of the city of San

Luis Obispo, and. adjacent to the Pacific Ocean and. Diablo Canyon Creek. The

site is about 190 mi3.es south of San Francisco and. 3.50 miles northwest of Los Angeles. Specifically this report is concerned. with the evaluation of the design criteria that determine the ability of the containment system, piping and. reactor internals to withstand. a design earthquake acting simultaneously witp other applicable loafs forming the basis of the design. The facility also is to be designed. to withstand. a maximum earthquake simultaneous'.y with other

applicable 3.oads to the extent of insuring safe shutdown and. containment. This

report is based. on information and. criteria set forth in the preliminary safety analysis report (PSAR) and. supplements thereto as listed. at the en'f this report. We have participated. in discussions with the AEC Regulatory Staff

ant the applicant and. its consultants, in which many of the design criteria were discussed. in detail. I I

I

P 4 DESCRIPTION OF THE FACILITY

The Diablo Canyon Nuclear Plant is described. in the PSAR as a pressurized. water reactor nuclear steam supply system furnished. by the Westinghouse Electric

Corporation and. designed. for an initial power output of 32/0 MWt (1060 MWe net).

The reactor cooling system consists of four closed. reactor coolant loops I connected. in parallel to the reactor vessel,.each provided. with a reactor coolant pump and. a steam generator. The reactor vessel will have an inside diameter of about l4.$ ft., a height of 42.3 ft.~ will operate with a design pressure 0 of'485 psig, a design temperature of 650 F, and. is made of SA-302 grade B low alloy steel internally clad, with type 304 austenitic stainless steel.

The reactor containment structure which .ehcloses the reactor and. steam generators, consists of a steel lined concrete shell in the form of a reinforped. concrete vertical cylinder with a flat base and. hemispherical dome. The cylindrical structure of 140 ft. inside diameter has side walls rising 142 ft. from the liner at the base to the spring line of the dome. The concrete side walls of the cylinder and. the dome will be approximately 3 ft. 6 and. 2 -W. 6 in. in thickness, respectively. The concrete reinforcing steel pattern is described. conceptually in Supplement 1 and. consists of bars oriented. at 30 from the vertical in such a manner that the pattern does not require termination of any bars in the dome; These diagonal bars are designed. to carry both the lateral 7 shear as well as vertical tensile forces. In addition there is hoop reinforcing in the cylindrical portion of the structure. For resistance to radial shears the applicant proposes to use a system of vertical wide flange beams spaced. four feet on centers. The beams are attached. by hinge connections to the base slab at the lower end. and. are terminated. about 20 ft. above the top of the base slab. The function of the beams is to provide resistance to the moments and. shears 1

I created. by the discontinuity at the base and. to provide a graclual transition of load. carrying elements between the base and the cylinder wall. These beams do not participate in resisting, either uplift due to pressure or shear and. tension due to earthquake loading; these forces are to be resisted. by the cU.agonal steel reinforcing gust described.. The concrete wall in this lower zone is divided into three zones. The inner zone, about 1 ft. thick, consists of reinforced. concrete and. is the basement to which the liner is attached.. The middle zone contains the vertical steel I-beams which in turn act as supports for the 16 in. thick reinforced, concrete slab spanning the space between the beams. The outer zone consists of about 14 in. of concrete in which the cLiagonal and. hoop reinforcement are embedded. The three zones are provided with bond.-breaking

ll material to insure that the elements will act separately. The reinforcing steel for the dome, cylindrical waLls and. base mat will be high strength reinforcing conforming to.the ASTM A432 specification. The A432 reinforcing bars of size larger than No. 11 are to be spliced. with Cadweld. splices except in cases where accessibility makes welding mandatory.

The liner, as described. in Supplement 2, will.bb a minimum of P/8 in. thick for the dome and. cylindrical AU.s and. 1/4 in. thick for the base >lab.

The anchor studs are to be L shaped. and. will be fusion welded. to the liner plate.

The studs will be spaced. at the corners of a 20 in. square gricL, and. the design is intended. to preclude ma)or affects arising from buckling of the liner.

Personnel and. equipment access hatches are provided for access to the containment vessel. In addition there are other penetrations for piping and. electrical conduits. The facility includes a sea water intake structure located. at sea level at the base of the cliffwith circulating water conduits and. auxiliary salt water conduits lea&ng to the nuclear plant. l The information on the geology at- the site is described in the PSAR and the several supplements. The bedrock at, the site area is of t'ertiary age and comprises marine shales, sandstone and fine-grained tuffaceous sediments, along with a considerable variety of tuffs of submarine volcanic origin. All these rocks are firm and compact, and are exposed. in the seaward. edge of the terrace on which the plant is to be 'built, which ranges in elevation from 60 to 100 W. above sea level, and is approximately 3.,000 ft. wide. The bedrock is overlain Py marine and non-marine deposits of Pleistocene age. The moor components of the power plant are to be founded. on bedstock in all cases. The site has been wel3. explored and there is no evidence of any significant fault offsets of recent origin. The report by the consulting geologist on the project, Dr. Richard H. Jahns, presented. as Appendix A of the third supplement, concludes that the possibility of fault-induced. permanent ground displacement within the plant area during the useful life of the power plant is sufficiently remote to be safely disregarded.

SOURCES GF STRESSES IN CONTAINMENT STRUCTURE AND TYPE I COMPONENTS The containment structure is to be designed for the following loadings: dead load of the structure; live loads (including construction loads and equipment loads); internal pressure, due to a loss-of-coolant accident, of about

47 psig; test pressure of 54 psig; negative internal pressure of 3.5 psig; stresses arising from thermal expansion; wind loading corresponding to the

Uniform Bd.lding Code - 1964 edition and, corresponding to 87 to 100 mph winds; and est.5iquake,~. loading as described next. The earthquake loading will be based. on -two separate earthquakes, which f'r the design earthquake condition correspond to maximum horizontal ground accelerations of 0.20g or 0.15g. The containment design also will be reviewed for no loss of function using response spectra corresponding to earthquakes of twice the nuud.mum acceleration noted. above~ namely 0.kg and. 0.30g, but with the latter earthquake having a mmdmum ground. velocity corresponding roughly to a value of 0.40g ground. acceleration. The U. S. Coast and. Geodetic Survey report (Ref. 3) concurs in 0.20g and. 0.40g values of maximum ground. acceleration for cLesign and. maximum conditions.

Class I piping and. equipment, as discussed. in Supplements 2 and. 5, will be designed. for normal load,s, (internal pressure, dead. load,, thermal expansion, etc.) combined. with pipe rupture loads and, earthquake loading.

The reactor internals are to be designed. to resist earthquake combined. with blow-down loacLings ant other applicgMe loadings.

COMMENTS ON ADEQUACY OF DESIGN

Seismic Design For this facility the containment design is to be made for two earthquikes corresponding to maxtunun horizontal ground. acchiLerations of 0.20g

(Earthquake D) and. 0.15g (Earthquake B). For the maximum earthquake loading the two earthquakes are characterized. by horizontal ground. accelerations of twice the values gust cited., namely 0.40g and. 0.30g. Spectra corresponding to these earthquakes are presented. as Figs. 2-11 through 2-14 of the PSAR and. again in Supplement No. 3 beginning on page 22, along with an envelope of the spectra for the no-loss-of function condition (Fig. III.A.12-5, Supplement 3).

We concur with the response spectra for the earthquakes when they are used. in the following manner.

Since'he response spectrum values for Earthquake D give values that control for high frequencies, and. for Earthquake 3, values that control for t C -6- intermediate and. low frequencies, both earthquakes must be used. and. the maximum response in either must be considered. to apply to the design or safe shut-down of single degree of freedom elements. This is permissible in view of the fact that Earthquake B gives response values for low and. intermediate frequencies that lie above the response spectrum values from TID 7024 when normalized. to an acceleration of 0.40g. Hence this earthquake .may be considered. to correspond. to a 0.40g earthquake for low and. intermediate frequencies. However, for safe shut-down of multi-Legree-of-freedom systems~ we take the position that the combined. or envelope spectrom for the two earthquakes I must be used. in order to avoid. a possible deficiency in the provision for safe shut-down. This envelope spectrum is consistent with an El Centro type'esponse spectrum for a maxinnm„grouzxl acceleration of 0.40g. With regard, to the method. of analysis of the containment structure~ it is noted. on page 2-29 of the PSAR that all modes having a period. greater than 0.08 secs. will be included. in the analysis and. that in addition for components or structures having multiple degrees of freedom, aU. significant modes, and. in no case less than 3 modes, will 'be considered.. It is further stated. that for single degree of freedom systems, the funclamental mode of vibration will be used. in the analysis. The applicant has agreed. however that for a single degree of freedom system, no matter what the period, whether it is above or below 0.08 secs., the appropriate period. and. spectral acceleration will be employed. in the design, and. further that for multiple degree of freedom systems all significant modes will be considered,. On this basis, we concur with the approach.

The method. of dymutd.c analysis is described. in Sections 2 and. 5 of the

PSAR and. again in answer to Question III.A.15 of Supplement 1. It is noted. C

4 w7 w that the dynamic analysis to be followed. for the Class I components aIKl structures is the modal participation factor method. Further the mochl analysis may be carried. out either through the use directly of the smoothed. spectra, or employing a time history of ground motion, employing earthquake records with amplitude values scaled. which lead. to essentially the same smoothed. spectra. Discussion of this point is presented. by the applicant in answer to question III.A.13 in Supplement 3. We concur in the use of the modal participation method. in the analysis and. 4esign, as well as the use of

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'ither provided. the smoothed. spectra or the time history inputr,"method., that ~ „. the time history input yields the same response spectra as given in the report without any maJor deviations below those smoothed. response spectrum values

I presented, in the PSAR for the envelope of the two earthquakes considered.. The has advised. that the time history input used. in its analysis yields applicant * substantially the same response spectra as the envelope spectra of'he two J earthquakes considered, Vertical acceleration values in all cases will 'be taken as,two-thirds the corresponding maximum horizontal ground. acceleration, and. the effects of horizontal and. vertical earthquake loadings will be combined., and. considered. to act simultaneously. In addition in the elastic. analysis, for the containment structure the usual fractional increase in stress for short term loading will I not be used, We concur in these criteria. The damping values to be used. in the design are given on page 2-29

(revised. 7-31-67) of the PSAR and. we concur with the values given therein. General Design Provisions for Containment

We have reviewed the design stress criteria presented. on page 5-9 of the PSAR and, the load. factor expressions to be employed. in the design and. find. these reasonable. Further, we note on page 5-12 of the PSAR that no steel reinforcement will, experience average stress beyond. the yield. point at the factored load., and, a statement on page 5-13 that the liner will be designed. to assure that stresses will not exceed. the yield point at the factored. loads. Further amplification on these points is given in answer to Question III.A.5 of Supplement 2. The applicant has confirmed. our interpretation that the average stress in the reinforcement and. liners will not exceed. yield and. Chat t the deformations will be limited. to that of general yielding under the maximum earthquake loading conditions. On this basis, we concur in this approach.

A discussion of the resistance of the lining to buckling from compressive thermal stress is given in Supplement 2 and. also in Supplement 0 in the answers to Question IIX.A.6. The conditions assumed. for buckling of Type I are conservative, and. we conclude that the spacing of the stud. supports is 'close enough to give a reasonable margin of safety against buckling of the liner. The detail for carrying the radial shear, namely through Che use of p a vertical I-beam, as described in the PSAR and, -in more particular beginning on page 30 of Supplement 1, is-ingenious and. appears acceptable to us.

We recommend. Chat careful attention Co be given to the detail at the base of the I section where it is keyed. into the foundation, to insure that no distress can occur in either, the liner or the diagonal, reinforcing bars through any rotation that might occur at this point under earthquake loadings or other . types of accident loadings. It is noted. in answer to Question III.A.9 of Supplement 1 that the diagonal reinforcing will be carried. over the top of the cylindrical shell and form a more or less completely tied. unit through the containment structure with tie-down into and. through the foundation as described. in answer to Question XII.A.10. It 'is further noted that the splices for the ASXM A-432 bars, which comprise the diagonal reinforcing in the side walls and. carry the lateral shears and vertical loadings'n the containment structure, will be spliced. by the l

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Cahwelh, process and that less than 1 percent of the splices will be inaccessible for Cadweld. splice units, and. will therefore require welding. The proposed. approach is acceptable to us.

The design of the'ntake structure located. at sea level is described. in detail in the PSAR and, the various supplements. This will be designed as a Class I structure, with due regard for expected. tsunami water heights. Although it appears that some protection has been provided against the possibility of rock masses from the clifffalling onto, or into, the pump house, we recommend. that consideration be given to impairment of the controls or the pumping system through any possible rock falls or slides. Cranes

The containment crane is listed, on page 2-27 (revised. 7-31-67) of the

PSAR as a Class I structure. We call attention to the design of the cranes to insure that these cranes cannot be displaced. from the rails during the design or maximum earthquake, or otherwise to have damage result from the movement of items supported. by them which could, cause impairment of the containment or the ability for safe shutdown. Penetrations

A discussion oi the design of the containment penetrations is given in answer to question III.A.2 of Supplement l. It is noted. there that for the large penetrations the diagonal rebars will be welded. cU.rectly to a heavy structural steel ring through use of Cadweld. sleeves. This approach appears satisfactory to us. The applicant further notes in the same section that the stress concen- tration in the vicinity of the opening will be considered. in the analysis. Although this approach may well be satisfactory, we believe that the penetration design should. take account of any secondary effects arising from local benfing, thermal effects, and. so on, to insure that the penetration-door detail behaves t 'I -10- satisfactorily, and, sccozvtly that there is no distress in the containment structure in the transition zone from the penetration into the remainder of the shell structure. Partial proof of the integrity of the penetration will be provided, by the measurement program to be made concurrently with the proof testing of the containment vessel. We recommend. that penetration deformation

calculations be made prior to the proof testing to provide demonstrated. evidence that the design does indeed meet the criteria set forth for both the large and small penetrations.

Pi i Valves and. Reactor Internals The design of the piping is described. in Section 2 of the PSAR, and,

in further detail in Supplements 1, 2, 4 and 5. On'page 1-22 of the PSAR a statement is made that all piping will be designed to withstand any seismic

disturbance predictable for the site. On page 2-30 of the PSAR it is indicated that there are regions of local bending where the stresses will be'quivalent to 120 percent of the yield stress 'based. on elastic analysis for the no-loss- of function criteria. Further elaboration on the piping design is given in

answer to Question IX.F and. Appendix A of Supplement 1, and again in answer to Question II.G of Supplement 2, Section XX of Supplement 4, and. in answer to Questions 10 through 13 of Supplement 5. The discussion presented. in

Supplements 1, 2, 4 and, 5 indicates that the earthquake loadings will be combined. directly with the other applicable loadings. For the most severe loading

condition (involving the maximum earthquake plus normal and. pipe rupture loads) oral discussions with the AEC staff have indicated that the limit curves as given in WCAP 5890-1 have been revised. such that the strain limits at temperature will consider limited strain hardening no more than 2A of the strain at the maximum stress of the stress-strain curve in simple tension. V ~ V

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The design criteria and. design approach as described above are acceptable to us.

The isolation valve design is discussed. in -several places but particularly in answer to Question II.A.14 of Supplement 1. The approach outlined. there is acceptable to us.

The design of the reactor internals has been reviewed in some detail with the applicant. The internals are to be designed to withstand. the combined

maximum earthquake spectrum concurrent with 'blow down in such a manner that

moderate yielding would. not impair the capability of safe shutdown. On the basis of our discussion with the applicant, and. the material presented in

Supplement 5, the design criteria and. design approach proposed, for the internals are acceptable to us,

CONCLUSIONS In line with the design goal of providing serviceable structures

and. components with a reserve in strength and. ductility~ and. on the basis of

the information presented., we believe the design criteria outlined for the

containment and. other Class I components including the reactor internals, piping, vessels, and supports can provide an adequate margin of safety for seismic ~resi,stance.

R1MZENCES

"Preliminary Safety Analysis Report, Volumes 1 and. 2," Nuclear Plant, Diablo t~ f Canyon Site, Pacific Gas and Electric Company, 1967. C

2 ~ "Preluded.nary„Safety Analysis Report, Supplements 1, 2,, 3, 4, 5, and. 6," Nuclear Plant, Diablo Canyon Site, Pacific Gas and. Electric Company, 1967. 3. "Report on the Seismicity of the Diablo Canyon Site," U. S. Coast and. Geodetic Survey, Rockville, Maryland, September 21, 1967; h

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Docket Eo. 50-275

Dr. Eathan N. EewIIIark 1114 Civil Engineering Building University of Illinois Urbana~ Illinois 61801 Dear Dr. EmaIark:

As you know we are presently preparing our Safety Evaluation regsrding Pacific Gas and, Electric CompanyIs Diablo Canyon nuclear Plant. An attaetuaent to our evaluation villinclude your report on the Adecpmcy'of the Structural Criteria for the Diablo Canyon Site Euclear Plant. Ue have placed. your draft report of December 3.967 in final form as per our telephone 'onversations. Ifthe report is 'acceptable to you, we would, appreciate your signature on one of the enclosed. reports to be included. in our record. files. Sincerely yours,

Roger S. Boyd~ Assistant Director for Reactor Prospects Division of Reactor Licensing

Enclosure He~nnark Report dated. la/67

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Dr. Nathan M. Newman, Head Department of Civil Engineering lllkCivil Engineering Rd,lding University of Xllinois Urbana, Xllinois 61801

Dear Dr. 'ewman: Enclosed. are two copies of your draft report which were transmitted to the ACES on December 6, 1967, and, copies "of Amendments 8 and 9 (Supp3.ements 7 and 8) for the Diablo Canyon Facility. At the ACRS meeting on December 7> 1967 it appeared. that She committee will complete its review and. furnish a report in early December. Xn this event, the final AEC Safety Evaluation with your report would. need. to be complete by the end, of December. Me shall contact your office early next week to further discuss this matter. Sincerely yours,

Don F. Knuth, Chief RPB Pg Division of Reactor Licensing

DFK>ds Enclosures. 2 cys. of draft report 1 cy. of Amendment 8 1 cy. of Amendment

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Dr. Nathan N. Ifevrmark 1114 Civil Engineering Building University of Illinois Urbana, Illinois 61801. Dear Dr. Hemnark:

A copy of license application Amendment Mo. 7 filed by Pacific Gas and Electric Company is enclosed for your use. The amendment consists of the Sixth Supplement to the Preliminary Safety Analysis Report for the Diablo Canyon Huclear Unit. Sincerely yours,

Original signed by, H. Steels Roger 8. Boyd, Assistant Director for Reactor Prospects Division of Reactor Licensing Enclosure: Amendment Ho 7

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Dr. Hathan H. Megmark 1114 'CivQ. Engineering Building University of Xllinois Urbsna~ Ellinois 61801

Dear 3)r 'MeMmark:

A copy of Amendment No 6 to Pacific Gas and Electric Company's facility license application is enclosed for your use. The amendment consists of the ment fifth Supple- to,the Preliminary Safety Analysis Report and contains, among other things» additional containment design data.

Sincerely

yours'riginal signed by K Steele Roger S. Boyd'ssistant Director for Reactor Pro)sets Division of Reactor Licensing Enclosure: Amendment Ho. 6 (H,fth Suppl,, to PSAR)

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Dr. %lathan H. Hemnarlc 1114 Civil Engineering Building University of Illinois Urbana, Illinois 61801 Dear Dr." Newmark:

A copy of Amendment Ho. 5 to the Pacific Gas and Electric Company's facility license application is 'enclosed for your use. In addition to certain financial data, the amendment contains the Fourth Supplement to the. Preliminary Safety Analysis Report for the proposed nuclear plant at the applicant's Diablo Canyon site. Sincerely yours,

Original signed bg K-Steely

Roger S. Boyd, Assistant Director for Reactor Pro)ects Division of Reactor Licensing

Enclosure: Amendment Ho. 5

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6 October 1967

Dr. Peter A. Morris o( Divis ion of Reactor Licens ing 3 U. S. Atomic Energy Commission 8 $ 20545 QQ$ @gory Washington, D. C. p>~~ yS~ Re: Diablo Canyon Site Nuclear Plant Docket No: 50-275 ~egutaterJJ SIIPyt File'Qi Dr. Norris: 'ear

As a result of the meetings held in Bethesda and Washington on October 3, 4 and 5 concerning the Diablo Canyon Nuclear Site, Dr. Newmark and I formulated two questions for which we should like answers. The first question is a rather lengthy question made up of many parts and will obviously require considerable documentation. It deals with the reactor internals, piping and vessels. Two questions follow:

1. For the reactor internals, piping, and vessels, separately, provide the fo1 lowing cr i ter ia type informat ion: (a) the loading combinations to be employed in the designs and the reasoning for selection of the loading combinations

(b) the stress or deformation limits for each. case (a) (c) the margin of safety between (b)" and the expected collapse or failure condition.

I For particular cases where calculations of maximum limits of deformation or stress (at which inability to function occurs) have been made, please supply such data. Also in. such cases supply the maximum design limit value, and the expected deformation or stress where this has been calculated. In all such cases the applicable loading combination should be 'identif ied, and any amplifying discussion of the margin of safety presented.

In cases where only stress intensity criteria are to be, employed, as outlined in WACP 5890-1, provide' realistic estimate, based on appropriate material properties at the applicable temperature of the strain in order that an estimate of the margin of safety can be made. Especially for those cases which fall outs ide the code-based "boxes" and in the region between the boxes and the limit curves it is imperat ive that the margin of safety be ident ified. f4 '-A+» = ~ ~" '4 Dr., Peter A. Morris -2- 6 October 1967

Confirmatory test data should also be supplied, if, available, with interpretative discussion. With regard to WACP 5890-1, provide additional discussion regarding the applicability of the derivations in the report to the strain hardening domain.

~ In connection with the above, provide information that will permit evaluation of the effect of welds, irradiation, corrosion, accidental imperfections, etc., in the design approach.

To the extent available, supply criteria or specific deformation and stress information connected with the relative motions between the reactor vessel and steam generators or other large items as well as interaction forces. Indicate how these relative motions will be controlled by snubbers or other means, and what reaction forces (and corresponding stresses) will be transmitted to the pipes.

2. The containment structure will be founded on bedrock and surrounded by some 30 feet of overburden. Describe how the forces arising from any soil- structure interaction arising from normal and seismic loading will be evaluated and handled in the design. The answers to these questions should permit us to proceed with finalizing our report on the Diablo Canyon application. Sincerely yours,

W. J. Hall bjw cc: N. M. Newmark r

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13 September 1967

Dr. Peter A. Horr is, Director Division of Reactor Licensing U. S. Atomic Energy Commiss ion Washington, D.C. 20545

Re: Draft Report on Diablo Canyon Site Nuclear Plant (Docket 50-275)

Dear Dr. Horris:

We are transmitting herewith two copies of our revised draft report on the above noted application. The revisions contained herein were transmitted to the DRL staff by telephone yesterday. Sincerely yours,

g ~ (0 >4 W. J. Ha 1 1 bjw Enclosure cc: H. H. Newmark

Qi, NATHAN M. NEWMARK CONSULTING KNGINKKRINGSKRVICKS 1114 CIVIL ENGINEERING BUILDING URBANA ILLINOIS 61801

DRAFT

. REPORT TO AEC REGULATORY STAFF

ADEQUACY OF THE STRUCTURAL CRITERIA FOR

THE DIABLO CANYON SITE NUCLEAR PLANT

Pacific Gas and Electric Company (Docket 50-275)

by

N. H, Newma rk

and

W. J. Ha 1 1

7 September 1967 1

4 r II ~ ~

ADEQUACY OF THE STRUCTURAL CRITERIA FOR

THE DIABLO CANYON SITE NUCLEAR PLANT

N. M. Newmark and W. J. Hal 1

INTRODUCTION

This report concerns the adequacy of the containment structures and

components, reactor piping and reactor internals, for the Diablo Canyon Site

Nuclear Plant, for which application for a construction permit and operating

license has been made to the U. S. Atomic Energy Commission (Docket No. 50-275)

by the Pacific Gas and Electric Company. The facility is to be located in

San Luis Obispo County, California, 12 miles west southwest of the city of San

Luis Obispo, and adjacent to the Pacific Ocean and Diablo Canyon Creek. The

s ite is about 190 miles south of San Francisco and ISO miles northwest of Los Angeles.

Specifically this report is concerned with the evaluation of the design criteria that determine the ability of the containment system, piping and reactor internals to withstand a design earthquake acting simultaneously with other applicable loads forming the basis of the design. The facility also is to be designed to withstand a maximum earthquake simultaneously with other applicable loads to the extent of insuring safe shutdown and containment. This report is based on information and criteria set forth in the preliminary safety analysis report (PSAR) and supplements thereto as listed at the end of this report. 'ale have participated in discussions with the AEC Regulatory Staff, and the applicant and its consultants, in which many of the design criteria were discussed in deta i l. ~ ~ -2-

DESCRIPTION OF THE FACILITY

The Diablo, Canyon Nuclear Plant is described in the PSAR as a pressurized water reactor nuclear steam supply system furnished by the West inghous Electric

Corporation and designed for an initial power output of 3250 Slt (1060 HWe net). The reactor cool'ing system consists of four closed reactor coolant loops connected in parallel to the reactor vessel, each provided with a reactor coolant pump and a steam generator. The reactor vessel will have an inside diameter of about 14.5 ft., a height of 42.3 ft., will operate with a design pressure of 2485 psig, a design temperature of 650 F, and is made of SA-302 grade 8 low alloy steel internally c)ad with type 304 austenitic stainless steel,

Tl;e reactor containment structure which encloses the reactor and steam generators, consists of a steel'ined concrete shell in the form of a reinforced concrete vertical cylinder with a flat base and hemispherical dome, The cylindrical structure of 140 ft. inside diameter has side walls rising 142 ft. from the liner at the base to the spring line of the dome. The concrete side walls of the cylinder and the dome will be approximately 3 ft. 6 and 2 ft. 6 in. in thickness, respectively. The concrete reinforcing steel pattern is described conceptually in Supplement 1 and consists of bars oriented at 30 from the vertical in such a manner that the pattern does not require termination of any bars in the dome. These diagonal bars are designed to carry both the lateral shear as well as vertical tens ile forces. In addition there is hoop reinforcing in the cylindrical portion of the structure. For radial shear reinforcing the applicant proposes to use a system of vertical wide flange beams spaced four feet on centers. The beams are attached by hinge connection to the base slab at the lower end and are terminated about 20 ft. above the top of the base slab. The function of the beams is to provide res istanc'e to the moments ~ ~ l "3" and shears created by the discontinuity at the base and to provide a gradual transition of load carrying elements between the base and the cylinder wall.

These beams do not participate in resisting either upliFt due to pressure or shear and tension due to earthquake loading; these forces are to be resisted by the diagonal steel reinforcing just described. The concrete wall in this

lower zone is divided into three zones, The inner zone, about 1 ft. thick, consists of reinforced concrete and is the element to which the liner is attached. The middle zone contains the vertical steel I-beams which in turn act as supports for the 16 in, thick reinforced concrete slab spanning the space between the beams. The outer zone consists of about 14 in. of concrete in which the diagonal and hoop reinforcement are embedded. The three zones are provided with bond-breaking material to insure that the elements will act separately.

The reinforcing steel for the dome, cylindrical walls and base mat will be high strength reinforcing conforming to the ASTH A432 specification. The A432 reinforcing bars of size larger than No, ll are to be spliced with Cadweld splices except in cases where accessibility makes welding mandatory.

The liner, as described in Supplement. 2, will be a minimum of 3/8 in, thick for the dome and cylindrical walls and 1/4 in, thick for the base slab.

The anchor stubs are to be L shaped and will be Fusion 'elded to the liner plate. The studs will be spaced at 20 in, on centers, and the design 'is made to preclude major affects arising from buckling of the liner.

Personnel and equipment access hatches are provided for access to the containment vessel. In addition there are other penetrations for piping and electrical conduits.

The facility includes a sea water intake structure located at sea level at the base of the cliff with circulating water conduits and auxiliary salt water conduits leading up to the nuclear plant.

The information on the geology at the site is described in the PSAR and the several supplements. The bedrock at the site area is of tertiary age and comprises marine shales, sandstone and fine-grained tuffaceous sediments, along with a considerable variety of tuffs of submarine volcanic origin. All these rocks are firm and compact, and are exposed in the seaward edge of the terrace on which the plant is to be built, which ranges in elevation from 60 to 100 ft. above seq level, and is approximately 1,000 ft. wide, The bedrock is overlain marine and non-marine deposits of Pleistocene age. The major by I components of the power plant are to be founded in bedrock in all cases.

The site has been well explored and there is no evidence of any fault offsets of recent origin of significance. The report by the consulting geologist on the project, Dr. Richard H. Jahns, presented as Appendix A of the third supplement, concludes that the possibility of fault-induced permanent ground displacement within the plant area during the useful life of the power plant is sufFiciently remote to be safely disregarded.

SOURCES OF STRESSES IN CONTAINMENT STRUCTURE AND TYPE I COMPONENTS

The containment structure is to be designed for the following loadings: dead load of the structures; live loads (including construction loads and equipment loads); internal pressure due to a loss-of-coolant accident of about

47 psig; test pressure of 54 psig; negative internal pressure of 3,5 psig; stresses arising From thermal expansion; wind loading corresponding to the Uniform

Building Code - 1964 edition and corresponding to 87 to 100 mph winds; and earthquake loading as described next. The earthquake loading will be based on two earthquakes, which for the design earthquake condition correspond to maximum horizontal ground accelerations of 0.20g and 0.15g. The containment design also will be reviewed ~ ~ -5- for no loss of function using response spectra corresponding to earthquakes of twice the maximum acceleration noted above, namely 0.40g and 0.30g,

but with the latter earthquake having a maximum ground velocity

corresponding roughly to a value of 0.40g ground acceleration. The

U. S. Coast and Geodetic Survey report (Ref. 3) concurs in 0.20g and

0.40g values of maximum ground acceleration for design and maximum 'I conditions. Class I piping and equipment, as discussed in answer to Question

II.G of Supplement 2 will be designed to the USA S. I.B31. 1 Code for pressure piping which includes consideration of internal pressure, dead load, and other appropriate loads such as thermal expansion. It does not contain provision for earthquake loading. However, the applicant indicates that they wi ll combine earthquake loadings with the loadings just noted and further elaboration on this point is given in Appendix A of

Supp lement 1.

The reactor internals-are to be designed for combined earthquake,

blow down loadings and other apglicable loadings.

COMMENTS ON ADE UACY OF DESIGN

Seismic Desi n For this facility the containment des ign is to be made for two earthquakes corresponding to maximum horizontal ground accelerations

of 0.20g (Earthquake D) and 0.15g (Earthquake B). For the maximum 0 1 -6- earthquake loading the two earthquakes are characterized by horizontal ground accelerations of twice the values just cited, namely 0.40g and 0.30g. Spectra corresponding to these earthquakes are presented as

Figs. 2"ll through 2-14 of the PSAR and again in Supplement No. 3 beginning on page 22, along with an envelope of the spectra for the no-loss-of function condition (Fig. III.A.12-5, Supplement 3). We concur with the response spectra for the earthquakes when they are used in the following manner.

Since the response spectrum values for Earthquake D give values that control for high frequencies, and for Earthquake B, values that control for intermediate and low frequencies, both earthquakes must be used and the maximum response in either must be considered to apply to the design or safe shut-down of single degree of freedom elements. This is permissible in view of the fact that Earthquake B gives response values for low and intermediate frequencies that lie above the response spectrum values from

TID 7024 when normalized to an acceleration of 0.40g. Hence this earthquake may be cons idered to correspond to a 0.40g earthquake for low and intermediate frequencies.

However, for safe shut-down of multi-degree-of-freedom systems, we take the position that the combined. or envelope spectrum for the two earthquakes must be used in order to avoid a possible deficiency in the provision for safe shut-down. This envelope spectrum is consistent with an El Centro type response spectrum for a maximum ground acceleration of 0.40g. Vertical acceleration values in all cases will be taken as two-thirds the corresponding maximum horizontal ground acceleration, and the effects of

horizontal and vertical earthquake loadings will be combined, and considered to act simultaneously. In addition in the elastic analysis, the usual

fractional increase in stress for short term loading will not be used. We concur in these criteria.

The damping values to be used in the design are given on page 2-29 (revised 7-31-67) of the PSAR and we concur with the values given therein. With regard to the method of analysis of the containment structure,

it is noted on page 2-29 of the PSAR that all modes having a period greater than 0.08 secs, will be included in the analysis and that in addition for components or structures having multiple degrees of freedom, all significant modes, and in no case less than 3 modes, will be considered. It is further stated that for s ingle degree of freedom systems, the fundamental mode of vibration will be used in the analysis. Our interpretation of these statements is that for a single degree of freedom system, no matter what the period, whether it is above or below 0.08 secs, the appropriate period and spectral acceleration will be employed in the design, and further that fol multiple degree of freedom systems all modes will be considered. On the basis of this interpretation, as interpreted" in the second paragraph of this section, we concur with the approach.

The method of dynamic analysis is described in Sections 2 and 5 of the PSAR and again in answer to Question III.A.15 of Supplement l. It is noted that the dynamic analysis to be followed for the Class I components and structures is the modal part icipat ion factor method. It is our understanding further that the modal analysis may bc carried out either through the use directly of the smoothed spectra, or employing a time history of ground motion, employing earthquake records with amplitude values scaled which. lead to essent ially the same smoothed spectra. Discuss ion of this point is presented

~ ~

-8- by the applicant in answer to question III.A.13 in Supplement 3. L4e concur in the use of the modal participation method in the analysis and design, as well as the use of either the smoothed spectra or the time history input method provided that the time history input yields the same response spectra as given in. the report without any major deviations below those smoothed response spectrum values presented in the PSAR.

As a further point on the dynamic analysis, it is our understanding that for the safe shutdown conditions particularly, for Class I components and structures, the design will be made for the envelope of the combined spectra of the two earthquakes for the appropriate damping level. On the assumption that this approach is the one being followed we concur in the design approach adopted,

General Desi n Provisions

!4e have reviewed the design stress criteria presented on page 5-9 of the PSAR and the load Factor expressions to be employed in the design and find these reasonable. Further, we note on page 5-12 of the PSAR that no steel reinforcement will experience average stress beyond the yield point at the factored load, and a statement on page 5-13 that the liner will be designed to assure that stresses will not exceed the yield point at the Factored loads. Further amplification on these points is given in answer to Question III.A.5 of

Supplement 2. We interpret these statements to mean that the average stress in the reinforcement and liners will not exceed yield and that the deformat fons will be limited to that of general yielding under the maximum earthquake loading condit ions. On the assumpt ion that this interpretat ion is correct we concur in the approach.

The detail for carrying the radial shear, namely through the use of a vertical I-beam, as described in the PSAR and in more particular A -9ee

beginning on page 30 of Supplement 1 is'novel and appears acceptable to us. >le reconmend that careful attention be given to the detail at the base of the I

section where it is keyed into the foundation, to insure that no distress can

occur in either the liner or the diagonal reinforcing bars through any rotation that might occur at this point under earthquake loadings or other types of

accident load in gs .

It is noted in answer to Question III.A.9 of Supplement 1 that the diagonal reinforcing will be carried over the top of the cylindrical shell and form a more or less completely tied unit through the containment structure \ with tie-down into and through the foundation as described in answer to

Question III.A.10. It is further noted that the splices for the ASTH A-432 bars, which comprise the diagonal reinforcing in the side walls and carry the lateral

shears and vertical loadings in the containment structure, will be spliced by

the Cadweld process and that less than 1 percent of them will be welded by virtue of inaccessibility for Cadweld splice units. The proposed approach appears acceptable to us.

The des ign oF the intake structure located at sea - level is described

in detail in'the PSAR and the various supplements. This will be designed as a Class I structure, with due regard for expected tsunami water heights. Although it appears that some protection has been provided against the possibility of rock masses from the cliff falling onto, or into, the pump house, we recommend that careful attention be given to any impossible impairment of the controls or the pumping system through any possible rock falls or slides, Cranes

The conta inment crane is 1 isted on page 2-27 (rev ised 7-31-67) of the PSAR as a Class I structure. Me wish to call attention to the design of the 0 vlP cranesto insure that these cranes cannot be displaced from the rails during the design or maximum earthquake, or otherwise to have damage result from the movement of items supported by them which could cause impairment of the containment or the ability for safe shutdown. Penetrat fons

A discussion of the design of the penetrations is given in answer to question III.A.2 of Supplement 1. It is noted there that for the large penetrations the diagonal rebars will be welded directly to a heavy structural steel ring through use of Cadweld sleeves. This approach appears satisfactory to us.

The applicant further notes in the same section that the stress, concentration in the vicinity of the opening will be considered in the analysis.

Although this approach may well be satisfactory, we believe that the penetration design should take account of any secondary effects arising from local bending, thermal effects, and so on, to insure that the penetration-door detail behaves satisfactorily, and secondly that there is no distress in the containment, structure in the transition zone from the penetration into the remainder of the shell structure, Part ial proof of the integrity of the penetrat ion will be provided by the measurement program to be made concurrently with the proof testing of the containment vessel. Me recommend that penetration deformation calculations be made prior to the proof testing to provide demonstrated evidence that the design does indeed meet the criteria set forth for both the large and small penetrations.

Pi in Valves and Reactor Internals

The design of the piping is described in Section 2 of the PSAR, and in further detail in Supplements 1 and 2. On page 1-22 of the PSAR a statement 'o is made that all piping will be designed to withstand any seismic disturbance predictable for the site. On page 2-30 of the PSAR it is indicated that there are regions of local bending where the stresses will be equivalent to 120 percent of the yield stress based on elastic analysis for the no-loss-of function criteria. Further elaboration on the piping design is given in answer to Question II.F and Appendix A of Supplement 1 and again

in answer to Question II.G of Supplement 2. The discussion presented in

Supplements 1 and 2 indicates that the earthquake loadings will be combined directly with the other applicable loadings for the piping and that the design limits wil) be established in terms of code allowable stresses, which In cases can be as large as 1.2 to 1.8 times the code allowable stresses.

The matter of concern to us is t~ at of the possible impairment of the serviceability of the piping through rupture or buckling if excessive deformations occur. As the result of discussions with the applicant we believe that for the specific materials used, and under the conditions cited, the deformations generally will be limited to acceptable values. However, we urge that this matter receive further consideration by the applicant during the des fgn process. The isolation valve design is discussed in several places but particularly in answer to Question II.A.14 of Supplement I. The approach outline there appears acceptable to us.

The design of the .reactor internals has been reviewed in some detail with the applicant. The internals are to be designed to withstand the combined maximum earthquake spectrum concurrent with blow down in such a manner that moderate yielding would not impair the capability of safe shutdown, It is our understanding that this matter is under detailed study and further documentat ion and review of the dos ign criteria for the internals is required. ~ P ~

k * "12

CONC LUS IONS

In line with the design goal of providing serviceable structures and components with a reserve in strength and ductility, and on the basis of the information presented, we believe the design criteria outlined for the primary containment, secondary containment and Type I piping can provide an adequate margin of safety for seismic resistance, Still remaining for review is a detailed evaluation of the criteria to be employed in the design of the reactor internals.

REFERENCES

1. "Prel iminary Safety Analysis Report, Volumes 1 and 2," Nuclear Plant, Diablo Canyon Site, Pacific Gas and Electric Company, 1967.

2. "Preliminary Safety Analysis Report, Supplements 1, 2 and 2," Nuclear Plant, Diablo Canyon Site, Pacific Gas and Electric Company, 1967.

3. "Report on the Seismicity of the Diablo Canyon Site," U. S. Coast and Geodetic Survey, Rockvi lie, Haryland, 'V

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. UR8ANA. ILUNOIS 61801

7 September 1967

Dr. Peter A. Morris Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D.C, 20545

Re: Transmi t ta 1 of Draft Reports Peach Bottom Unit No. 2 and 3, (Dockets 50-277 and 50-278) Diablo Canyon Site Nuclear Plant (Docket 50-275)

Dear Dr. Morris:

Transmitted herewith are two copies each of the reports on the above noted applications prepared by Dr. N. M, Newmark and myself. These are draft reports, and are submitted for use by your staff. If there are any questions we should be glad to attempt to answer them. Sincerely yours,

W. J, Hall bjw Enc losures cc: N. M, Newma rk I,~ 0 C 4

I 0 ''AY H A N M . N E W M A R K CONSULTlNG ENGINEERING SERVICES 1114 CIVIL ENGINEERING BUILDING URBANA ILLINOIS 61S01

REPORT TO AEC REGULATORY STAFF

ADEQUACY OF THE STRUCTURAL CRITERIA FOR

THE DIABLO CANYON SITE NUCLEAR PLANT

Pac i f i c Gas and E lect r i c Company (Docket 50-275)

by

N. M. Newmark

and M. J. Hall

September l967 t ~ ~,( r f

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1 'I

ADEQUACY OF THE STRUCTURAL CRITERIA FOR

THE DIABLO CANYON SITE NUCLEAR PLANT

by

N, H. Newmark and M. J. Mall

INTRODUCTION

This report concerns the adequacy of the containment structures and

components, reactor piping and reactor internals, for the Diablo Canyon Site

Nuclear Plant, for which application for a construction permit and operating

license has been made to the U. S. Atomic Energy Commission (Dorket No. 50-275)

by the Pacific Gas and Electric Company. The facility is to be located in

San Luis Obispo County, California, 12 miles west southwest of the city of San

Luis Obispo, and adjacent to the Pacific Ocean and Diablo Canyon Creek, The

site is about 190 miles south of San Francisco and 150 miles northwest of

Los Angeles. Specifically this report is concerned with the evaluation of the design criteria that determine the ability of the containment system, piping

and reactor internals to withstand a design earthquake acting simultaneously with other applicable loads forming the basis of the design. The facility also

is to be designed to withstand a maximum earthquake simultaneously with other applicable loads to the extent of insuring safe shutdown and containment. This report is based on information and criteria set forth in the preliminary

safety analysis report (PSAR) and supplements thereto as listed at the end of

this report. '

and the applicant and its consultants, in'which many of the des ign criteria were discussed in detail. ~ ~ \ I ~ ~ DESCRIPTION OF THE FACILITY

The Diablo, Canyon Nuclear Plant is described in the PSAR as a pressurized water reactor nuclear steam supply system furnished by the Hest inghous Electric

Corporation and designed for an initial power output of 3250 %It (1060 HWe net),

The reactor cooling system consists of four closed reactor coolant loops connected in parallel to the reactor vessel, each provided with a reactor coolant pump and a steam generator. The reactor vessel will have an ins ide diameter of about 14.5 ft,, a height of 42.3 ft., will operate with a des ign pressure of 2485 ps ig, a des ign temperature of 650 F, and is made of SA-302 grade 8 low alloy steel internally clad with type 304 austenitic stainless steel.

The reactor containment structure which encloses the reactor and steam generators, consists of a steel lined concrete shell in the for@ of a reinforced concrete vertical cylinder with a flat base and hemispherical dome. The cylindrical structure of 140 ft. inside diameter has side walls rising 142 ft. from the liner at the base to the spring line of the dome. The concrete side walls of the cylinder and the dome will be approximately 3 ft. 6 and 2 ft. 6 in. in thickness, respectively. The concrete reinforcing steel pattern is described conceptually in Supplement 1 and consists of bars oriented at 30 from the vertical in such a manner that the pattern does not require termination of any bars in the dome, These diagonal bars are des igned to carry both the lateral shear as well- as vertical tensile forces. In addit ion there is hoop reinforcing in the cylindrical port'ion of'he structure. For radial shear reinforcing the applicant proposes to use a system of vertical wide flange beams spaced four feet on centers. The beams are attached by hinge connection to the base slab at the lower end and are terminated about 20 ft. above the top of the base slab. The function of the beams is to provide resistance to the moments ~ ~

S "3" and shears created by the discontinuity at the base and to provide a gradual transition of load carrying elements between the base and the cylinder wall.

These beams do not participate in resisting either uplift due to pressure or shear and tension due to earthquake loading; these forces are to be resisted by the diagonal steel reinforcing just described. The concrete wall in this lower zone is divided into three zones. The inner zone, about 1 ft. thick, consists of reinforced concrete and is the element to which the liner is attached. The middle zone contains the vertical steel I-beams which in turn act as supports for the 16 in, thick reinforced concrete s lab spanning the space between the beams, The outer zone consists of about 14 in. of concrete in which the diagonal and hoop reinforcement are embedded. The three zones are provided with bond-breaking material to insure that the elements will act separately,

The reinforcing steel for the dome, cylindrical walls and base mat will be high strength reinforcing conforming to the ASTM A432 specification. The

A432 reinforcing bars of size larger than No. 11 are to be spliced with

Cadweld splices except. in cases where accessibility makes welding mandatory.

The liner, as described in Supplement 2, will be a minimum of 3/8 in. thick for the dome and cylindrical walls and 1/4 in. thick for the base slab.

The anchor stubs are to be L shaped and will be fusion 'elded to the liner plate. The studs will be spaced at 20 in. on centers, and the design is made to preclude major affects arising from buckling of the liner.

Personnel and equipment access hatches are provided for access to the containment vessel, In addition there are other penet rations for piping and electrical conduits.

The facility includes a sea water intake structure located at sea level at the base of the cliffwith circulating water conduits and auxiliary salt water conduits leading up to the nuclear plant. 1 t i ~ 0

The informat ion on the geology at the site is described in the PSAR

and the several supplements. The bedrock at the s ite area is of tert iary age

and comprises marine shales, sandstone and fine-grained tuffaceous sediments,

along with a considerable variety of tuffs of submarine volcanic origin ~ All

these rocks are f irm and compact, and are exposed in the seaward edge of the

terrace on which the plant is to be built, which ranges in elevation from 60 to 100 ft. above sea level, and is approximately 1,000 ft. wide. The bedrock

is overlain by marine and non-marine deposits of Pleistocene age, The major components of the power plant are to be founded in bedrock in all cases.

The site has been well explored and there is no evidence of any fault offsets

of recent origin of significance. The report by the consulting geologist on

the project, Dr. Richard II ~ Jahns, presented as Appendix A of the third r supplement, concludes that the possibility of fault-induced permanent ground

displacement within the plant area during the useful 1'ife of the power plant

is sufficiently remote to be safely disregarded.

SOURCES OF STRESSES IN CONTAINMENT STRUCTURE AND TYPE I COMPONENTS

The containment structure is to be designed for the following loadings: dead load of the structures; live loads (including construction loads and

equipment loads); internal pressure due to a loss-of-coolant accident of about

47 ps ig; test pressure of 54 ps ig; negat ive internal pressure of 3,5 ps ig; stresses arising from thermal expansion; wind loading corresponding to the Uniform

Building Code - 1964 edition and corresponding to 87 to 100 mph winds; and

earthquake loading as described next. The earthquake loading will be based on two earthquakes, which for the design earthquake condition correspond to maximum horizontal ground accelerations of 0.20g and 0.15g. The containment design also will be reviewed ~ 'E for no loss of function using response spectra corresponding to earthquakes of

twice the intensity just noted, namely 0.40g and 0.30g. The U. S. Coast and

Geodetic Survey report (Ref. 3) concurs in the 0.20g and 0.40g values selected

for des ign purposes.

Class I piping and,equipment, as discussed in answer to Question II.G

of Supplement 2 will be designed to the USA S, 1.831.1 Code for pressure piping which includes cons iderat ion of internal pressure, dead load, and other appropriate loads such as thermal expansion. It does not contain provision for earthquake loading. However, the applicant indicates that they will combine earthquake loadings with the loadings just noted and further elaboration

on this point is given in Appendix A of Supplement l. The reactor internals are to be designed for combined earthquake, blow down loadings and other applicable loadings.

COMMENTS ON ADE UACY OF DESIGN

Seismic Desi n

For this facility the containment design is to be made for two earthquakes corresponding to maximum horizontal ground accelerations of 0.20g V and 0.15g. For the maximum earthquake loading the two earthquakes are characterized by horizontal ground accelerations of twice the values just cited, namely 0.40g and 0,30g. Spectra corresponding to these earthquakes are

presented as Figs. 2-11 through 2-14 of the PSAR and again in Supplement No. 3

beginning on page 22, along with an envelope of the spectra for the no-loss-of

function condition (Fig. III,A.12-5, Supplement 3). Sle concur with the

earthquake values selected and the spectra as presented.

Vertical acceleration values in all cases will be taken as two-thirds the corresponding maximum horizontal ground acceleration, and the effects of

-6-

horizontal and vertical earthquake loadings will be combined, and considered to act simultaneously. In addition in the elastic analysis, the usual

fractional increase in stress for short term loading will not be used. We concur in these criteria.

The damping values to be used in the design are given on page 2-29

' (revised 7-31-67) of the PSAR and we concur with the values given therein, With regard to the method of analysis of the containment structure,

it is noted on page 2-29 of the PSAR that all modes having a period greater than 0.08 secs, wi ll be included in the analys is and that in addition for components or st ructures having multiple degrees of Freedom, all significant modes, and in no case less than 3 modes, will be considered. It is further

stated that for single degree of freedom systems, the fundamental mode of vibration wi ll be used in the analysis. Our interpretation of these statements is that for a single degree of freedom system, no matter what the period, that is above or below 0.08 secs, the appropriate period and spectral acceleration will be employed in the design, and further that for multiple degree. of freedom

systems all modes will be considered. On the basis of this interpretation we concur with the approach.

The method of dynamic analysis is described in Sections 2 and 5 of

the PSAR and again in answer to Question III.A.15 of Supplement l. It is noted that the dynamic analysis to be followed for the Class I components and structures. is the modal part icipat ion factor method, It is our understanding further that the modal analysis may be carried out either through the use directly of the smoothed spectra, or employing a time history of ground motion, employing earthquake records with amplitude values scaled which lead to essentially the same smoothed spectra. Discussion of this point is presented / ~ ~ P

N

by the applicant in answer to question III,A.13 in Supplement 3. We concur

in the use of the modal part icipat ion method in the analys is and des ign, as well as the use of either the smoothed spectra or the time history input

method provided that the time history input yields the same response spectra

as given in the report without any major deviations below those smoothed

response spectrum values presented in the PSAR.

As a further point on the dynamic analysis, it is our understanding that for the safe shutdown condit ions part icularly, for Class I components

and structures, the des ign will be made for the envelope of the combined

spectra of the two earthquakes for the appropriate damping level, On the

assumption that this approach is the one being followed we concur in the design approach adopted.

General Desi n Provisions

He have reviewed the design stress criteria presented on page 5-9

of the PSAR and the load factor expressions to'be employed in the design and

find these reasonable. Further, we note on page 5-12 of the PSAR that no steel reinforcement will experience average stress beyond the yield point at the

factored load, and a statement on page 5-13 that the liner will be designed to assure that stresses will not exceed the yield point at the factored loads. Further amplification on these points is given in answer to Question III.A.5 of

Supplement 2. We interpret these statements to mean that the average stress

in the reinforcement and liners will not exceed yield and that the deformat ions

will be limited to that of general yielding under the maximum earthquake loading

conditions. On the assumption that this interpretation is correct we concur in the approach.

The detail for carrying the radial shear, namely through the use of

a vertical I-beam, as described in the PSAR and in narc particular P 4 beginning on page 30 of Supplement 1 is novel and appears acceptable to us.

We recorwnend that careful attention be given to the detail at the base of the I section where it is keyed into the foundation, to insure that no distress can occur in either the liner or the diagonal reinforcing bars through any rotation that might occur at this point under earthquake loadings or other types of accident loadings.

It is noted in'nswer to Question III.A.9 of Supplement 1 that the diagonal reinforcing will be carried over the top of the cylindrical shell and form a more or less completely tied unit through the containment structure with tie-down into and through the foundation as described in answer to Question III.A.10. It is further noted that the splices for the ASTH A"432 bars, which comprise the diagonal reinforcing in the s ide walls and carry the lateral shears and vertical loadings in the containment structure, will be spliced by the Cadweld process and that less- than 1 percent of them will be welded by virtue of inaccessibility for Cadweld splice units. The proposed approach appears acceptable to us.

The design of the intake structure located at sea level is described in detail in the PSAR and the various supplements. This will be designed as a Class I structure, with due regard for expected tsunami water heights. Although it appears that some protection has been provided against. the possibility of rock masses from the-cliff falling onto, or into, the pump house, we recommend that careful attent ion be given to any impossible impairment of the controls or the pumping system through any possible rock falls or slides ~

Cranes

The conta inment crane is listed on page 2-27 (rev ised 7-31-67) of the

PSAR as a Class I structure. We wish to call attent ion to the des ign of the 'C v

L ~ cranesto insure that these cranes cannot be displaced from the rails during the des ign or maximum earthquake, or otherwise to have damage result from the movement of items supported by, them which could cause impairment of the containment or the ability for safe shutdown. Penet rat ions

A discuss ion of the design of the penet rations is given in answer to question III.A.2 of Supplement l. It is noted there that for the large penetrations the diagonal rebars will be welded directly to a heavy structural steel ring through use of Cadweld sleeves. This approach appears satisfactory to us. The applicant further notes in the same section that the stress concentration fn the vicinity of the opening will be considered in the analysis.

Although this approach may well be satisfactory, we believe that the penetration design should take account of any secondary effects arising from local bending, thermal effects, and so on, to insure that the penetration-door detail behaves satisfactorily, and secondly that there is no distress in the containment structure In the transition zone from the penetration into the remainder of the shell structure. Partial proof of the integrity of the penetration will be provided by the measurement program to be made concurrently with the proof testing of the containment vessel, Me recommend that penetration deformation calculations be made prior to the proof testing to provide demonstrated evidence that the design does indeed meet the criteria set forth for both the large and small penetrations.

Pi in Valves and. Reactor Internals

The design of the piping is described in Section 2 of the PSAR, and in further deta i 1 in Supplements 1 and 2. On page 1-22 of the PSAR a statement ~ Q r ~

I,( -10-

is made that all piping will be designed to withstand any seismic

disturbance predictable for the site, On page 2-30 of the PSAR it is indicated that there are regions of local bending where the stresses will be

equivalent to 120 percent of the yield stress based on elastic analys is,for the no-loss-of function criteria. Further elaboration on the piping design is

given in answer to Question II.F and Appendix A of Supplement 1 and again

in answer to Question II.G of Supplement 2. The discussion presented in

Supplements 1 and 2 indicates that the earthquake loadings will be combined directly with the other applicable loadings for the piping and that the design limits will be established in terms of code allowable stresses, which in

cases can be as large as 1.2 to 1.8 times the code allowab)e stresses.

The matter of concern to us is ti at of the possible impairment of the serviceability of the piping through rupture or buckling if excessive deformations occur. As the result of discussions with the applicant we believe that for

the spec ific materials used, and under the condit tons cited, the deformat ions . generally. will be limited to acceptable values. However, we urge that this matter receive further consideration by the applicant during the design process. The isolation valve des ign is discussed in several places but particularly in answer to Question II.A.14 of Supplement 1. The approach outline there appears acceptable to us.

The design of the reactor internals has been reviewed in some detail with the applicant. The internals are to be designed to withstand the combined maximum earthquake spectrum concurrent with blow down in such a manner that moderate yielding would not impair the capability of safe shutdown. It is our understanding that this matter is under detailed study and further documentation and review of the design criteria for the internals is required. ~ h ~ a~ ~ ~ ( ~ ,4

~ j ' 9'11-

CONC LUS IONS

In line with the design goal of providing serviceable structures and

components with a reserve in strength and ductility, and on the basis of

the information presented, we believe the design criteria outlined for the primary containment, secondary containment and Type I piping can provide an adequate margin of safety for seismic resistance, Still remaining for review is 'a detailed evaluation of the criteria to be employed in the design of the reactor internals.

REFERENCES

1. "Prel iminary Safety Analysis Report, Volumes 1 and 2," Nuclear Plant, Diablo Canyon Site, Pacific Gas and Electric Company, 1967.

2. "Preliminary Safety Analysis Report, Supplements 1, 2 and 2," Nuclear Plant, Diablo Canyon Site, Pacific Gas and Electric Company, 1967. 3. "Report on the Seismicity of the Diablo Canyon Site," U, S. Coast and Geodet ic Survey, Rockvi lie, Haryland, .':" 0 ()~ ~ A', 4 FROM: DATE OF DOCUMENT: 8-ILL: LTR< ~~~MEMO REPORT: OTHER:

TO; ORIG.: Ccs OTHER: 5C

ACTION NECESSARY Q CONCURRENCE P DATE ANSWERED: NO ACTION NECESSAR~ COIIMhENT P BYs C LASS IF.I POST OFFICE FILE CODEs

REG. Nos (m.-m> Gulp) DESCRIPTION: (Must Be Unclessifiesi) R EFsERREILXD~n~ DATE RECEIVED BY DATE

', Ee: Contract iso Z(49-P)-266'f Shx&o C~ PLant V~s

ENCLOSURES:

REMARKS: origfmi1 in Cochc4 fDe.

U. S. ATOMIC ENERGY COMMISSION MA)L | QQTRQ< FORM FORM AEC-326S. I8-60) *ll S. GOVERNMENT PRINTING OFFICE. I966 235 5I9 ~'g.~ x~4 +.-c le~ 1I.'V r , *

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1 + 1 I NA'THAN. M. NEWMARK CONSULTING ENGINEERING SERVICES 1114 CIVIL ENGINEERING BUILDING URBANA. ILLINOIS 61801

21 August 1967

Dr. Peter A. Morris, Director Division of Reactor Licensing U. S. Atomic Energy Commission Washington, D.C. 20545

Re; Contract No. AT(49-5) -2667 Diablo Canyon Plant Discussion with Westinghouse Engineers

Dear Dr. Norris:

In accordance wi th the suggestion made at our meeting in Bethesda 'on 15 August 1967, several engineers from the Westinghouse Corporation ~ visi ted me on Thursday, 18 August, to discuss some of the problems related to the reactor internals under combined earthquake and blowdown loadings. Those present were Floyd Hoschini, George Bohm, Romano Sal'vatori, Roger C. Nichols, all of Westinghouse, and myself.

The Westinghouse people understood that I could not give them design advice nor did my discussion commit DRL in any way. I listened to their presentation and suggested that they make „a formal submittal, through channels, with regard to any points on which our previous formal discussions, including that on 15 August, indicated questions which still needed answers.

Although my position and I believe that of your personnel, is that we cannot compromise on the earthquake hazard for the maximum earth- quake, and must insist on response spectra (or earthquake ground motions used for computer analysis) representative of a broad-band earthquake similar to a'combination of earthquakes 8 and D as presented by the applicant, with a maximum ground acceleration of 0.4 g for no loss of function for safe shutdown I might be willing to consider adequately conservative methods of analysis, and choice of damping factors and other factors, that tike into'account the conditions in the yield range provided that the safety of the reactor is not impaired. 'With this philosophy in mind, and subject to presentation of adequate supporting data Westinghouse may choose to present more evidence on the following points.

1. The assumption that only two of the six lateral supports of the internal assembly take shear may be r'estudied to take into account some of the shearing forces that may be carried by other than the two most heavily loaded supports, provided that this can be done without undue deformati on. I ~

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I C P~ J e ~ t~ Dr. Peter A. Morris -2- 21 August 1967

2. The damping factor of one percent used for the no loss of function conditions may be restudied to justify possibly a higher value, perhaps of two percent, provided that this is done as a function of stress and deformation level, and that this stress or deformation level is consistent with safety. 3. For the combined earthquake spectrum, i.e., for earthquake excitations B and D combined, as representative of a possible extreme earthquake, and with concurrent blowdown conditions, higher strain levels may be used than those implied by yield limits, provided that major yielding is limited to values which would not impair the capability of safe shutdown.

4. Although for the maximum earthquake of 0.4 g, there will be no loss of function for safe shutdown, it may be that, the allowable code limits would be exceeded for the 0.2 g design earthquake combined with blowdown. If this proves to be the case, informati'on may be submi tted to indicate under what conditions the code limits would not be exceeded, either'or the individual earthquakes, acting separately, or for some lower level of combined earthquake, or for some slightly increased stress or deformation level. Consideration of these items will await submittal of the necessary data and justification. No indication was given by me as to any action that might be taken in advance of such presentation and justi fication.

1 indicated that I thought it would be desirable for any future conferences of this sort to be arranged through your office in order that a representative of DRL could be present. Very truly yours,

N. M. Newmark

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Dis tribution: Suppl. AUG 11 1967 DRL Reading RPB 2 Reading Docket Mo. 50-2?5 Orig: HSteele (2) R. S. Boyd Tech Reviewer J. P. Newell

Dr. Nathan H. Deanery 1114 Civil Engineering Building University of Xllinois Urbana, Illinois 61801

Deax'r. Eewmar1c:

Two copies of the Third Supplement to the Preliminary Safety Analysis Report for the nuclear reactor which Pacific Gas and Electric Company proposes to construct and operate at its Diablo Canyon Site are enclosed for y your use,

The supplement contains addi,tional technical data in the form of answers to questions raised by the Commission. Sincerely yours,

Original signed by. H. Steele Roger S. Boyd, Assistant Director for Reactor Projects Division of Reactor Licensing

Enclosure: Third Suppl. to PS'2 cys) (Diablo Canyon Site)

OFFICE > .....DRI RP......

SURIIAME> ...HSteele/d)......

DATE > 8/10/67 Form AEC-318 (Rev. ~) US.GOVKIINMFNTFNINIINGOFFICE.1~21L&22 RS-~':trod~ udi wlaI Q galbsell~r JJi() reer

Otal'X"usV tribution: suppl.~ CN DRL Reading egg'isRPB'2 Reading SUL 31 Docket Mo. 50 275 Orig: HSteele (2) R, S. Boyd Tech. Reviewer J. F.'ewell

Dr~ Nathan H. HeTmark 1114 Civil Engineering Building University of Xllinois Urbane, Xllinois 61801

Dear Dr. Hewmark:

Copies of Amendments Mos. 1 and 2 to Pacific Gas and Electxic Company's facility license application are enclosed fox'our use+

The amendments consist of the First and Second Supplements to the Prel|minary Safety Analysis Report fox the proposed Diablo Canyon nucleax'eactor, and contain additional technical data requested by the Commission, including answers to questions on the design of the containment structure. Sincerely yours,,

Original signed by H. Steele Roger S. Boyd, Assistant Director for Reactor Pro)acts Division of Reactor Licensing Enclosures: As stated above (2 sets)

OFFICE P

SURNAME W

DATE ~ 0-53) Form ARC-818 (Rev. II% t'AWPNMFNTDPINTINt:AFRIC'F' 14'~ 'plA R& :,'. 05

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Dear Dr. Newmark: Several applications for reactor construction permits or operating licenses are currently being reviewed by you. To aid you in scheduling work on these various projects and to help in assuring that we receive your reports in time to send to the ACRS for its leview of particular applications we have compiled a list of'nticipated deadlines for receiving consultant reports on the various projects. In each case we would like to receive your report during the first week of the month bef'ore the project is considered by the ACRS. Considering this, the contemplated schedule for your sending reports to us is as follows:

l. Duke Power Company (Oconee 1 8c 2) - May

2. Vermont Yankee (Vermont Yankee) - May Public Service of Colorado (Ft. St. Vrain) - June

4, PG8:E (Diablo Ca ) - June

5. Philadelphia Electric (Peach Bottom 2 8e 3) - July ~

6. Virginia El.ectric (Surry 1 8c 2) - August 7. Jersey Central (Oyster Creek) - August 8. Public Service of N.J. (Burlington) - October

Some of these project deadlines will likely slip from time to time. Therefore, I would expect to send you revised listings on a periodic basis. Sincerely yours,

ariginai signed by: Roger S. Boyd Roger S. Boyd, 'Assistant Director f'r Reactor Projects Division of'eactor Licensing Vip)7th 'I

h, 0,.~.; CY' 0 ~,''B 0 0—0——EB 0.—9—0—0I ~H PH- .II~ II .:P . PHOOP

,,TYID;P DATE OF DDCUMEITT: DATE RECEIVED NO.I "'Xat5aa $3'44~T'R 9-%MY 4-%ATE LGb2 I IIEIIO IIEPORE HIRER x TO: ORIG CC OTHER Gr. 26orrle- g miaeOgmyhei ay@a roe~4 ACTION NECESSARY Q CONCURRENCE Q DATE ANSWEREDE NO ACTION NECESSARY Q COhlAIENT Q BYs CLASSIF.I POST OFFICE (8UPPL- REG. NOI a0c>ma 50-K5 Mp) DESCRIPTION: (Mvsi Be Unclassified) REFERRED TO DATE RECEIVED BY DATE Ltr..Zurniahing comenta by Ha11 enC Mwanrk v/re ard. & the "Peel9aiaEErg S~.t»~a.R,~~, V.l..z aX CO a I U/'I ys Zor the Keble Canyon Seto Nuclear FLn as ENCLOSURES

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'ATHA N M ~ NEWMA RK I Talbot Consulting Engineering Services II Laboratory, Urbana, Illinois

30 March 1967

Dr. Peter A. Morris, Director Division of Reactor Licensing U.S. Atomic Energy Commission Washington, D.C. 20545

Re; Cont rac t No. AT (49-5) -2667 Nuclear Plant--Diablo Canyon Site Pacif ic Gas and Electric Company Docket No. 50-275, pegulatory Suppl Filo Gy. Dear Or. Morris:

The fol lowing comments and questions are based on the review by Dr. W. J. Hal I and myself of the material presented in "Prel iminary Safety Analysis Report," Volumes I and II, for the Diablo Canyon Site Nuclear Plant, submi t ted by the Pac i f ic Gas and Electiic Company.

The reactor will consist of a four-loop pressurized water reactor, similar to Indian Point No. 2 except that the steam generators are slightly larger. The plant is to have a power output of 3250 MWt (1060 MW(e) net). The primary containment consists of a steel lined, reinforced concrete cylinder with the hemispherical roof supported on a substantial foundation base which in turn is supported on rock. The plant is located in San Luis Obispo County, California, 12 miles WSW of San Luis Obispo on the Pacific Ocean, and adjacent to Diablo Canyon Creek.

I. As a result of the study of four sources of earthquakes, the report recommends the use of two earthquakes for design purposes, namely, Earthquake B, patterned after the Taft 1952 N69'W earthquake, and Earth- quake D, patterned a'fter the Golden Gate 1957 SBO'E earthquake. These two earthquakes are characterized by the applicant as corresponding to maximum ground acceleration values of 0. 12g and 0.20g at the sites, respectively. However, the response spectra associated with the time histories of these two earthquakes are quite different. In the region of probable design interest for the containment structure and.for other items of equipment, Earthquake B controls the response for frequencies between about 0.5 to 4 or 5 cycles per second, whereas in the higher frequency range above about 5 cycles per second, Earthquake D controls the response. Comparison of the spectra as just indicated indicates that the containment design is probably ~ to be made for a 0.12g earthquake, which seems entirely too low For the region under consideration. A more reasonable value for the design earthquake would correspond to a maximum ground acceleration of 0.20g, with the spectrum amplified over the entire frequency range. Such a properly amplified spectrum in the low frequency range would be significantly greater (by a factor of nearly two) than the values now obtained using Earthquake B.

On the basis of our evaluation of the information presented, we are agreeable to the use of a value of 0.20g ground acceleration as describing the design earthquake, and a value twice as great as describing the maximum h - 2 credible earthquake. However, the response spectra presented by the appl icant are not acceptable to us. We request that new spectra be prepared which are representative of the proper velocities and accelerations over the entire range of frequencies of interest so that we can be assured of a reasonable margin of safety for design throughout the entire frequency range. *

2. It is our understanding that two types of analyses may be carried out, one involving a moda I ana lysis in which the spectra, are employed, modal excitation 'handled through the use of participation factors, and the combination of modes handled by the square root of the sums of the squares, which is acceptable if at least three modes are included in the analysis. The alternative involves a time history of motion, employing earthquake records with the amplitude values scaled, used as the excitation for the base motion of a lumped-mass spring-dashpot model of the system. Both approaches are acceptable, provided that they are employed in a consistent manner. By this we mean that the time history employed for the model analysis must yield a response spectrum over the entire Frequency range which falls on or above the response spectrum that is used in the spectral modal analysis. In the event that a time history analysis is to be used, we would insist on a calculation being made by the applicant of the response spectra for various degrees of damping corresponding to the time history input used. 3. It is our understanding, from examination of the material presented in the PSAR, that an inactive shear zone may be located near the containment vessel site. It is our recommendation that the reactor and containment structure be relocated off this zone, to avoid any question of possible relative motions occurring.

4. On page 1-25 and page 6-48, comment is made concerning the containment isolation valves't is our understanding, from discussions with the applicant and their consultants, that these valves will be designed to withstand seismic loading. We should like to be advised of the nature of the design to insure that these valves will operate under seismic loading.

5. On page 2-29, and later in Appendix 0, the statement in made to the effect that a 11 modes having a period greater than 0.08 seconds shall be included in the analysis. We see no reason for this limit. We believe that a sufficient number of modes of excitation should be included in the analysis of the containment structure, piping, or other items to insure that the analysis is meaningful. A better criterion, perhaps, would be to state the number of modes that are to be included. In many cases we can conceive of equipment items or piping which will have periods of much less than the limit cited. It is our belief that there can be no restrictive bound placed on the period as such, and that the proper response spectra and frequency should be employed as appropriate.

6. The table of damping values is',iven on page 2-29, and the following two paragraphs thereafter indicate that the rocking of the structure on its foundation will be considered in the analysis. No value for the damping to be employed with this rocking motion is presented. We should like to be advised of the value that is to be employed. ~X ~

p

J 7. On page 2-30, in the last paragraph, a statement is made, "... (2) ln pressure vessels and piping systems, there wi I I be regions of local bending where the stresses wil I be equivalent to 120 percent of the yield stress, based on an elastic analysis;..." This statement is used in conjunction with the criteria to satisfy the "no loss of function" criterion, we interpret to mean safe shutdown of the reactor and system under the 'hich maximum earthquake. Such a provision has little or no rational interpretation in terms of limiting deformation. It is our belief that a more rationa I and acceptable criterion would be one that places a limit on the tota I deformation, such as, for example, a maximum of two or three times the yield point'deforma- tion, to insure that no significant distortion or rupture is likely to occur in the system. An increased yield stress value may not provide the necessary .constraint on the amount of deformation that may oc'cur', under certain condi- tions of dynamic loading.

8. The base slab analysis, as described briefly on page 5-22, needs to be re-evaluated. Statements are made therein that the base slab will be treated as a flat circular plate supported on a rigid, non-yielding foundation. for the rigid, non-yielding situation noted, it is impossible to understand how the ana lysis will be carried out.

9. The large openings receive brief mention on page 5-22. Huch more detail on the method of analysis to be employed is required. The problem is one of providing for stiffening around the opening, and also providing for a proper distribution of deformations and forces around the opening to insure that no distress will occur in the transition zone between the reinforced opening and the vessel shell.

10. Of particular interest in the penetration design is the detailing of the reinforcement, both radial, vertica I, and diagona I, in the vicinity of the openings. Reference to the reinforcing sketch on Fig. 5-1 leaves some question as to what happens to the diagonal bars in the vicinity of both the large and the small penetrations.

11 'hapter 7 is devoted to a discussion of plant instrumentation. We should like to be apprised of the steps taken in designing the instrumen- tation with relation to the earthquake loadings that may be experienced. This discussion should include not only the effect of the inertial forces arising from the effects of the earthquake, but also any effects of tilt or other motions that might have some influence on the critical instrumentation required for safe shutdown.

12. The compounding of the loading that is to be employed in arriving at the design is described in Chapter 5. We find little discussion of the stress or deformation levels that will be permitted in the design under the maximum earthquake loading condition. Amplification on this aspect of the design is requested.

13. Although it is not stated in Chapter 2 explicitly, we assume that the table of damping values given therein will be employed for both the design and maximum earthquake conditions. Is this assumption corrects 4 4

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l4. Little information appears to be available in the PSAR concerning the design of the piping for earthquake loading and the types of support and method of analysis that wi I l be employed. Elaboration on these aspects is desired.

15. A description of the types and locations of the instrumen- tation to be employed in the proof test of this vessel is desired for further consideration and study. Respectfully submitted, G.>n. g~m

N. N ~ Newmark bd cc: W. J. Hall C F

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foal CDF p Ql n v~m~JAR Pl cn Mm rQC) ~ C7 n 0n n ~ Dis tx'ibution: 'Supp'. DRL Rdg,~ RGPRSB Rdg. Orig: HSteele (2) FEB 1 4 1967 E. G. Case (2) Docket Ho. 50-275 R. S ~ Boyd X. Moodard H. Shapar, OGC Dr. Hathaa H. HeTmark R. Hart, DC Newel1 1 11 Talbot Laboratory J. F. S. A. REG University of Xl1 inois Teets, „R. OC Urbana, Xl1 inois 61803 Leith,

'Dear Dr. Hallmark:

Re: Contract Ho. AT(49 5) 2667

Hathan H. Hemmrk Consulting .Engineering Services is hexeby requested, pursuant to the conditions, of Contract AT(49-5)2667, to provide the follo&ng services for the Commission concerning the proposed construction of a pressurised eater reactor by 'Pacific Cas and Electric Company at its Diablo Canyon site in San Luis Obispo County, Cal ifornia: 'the 1 . Analyses of the, engineering factors included in proposed design to minimise damage from seismical ly- iaduced gxound mot ions.

2. Preparation of a x aport. on (1) above.

3. Serving as an expert witness in the public hearing on this facility.

The maximum amount payable to your fixm for this project is $5,000 ~

Enclosed for your rev iver are Volumes X and XX of the Preliminary Safety Analys is Report for the Diablo Canyon site nuclear plant.

On the basis of our tentative s'chedul e fox'his project, it auld be desirable to have youx report available for our use by April 15, 1967. Sincerely -yours,

Original signed

by'",. G. Ca sc Edsoa C. Case, Deputy Director Divis ioa of Reac tor Licens ing

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