APPENDIX B-20

EVALUATION OF POTENTIAL HAZARDS OF DEPLETED URANIUM V.

"E77AJWATION OF POTENTIAL HAZAFDS 0V DEPT= UPANIU o 'aximur. Amount of Source Paterial Involved in Each -A Process process at Mn7 One Time ",--Itir'9 500 lbs. Ca t 1mg 500 lbs. :ieat Treatment 200 lbs. 7-, r-• n; 250 lbs.

_*tr-dinr 250 lbs. 2'.,' r' 150 lbs. ,qas-ýiriZ,500 lbs.

...ran•.•u.- presents a two fold hazard: first from its chemical toxicity; e~d scond, frcm the ionizing alpha, beta, and garma radiation emitted in the process of radicactive decay. The ionizing radiations are hazardous or when relatively -,h en srall rcLur.ts of uraniun are taken into the body "ar2,e a*ounts are present in close proximity to the body. However, the c'•<'a yprorerties of uran!u'=. -resent a hazard only after it is absorbed limited Intc the blood streams. rortunately, uranriun is absorbed to n very and its specific extent through unbroken sl:in or the gastronintestinal tract, elements. actlvity is quite low in comparison with most other radioactive Ma.z.T'ful exposures to either hazard can be prevented by careful handling technIques and cc.-on sense. a. External. The isotopes of uranium found in normal or depleted mixtures emit alpha particles accompanied bl' very low energ a rad ation nrc hazarrý in t he nrcces of radioactive decay. The alpha radiaticn nresents low unless the uraniur'. gets into the body. Th•.e ga-rma radiation Is of such no hazard exce-t to parts of the hcd:, in contact energL" that it constitutes time. *Af .Ith larse quantit.es of urcniur. for extended periccds nr ,-3 and chemicýl refiýnn%" the beta particle emissions of UJX, and UTX2 ( 9ý1a23'), the first t;'o dau7ghters of n2U23°, rnre up near, al- the rcnctrat'lrC racli;iticn asszooa.eJ -. w1th'et),= normal cr r'em~lete-l uranlu-.. of rletal sl( I 7-. raitationd dose rate at the surrape2 a bare uranw-. Pnd tre 2r3 nrZr./hr. Te 2.3, •-0 Cevrom 9 P 3a contributes 240 mrer/h•r n. 1 r . 'ev B- from %,Th2&7acds 9nother 20 rmaem/hr. -he gamra ras are ail qu'ut soft and! all tr.ly 2.7 mrem/hr. ••he nelting and casting of urnanlur surface of the resujt In the nigration of the ",71 and IJX2 daughters to the cnst!,. The concentration of these beta. emitters on the interior surfaces of ncl-Is and crucibles, on the exterior surfaces of castings, and in the slag results in dose rates as high as 2 R/hr. These surface deposits are re-cid quicklTy and easily by washinzr resulting In limited exnosure tn rersonnel. ,. Internal. Uranluri ca: g;in access to the "c(:y by way of injection, estion, or inhalation. Alsor1ptlon t)rcu) unbro-e shin is negligible; -rsorption via injection is likely to occur onlyv in such cases as contamina tion of open wounds; and absorpt!:)n via i is a:croximateiv 1% of intake. Inhalan o: uranium ccmtA4s 'F the ;nficant,io mode of entry. Once in the bo raniumt cai cailse d b,' rcj:a-iOn and by chemical toxicity.

c. Chemical Toxicity. Once uranium enters the blood stream in cally active a chemi form, its toxicity i.: comparable to that of arsenic, mercury. Fortunately, lead, or the dusts ri:ost likely to be encountered in industrial processing of uranium are relitively insoluble and so inert physiologically that they are considered as r-idiclorical hazard-; rather than toxic chemicals. These-are deposited prima-ily in the res-liral-cri system from which they are mobilized slowly. The more soluL_,ý corMIpouInd or uranium are quickly taken into the blood stream via lunrs or ccntan,-inatý-J wounds and may result in significant deposits of U0 2 in the kidney. There some of the uranium combines with the protein of cell walls, poisoning the cells and interfering with the vital functions of waste eliminaticn ana maintenance of electrolyte balance. The uranium does not remain fixed in the kidney, but is eliminated at the rate of about half every two weeks. Moderately severe damage to the kidney as a result of acute exposure is reparable, and a return toward normal kidney function may occur even during continued exposure.

d. Radiation Hazards. The principal radiation hazard from internal deposits of uranium is the intense ionization in tissue produced by the alpha particles emitted during radioactive decay. The more than 4 of the alpha particles Mev energy is absorbed in the first 0.1 mm of tissue, resulting in localized cellular damage. On thie otherhand, particles dissipate their gamma rays and beta energies 1n •latively larger volumes of tissue and produce comparatively little dariargj Many industrialF uranium dusts are relatively insoluble and are deposited primarily in the respiratory system. A fixed deposit of uranium in the lung is eliminated at the rate of about half every 120 days.

2. Hazard Control and Evaluation.

a. External. Uranium does not constitute a serious external radiation hazard. The time honored methods for controlling exposure to external sources of radiation are distance, time, and shielding. The intensity of gamma radiation from a point source rapidly decreases with distance away from the source. Beta radiation intensity is decreased even more rapidly with distance. In the case of uranium there is relatively little radiation exposure at a few feet from the material. The length of: time a person may remain in any given area or at any particular jab can be limited on the basis of instrument evalua tions of the radiation conditions. It is not necessary to use massive shield ing or special manipulating devices to decrease exposures in working with normal or depleted uranium. The 2.32 Hev betas from these materials will be stopped completely by about 0.5 in. of water, even less plastic (Lucite), or less than 0.25 in. of glass. A horse-hide leather glove can decrease the radiation dose to the hands as much as 80%.

2 P'17 '.

with t 1. Since the principal health hazard in dealing -mpounds is that of inhalation, the b sic methods of control are andoure ventilation. Depleted uraniun. ptocessilng areas are provided appropriate and special or local ventilation u adequate general ventilation Commercially available respiratory or the kind of operations performed. term high concentra for protection against short protective devices are used that place programs and administrative procedures tions. Educational supplement mechanical handling techniques are used to emphasis on proper in the atmosphere, Usually the sampling of uranium particulates controls. is accomplished by method of evaluating inhalation hazards, the standard of uranium, a filter at a measured rate. The amount drawing air through determined filter from a known volume of air is UX and UX2 collected on the 1 radioactivity. The procedure for by measurement of the alpha and beta follows: determining airborne activity is as air through a filter (1) Air samples are collected by filtering time. Routine spot samples at a known rate of flow and for a predetermined for a 20 minute period. are collected by running the air sampler for holding the (2) Counting technique utilizes a 2" planchet is placed in the planchet and counted sample to be counted. The filter paper for 30 minutes. by the counting time to (3) The total count obtained is divided per minute. determine the counting rate in counts is subtracted from (4) The background ccunt rate of theldetectcr giunts per minutes. the counts per minute to obtain the corrected is divided by the efficiency (5) The corrected counts per minute per minute (dpm). of the detector to determine the disintegrations as follows: (6) The airborne activity is then computed

airborne activity = dpm (2.22 X lO~dpm/uc) (volume of air sampled)

with limits specified (7) The calculated activity is then compared in AEC Reg 10 CFR Part 20. and cast under either a c. Melting and Casting. Uranium is melted all radiation and contamination vacuum or some inert gas. This contains the radioactive daughter during the melt. During melting and casting, They are found mostly in the crucible products segregate from the uranium. This segregation is so pro residues and on surfaces of rough castings. will be found. nounced that very real radiation hazards

LI

3 (1) Melting. The vacuum melting operation is uiique in that the .,grhtO~j oducts of uranium are brought to the surface of the melt and are found In're , the surface of the melt, and the lining of the furnace. 'This radioaco material must be removed. After pouring, the top surface of the ingot is cropped and the sides are machined under local exhaust ventilation. Patching of the furnace lining periodically results another health physics ?roblem in involving external radiation and airborne culate matter. Shielding parti the personnel who perform this job because of the is difficult freedom of movement required for the operation. lead aprons are unsatisfactory. Gloves and One solution is to use a movable aluminum shield which is placed Inside the furnace. Aluminum was chosen higher atomic number since elements produce Dremstahlung radiation to beta radiation. when exposed The beta radiation associated with has an effective the daughter products range of 1100 centimeters. This trate is more than enough to pene the epidermes layer of skin and may potentially cause beta burns. How ever, the aluminum shield is only open in that quadrant in which the worker is either cleaning or patching the lining. Even with the shield, worker must be limited the as to the amount of time spent in Respirators the furnace. are required during the patching operation.

(2) Casting. When graphite crucibles are used they must be machined after for casting uranium, each heat. Considering that the crucible contaminated with radioactive is now daughter products, the ventilation during machining problem operation requires careful consideration. particulate matter Airborne may be far above the MPC. The ventilating this system used for operation utilizes a hood enclosure of a combination of sheet metal and luci 'alastic in conjunction with the exhaust system. d. t Tlatment. No special measures are required operations. for heat treatment

e. Hot Working.

(1) rorging. Health physics precautions are not press forging because stringent in there is very little airborne contamination.

(2) Extrudina. No special health physics precautions are considered necessary with the exception of conducting proper clean up after extrusion was completed. The heating of the billets is conducted in properly vented salt baths.

f. Cold )Jorkin),(Sviaging). ho special measures are required for normal swaging operations.

g. Machining. To maintain the level of airborne particulate below the MPC, all machining uranium operations are provided with local exhaust ventilation. The degree or extent of ventilation varies with the nature, amount, and method of release of the contaminant. All machining is performed under coolant. Since uranium is pyrophoric, a generous supply of coolant is used to flood both the tool and work piece to prevent fires and to reduce airborne contamination. All machines are thoroughly cleaned at least once a month.

4 r-"

ory Protection.

S(I) Respirators are required for all operations in which airborne adi•oactivity concentrations might exceed 10% of the maximum permissible they will be concentrations established in Title 10 Part 20. In addition, worn when directed by the Health Physicist.

(2) The type respirator to be used is the American Optical R-6057 Sure Guard Respirator with the Super Micro-Toxisol R-57 Filter. See Figure I for manufacturer's instructions regarding fitting, cleaning and maintenance of these respirators.

(3) The supervisors are responsible for insuring that personnel are instr.ucted in the proper use of respirators and wear them as required. Work will be programed in such a manner that respirators will not be worn for periods longer than 45 minutes at any one time nor more than 5 hours in any one work week.

(4) Experience has shown that the average concentrations encountered in areas occupied by employees fall within three to five times the MPC established in 10 CFR 20.

FLJAL7.ACI1N 0F P=TLIAL HAZAPDS Or 77.07I.1

. . .r-c.urnt of,. urce "aterial Invclve&ý in Each llrcces.. ".t Tny .. "'--

•.'{-z n. .ds

The thcria is used as P crucible rm-terial because of it7,-.- tr--err -..... ','-st 7.-crci. . .. r.ts no h-zar,.9 In the • u~eK ' r t,'.¶ -"c 7..-. e thoria cruciae is set ½nsl, a tantulhTv cr'r:cb]e ýnr •-'* -. r-turp of 20CC - 23000 0 in a high Vacuur syste7. T t -' 'ru•'r ,- - t_.ct. durrtis the meltinf cycle. T-he crucibles Pre iis'vul u-rp r'c -5 K •r~cweK of as radioactive .... te.

Of-•R--. _ C .- t .. L U. .. APPENDIX C ARGONNE NATIONAL LABORATORY DATA ý\7*rf DOE/EV-0005138 1 0 ANL-OHS/H P-83.108 01 C 'C.,.

FORMERLY UTILIZED MED/AEC SITES REMEDIAL ACTION PROGRAM

RADIOLOGICAL SURVEY OF THE FOR MER WATER WN ARSENAL PROPERTY GSA SITE VVATERTOWN, MASSACHUSEl TS

OCCUPATIONAL HEALTH AND SAFETY DIVISION Health Physics Section ARGONNE NATIONAL LABORATORY, ARGONNE, ILLINOIS

(-f Operated by THE UNIVERSITY OF CHICAGO for the U. S. DEPARTMENT OF ENERGY under Cc'-.ract W.31.109.Eng.38 233 234 m NI 229 0 193 192 191 190 L 230 185 21 18 @7 133

232

235 220 20 238 I 239 237 194 195 196 1971 - 243 241 242 236

0 FEET 30 n SMAR ET ES Q OVERHEAD SMEAR 0 METERSI 0 N AIR SAMPLE

Q GAMMA BACKGROUJN

Fig. 9. Building 234. ANL-IIP Dwg. No. 82-13

f ( ( I

6 5A

v9 9 I 109 J12 120 ,,,©,190 2©@ ,,o2 ,,g(430®- 0 02-8 4o 1 A'" L- 11 57(100 1073ýý 10 11

3/ If ROOM NUMBER

n SMEAR

(D OVERHEAD SMEAR FEET oI- -- 30 ! A

0 METERS 10 N A, AIR SAMPLE

Q GAMMA BACKGROUND

Fig. 10. Building 235. ANL-II1 Dwg. No. 82-12. 174 III Li Li

I 168 169 170 171 172

GARAGE 1 (9 200 199 A 199 OFFICE AREA 2 175 0 RADIO SHOP 3

-E ROOM NUMBER 0 FEET I0 n SMEAR I I 0 METERS 3 N 0 OVERHEAD SMEAR A AIR SAMPLE Q GAMMA BACKGROUND

Fig. I. Building 236. ANL-IlP Dwg. No. 82-14 ( ( 181

1AA

1o 179

N

0 FEET I0 -- - - Im.- n SMEAR

0 METERS 3 /A AIR SAMPLE

Q GAMMA BACKGROUND

Fig. 12. Building 237. ANL-IIP Dwg. No. 82-15 37

TABLE 2

AMBIENT RADIATION LEVELS

Duration of Radiation Level Corresponding 0 Location Measurement RSS-111 PRM-7 Measurement Area No. Grid (h) (pR/h) (PR/h)

INTERIOR

Bldg. 234 18 65.5 8.9 7 Bldg. 235 11 4.0 8.8 7 12 3.0 8.3 7 13 4.0 9.0 8 14 3.0 10.2 8 16 3.4 8.9 8 17 4.1 9.4 8 19 6.0 11.2 8 Bldg. 236 15 6.2 8.6 8

Bldg. 237 20 4.1 8.8 8 ------EXTERIOR I 1 M-2 2 M-2 2.5 11.6 13 II 3 .-- 3 4.5 9.8 7 4 K-3 2.1 11.7 10 7 H-2 6.2 7.5 IlI 5 5 H-3 3.0 10.7 9 6 F-4 3.8 12.6 11 10 E-4 2.3 10.0 10 IV 9 1-1 2.5 10.2 10 V 8 0-2 1.8 9.6 10 21 Q-2 2.9 14.6 15 22 Q-1 3.1 12.4 12 aLocations are shown on maps in Figures 5 and 9 through 12. 38

TABLE 3 a RADON-CONCENTRATION DETERMINATIONS

Radon Air Sample b (2i/£ pCi/9 Number Location

0.74 4 Building 235, 0.0074 -Room 1

0.65 5 Building 235, 0.0065 Room 2

1.02 6 Building 235, 0.0102 Room 3 East

0.85 7 Building 235, 0.0085 Room 3 West

0.38 8 Building 235, 0.0038 Room 5

0.58 9 Building 235, 0.0058 Room 10

0.46 10 Building 236, 0.0046 Office

0.15 11 Building 236, 0.0015 Garage

0.04 12 Building 237, 0.0004 Shed

0.06 13 Building 236, 0.0006 Radio Shop

0.10 14 Building 234, 0.0010 East

0.96 15 Building 235, 0.0096 Pistol Range

0.27 16 Building 234, 0.0027 Center

0.54 17 Building 234, 0.0054 West 39

TABLE 3 (coat'd.)

Air Sample Number Location WLb

18 Building 237, No actinon Shed

20 c Building 236, No actinon Garage

Building 235, No actinon Room 3 Center

22 Building 234, No actinon Center

aLocations are shown on maps in Figures 9 through 12. b A Working Level (WL) is defined in 10 CFR 712 as any combination of short-lived radon-daughter products in 1 liter of air that will result in the ultimate emission of 1.3 x 105 MeV of potential alpha energy. The numerical value of the WL is derived from the alpha energy released by the total decay through RaC' of the short-lived radon-daughter products, RaA, RaB, and RaC at radioactive equilibrium w'ith 100 pCi of 222Rn per liter of air.

Actinon determination. TA ILE) DATA SHEET OF AREA SURVEYS I Window~EndI Percent of Area I'AC 4G-3 8 Accessible Air Direct Rleadings (M PRiM-7 PRM-5-3 Smear flesultr. Room or for Survey Sample (dis/nin-l0O cmI) (miR/h) (pR/h) w/PG-2 (dim/min Area No. Floor Wall (WL) Both Alpha Contact I meter (cts/rain) 100 cml) Comments

AREA 1: 2 cm IlKGI) 0.8 40 45000 100 34 I000 2 c-m 50000 100 2500 RKGI 0.03 40 35 2 c-m 20000 100 400 KGDI) 0.03 30 36 2 100 cm 500 BK(;I) 0.07 10 10000 37 100 0.04 20 3000 )00 2 38 Cm 10000 ( 100 15000 0.2 20 39b 2 100 cm b 5.0 20 35000 4 0 50000 400 2 cm ( 100 0.1 20 5000 w- 41 2000 2 100 cm FIKGI) 0.1 20 5000 42 500 100 BKGI) 0.15 20 15000 43 3000 100 BKGI) 0.5 20 15000 3000 2 44 Cm 100 20 10000 2000 100 0.6 45 2 20 5000 < 100 cm 500 BKGI) 0.05 46

AREA I:I

< 700 CM2 BKGI) 0.14 30 30000 47-53, N-ý 4500 2 50000 < 200 cm b 451000 250 7.0 30 54 , 60, N-3 TABLE I DATA SHIEET OF AREA SURVEYS

I 1 1 - Percent of Aroa PAC 4G-3 End Window Accessible Air Direct Rnoadinsa GM PRM-7 PRM-5-3 CImOar Resultr floom or for Survey Sample (dlis/ in-100 crul) (mR/h) (pR/h) w/PG-2 (dis/rnin Area No. Floor Wall (WI1) srpin Alpha 1 mnoler 10[) era1 Contact (cts/nin) Cormnin n t r, . 100 C.1...

55-5 7, N-3 IlKG(I) 2 0.7 30 30000 1100 cm 59, 61-63, 25010101 )00 0.7 2 N-3 30 50000 47000 cm

58, H-3 400 IK(;I) 2 0.03 30 2000 900 cm 71, L-2 300 OK OIl 0.03 2 30 2100 3700 cm 64-66, L-3 BK(;1) 1000 0.08 30 2 10000 < 300 cm 67-70, K-3 HKGI) 0.02 30 50000 < 400 CM2

AREA III t-n General 11K(;ID 1000 1(0GD I0 2000

AREA IV General 500 IKGD 20 3000

AREA V

72. 73, 2510 2 "1K(;I) 0.03 20 10000 < 300 cm 77, N-I

( ( TABLE 1 DATA SHEET OF AREA SURVEYS

i'AC 4G-3 Window PercentAccessible of Aiea Air Direct Readingsa GM PRM-7 PRM-5-3 Smear Results

Boom or for Survey Sample (dis/min-100 cml) (mR/h) (pn/h) w/PG-2 (diu/min Area No. Floor Wall (WL) fla Alpha Contact I meter (cts/min) 100 cmI) Comments

AREA V

(cont'd.)

2 cM 74-76, N 15000 PK(;I) 3.0 20 25000 ( 300 2 flK(WD 3000 300 cm 79-82, 0 250 0.04 20 2 2000 100 78, 0-2 250 0.04 20 Cm BKGD 2000 ( 100 2 83, P-I 250 0.03 20 cm BK(;,D 0.03 20 3000 ( 100 89, P-2 250 2 cm BKGI) 0.03 20 2000 100 84, Q-I 250 2 HKGI) cm aI' 0.03 20 7000 300 85-88, Q- 400

All instr ment reii ings I clude bardgrounds (P4 C-4GR, 250 4im, PRM-!-3, 400 cpni. G", 0.03 mR, I'RK-7, I'I pR).

b etsl chills were 4ound at these loc tLi oilii.

t" "Grid loclkions arq shown n Fipt,,re 37

TABLE 2

A{fBIEN-T RADIATION LEVELS

Duration of Radiation Level Corresponding a Location Measurement RSS-11l PRM-7 Measurement Area No. Grid (h) (pR/h) (pR/h)

INTERIOR

Bldg. 234 18 65.5 8.9 7

Bldg. 235 11 4.0 8.8 7 12 3.0 8.3 7 13 4.0 9.0 8 14 3.0 10.2 8 16 3.4 8.9 8 17 4.1 9.4 8 19 6.0 11.2 8

Bldg. 236 15 6.2 8.6

Bldg. 237 20 4.1 8.8 ------10P EXT.ERI OR I 1 M-2 3.3 17.7 34.

2 M-2 2.5 11.6 13 !I 3 M-3 4.5 9.8 7 4 K-3 2.1 11.7 10 7 H-2 6.2 7.5 5 III H- 3 5 3.0 10.7 9 6 F-4 3.8 12.6 11 10 E-4 2.3 10.0 10 iv 9 1-1 2.5 10.2 10 ',7 8 0-2 1.8 9.6 10 21 Q-2 2.9 14.6 15 22 Q-I 3.1 12.4 12

TLocations are shown on i-aps in Figures 5 and 9 through 12. 38

TABLE 3

RADON-CONCENTRATION DETERMINATIONS

Radon Air (2i/£ Sample b Location Number

0.0074 0.74 4 Building 235, -Room 1

0.0065 0.65 5 Building 235, Room 2

0.0102 1.02 6 Building 235, Room 3 East

0.0085 0.85 7 Building 235, Room 3 West

0.0038 0.38 8 Building 235, Room 5

0.0058 0.58 9 Building 235, Room 10

0.0046 0.46 10 Building 236, Office

0.0015 0.15 11 Building 236, Garage

0.0004 0.04 12 Building 237, Shed

0.0006 0.06 13 Building 236, Radio Shop

0.0010 0.10 14 Building 234, East

0.0096 0.96 15 Building 235, Pistol Range

0.0027 0.27 16 Building 234, Center

0.0054 0.54 17 Building 234, West 39

TABLE 3 (cont' d.)

A: r Sample Number Location WLb

16Cc U, I -; No actinon Shed c 2 0 Building 236, No actinon Garage

Building 235, No actinon Room 3 Center

Building 234, No actinon Center a Locations are shown on maps in Figures 9 through 12. b A Working Level (WL) is defined in 10 CFR 712 as any combination of short-lived radon-daughter products in I liter of air that will result in the ultimate emission of 1.3 x I10 MeV of potential alpha energy. The numerical value of the WIL is derived from the alpha energy released by the total decay through RaC' of the short-lived radon-daughter products, RaA, RaB, and RaC at radioactive equilibrium W- 100 2 2 2 th pCi of Rn per liter of air. cActinon determination. TABLE 4

(;AMtIA SIECIIAL AND URANIIUR FLUOROME'RIC ANALYSES OF SOIL SAMIPLES

Gatunn Sjpectra, yCi/&!-J

2 32.rI, 226H, Fluorouetric a Decay Decay Uranium Sample 3 (Chain Chain PR/8 1 10% pCt/g 1 10% No. 1 7c

SOIL COHINGS

33.4 :1 1.36 ± 0.09 824.0 t 82.4 334.0 t b I-S47-A 1.54 f 0.11 1.03 0.07 ± 902.0 90.2 0.07 1.21 ± 0.09 2227.0 222.7 B 1.96 t 0.14 1.04 ± 2 9 . b ± 1 .52 ± 0.11 736.0 ± 73.6 298.0 b 0.53 0.05 0.86 t 0.07 C 46.2 ± 4.6 18.7 1.9 <0.03 0.35 1 0.07 0.62 ± 0.06 D ± t 241.0 t 24.1 1.03 1.60 t 0.11 595.0 t 59.5 1-548-A 1.10 ± 0.08 t 0.07 48.4 196.0 t 19.6 t 0.09 1.89 ± 0.13 484.0 ± B 0.79 0.07 1.33 40.5 41. ± t t 0.13 100.0 t 10.0 0.04 1.24 0.09 1.81 C 0.24 ± 47.0 t 4.7 19.0 1.9 0 0.98 ± 0.07 1.53 t 0.11 D 0.08 0.03 ± 151.0 15.1 b 1.21 t 0.12 372.0 37.2 ± b 1 .48 ± 0.15 i-549-A 1.08 it 0.11 t 412.0 ±f 41.2 167.0 ± 16.7b it 1 .62 ± 0.16 0.92 0.09 B 0.90 0.09 88.3 ± 8-8b 1.30 ± 0.13 218.0 t 21.8 0.05 I .05 it 0. 11 C 0.51 it ± 84.3 8.4 34.1 t 3.4 1 .08 it 0.11 I .•4 0.10 ± D 0.29 0.03 ± b it 16-3b 0.83 0.08 403.0 40.3 0. 10 0.67 it 0.07 it 163.0 1-S50-A 1.03 761 .0 ± 76.1 308 .0 ± 30.8b 0.83 it 0.08 0.97 0.10 B 0.67 0.07 ± 348.0 ± 34.8b it 1.03 0.10 859.0 85.9 0.05 0.73 it 0.07 ± ± ± 25.8 C 0.53 it 637.0 63.7 258.0 0.87 it 0.09 1 .40 0.14 D 0.63 0.06 ± ± it 2.4 1.6 ± 0.2 it 0.0 7 1 .08 0.11 ± 0.2 0.33 0.03 0.70 ± 1 it 0.2 I-S51-A it 0.10 3.3 0.3 2.3 0.78 it 0.08 1 .00 ± ± B 0.70 it 0.07 3.8 0.4 2.6 ± 0.2 1.18 0.12 ± 0.10 1.01 it 0.10 ± it 0.2 C 1.01 it 0.10 2.2 0.2 1.5 0.84 it 0.08 0.97 D 0.35 0.04 ± ± ± 4.4 ± 0.4 1 0.19 0.6 I .25 it 0.13 .85 it 6.4 ± !-S52-A 1.12 it 0.11 5.2 0.5 3.6 ± 0.4 0.14 1 .84 0.18 ± 0.81 o.08 1.36 it 3.0 it 0.3 B it 't 0.18 4.4 0.4 1.22 "t 0.12 1 .76 ± C 0.58 it 0.06 't 1.9 0.2 1.3 £ 0.2 .010 it 0.10 0.90 0.09 D 0.04 0.02, TaI'iie 4

(uoniSii.d . )

Giminn Spec-tra1 jpCI/8ti•

2 24BRaq Sample Iirca y Uraniim 1'luoronetci/ No. I 37c(:t Chai iti CIh I n Pg/g ± (lPci/g f 107. I-$53-A 1.91 0.19 0. 76 (I. OR 1 .35 7 . 0 B it 00.14 0.7 3.9 t 0.4 2.11 0.21 1 .20 0. 12 2.02 - 0.20 5.7 it 0.6 C 4 3.9 I .42 0. 14 1.15 0.12 1 t it .60 ± 0.16 3.7 0.4 2.5 ± 0.3 D 0.20 0.04 1.26 + 0. 13 1.61 i0. 16 2.4 0.2 1.6 1 0.2 it I-S54-A 2.49 0.25 0.67 0. 07 it 1.10 .t 0. II 10.6 1.1 5.2 0.5c B 2.68 0.27 it it 0.96 0. I0 1 .20 0. 12 6.6 0. 7 3.6 0.4 itit C 0.59 0.06 0.94 0.09 1.12 0.11 0.2 it it 2.9 0.3 2.0 ± D it it 0.12 0.04 I .44 it 0. 14 1.15 0.12 2.1 it 0.2 1.4 0.2 it it 1± I-S55-A 1 .55 0.16 1.10 0.11 it 0.2 it 0.49 0.05 1.8 ± 0.2 1.2 B 1.74 0.17 1 .20 0.12 0.88 +. 0. 09 it 2.6 0.3 1.8 it 0.2 C 1 .62 0.16 I. 00 0.10 4 it '-. it 1.31 0.13 4.4 0.4 3.0 it 0.3 D 0.36 0.04 1.51 it 0. 15 1.31 0.13 2.2 0.2 1.5 0.2

I -956-A 0.20 0.04 <0.06 0.15 it0.05 <0.7 8 0.03 0.04 (1.0 0.11 0.05 <0.02 <1 .0 <0. 7 C 0.21 0.04 it 0.34 it 0.06 0.53 it 0.05 (1.0 <0.7 D 0.13 0.04 1. 05 it 0. 11 1.35 f 0.14 2.0 it0.2 1.4 t 0.2

I-S57-A 5.01 0.50 <0.06 it 0.91 0.09 2.1 it 0.2 1.4 it 0.2 B 7.80 0.78 0. RO 0.08 it 1.15 it 0.12 1.8 it 0.2 1.2 it 0.2 C 2.35 0.24 1.07 0.11 1.12 0.11 1.7 it 0.2 1.2 it 0.2 D 0.99 0.10 0.70 0.07 it 1.20 it 0.12 2.1 it 0.2 1.4 it 0.2 it it I-S58-A 1.44 0.14 I .38 0.14 it 0.80 0.08 1.9 it 0.2 1.3 it 0.2 B 1.65 it 0.17 it 0.94 0.09 0.88 0.09 1.9 it 0.2 1.3 0.2 it it C 0.93 0.09 1.10 0.11 1 .24 0.12 1.8 0.2 t it 1.2 0.2 D 0.45 1.06 it 0.05 0.11 1.01 0.10 1.7 0.2 1.2 0.2

( TA F1F. 4

G a cnctJra)Ci r a [&to

232-11, 22nRa Sample D)ecay Decay Urniijum Fluorometric No. asic, Chla Ii Ch init Pg/g ± 1O% pCi/g t 10%

1-559-A 1.55 ± 0.16 0. 1 1 1.86 0.19 4.2 0.4 2.9 ± 0.3 B 2.74 t 0.27 1.18 0. 12 1.72 0. 17 4.8 0.5 3.3 £ 0. 1 C 2.27 t 0.23 0.68 0.07 1.46 0.15 3.6 0.4 2.5 ± D 0.33 t 0.04 0.3 1.11 0.11 2.01 0.20 3.6 0.4 2.5 ± i-S60-A 5.19 t 0.52 1.47 0.15 2.07 0.21 3.9 0.4 2.7 ± 0.3 B 3.48 t 0.35 2. 1Q 0.22 3.39 0.34 6.9 0.7 4.7 ± 0.5 C 0.78 t 0.08 3.32 0.33 4.85 0.49 8.9 0.9 6.1 ± 0.6 ± D 0.20 0.04 1 .09 0.11 1.45 0.15 2.5 0.3 1.7 ± 0.2 ± I-S61-A 0.97 0.10 1.15 0.12 0.81 0.08 2.3 0.2 1.6 ± 0.2 ± B 0.62 0.06 I .39 0.14 0.73 0.07 2.5 0.3 1.7 ± 0.2 ± C 0.61 0.06 0.88 0.09 0.76 0.08 2.6 0.3 1.8 ± 0.2 D 0.95 0.10 1 .03 0.16 0.84 0.08 3.0 0.3 2.1 ± 0.2

it 1-$62-A 1.10 0.11 1 .59 0.16 1.10 0.11 27.0 2.7 11.8 ± 1.2c ± B 0.50 0.05 0.80 0.08 1.67 0.17 15.5 1.6 7.6 ± 0.8c ± C 0.11 0.03 1 .28 0.13 1.20 0.12 4.6 0.5 3.2 ± 0.3 D <0.03 0.90 0.09 1.21 0.12 2.5 0.3 1.7 ± 0.2

1.63 t 0.16 0.07 1 0.04 1.34 ± 0.13 1.9 1 0.2 1.3 ± 0.2

0.48 1 0.05 1.75 ± 0. I0 3.84 t 0.38 962.0 ±96.0 390.0 139.0

SOIL. BORINGS

1-SI7-1 0.23 ± 0.04 0.58 t 0.06 0.72 ± 0.07 3.5 it 0.4 2.0 ±" 0.2c it it 2 0.30 0.04 0.73 0.07 0.43 0.04 3.8 it 0.4 1.9 0.2 it it 0.34 0.04 0.49 t 0.05 0.36 0.04 1.1 it 0.1 0.8 0.1 4 it it i" 5 0.51 0.05 1.21 t 0.12 0.78 0.08 2.6 it 0.3 1.8 0.2 ± it it 6 0.17 0.04 0.83 0.08 0.74 0.07 2.6 0.3 1.8 it 0.2 1AII.E 4 (( -nlt , d. )

t;RhIw1l,1 jf( Liii, j'L. I /$J

213 11h 22n in SAmple I~rn y Ilech y Utrlijum Fll1oromietric No. 37Cp, (:hn t n c hmi IR/R t 10% I)Ci/g ± 10% 1-578-1 0.35 ± 0.04 2.29 0. 23 2.42 0.24 11.2 ± I1 2 ± 6.5 t 0.7" 0.57 1 0.06 1. 14 0.11 I.II 0.11 8.3 ± 0.8 4.3 t 0.4c + 3 0.57 ± 0.06 3.66 0.37 2.32 0.23 7.5 ± 0.8 5.1 f 0.5 4 0.21 t 0.03 4. 1 .98 0.20 1 .69 0.17 3.0 + ± 0.3 2.0 ± 0.2 5 0.24 ± 0.03 1 . 76 0. I8 I .76 0.18 3.2 ± 0.3 it 2.2 t 0.2 6 0.25 ± 0.04 I .82 it 0. i8 1 .69 0.17 3.6 ± 0.4 2.5 ± 0.3 4` ± 1-S79-1 0.53 it 0.05 1.65 0.17 ±t 1.78 0. 18 22.5 it 2.3 10.6 2 0.44 it 0.04 it 1.1 1 .29 0. 13 1.25 0.12 4.9 it 0.5 it it ± 2.9 0.3 3 0.18 0.04 0.15 0.05 0.29 0.03 0.9 it 0. 1 0.6 it 0.1 4 1.70 it 0.17 0.33 it 0.07 0.68 S.3 it 0.1 it it 0.07 0.9 0.1 5 <0.03 0.23 0.04 0.60 + 0.06 2.0 it 0.2 0.1 6 <0.03 it 1.4 .r- 1.15 0.12 0.69 1.6 0.2 + it 0.07 i. 1 0.1 !-980-I 0.36 t 0.04 0.89 t 0.09 1.07 it 0.11 23.3 2.3 C 2 10.3 it I . o <0.03 1 .85 t 0.19 2.10 ± 0.21 6.7 0.7 4.4 0.4 3 <0.03 <0.06 0.48 it o .05 1.7 + 0.2 1.2 4 <0.03 0.68 t 0.07 it 0.38 0.04 4.1 + 0.4 2.0 0.1 5 it 0.14 1.35 1.01 it 0. 10 1 .48 + 0.15 7.0 + 0.7 4.0 it 0.24 6 0.22 i 0.02 0.98 ± 0. 10 + 0.60 0. 06 7.4 + 0.7 3.5 0.4c

1-S 1-I 0.20 0.04 0.95 0. 10 1 .41 0.14 622.0 it 62.2 252.0 1t25.2 2 0.77 0.08 0.24 0.02 I .36 0.14 1400.0 it140.0 567.0 ±56.7 4 0.22 0.04 0.60 4. 1.44 it 0.06 0.14 232.0 + 23.2 94.0 i 9.4 5 0.34 0.03 0.78 it 0.08 4` 0.83 0. OR 101.0 it 10.1 40.9 6 <0.03 0.60 it 0.06 1 0.1") 1 1.19 0.12 14.2 1.4 6.7 it it 1-$82-1 0.57 it 0.06 1 .32 it 0.13 1.06 it 0.11 119.0 + 12.0 48.2 2 0.51 0.05 1 .42 0.14 1.15 0.12 62.4 6.2 fit it +` 25.3 2.Ab 3 0.88 0.09 1.18 0.12 1.17 0.12 it it it 54.3 5.4 22.0 2.2 4 0.21 0.02 I .35 0.14 0.74 4. 0.07 10.4 1 . 0 4.8 it 0.5 5 it 0.21 0.02 0.25 0.05 0.36 0.04 2.0 0.2 1.4 it 0.2

6 0.25 i 0.02 0.63 t 0.06 0.79 it 0.08 1.6 t 0.2 1.1 t 0.1 ( ( TABILE 4 (cont'd.)

Gammsn Spc~ctra. PCi/pit?

2 3 2 Th 2 2 Oia

Sample Deciay Decay Uranium Fluorometric 7 No0. 13 Cu Chlion ch ain,| pg/K 1 10% pCi/R ± 10C I) 1-883-1 0.08 4 0.05 0.60 ±. 0.06 1.13 0.11 136.0 ±. 13.6 55.1 ± 5.5 2 0.37 1 0.04 o.61 ± 0.06 1 .56 0.16 928.0 ±. 92.8 376.0 :t37.6 ± 3 <0.03 0.31 ± 0.09 0.60 0.06 33.4 ±. 3.4 13.5 ± 1. 4 I 4 <0.03 0.34 ±. 0.07 0.83 t 0.08 15.2 ±. 1.5 6.8 1 0.7 .± ± ±. 5 <0.03 0. 13 0.05 1 .04 0.10 39.0 3.9 15.8 4. 1.6 b 6 0.08 ± 0.05 0.46 ±. 0.07 0.99 0.10 35.9 ±. 3.6 14.5 t 1.5 ± ±. ±. !-S84-1 0.90 0.09 0.89 0.09 1.06 ±t 0.11 257.0 26.0 104.0 ±10.4 ±. ±. ±. 2 0.35 ± 0.04 1.07 0.01 1 .35 4.t 0.14 136.0 14.0 55. 1 t 5±.5 ± ±. "±" 3 0.63 I 0.06 1.14 0.11 0.28 4± 0.03 8.9 0.9 3.6.±t 0.4 ±. ±. 5 0.13 0.03 0.73 0.07 0.91 ±. 0.09 6.1 0.6 3.2 ± 0.3 ±. ±. 6 <0.03 0.58 0.09 1.01 0.10 5.8 0.6 3.2 ± 0.3 4

±.28.b 1-185-1 3.62 t 0.4 0.94 ± 0.09 0.68 0.07 710.0 ± 71.0 288.0 2 0.68 0.07 1.75 0.18 1.62 0.16 1452.0 ±145.2 588.0 ±58. 8 ± 3.81 ± 0.38 2.42 0.24 254.0 t 25.4 70.1 "t 7.0 3 0.47 0.05 b 4 0.23 0.02 0.40 0.08 1 .00 0.10 27.4 ± 2.7 11.1 ± 1.1b ±. 5 0.38 ± 0.04 1 .46 0.15 1.07 t 0.11 18.9 ± 1.9 7.6 ± 0.8 t t t" 0.4b 6 0.47 0.05 0.62 t 0.06 0.78 ±.± 0.08 10.1 ± 1.0 4.1 ± t ±.t b ±. I-586-1 0.57 ± 0.06 0.36 ±. 0. 07 0.78 I 0.08 393.0 39.3 159.0 ±15.9 ±. 597.0 ±. t.24. 2 1.18 1 0.12 0.57 0.09 1.41 0.14 59.7 242.0 2 ± t ±. ±. b 3 0.55 1 0.06 1.12 ±. 0.11 1 .04 0.10 33.5 3.4 13.6 ± ±. 8.1 f. 0.8 b 4 <0.03 1.18 ± 0.12 1.25 0.12 19.9 2.0 ±. ± 0.4 5 0.03 ± 0.02 o.84 ± 0.08 1 .30 0.13 8.2 4± 0.8 4.4 6 <0.03 0.56 0.08 0.90 ±. 0.09 2.4 0.2 i.6 ± 0.2 ± ± ±. 1-$87-1 1 .00 ± 0.10 1.74 ± 0. 17 11.02 1.10 14.1 ± 1.4 9.6 f 1.0 :t ±! 2 0.19 t 0.02 1 .03 0.10 1.72 0.17 2.4 ± 0.2 1.6 t 0.2 ±. ±. ±" 3 0.42 t 0.04 I .56 0.16 2.11 0.21 4.5 "± 0.5 3.1 0.3 ±. -t ±. 4 0.15 0.04 2.21 0.22 2.32 0.23 5.7 ± 0.6 3.9 0.4 5 0.15 ± 0.04 2.15 0.22 2.44 0.24 5.8 0.6 4.0 0.4 4.4 1. 0.4 f. 6 0. 13 f. 0.03 2.35 1 0.24 2.05 ± 0.20 3.0 0.3 lABLl.E 4 (-o ll 'i . )

(3nnwna SJeCArn, pCi/gIu

232Thi 22f3Rt Sample lIeray I)eray Urnnium Fluorometric Me. 1-3 C7 Chlin Clhbnini I'R/R ± I o pCi/a if I(IV

I-S8-I 0.76 ± 0.08 0.65 4 0.06 1.03 0. 10 9.0 ± 0.9 4 4.5 it 0.4 2 0.29 it 0.04 0. 14 1 40 ± 1.06 0.11 4.8 4+ 0.5 2.8 0.3 3 1 .24 ± 0.12 0.33 4 ± 0. 10 1 .21 0.12 3.0 ± 0.3 2.0 it 0.2 4 ± ± 0.36 0.04 0.99 0. 10 0.93 0.09 2.9 ± ± ± 0.3 2.0 0.2 5 0.61 £ 0.06 2.04 0. 21 + 1.77 0.18 3.8 0.4 2.6 0.3 6 ± ± 1.19 0.12 2. 1 0.22 2.65 0.26 3.7 0.4 t 4 2.5 0.3 it ± 1-589-I it 0.15 t 0.04 0.57 0.09 0.56 0.06 8.7 0.9 t ± 4.0 0.4 2 0.16 1 0.04 0.08 0.04 it 0.3c t 0.40 0.04 5.5 it 0.6 2.6 3 <0.03 0.48 ± 0.07 0.89 0.09 3.2 0.3 2.2 4 t ± 0.2 0.11 t 0.03 0.50 0.08 0.89 0.09 2.1 it t ± it 0.2 1.4 0.1 5 0.33 t 0.04 0.67 it 0.07 0.75 0. 0R 1.8 it 0.2 1.2 0.1 6 ± 0.33 it 0.04 0.83 0.08 0.99 0. 10 2.4 ± 0.2 it ± 1.6 0.2 1-990-1 1.50 t 0.15 1.14 0.11 1.07 0.11 42.3 it 4.2 17.1 t 1.7b 2 ± 0.21 -i 0.04 0.70 0.07 0.82 0.08 6.6 it 0.7 ± 3.3 itf (1.3 3 0.15 i 0.04 0.47 it 0.09 0.73 0.07 3.7 it 0.4 ± 2.1 0.2c 4 <0.03 0.71 0.07 0.75 0.08 1.4 it 0.2 1.0 0.1 t ± 5 0.14 0.04 1.12 0.11 0.85 0.08 1.8 it 0.2 ± 1.2 0.1 6 0.06 t 0.02 <0.06 0.78 0.08 1.7 ± 0.2 it ± 1.2 0.1 it 1-S91-1 0.44 ±- 0.04 2.96 0.3(0 3.61 0. 36 11.6 ± it it 1.2 7.9 it 0.8 2 0.03 t 0.02 !.13 0.11 4 0.91 0.09 2.5 it 0.3 1.7 ± Itit 0.2 3 <0.03 I .43 0.14 I .29 0.13 2.8 it + it 0.3 1.9 0.2 4 <0.03 2.21 0.22 it 0. 1 it 1.70 0.17 3.7 it 0.4 2.5 5 <0.03 0.43 ± "it 0.06 0.39 0.04 2.2 t 0.2 1.5 0.2 6 ± <0.03 1.72 0.17 1.02 0.10 4.4 it 0.5 ± 3.0 0.3

( ( TABLE 4 E(-ont' d. )

Garga Sj ectra, plgi_/Ao

232Th 22ORS

Sample Decay Decay Uranium Fluorowetric 1 No. 37C, Chain Chain pg/g f 10% pCi/K 1 10%

I-S92-1 BIDLR 2.84 ± 0.28 13.66 t 1.37 1.4 t 0.2 1.0 t 0.1 2 0.19 t 0.06 2.08 t 0.21 11.67 t 1.17 2.5 t 0.3 1.7 t 0.2 3 0.14 f 0.04 0.94 t 0.09 4.44 1 0.44 2.3 t 0.2 1.6 t 0.2 4 0.09 - 0.04 0.93 t 0.09 1.98 t 0.20 1.9 t 0.2 1.3 t 0.1 5 BDL 0.35 1 0.07 0.97 ± 0.10 1.0 1 0.1 0.7 t 0.1 6 BDL 0.55 t 0.08 0.87 t 0.09 1.2 t 0.1 0.8 1 0.1

t i-$93-1 0.25 t 0.04 0.79 1 0.08 1.65 ± 0.16 2.7 1 0.3 1.8 0.2 2 0.22 1 0.04 0.92 1 0.09 1.34 t 0.13 2.0 ± 0.2 1.4 1 0.2 3 0.04 ± 0.02 1.10 t 0.11 1.32 t 0.13 2.3 1 0.2 1.6 t 0.2 4 <0.03 0.83 ± 0.08 0.95 ± 0.10 2.9 ± 0.3 2.0 1 0.2 ± 5 <0.03 1.06 t 0.11 1.72 t 0.17 3.3 t 0.3 2.3 0.2 t 6 0.03 t 0.02 0.95 t 0.10 1.28 t 0.13 2.7 1 0.3 1.8 0.2

l-S94-1 0.63 t 0.06 2.08 ± 0.21 5.54 t 0.55 17.8 ± 1.8 12.2 t 1.2 t 0.7 2 0.03 t 0.02 1.63 t 0.16 7.99 ± 0.80 10.3 1 1.0 7.0 t 9.6 t 1.0 3 0.17 t 0.05 1.15 1 0.12 3.44 t 0.34 14.1 1.4 1.6 t 0.2 4 <0.03 - 1.46 ± 0.15 2.4 ± 0.2 t 0.2 1.2 t 0.1 5 <0.03 0.77 ± 0.08 1.23 t 0.12 1.8 ± 1.6 1 0.2 6 <0.03 0.58 ± 0.09 1.85 ± 0.18 2.4 0.2

t 0.3 1.8 1 0.2 i-595-1 0.55 t 0.06 2.18 f 0.22 5.04 t 0.50 2.6 1 2.0 t 0.7 2 0.12 f 0.04 1.88 1 0.19 4.24 1 0.42 2.9 0.3 t 0.2 1.6 t 0.2 3 0.28 t 0.04 1.76 ± 0.18 4.14 t 0.41 2.3 ± 2.8 ± 0.3 4 0.09 t 0.04 0.97 1 0.10 2.41 ± 0.24 4.1 0.4 4.3 ± 0.4 2.9 t 0.3 5 0.15 ± 0.04 0.31 1 0.03 2.09 t 0.21 t 9.2 t 0.9 6 <0.03 1.00 1 0.10 4.18 t 0.42 13.5 1.4

1 1-R96 f BDL 274.0 ±27.0 215.0 122.0 708.0 71.0 483.0 ±48 TAIIIE 4 (cfjmt d'. )

(;Ofvnun_ pcupc~ l

2321h 226pa IVrcay S mple IDecay 1 7 Urnnlum FbjoromeLrjc No. a. Cn Cha I ) Chain I'R/R ± I0% pCi/R 1 10%

1-597-A 0.84 ± O.O0 0.R5 t 0.08 1.01 1 0.10 3.4 ± 0.3 2.3 t 0.2 B 0.24 t 0.05 1.11 f 0.11 1.07 ± 0.11 3.4 f 0.3 2.3 ± 0.2 C 0.16 t 0.05 0.92 t 0.09 1.24 ± 0.12 2.4 f 0.2 1.6 t 0.2 D 0.30 ± 0.04 0.95 1 0. t0 1.45 ± 0.14 2.6 ± 0.3 1.8 : 0.2

I-S98-A 1 .39 1 0.14 0. 70 0.07 0.88 ±t 0.09 3.3 0.3 2.1 ± 0.2 C B 0.79 0. OR 0.8R. 0.08 0.85 0.08 t± 6.0 0.6 3.1 :t 0.3 C 0.35 0.04 0.64 O.06 0.48 0.05 7.6 0. 4c "± ± 0.8 3.5 :± D 0.26 it 0.04 I .09 0.11 0.4 c 0.82 0.04 7.5 0.8 3.7 ± ±1 ±t 1-599-A 0.47 -± 0.05 1 .82 0. 1R ± 2.04 0.20 251.0 25. 1 102.0 f 10.2, B 0.16 0.05 0.24 ± 2.45 4.08 ±t 0.41 322.0 32.2 130.0 ±13.0 C 0.16 0.05 2.25 ± ±I ± 0.22 5.89 0.59 545.0 54.5 221.0 ± 22.01 D (0.03 ± 1.16 ±t 0.12 5.42 0.54 272.0 27.2 110.0 ±t ± ±11.0 ±I 1-5100-A ± 1.17 0.12 1 .75 0. 18 2.10 0.21 5.3 ± 0.5 3.6 ±t 0.4 B 0.66 ± 0.07 1 .90 0.19 2.06 0.21 5.8 0.6 4.0 0.4 C ±" ± ±t 0.60 0.06 2.22 0.22 I .95 0.20 8.8 0.9 ± 3.6 0.4 D 0.69 0.07 3.70 0.37 3.09 0.31 8.3 ±t 0.8 ± ± 3.4 0.4c ±f I-S1OI-A 0.51 ±! 0.05 0. R6 0.09 ± 0.77 0.08 4.5 ±t 0.5 3.1 0.3 B 0. 05 0.02 it ± 1.15 0.12 1.01 0.10 3.0 0.3 2.0 +t ± ±t 0.2 C 0.21 0.04 1 .224 0.12 0.90 0.09 3.8 0.4 ± D ± + 2.6 0.3 0.34 0.05 I .00 0.10 I .25 0.12 3.3 0.2 ± 0.2 2.3 1 -9102 e 1.55 ± 0.16 1.29 it 0.13 3.06 it 0.31 12.8 f 1.3 7.7 1 0.8c

1-S103 h-A 3.82 It 0.38 0.94 it 3 0.09 1.73 it 0.17 1. 75x 104 it 1. 75x103 7.1x 0l It 7.1xlO2b 1 .48 2 B it 0.15 1.10 it 0.11 2. 73x 103 73x10 1.lx103 j it 2. ,.•? O2b C 0.18 0.05 1.09 1 0.11 1 .40 0.14 463.0 46.3 188.0 D 0.07 0.04 1.30 t (0.13 1 .65 it 0.16 343.0 118.8 34.3 139.0 ft3 E (0.03 1.22 1 it 3.91 0.12 2.17 0.22 146.0 14.6 59.1 t 5.9

( ( IAIII.E 4 (cont. d. )

Ga mm.ua Lr a 2 __,Ci IsU

3 2 2 2 2 Tit e1na Sample I)Chiay D)ecay Uranium Fluorometric No. 137c -Cl Chn 1in Cli. in Pg/8 t 10% pCi/g ± 10).

3 1. 3xO2b 1-S104-A 3.13 ± 0.31 IIDL 1.88 1 0.19 3. lOXI3 t 3. Ix102 1.3xlO ± ±t ± 2.6x10 3 b B 1.01 ± 0.10 BDIL 1.34 ± 0.13 6. 39x 10' 6. 4x 03 (2.6x10' ± 5.3x10 2 ±: b C 2.14 ± 0.21 0.72 t 0.07 1.23 t 0.12 5. 26x 103 2. 1xlO1 2. 1 xO 2

4 3 ± . ;XiO 2 b 2.53 t 0.25 0.30 1 0.09 1.45 t 0.14 1.67x10 ± 1.7x10 6.8x103 6 1

4 3 t 6.8± 102b 2.62 t 0.26 0.85 - 0.08 1.05 1 0. 10 1.67x10 ± 1.7x10 6.8xi03

BACKGROUND SOIL ENVIRONMENTAL

I-SBI07-A 1.25 t 0.06 1.2 ± 0.1 0.96 1 0.06 3.4 ± 0.5 2.3 t It 0. A B 4.3 t 0.6 2.9 ± C 4.1 t 0.6 2.8 0. 4 ± D 3.1 t 0.4 2.1 0..

I-SD108-A 0.91 ± 0.05 1.5 t 0.1 1.00 1 0.07 2.5 t 0.5 1.7 t 0.3 4.6 B 6.8 1 0.6 t O.4 t 0.3 C 3.5 f 0.5 2.4 2.2 t 0.3 D 3.2 ± 0.4

1.7 0.3 I-SBI09-A 2.20 ± 0.10 0.9 t 0.1 0.68 1 0.06 2.5 t 0.4 ± 0.4 1.5 0.3 B 2.2 t ± 0.9 £ 0.3 C 1.3 0.4 t 1.6 0.3 D 2.4 0.4 ± ± 0.91 1 0.1 0.72 ± 0.06 4.0 t 0.4 2.7 0.3 i-SBIIO-A <0.05 ± 17.4 1 0.8 11.8 0.5 B ± 5.0 ± o.4 3.4 0.3 C 3.2 ± 0.4 2.2 0.3 D TAIIE 4 it-+-i! 'd.)

Conversion per Appesidix S.

Ilpleted uranium coniver•mun factor of 0.406(, 1 dCI/R/g Rad oui RialnInuin-Pr given its Table 6'.

IDepleted uranium 7 2 6 corrected for natiirntl iraltir •Inredrni (in Rn Cotkc sit rat ion. dSoil from sewer (see FiR. 14). r Surface scrapingm. fRock sample from surface (see Fig. 8).

BDL = Below Detectable Limits hsample subdivided into 2-in, 2-in, 2-in, 6-in, and I-in segments.

-tD

( 50

TABLE 5

GA_-"biA SPECTMAL AN-'D URANTUM FLUORODTRIC ANALYSES OF WATER (W) AND SLUDGE (SS) SA--PLES

Gamma Spectra (pCi/m.tc)

2 3 2 Th 2 2 GRa Sample Volume Decay Decay Uranium Fluorometric No. (•.f) Chain Chain pg/m•m.±10% pCi/mslO~a

DISSOLVED SOLIDS

I-W63 132 <0.01 <0 .01 0.0011±0.0001 7.5xl0 4±7.5xlOs

3 I-SS64 41 0.36±0.07 <0.01 0.0027±0.0003 1.8x10 ±1.8x10 '

1-SS65 43 BDLb 0.21±0.03 0.0012±0.0001 8.2x10'4-8.2xlO0s

I -W66 147 <0.01 <0.01 0.0014±0.0001 9.6x10 4±9.6x1O 5

I-W67 125 0.05±0.02 <0.01 0.0002±0.0001 1.4x10 4±1.4xi0 S

1-SS68 42 BDL 0.09±0.03 0.0010±0.0001 6.8x10 4l6. 8xi0 5

1 -W69 135 <0.01 <0.01 0.0007±0.0001 2.8x10"'±2.8xlO-sc

I -Ss70 58 0 .05±0.02 <0.01 0.0022±0.0002 1.5x10-3+i.5xxO-4

1 -W71 135 <0.01 <0.01 0.0002±0.0001 1.4x10 4±1.4x10 5

I-SS72 85 0.04±0.01 <0.01 0.0012±0.0001 8.2x10 4 ±8.2x10l5

1 -W73 132 0.12±0.05 <0.01 0.0008±0.0001 5.5xO0 4-5.5x10 5

4 5 I-SS74 47 BDL 0.07±0.02 0.0006±0.0001 4.ix10 -4.1x10

-4c 1 -W86 135 0.04±0.02 0.03±0.02 0.0215±0.0022 8.7x10-3±8. 7 x 1 0

5 I -W90 38 BDL <0.01 0.0011±0.0001 7.5x10 -47.5x10

3 c 1-W91 147 BDL 0.02±0.01 0.0038±0.0004 1.5x10 ±1.Sxl0"

1 -W92 137 BDL <0.01 0.0035±0.0004 2.4x10 -3 2.4x10 4

1-W93 134 <0.01 <0.01 0.0014±0.0002 9.6x10-4±9.6x10"s

I-W95 142 0.04±0.02 <0.01 0.0134±0.0013 9.2x10 4±9.2x10 5 51

TABLE 5 (cont'd.)

Gamma Spectra (pCi/mZ±a) 232Th 2 2 6 Ra Sample Weight Decay Decay Uranium Fluorometric No. (g) Chain Chain pg/g±10, pCi/g±10•

SUSPEhNED SOLIDS

I-W63 0. 033 BDL <0. 02 3.0 ± 0.3 2.0 0.2

I-SS64 109 .2 1.00±0.10 <0.02 3.4 ±0.3 2.3 0.2

1-SS65 97.4 0.36±0.07 1.04±0.10 2.5 ±0.3 1.7 0.2

1-W66 0.027 <0.06 <0. 02 3.3 ± 0.3 2.3 0.2

I-W67 0 .009 <0.06 6.4 ±0.64 2.4 ±0.3 1.6 0.2

1-SS68 159 .0 0.6 1±0.06 0. 60±0.06 1.2 ± 0.2 0.8 0.1

I -W69 0.008 1.5 ±0.15 <0. 02 6.8 ± 0.7 4.6 0.5

I-SS70 165.5 0.46±0.07 0. 82±0.08 1.8 ± 0.2 1.2 0.1

I -'W7 1 0.011 <0. 06 <0. 02 2.7 ± 0.3 1.8 0.2

I-SS72 19.6 <0. 06 2.46±0. 25 2.2 ± 0.2 1.5 0.2

1 -W73 0.008 <0.06 <0 02 2.5 t 0.3 1.7 0.2

121.6 0. 78±0.08 0. 63±0.06 1.0 ± 0.1 0.7 0.1 I-SS76 I -WS6 12. 3 <0. 06 1. 06±0. 11 135.0 ±13.5 54. 7 5.5c

i09 .1 0.65±0. 06 0. 85±0.08 4.4 ± 0.5 3.0 0.3 I -W91 0.29 <0. 02 10.3 ± 1.0 4.2 o.4c 1 -W92 10.2 2.03±0.20 1 26±0. 13 2.8 ± 0.3 1.9 0.2

1 -W93 13.0 <0.06 1 .80±0. 18 5.1 ± 0.5 3.5 0.4

1 -W95 5.1 <0. 06 7.11±0.71 5.1 ± 0.5 3.5 0.4

aConversion for Appendix 5. BDL = Below Detectable Limits cDepleted uranium concentration factor of 0.405 as in Table 4. 52

TABLE 6

UJRANIUM MASS SPECTROMETRIC ANALYSES OF SELECTED SOIL SAM'PLES

U Isotopic, Atom Sample No. 233 234 235 236 238

J-S47-A <0.001 0.001 0.228 0.005 99.766 D <0.001 0.001 0.235 0.005 99.759

I-S48-A <0.001 0.001 0.237 0.005 99.757 D <0.001 0.001 0.273 0.005 99.271

1-S49-A <0.001 0.001 0.230 0.005 99.764 D <0.001 0.001 0.236 0.005 99.758

I-SSO-A <0.001 0.001 0.227 0.005 99.767 D <0.001 0.001 0.228 0.005 99.766

I-S76 <0.001 0.001 0.226 0.005 99.768

1-SI03-A <0.001 0.001 0.226 0.005 99.768

1-S105-A <0.001 0.001 0.225 0.006 99.768

I-R96 <0.001 0.005 0.711 <0.001 99.283 54

APPENDIX 1

I NSTRUMENTAT ION

I. PORTABLE RADIATION SURVEY METERS

A. Gas-Flow Proportional Survey Meters

The Eberline PAC-4G-3 was the primary instrument used for surveying. This instrument is a gas-flow proportional counter which utilizes a propane gas 2 2 proportional detector, 51 cm (AC-21) or 325 cm "(AC-22) in area, with a thin 2 double-aluminized Mylar window (- 0.85 mg/cm ).

Since this instrument has multiple high-voltage settings, it can be used to distinguish between alpha and beta-gamma contamination. This instrument was initially used in the beta mode. In the beta mode, the detector responds to alpha and beta paticles and x- and gamma-rays. When areas indicated a higher count rate than the average instrument background, the beta-mode reading was recorded, and the instrument was then switched to the alpha mode to determine any alpha contribution. In the alpha mode, the instrument responds only to particles with high-specific ionization. This instrument is calibrated in the 2 3 alpha mode with a flat-plate infinitely-thin NBS traceable 9Pu standard, and 9 9 0 in the beta mode with a flat-plate infinitely-thin NBS traceable SSr- Y stan dard. The PAC-4G-3 instruments are calibrated to an apparent 50% detection efficiency. An input discriminator threshold sensitivity of 1.5 mV is used with these detectors.

B. Beta-Gamma End Window Survey Meter

When an area of contamination was found with a PAC instrument, a reading was taken with an Eberline Beta-gamma Geiger-Mueller Counter Model E-530 with a HP-190 probe. This probe has a thin mica end window and is, therefore, sen sitive to alpha and beta particles and x- and gamma-rays. A thin piece of 2 aluminum is added to the mica, thus making the window density -7 mg/cm . At this density, the instrument is not sensitive to alpha particles. A maximum reading is obtained with the probe placed in contact with the area of con tamination. In this position, the response (in mR/h) to gamma radiation is generally conservative relative to a determination of mrad/h at I cm. Another reading is obtained with the probe held 1 m from the contaminated area. This 2 2 6 instrument is calibrated in mR/h with a Ra standard source.

C. Low Energy Gamma Scintillation Survey Meter

An Eberline Model PRM-5-3 with a PG-2 gamma scintillation detector was used to determine low energy x and gamma radiation. The PG-2 detector consists of a thin NaI(T£) scintillation crystal 5 cm in diameter by 2 mm thick. This instrument is calibrated on three separate discriminators for three energy 2 4 1 2 regions using 2 3 9 Pu (17 keV), Am (59.5 keV) and 3SU (185.7 keV) sources. This instrument can be operated in either a differential (to discriminate between different energy regions) or integral mode. 55

APPENDIX I (cont'd.)

D. High Energy Micro "R" Scintillation Survey Meter

An Eberline Micro "R" meter model PRM-7 was used to detect high-energy gamma radiation. This instrument contains an internally mounted NaI(Tk) scin tillation crystal 2.5 cm in diameter by 2.5 cm thick and can be used for measuring fields of low-level radiation between 10 pR/h and 5000 VR/h. This instrument is also calibrated with a 2 2 6 Ra standard source.

E. Integrating Radiation Meter

In addition to the PRM-7, a pressurized ion chamber (Reuter Stokes Model RSS-1l1) was used at selected locations to determine the ambient radiation field. The RSS-111 has three output modes; (1) instantaneous exposure rate, (2) strip chart differential readout, and (3) integrated exposure. This instrument is mounted on a tripod, 3 ft (- I m) above the surface and has a uniform energy response from about 0.2 MeV to about 4 MeV. A 3-h period of operation is usually sufficient to obtain significant data.

II. SMEAR COUNTING INSTRUMENTATION

An ANL-designed gas-flow proportional detector connected to an Eberline Mini Scaler Model MS-2 was used to count multiple smears simultaneously. This 2 detector has a double-aluminized Mylar window (400 cm ) and uses P-10 (90% argon and 10% methane) as the counting gas. The metal sample holder for this detector has been machined to hold ten smear papers. This particular system consists of two Mini Scalers and two detectors. One is used for counting in the alpha mode; the other is used in the beta mode. Up to ten samples can be counted simul taneously.

Any smear taken from a contaminated area was counted individually in a Nuclear Measurements Corporation (PC-5 or PC-3A) gas-flow proportional counter. These instruments have been modified to contain a double-aluminized Mylar spun top. This top is placed over non-conducting media (e.g. paper smears) to negate the dielectric effect on the counter. These counters also use P-10 counting gas. Smears are counted in both the alpha and beta modes. These instruments are calibrated by determining the input sensitivity using an alpha source.

III. AIR SAMPLING DEVICE

Air samples were collected using a commercially available (ANL-modified filter queen) vacuum cleaner identified as a "Princess Model." The air was 3 drawn through a filter media at a flow rate of 40 m /h. The filter media consist 2 of 200 cm sheets of Hollingsworth-Vose (HV-70 or LB5211-9 mil) filter paper. The collection efficiency at these flow rates for 0.3-micron particles is about 99.9%.

A separate air sample can be taken with a positive displacement pump drawing about 20 liters/min through a millipore (0.5 to 0.8 micron) filter paper 56

"APPENDIX I (cont' d. ) for abcut -ne hour. An alpha spectrum can be measured from a section of this 2 1 9 2 2 2 filter paper. The ratio of actinon ( Rn - 6.62 MeV a AcC) to radon ( Rn 7.69 MeV o FaC') can be determined from this spectrum.

IV. GAMIA SPECTRAL INSTRUMENTATION

A Nuclear Data Multichannel Analyzer Model ND-100, utilizing a 7.6-cm diameter by 7.6-cm-thick NaI(Tk) scintillation crystal is commonly used for determining gamma spectrum. This instrument is calibrated with NBS traceable gamma sources. Samples from contaminated areas were analyzed using this sytem and the contamination radionuclides were identified.

Hyperpure Germanium detectors (ORTEC - 17% efficiency right-circular cylinders) can be used when more sophisticated gamma-ray analyses are required. These detectors are coupled to Nuclear Data Multichannel Analyzers (Models ND-60, ND-66 or ND-100). 57

APPENrDIX 2

CONVERSION FACTORS

I. INSTRUMENTATION

The factors used to convert the instrument readings to units of disintegra tions per minute per 100 cm2 (dis/min-]O0 cm 2 ) and the derivation of those factors are listed below.

A. Conversion Factors

Floor PAC-4G-3 Monitor (FM-4G) Alpha Beta Alpha Beta

2 To 100 cm 1.96 1.96 0.31 0.31

cts/min per dis/min - 2 - 2 for 9 0 Sr- 90 Y

2 3 9 cts/min per dis/min for pu 2 2

cts/min per dis/min for 3.1 3.0 2.9 2.9 normal U

2 2 6 cts/min per dis/min Ra 1.6 1.7 1.6 1.7 plus daughters

B. Derivation of Conversion Factors

Floor Monitor

2 Window Area: - 325 cm Conversion to 100 cm2 = 0.31 times Floor Monitor readings

PAC-4G-3

2 Window Area: - 51 Cm Conversion to 100 cm2 = 1.96 times PAC reading

22n Internal Gas-Flow Counter. PC counter

Geometry: Solid Steel Spun Top - 0.50

Geometry: Mylar Spun Top - 0.43 Mylar spun top counting {double-aluminized Mylar window (-- 0.85 mg/cm2 )) utilizes the well of the PC counter and is a method developed and used by the Argonne National Laboratory Health Physics Section for negating the dielec tric effect in counting samples on nonconducting media. 58

APPENDIX 2 (cont' d.

The PAC-4G-3 and PC counters are calibrated (see Appendix 1) using a flat plate, infinitely thin 2 2 6Ra (including all short-lived daughters) standard as a source of alpha emissions. The plate was counted in a 2n Internal Gas-Flow Counter (PC counter) with the source leveled to an apparent 2n geometry. The alpha counts per minute (cts/min) reading was found to be 1.9 x 104 cts/min, or 1.9 x 104 - 0.51* = 3.8 x 104 disintegrations per minute (dis/min) alpha. Since the source was infinitely-thin, the alpha component was used as the total alpha dis/min of the source.

The same 2 2 6 Ra plus daughters source, when counted with the PAC instrument in the alpha mode, was found to be 2.3 x 104 cts/min at contact. The conversion factor for cts/min to dis/min for the PAC instrument is 3.8 x 104 - 2.3 x 104 1.6 dis/min alpha to cts/min alpha.

The same source was covered with two layers of conducting paper, each 6.31 mg/cm2 , to absorb the alpha emissions. With the PC counter in the beta mode and the paper in good contrast with the chamber, the count was found to be 1.25 x 104 cts/min or 1.25 x 104 - 0.50 = 2.45 x 104 dis/min beta. With the PAC-4G-3 in the beta mode and in contact with the covered source in the center of the probe, the count was found to be 1.45 x 10' cts/min. This indicates a con version factor of 2.45 x 104 1.45 x 104 = 1.7 dis/min alpha to cts/min beta gamma. All three detectors (51 cm2 , 100 cm 2 , and 325 cm 2 ) gave readings similar to those reported above for the alpha and beta-gamma mode.

A similar method was used to determine the conversion factors for normal uranium.

II. SMEAR COUNT

The conversion factors for cts/min-100 cm 2 to dis/min-100 cm 2 for smear counts are given below:

A. Conversion Eouation (Alpha)

cts/min - (Bkgd) = dis/min a g x bf x sa x waf

A geometry (g) of 0.43 is standard for all flat-plate counting using the Mylar spun top.

A backscatter factor (bf) of 1.0 was used when determining alpha acti vity on a filter media.

The self-absorption factor (sa) was assumed to be 1, unless otherwise determined.

*The value of 0.51 includes the following factors: geometry (g) = 0.50; back scatter factor (bf) = 1.02; sample absorption factor (sa) = 1.0; window air factor (waf) = 1.0. The product of g x bf x sa x waf is 0.51.

*~~~~y. ,*. My 59

APPENDIX 2 (Cont'd.)

If the energies of the isotope were known, the appropriate window air factor (waf) was used; if the energies of the isotopes were not known, 2 3 9 the (waf) of pu (0.713) was used.

2 2 6 The (waf) for alpha from Ra plus daughters is 0.55.

B. Conversion Equation (Beta)

cts/min - {P Bkgd (cts/min) + G cts/min = g x bf x sa x waf

A geometry (g) of 0.43 is standard for all flat-plate counting using the Mylar spun top.

A backscatter factor (bf) of 1.1 was used when determining beta activi ty on a filter media.

A self-absorption factor (sa) was assumed to be 1, unless otherwise determined.

If the energies of the isotopes were known, the appropriate window air factor (waf) was used; if the energies of the isotopes were unknown, 9 9 the (waf) of °Sr- 0 Y (0.85) was used.

2 2 6 The (waf) for betas from Ra plus daughters is 0.85. APPENDIX D CHEM-NUCLEAR SYSTEMS, INC. DATA Comprehensive Site Assessment General Services Administration (GSA) Federal Property Resources Center Watertown, Massachusetts

Volume IV

Radiological Survey Records

prepared by Chem-Nuclear Systems, Inc. O'Brien and Gere Engineers, Inc.

October 1990 zu

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. 4-24-21•9)

2 * Project Name/No. G:-.s','-r,.'.j/ Date b; dv^1 f6

Sample Location -, s-,- 6- Y',j s- ' Technician 5 .J,•,.,,.,-'

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. _2;'-.,(')

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Sample Location tf.L. serC Technician.. ,,.

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NOTE THISTHE KNOWING A&WWILLFUL ALEC ONU OF FALSEFICTICIOUS. OR FRAUDULENTSTATEMENTS OR ENTRIES ON DOCUMENT MAY BE PUNISHABLE AS A FELONY UNDER FEDERAL STATUTES.

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. k-29-0/d•A

* Project Name/No. GSA-,-A-)5T0,4.3 /y/_0/7 Date 2-7 J(C'j qO

Sample Location PRILL. S7C (LJC.'fA"4 C. Technician 5 ,o,,•

Air Sampler Type/No. RRAEC.•0--,/-"=, Filter Used "e-r't- AX

Activity (uCi/mQ) = (net cpm)x(C.F.) x (4.505 x 10-' uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 mIA) or (2.83 x 10' ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume S... "/..57 ff-.- •,• :r

-\ •" Counting Inst./Serial# - C.F.!-,w5- MDA *?.400x 3 Total Counts ' Count Time = cpm cpm C =Net cpm Activity (uCi/ml) CC 7- 7 & ___LI__7_ _ 4s.00 X10

Ce Counting lnst./Serial# C.F.__ MDA

Total Counts ' Count Time = cpm cpm " Cb _-- r Net cpm Activity (uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

6-/3?F Counting lnst./Serial# C.F.__ MDA

Total Counts - Count Time = cpm cpm - C = Net cpm Activity (uCi/ml)

Q' Counting lnst./Serial# C.F. MDA_ Total Counts - Count Time cpm cpm - C Net cpm Activity (uCi/ml) -b CHEM-NUCLEAR SYSTEMS, INC C014T AMCO/R ADIATION SURVEY REPORT CONTINUAO'?ON SHEET

ACIIVITV' Týý.. J17Ci~rT jPA~ J MAP II I n LOCAHONION 6 PS1/( of~,O 3~5 ____,c'IIII L IL ______I 3Vf14

NOTE, THE KNOWINO0 A WILLFUL. RECORDING OF FALSE. FICTITIOUS. OR FRAUDULENT STATEMENTS On ENTRI1ESO. THIS DOCUMENT MAY BE PUINISHABLE AS A FELONY UNDER FEDERAL STATUTES.

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. -7-Z-0104

Date OZ JUL 9QU 0 Project Name/No. 1.1210- WO" ,77 ,3144.6k , Sample Location bRILL S•TE ,WCI-AiflB Technician 5'J - J0 415o

Air Sampler Type/No. RAEr-0o / Z•,.zS Filter Used GELhi' f/tr

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-7 uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 mi/l) or (2.83 x 10Y ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off T otal time X Flow Rate = Sample Volume

8 2F•- Counting Inst./Serial# Es F- I/A if,. C.F._,I MDA , -IA Net cpm Activity (uCi/ml) Total Counts - Count Time = cpm cpm - C - 7- -/2

aY Counting Inst./Serial#. C.F.___ MDA Activity (uCi/ml) Total Counts + Count Time cpm cpm - Cb Net cpm

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off T otal time X Flow Rate - Sample Volume

,-/ 3 Counting Inst./Serial# CF.F__ MDA _ Total Counts - Count Time = cpm cpm - CEt - Net cpm Activity (uCi/m!)

a Counting Inst./Serial# C.F . MDA Activity (uCi/ml) Total Counts "-- Count Time = cpm cpm Net cpm

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. -7-01(A)

Project Name/No. 6;e-M /,•.,, Date ,z] JiL. Sample Location DRILL SiTe WC.-1 Technician n. I/,-,JSo,.

Air Sampler Type/No. RrbFCg / z as- Filter Used GL--0,-A AlE

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Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

,3-\ 3' Counting Inst./Serial# FSP-i . ( .F . MDA __,___-, Total Counts Count Time = cpm cpm - = Net cpm Activity (uCi/ml) ý.-S 9 97'(y 20, 3;7 3"( 0 '/f/z J

a Counting lnst./Serial#_ C .F.__ MDA Total Counts + Count Time cpm cpm - b = Net cpm Activity (uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate - Sample Volume

,/ - ?r Counting Inst./Serial# C ".F.__ MDA Total Counts * Count Time cpm cpm - 'b Net cpm Activity (uCi/ml)

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. 7 -3y-06('d

*01 Project Name/No. '-•'/,o', Date -•,,, JL--. O Sample Location file- s,rc 11,'4-16, g-2 Technician J--,,.,-.

Air Sampler Type/No. O-,

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-' uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 ml/I) or (2.83 x 10 ml/ft3) Fa = 1.00 forOther Emitters

Time Sampler on Sampler off Total time X Flow Rate - Sample Volume

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/ \ -'- Counting lnst./Serial# r 11-, C

Total Counts * Count Time = cpm cpm -- b- = Net cpm Activity (uCi/ml) C -1Z

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a Counting Inst./Serial# C.F.-____ MDA

Total Counts * Count Time = cpm cpm C.b - Net cpm Activity (uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

, -/a Counting Inst./Serial# C.F.- MDA Total Counts * Count Time cpm cpm - -b- = Net cpm Activity (uCi/ml)

0 Counting Inst./Serial# C F.__ MDA Activity (uCi/ml) Total Counts - Count Time - cpm cpm - -b- Net cpm

9 _ _ _ _

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT NoA4'S-O5d(,9)

-0 Project Name/No. G-SA. £,-D,,) Date -4-di t&,I Sample Location pz,,L, 'r -- 4. R Technician ! Je-,,J

Air Sampler Type/No. 4',orr•, /7o.- Filter Used 6-L.PoJ O/F"

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Time Sampler on Sampler off Total time X Flow Rate = Sample Volume S... 3 . 5- -,, 3

Counting lnst./Serial# _..•P2-i -1k, C.F. ,S MDA 1-52-10-12

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a Counting Inst./Serial# C.F.-_ MDA Total Counts00 Count Time = cprn cpm Cb- = Net cpm Activity -uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

2!y-/ Counting Inst./Serial# C.F MDA

Total Counts ± Count Time = cpm cpm - C' = Net cpm Activity (uCi/ml)

Ce Counting Inst./Serialt C.F.____ MDA

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IS I ______9 ______I - A ~I I______lý4lT KNOWINO B WILLI OBOINO OF FALSE, FICTICIOUS. OR FRAUUETSAEj5Jf.fl1IOF4IjlCMNALLU. L1_04 I" ILtOMUu" IJOE OKA"..t1 C ON TA~l@IOH RADIATION SURVEY REPORT CONTINU.lpION I EET

AC TIVITY/' GS-,Wr.rW MAPIO *

NTE H NWN WIlttrL RECORDING OPFALSE. FICTITIOUS. OptSUU N TTMET RETISO THISDOCUENTAY S PUISNALE At A FELONtyUNDER FEDERAL STATUTES, "'F,ALP.A RETA GALMA QALPHA EOU'v - EOuvUIVL-Z-8 RE-*A4AMMA BETA-GAMMA *ITEM SWIPE/ "0dol'/ don. do", dpntI NEUTRON 0LOCATION PRS S ~ ct~NO~ c~ R PROBE ' pdp 'rs dp~ Oi _ EAGMA0IE do ,, do NEUTRON clLOCARTION 0DI PnB 10D "'m POErlu j'PROSE tooc mvI PRO BE toocm mIcIr A/hr.

RADIOLOGICAL CONTROL nrndI~ntoniCWnmInatilon Survey Grd a cJCGrT _Map IACTIVITY/M PAGE

wj/oi.-e, ,II I OA IIT -on~ OATE 11 UnV• Ton IS. JQ'/Ak-c,) c2~~s-jut-q ,¥ NOTE: THE KNOWINO &WILLFUL RECORDING OF FALSE. FICTICIOUS, OR FRAUDULENT STATEMENTS OR ENt'1t1e THIS DOCUMENT MAY BE PUNISHABLE AS A FELONY UNDER FEDERAL STATUTES. .. I Lit

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"I'D NUMBER ._. ')S'--0 RADIOLOGICAL CONTROL Sk N1/4" = CO (4TAM INNA 'IAD AT ION T OfI~ TIME I 7I AG SURVEY REP 1 PR Je('-Lf ILE j L_ qg START 125-- cor AC.7VITY SURVEY^R DAILY WEEKLY Y CONTAMINATION AND DFXLY C MONTHLYD 0 RAITONSRE MORDIAIOHSUVE COMMENTS RM -onr MAP ID gr -7 - I I "(FU'SSIALIELEVELS CC.A AREA CONTROL.LEVELS ol OTHER dpnIII0- A'n LPHA "d:7/n'IOCl'ALIPHA0- ISEE COMMENTS) IJP1.VI0 Cm' BETA GAMMA A d nýl 00 tn' BETA-GAMMA NOA7O YOURCE CHECA DATA t p II SCLPnCE CHECK CATA CONTAMINATION SURVEY$ RADIATION CONTAMINATION ALPHA BETA-GAMMA SURVEY ALPHA B ETA'G AM MA BETAJGAMMA INSTRUMENT TYPE'TAONO EPI dl t tII i souU'I~t I RAIA)O ~ NEUTnoN /1 I)-7 SURVEY BETA-GAMMA INSTIFILMENT TyP~f/AG NfI Sc)UnCF STRENGTH - Iiii~t~dpm ffii4 7 L cl .- r- -86 INSTRUMENT SESPGI.SF I..-' Rnflffl.a flCvrtva CL... -- J*/ IHj .-4h - SS124 '," - iY,"/b- - '-- - . - . - - DATE t.' eic, (IFFICIENCY/COFITECTION FACT0R- -t T- - ALPHA OUIA.GAMMA m,.ýn, 0:

k'A- dprA p~ SAT, UNSAT. SWIPE, EDUIY EOUvII(Zl? &e4A-GAMMA BITEM ______I_ SIMIU PRO~BE NETO0 OR PACIIGROUNOUTRO 1 NOco' ~ " OI' dn LOCATION ______3 ep., NO PROQE oTT,I,' P00136 dpm/, lICO ~

GEASON FOR SURVEY 0 PROCIEDURE-NO0 ____z__MAP______!7______02

0 SPECIAL. 19

ROUTINE CACfIXEKL U 20 73

swP' ALPHA BETA-GAMMA .1W 0 TE 21 . nOBE EOUIV __ EOUIVLJAJO$ BE*AGAMMA E oR 72 NoD TOr" UP" oon', don" NEUTRON Ql LOCATION ___ PROBE 200cm, PROBE 100 ciYI tic'o Rn,, 23

2 1 I 1 7. nf -so _

I __ _ 26______

7_ _ I 30_ _ _ _

0 I 32 II m 34 I1 I . i f + + -ir 1 . i- -t -t + -4 -ii- 1 IT

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I CHEM-NUCLEAR SYSTEMS INC

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0:7 n'ý- l~ CHEM-NUCLEAR SYSTEMS INC

4

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-i. CHEM NUCLEAR SYSTEMS INC

AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT N

Project Name/No. 6-s 7,') /V•.G"/,/ Date 0 1? Jut.L Crn Sample Location nR,-i sarrcs 13-I • Ic, Technician s. ,ounJ Air Sampler Type/No. Rn$-C,/i-/ - Filter Used G&t Mrn,J f/ir

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-' uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 mo/l) or (2.83 x 10' ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate Sample Volume _- - - i0.ir"• I

Counting lnst./Serial# E.Z•- i C.F.4_5-.s. MDA /1 -1-10 Total Counts - Count Time = cpm cpm -- b-- Net cpm Activity (uCi/ml)

-t 0T.D (,,. 21.,9 <_ I_ __ __r._In-_.

Ce Counting Inst./Serial# C.F.-_ MDA Total Counts - Count Time = cpm cpm " -b-- = Net cpm Activity (uCi/ml) 0

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

-/3' Counting Inst./Serial# C.F.-__ MDA Total Counts + Count Time = cpm cpm - Cb-- Net cpm Activity (uCi/ml)

MDA a Counting Inst./Serial#_ C.F.-__ (uCi/ml) Total Counts - Count Time cpm cpm - b Net cpm Activity

RADIOLOGICAL CONTROL TA MINA 9DIATA, 10N 'All M CO0N 0 COMPL. SURVYR IK.---- FILE.- JUL ______I-PR OR DAILY DAItLY *U 0 I-CAIOZ10N, I AND VVEEKLY 0 RADIATION SURVEY G~v2- WA7EQTos,),? 15"nvly"Z I_ .1 .1 ~EE0LKGCONTAMINATION 1 12 ý _ II MONTHLY 0 mONTIHLY 0 COMMENTS COA-7etzotMAP -i 13-1 03-I9 (3-116 MAP I D, t31ELL -IrES _7 _,n,* _ (D /

IPEPUSSIBLELEVELS CSCA AREACONTROL. LEVELS C1 OTHER dpffVI0cIWn ALPHA 'Ij/ dpinJI00 em ALPHA (SEE COMMENTS) 0pQd0fl/T3 .P8ETA-GAMMA :=AdpWvI/ItOCrWOETA-GAMMA UNOACTION6EOD

nouTTCE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPHA EIETAGAMMA ______SURVEY AL.PH-A BETA/GAMMA BETA/GAMMA iNSTI~mtMEJ? TYPE'TAGNO SORC I AADIATIOTI NEUTRON BETA-GAMMA - NSTinuuENt I~IPIAG NO E-si' 7 ,OUEICE STRENGTH /1 ) 4F71TT -

-- DATE - 19I4 INSTRUMENT RESPONSE epm 7.ys cpmT - TIYT ADCON IEZa =

EFFICIENCY/COTTPECTION FACTOR 0.2- -ys ALPHA BETA-GAMMA fRPA0

IDA.5pm8pm SAT. UNSAT. SI'TO4 AM ITEM dp 4 0 ROB EOUTV I.EOUIVE.L1Z! OR U ______NEUTRON 0LOCATION dpP.T 8Ep.T dpIVI 5ep./ P1B I DACKGROUND IPIT -at NO POE TP 1 POB 00C

nEASON FOR SURVEY C) PROCEDURE-NO. ______<______MA -f -011-_0

0 SPECIAL I ______M__0 X ROUTINE WgQ bJ E, It ___

ALPHA BETA-GAMMA P.Ror'/tVI ITEM 2 -P EOUV - EOUIVQMj OA-E GAMMA onOR I TORE NEUTRON 0l LOCATION '40 dvTI, op"IT YTPmI dpm ______PROBE 100cm, PROBE iTOmt IvP.0 A,?, 23______

2 I25 ______

I I _ _ _ _ ~~~26 I ______' I I 27_

Es 9 32 i m 10 1 I ______

TI1 _ _ __ _

12I ______3 zn

______Q ______315______

T14_ I______31 ______3______

______9 3 ______I ______I ______~~~~~~~~'o______

I ' H KNOINGA WLFLn(TDN OF FALSIE FYYCOII OR FRAUOULFNT STATEMENTS OR ENTAITES01H THIS DOCU)MENT MAY TIE PUNISHAOLE AS A FELONY UNDER FEDERAL STATUTEII.I CON TAM BON/RADIATION SURVEY REPORT 0 CONTINUORTON SHEET

PAGE OF I ACTIVITY•/ 2 3 to. LOCATION C rnwavT. A 7

S. JONJOA)

NOTE: THE KNOWING AWILLFUL RECORDING OF FALSE, FICTITIOUS, OR FRAUDULENT STATEMENTS OR ENTRIES ON THIS DOCUMENT MAY BE PUNISHABLE AS A FELONY UNGER FEDERAL STATUTES.

-remJN ALPHA BETA-GAMMA mre,,/ c0 ALPHA OETA-GAMMA 0 _- BETA-GAMMA 0 ITCORM SWIPE/ EOUIV EOUIV . -AE•*-CAMA ITEM SWIPE/ EOUIV. -OUiV COUIE On PROBE NEUTRON cl LOCATION PnOSE PROBEIIýln l No ] pm/ dOlJ NEUTRON 0 LOCATION NO OPTI/ dpI/ df,'I E U0A B/Tr r pnROE I1oDoc PROBE 1lo mionm R/I OE 100 •l PROB' mIcO I ______lI ______,....AP •-a:,9- i I I I__ ,I ,I.NEII I I

______,,,,____ I I I______,,I I_ _ I I_ _ ,[ I ______I q,,- I ______I I ______I______,,T! I ______,___, I ______I I_ Sd', I ______I ______I,' I _ _ _I I______.zi I I __ _It _ _ _

'.-3 I ______II

______I I -_ I I ______I______-. ,I I ______I >~zI~ ! N'$Ž~n- II ______I I ______I I"C) ______m ______I______I i_ zF cC) I__ _ I______I I 0

______I I _ _ _ _ _ I______I I ______I _ _ _ I_ z

*j NoI- Dolecl I, RADIOLOGICAL CONTRý rlndlnhlonl/C.9 mInallon Survey Grid Map_ _ __

LOCATION . 5':, PAGE-

SUnVEYOn DATE s. JOW.so•09 JUL q(D

NOTE THlE KNOVN A£WLtLFUL. RECORDINO OF FALSE.FICTICIOUS OR FRAUD1UEf NT STATEMENTS Or ENT•r•s ON THIS DOCUMENT MAY BE PUNISHABLE AS A FELONY UNDER FEDERAL STATUTE$ 'iiI

. .______.. ____ 4 :1 11 S1 32 C-1 7 -11-I

0l I OfzJ S. 4/ mn DOWo• JE)------I5I I7L I

5 6 7 8 9 1 11 12 13 14 115 16 8 19 20 21 22 23124 26 27 28 29 30 1 31 32 33 134 135 36 37 38 39 40 RADIOLOGICAL CONT[ROL ? -wcq-•-De r0ID NUMBEn CHEM-NUCLEAR SYSTEMS INC

AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No.'-e"k-/0-0"6()

. Project Name/No. &5.- w, , Date 16 101- 10 Sample Location b.,z, .SITc z-VA Technician . jo•u-j'.an, Air Sampler Type/No. RAcc,, / d, T-r Filter Used G-C_.,v,

Activity (uCi/ml) = (net cpm)x(C.F ) x (4.505 x 10-' uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 ml/I) or (2.83 x 1 01 ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

,8-\2-Counting Inst./Serial# /it CF.±t.5"C.F-I MDA /,'fo Total Counts Count Time = cpm cpm C' = Net cpm Activity (uCi/ml)

aY Counting Inst./Serial# C.F. - MDA

Total Counts * Count Time = cpm cpm - Cb = Net cpm Activity (uCi/mI)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

,6 -/a, Counting Inst./Serial# C.F. - MDA

Total Counts -•- Count Time = cpr cpm - C Net cpm Activity(uCi/ml)

a' Counting Inst./Serial_ C.F.____ MDA

Total Counts + Count Time cpm cpm - b - Net cpm Activity (uCi/ml)

RADIOLOGICAL CONTROL CONTAMINAYJ4ADIA TION To SURVEY REP. ~. Plzeiu-rT PILIE ACTIVITY/ SUnVEYQn V LOCATION &/-LA7,7V.A IIONE DAILY 0 DAILY *Za WEEKTLY 0 CONTAMINATION AND WEEKLY 0 RADIATION SURVEY ri s ^.*i M4ONTHLY 0 MONTTAV 0 C 0 .ME N TS MAP I 0

1 -1 - PERMISSIBLELEVELS CSCA ARELA CONTROL. LEVELS o OTHER dPrY./TO0C,,' AL PHA dpTYI/Tl00cTTALPHA (SEE COMMENTS) "•1QIDYý. dprý,/TOc" BETA GA MMA doWI005CI,, BETA-GAMMA *NOACTioNREOD.

souTICE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPHA BET-GAMMA ______ALPIHA BETA/OAMM.A BETA/GAMMA INSTRUMENT TYPEVTAGONO P -l soUflCE ID . RADIATION NEIJITTON DETAAMMA ____1 ___3 _ SUOIVE BT SOURCE STRENGTH P, Icr? INTUMN TYPIAC -2,h.L

IN4STRUMENT RESPOcNSE cp~pn - AIADCON IREVIEW ______- DATE t~'!f/J EFFICIENCY/COnnTECTION FACTOR -ALPHA BETA.GAMAMA ,.nflT0

IOA. dp' d SAT, UNSAT. SWIPE/ EETýOuIVI ITEM~i ______/418U PROBE NEUTRON j LOCAIO

SACGROND ERT 38 CTIN PROBE TR)CR' PROBE I~O CRY R/LCAIO

REASON FOR SURVEY 0 PnOCEOURE-NO III______I______flfl r P

* SPECIAL 19______

* ROUTINE TA091C I&I PR06Q-A.Ss______0______

ITEM 7 SWIPE/ ALPH-A BETA.GAMMA grm/r POE EGUIv - EOUIVtdzZ.R ee+R*OAMMA onR2 NO o __-'pT'Y 8/D~ dp/ NEUTRON 0 LOCATION______PROBE ICO c"' PRO0BE T00 c^ lIu4o A&,. 23

2 _ 25__

I~ _' (n_ _I I 2__10 _ _ _ _ _

4 ______I______

S ______,27

IT _ I______II ______30______

I? ______'S______I______m

-F r-r- 1 5 ir I 1 -I 4 ITT 37 I T Tt- 1 E iF I I I 4 I I I I ____ I I *I I I I 1 i 1 II iI I t TI-EKNOWAING & W'ILLFUL AECORDING OF FALSEF FICTICIOUS.OR FRAUDULENT STATEMENTS OR ENTRIE NTI .c f6 7 18 19 1101 11 112 113 114 1151 161 1 7 L 1 8 19 20 21 22 23 [" 25 26 27 28 291 30 31 32 33 34 35 36 37 38 39 I e - 1/4" = - I D NUMBER RADIOLOGICAL CONTROL CHEM-NUCLEAR SYSTEMS INC

AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. 3-/i-0'&,)

* Project Name/No. 6,•-w,7"r~ w!X 14,/z ,,f Date '/I,'t

Sample Location Jzie_ s,, "t. Technician S. Jo,•,w,

Air Sampler Type/No. ",b,, • Z7.• ,.-• Filter Used GE4.,AwA,, &Q/A

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-i uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (101 mI/A) or (2.83 x 10' ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

I

16-\ 3ý Counting Inst./Serial# EC5P-, C.F.Y.?(, MDAI ?.,Sy____ Total Counts + Count Time = cpm cpm Cb- = Net cpm Activity (uCi/ml) C

&t Counting Inst./Serial#• C.F.-__ MDA Total Counts * Count Time = cpm cpm - Cb = Net cpm Activity (uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

6 -/ z Counting Inst./Serial# C.F.-__ MDA Total Counts- Count Time = cpm cpm C'b = Net cpm Activity (uCi/ml)

a Counting Inst./Serial__ C.F.__ MDA Total Counts Count Time - cpm cpm ._C Net cpm Activity (uCi/ml)

RADIOLOGICAL CONTROL TII TIME CONTAMINA7 SADIATION "tI f STAR?1 130 SURVEY RE~b& ) FYPcAMCT FILE \, j it luL '70 COMP, 1310 lPAGE.1...j J 7. DAILY a rCI m TY SUnvfiYOR I DAILY U Lo - TON Cr-W-d7Wl WEEKL 0 CONTAMINATION AND WEEKLY E. RADIATION SURVEY MONTHLY 0 MON?IIIY 0

(ý)Tf Towý3~l COMMENTS IAAP 10. DRILL 5IJTE tJC-100

PERMISSIBLELEVELS CSCAAREA CONTROL LEVELS 0l OTHER -_ dj>,IVIDOCY, ALPHA dpvV100 cCIYIALPHA (SEE COMMENTSI ______!5LQa dpIISG cn- BETA-GAMMA dpnIvJ0CW8 ETA-GAMMA UNO ACTIONREaDO.

SOURCE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPHA BETA-GAMMA SURVEY ALPHA BE-TA/?3AMMA BETAIGAMMA INSTRUMENT TYPfnAGNO it "I(l RADIATION NEUTRON BETA-GAMMA. SOURCE ID O2 -SURVEY TYPEITAG-NOaag7 SOUPICESTRENGH dpovImR/hr.INStRUMENT

INSTRUMENT RESPONSE e cpm - ,.,RA. AACNREVIEW -- DATE /y.d 7

EFFICIENCYICORRECTION FACTOR I~2lt.4 -ALPHA BETA.GAMMA ,,*,V, SAT. UNSAT. SWIPEI etiA-OAMkAA ITEM LDA.< -POBE 11 GUv- EUv.L3BNEUTRON 0LOCATION NO PITYYI doIYI d ~lYaBI'Ilt" BACKGROUND cpY, cme PRB POB c, M-rvnclonr U

TISASON FOR SUnVEY C PROCEDURE-NO, ______ak.______~ ~ I~

___ ALPHA I~ ~~~FOJCBETAG0AMMA Y1@L07 FILE 0IEM ______4I ______S"-PE' EOUIV - EOUIV(.~L-M bel*,GAMMA DRon PAOBE NEUTRON LOCATION NO dpI,, dp-, OB,Y/ ABIY/ ______PROBE 1t00 C' PROBE ISO mY RivCa Rnft 73

3 H t L~ 26~I)3 2 I A1 ~ ~ I ______

__ li 1 30I

m 9 32 ______I______z ID I ______

II ______I______34 I (AC 12 I ______I______

13 I ______36 ______4 m 14 ______3' ______m/

35 16 1 -. 4- *0 17T A ZJ TIlf KNOWING a -1 ECORDING OF FALSE. PICTICIOUS. OR FRAUDULENT STAE QRLLNBILS.OtLk1IS.DOcuML)A~tM"*-* I I I I I I I I I I CHEM NUCLEAR SYSTEMS INC

AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. _7-_2-___)

"Project Name/No. Date /z 1JUL.

Sample Location ,P-,1- sac "(.'. .- 8 Technician $5.Jcw)N•J Air Sampler Type/No. ,tob~s-e6, 7O•rf Filter Used G&,6LAl ,Q/t

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10- uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 mIA) or (2.83 x 10' ml/ft3) Fa 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

,8-\3Counting Inst./Serial# ESP-' -/WC C.F.-•• Mc-,

•j•-b Total Counts *• Count Time =cpm cpm ---- b-= Net cpm Activity (uCi/ml)

SCounting Inst./Serial# C.F.- "_ MDA Total Counts + Count Time = cpm cpm b- = Net cpm Activity (uCi/ml)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate =Sample Volume

3- Counting Inst./Seriallt C.F.__ MDA

Total Counts -'- Count Time = cpm cpm Gb-- = Net cpm Activity (uCi/ml)

a Counting lnst./Serial_ C.F.___ MDA

Total Counts - Count Time cpm cpm - b-- Net cpm Activity (uCi/ml)

RADIOLOGICAL CONTROL F

TO 'ATE SlAIM TIME 7 2 SUPVEYPEP JADIATION PE0 reT Cl,:: -~ll ,s-.,--I... -L I%3E ' r.TION SURVEYOR T=IONtDIR UO.L ______l!5?____ WEEKLY 0 CONTAMINATION ANO WEtEKL 0 RADIATION SURVEY MONTHLY 0 MONTHLY 0

LMT 6jAlMAP ID CMETS DILL. :rTE W~C-S'I7 ______-a7- 01

Pr"MISSIBLE LEVELS CSCA AREA CONTROL LEVELS 0l OTHER - d'1C33c,,,ALP'HA dpnVTDD ml ALPHA (SEE COMMENTS) ______dpWI'IIc c,'BE7A-GAMMA dprI,1IDcO ,,'BETA-GAMMA U NO ACTION REDOO

SOURCE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMI1NATION ALPHA BETA GAMMA SURvEy ALPHA BETA/OAMMA BETA/OAMMA INSTRUMENT_ TYPS'TAGNO E3p-t Afi SOURCE 0 RADIATION NEUTRON BETA-GAMMA

!F SORC 1TRNGH71l dpI? INSTRUMENT TYPE/T.AO NOo 17 -sr zS 'a

"IISTnUMENT RESPONSE Ccll?Y -- OATENREIE 26;P?4 s'. RADON REVIE DAT -,,

EFFICIENCY/CORRECTION FACTOR A/~5s ALPHA BETA-GAMMA m,,,, 0

MD.SAT. ULNSAT. SWIPE, BtAOAM ITEM pm~ dp * 0 POBIE EOI EOI -h~ NEUTRON 0LOCAIO BACxGROUND IvlV NOm dp"f. -vo'dCOCTO (0. "N. PROBE 100cm' PROB,9E 100cm n,,B

nFASON FOR SUJRVEY PROCEDURE-NO.I 0 IIA k1-3& -- MAP_____

O SPECIAL _ _ _ _ _ ' g__

0 BouTiNE w0IZK W' PRObfRESS ___20______4 ~ ~~~~ CI Clip______ALPHA BETA GAMMA mrqn/N. ITE 21

""OREGiY EOUIVLLZJR 0Ef-rG~AMMA ITEon '1 P '? d'-I AIV/ d??J NUTO LOCATION______PROBE IcO C"" PROBE 1T0 Cm ??ICo9/9,, U

2 Ir~ -- 12

.- 3 ______I______

4 2

5______'

S ______~29 ______

___0_ 33______T

0 12 ~ 3S______

m 14 ______3 ______

II ____I ______1

1____ I ______m tn I__ _ __ II3

17: ______

TIIF RN flWI.JIY...,,,,t,,, *,.*fllI ffltt.tt.. V,,. rrlr,,..r.,r U., fit I Týlf KNOWING & WILLF UL A 1- n DING OF FALSf.FICTICI 0 US.On FnAUOL) LEP 4T STATEMINTS OR ENTRIES ON T H 19 DOC U MEN T MAY DE P u NISHADL fA twi rn m z0

10

-4 m c,

6 17 8 1 101 11 1 12 1 13 114 1.5 161 17 18 19 20 12 2 23 ( RADIOLOGICAL CONTROL i.Inlrm ,arInMDcf CONTAMINAT' 1ADIATION TIEI IM IIMET SURVEY nP,., 1 10M eC-T Fltr IZJU'b SART COMPIL. i PAGE...I. ATcIIVIT Y, Z. IOCKAIION "o a '~ DII*LY 0DAILY 0 I -". JOn"ASO.) WEEKTLY 0 CONTAMINATION AND WEEKLY SRADIATION SURVEY MONTMY a MONTHLY0 COMMENTS MAP ID. ~-'CBKLY 3UCVFY 01' RIR$A :SrOW.)Ii e~AC49-

PERMISSIBLELEVELS CSrA AREACONTROL LEVELS 0 OTHER - dpnVI0t0 MIALPHA dp.n/II0crrnIALPHA (SEE COMMEITS) ______!20-0 IdPns~iOt cmi, BETA-GAMMA .A. dprIVI0 ear-0BE-TA-OAMMA UNO ACTION REODO.

SOURCE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION APABETA-GAMMA LH SURVEY N ALPHA BETAtOAMMA BETA/OAMMA INSTRUMENT TYPEITAON 001/ SOURCE ID -RADIATION NEUTRON BETA-GAMMA SOURCE STRENOTH pm dp - /r INSTRUMENT TYPC/7AGONO fEs mZ lVir3

INSTRUMENT RESPONSE corn fsR.,T con, RAD REVIEW____COCON, Y D-ATE* /y..fl'Iva

EFFICIENCY/CORRECTION FACTOR %L/,.s -. ALPHA BETA-GAMMA m.nr0 kIDA - SATý UNSAT. SWIPE, BETA-OAMMA Q1 ITEM dpm dpI, PRE EOUIV - EOUIV NETO NOS oR O~' 01 NEUTRO 0pT LOCATION BACKGOROUND 1 corn 7s cn,R 0. '/. IOSER 007cm' PROBE ICETcm ic*1oRII, 0

PnjASON FOR SURVEY 0 PROCEDURE-NO,'

0SPECIAL l

*ROUTINE SEE - ______20

ALPHA BETA-GAMMA 0lsV, ITEM 21

fOUIV COUIVQJ)V,11 letOIAMUA U on 2 '10 El DpI, 011 ~ NEUTRON 0 LOCATION____ PROB3E Itu -c_, PROBE 100 eni mnluo Rft,, U3 eIe"

I MAI - it - b Z 1

I 111t 27

S 2R

9 32

1o0 _ _ _ 31 m

C; 12 35 3 I ______v.3

1 _ _ 3f...~...... I _ _ _ _ _ -4 m 14 _ _ _ _I 37_

I1 7. Z.______

IT I 93 4

*T14E KNOWING & WILtfITL rECORDING O FALSE. FICTICIOUS, OR FRAUOULIPNT STATEMENTS OR ENTRIES ON THIS_DOCUMEN MAYS _ný ~ - AJELuýALLrLNIKLU- KuýtLLIJLJIIAI 0-TAITTIlL I) tlUIuII / ,i•U~dII)IIInhIIUI ;,urvey U nIa Mi'p ACTIVITY/i LOCATION IPAGE. SA - I~rroT~eT.w., - -4 - ,n Sfl1VEYO DATE s.J1F50&) /Z .JcIL q70 NOTE: THEKNOWNO&WILLFULRECOARDINGOFFALSEFICTCIOUS.ORFRAUDULENTrSTATEMENS opRENTRIESON THIS DOCUMENT MAY OE PUNISHABLE AS A FELONY UNDER FEDERAL STATUTEIL

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. =-, -", 4)

Project Name/No. G5,•-,A're-m • m Date /3 JULC,'t-. f

Sample Location _o-,m ,Tr ,.c-s,- Technician s. J),v,; Air Sampler Type/No. ,gbrc. //z-s- Filter Used G-,n4-t ,/!

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-'uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (1UP mI/I) or (2.83 x 10' ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

Counting Inst./Serial# Es5-I / u.l. C.F. Jz?(, MDA ,•Or•/o Total Counts Count Time = cpm cpm C = Net cpm Activity (uCi/ml)

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a Counting Inst./Serial# C.F.-__ MDA Total Counts ' Count Time = cpm cpm b- = Net cpm Activity (uCi/ml)

...... Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

,•/ / - Counting Inst./Serial# C.F.__ MDA Total Counts ' Count Time = cpm cpm - C-b Net cpm Activity (uCi/ml)

a Counting Inst./Serial_ C.F.- MDA Total Counts ' Count Time cpm cpm - C - Net cpm Activity (uCi/ml)

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souncE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMliNATION ALPHA BIETA-GAMMA SUnVEY S nCI.ALPHA BETA/AMMA BETAJGAMMA T.sTInUMENT TYV'E'TAONO Cs#, - 11 OUCIDU238- RADIATION NEUTRON BETA-GAMMA

SounCE STRENGTH /60, dm - m. NSRUMENT TVPE/TAO NO t.P. I

'ISTnUMENT RESPONSE c cpm - PIADRfl?,.W DATE ?92______EFFICIENCY/COARECTION FACTORt a - ALPHA BETA-GAMMA Q0 KIA -d SAT. UNSAT, SWIPE/? I OII-U ITEM l 8fV, * 0 PROBE EORLL3 NO~AOAM FPACXGROUND cpn wl 4. No pdpn dpn'/ dpn' do,,/ NEUTRON 0 LOCATION CrPROBE4.5' 00 C.,' PROBE 100 m n'veRA,, m

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PAGE OF MAPIO - IC-O*,I

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NOTE- THE KNOWING A WILLFUL RECORDING OF FALSE, FICTITIOUS, ORtFRAUDULENT STATEMENTS OR ENTRIES ON THIS DOCUMENT MAY BE PUNISHABLE AS A FELONY UNDER FEDERAL. STATUTES.*-

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GICAL CONT4(* '-.4- nadintlo n/C, mlnatlon Survey Grid Map dilL T ACTIVIT/ L Is PAGE ' < ,',.4[L•C SunvEYOn OATSE 115. JOHAJ5oFJ r- I NOTE: THE KNOWING & WILLFU•.RECOnOING OF TALSE.FICTICIOUS.OR FRAUDULENT STATE MENTs OR ENTRIES ON T IS DOCUMENT MAY BE PUNISHABSLEAS A FELONY UNDER FEDERAL STATUTE&

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. "

* Project Name/No. GS'm'•. ' . Date /1 J-/L *¶0 Sample Location . sref 8-2p: W-f, f Technician ,- J•"• Air Sampler Type/No. Rb[./ZdSg" Filter Used Gr,0,', 9/E

Alpha Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-? uCi/dpm) X Fa Fa = 1.25 for (Sample volume) x (103 mI/l) or (2.83 x 10V ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate Sample Volume

,8 3ý Counting Inst./Serial# •"-so-/ Z /,( C.F. 2 .20 M DA 9-.3-k- 1

Activity (uCi/ml) Total Counts - Count Time cpm cpm - -b = Net cpm -3

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Ce Counting Inst./Serial# C.F._- MDA (uCi/ml) Total Counts ± Count Time = cpm cpm - - = Net cpm Activity

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Sample Location Technician Air Sampler/# Filter Used Volume Time Sampler on Sampler off Total time X Flow Rate Sample

MDA /3-/a, Counting Inst./Serial# C.F.- = Net cpm Activity (uCi/ml) Total Counts - Count Time = cpm cpm -Cb

MDA Inst./Serial# C.F.___ 0( Counting Activity IuCi/ml) Total Counts -'-Count Time =cPrn cpm -•b•=Net cpm T-b

RADIOLOGICAL CONTROL (

CONTAMINAT' 'ADIATION TO %IE c SURVEY FIEp&. 2 PRQjwr FILE ~L START0220 OPL/S5 PAGE.L! ICII~ PP Jc l FILE~n TiL'1 119,, LOCARTIONr.-,03 1WMT#rP-Tf,.,P DAILY U UP4SIIAJ WEENLY 0 CONTAMINA TIOAD WEKYA MONIHLY 0 RADIATION SURVEY

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SOURCE CHECK( DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPH BETA-GA06IMA SURIVEYI ALPHA BET"IAMMA BETAXIAMMA INSTRUIMENT TYPIE'TAONO SOURCEID. RADIATION NEUTRON @ETA-GAMMA /--0 SURVEY tORESRNT md.mjf NSTITuMENT TYPE/TAONO IESIP- Z '0

INSTRUMENT RESPONSE ep ~epm - t'nY/, AOCONRREVIEW____ ~ . DATE ______

[F FICIENCY/CoRRECT ION FACTORT ALPHA BETA-GAMMA m,.mdlv 0 VD.SAT. UN;S-AT. SWIPE/ Be'PA-GAMMA MOA.8pm pm EOUIV EOUIvIIJL UITEM ______. PIoR PROBE T NEUTRON 0 LOCATION PICKRON 3 &.nS -'~RODE 100cm, PROBE 100C.m ~ l,

nflASON SURVEY POn 0 PROCEDURE-NO. [(I3 ACR -______4lA 1-~e 0 SPECIAL 13

8 AOUTINE 009OfLK IN8 PROCR-S 20___ II ______

21 s E ALP14A BETA-GAMMA -01h ITEM EoutV EOUIVQ:139 OB#*GAMUA U OR 22 rnosE NEUTRON 0 LOCATION ______NO 8Dm ap-1 dY~mI 8pm' PROBE T m' PROBE 100 cm inlc A,eBt 23 L

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TI"( KNOWING A WILLFUL nrCOnLIINr. OF FALE!. FICTICIOLIS OR FRALIJUIINT STATEMtNTS OR ENTAIES ON THIS130CIIENTMAYft Eg~aI l SUA _A 5 CoNH AM 0H/RADIATION SURVEY REPORT CONTINUlk" SHiEET 0

OJ'. GA-wLT9&1f.w3.-) MAPID0 t: P 0f-TLOCATION~LCACTIVITY/ u)ip-o-ý,m Ifg,.dl PAGE ý O

S. JO qeX1 NOTE: THEKNOWING A WILLFUL RECORDINGOF FALSE.FICTITIOUS. OR4FRAUDULENT STATEMENTS ORt ENTRIEsON THIS DOCUMENTMAY BE PUNISHABLEAS A FELONYUNDER FEDERAL STATUTES. i

ALPHA BTETA-GAMMA mN~,enn ITAEM BETA-GAMMA M~m,.yh, ,.,PP-I -Goi4i3 8 BE*'R~-AMMA U TMSWIPE/ EOI..... OUIV - BETA-GAMMA EnOPE Fol013 ITEM '.O on PROBE on 7n, TF NEUTRON 0 LOCATION NO C.I p. dm pjNEUTRON 0 LOCATION ____.r l c Cm' 2 ~I.0Ctooc00vcm~l .I~R, ROBE 100 PROBE mlc~oRAft. 0

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. "7-0-01(A)

Date I "J- - 17,D 0 Project Name/No. G4.,,,A-O,,,/,/OIT Sample Location eLL,. s.',rW-qr Technician o.,o" -. Air Sampler Type/No. ",Efr.o/Z',.r- Filter Used GC&1e.' ,9/A,

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10- uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 ml/l) or (2.83 x 104 ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

/3 \ 1'-Counting Inst./Serial# C.F... MDA . .,,.,'1• Total Counts * Count Time cpm cpm Cb = Net cpm Activity (uCi/ml) e

a Counting Inst./Serialt# C.F.___ MDA

Total Counts - Count Time = cpm cpm - b = Net cpm Activity (uCi/mI)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Total time X Flow Rate Sample Volume

S-/ ~Counting" Inst./Serial# C.F.___ MDA

Total Counts - Count Time = cpm cpm C'b = Net cpm Activity (uCi/m!)

a Counting Inst./Serialt C F.C__ MDA Total Counts - Count Time cpm cpm b Net cm Activity (uCi/mI)

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CONTAMINAlI IADIATION TO1 SURVEY flEP&....J PROjE4CT FitLI- ACT Alt 5/ I.OCATION s n sunJ'VEY0AP WEEKLY 0 CONTAMINATION AND - WEAILY CRDAINSRE LINIIY 0MONTHLY0 0 WA7eOfJ-To3 MA -- I OMMENIS MAPID 1791L.L. 317,c K______-4i-: .I PERMISSIBLELEVELS CSCA AREACONTROL LEVELS 0 OTHER d-rWTdL00U,' AL PHA - 7L-dpW/T00c','ALPHA (SEE COMMENTS) 61QQpW100~Cm BETA.InAMMA Adpm.VII76cm' BETA-GAMMA *NO ACTION REa-D.

SOURCE CHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPHA BETA GAMMA ALPHASURVEY ______LPABETA/GAMMA BETAIGAMMA ONSTInUmENE TyPt 'TAG POO 1- 1fi SLUInCE iD 7 - RADIATION NrUIION- EttAQ0AMMA

'(UURCE STRENGTH pn.ZW INSTRUMENT TYPE/T AD NO r 7 ?a

INSTRUMENT RESPONSE 2sv? cpn, - AADAO, REIE z______DATE ;Z J(14 '?0

CFTICIENCY/ConRECTION FACTOR 2 7 -5 ALPHA BETA-GAMMA .,e.w0

MD,-o.dý SAT. UNSAT. SWIPIE, 9S.GAMMA UITEM ~"' 13 ~ * PROBE EOU'v foulvv-ý NETRO f OR NO 4O dr.OPW dp' NEUTON LOCATION I7ACIIGnOUND p - -A '1/1n4 N PROBE 1762cm' PROBE 100cýcd~ '~~h,~ /,

IlEASON FOR SURVEY 0 PROCEDURE-NO Ift -c43.______m~~.~~~

C3 SPECIAL I9

*ROUTINE WORK( Itj. PRC6P~fC3. - 0______

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AIRBORNE RADIOACTIVITY SAMPLE/MONITOR REPORT No. 7-13 -0169

Project Name/No. c-s4-Tem-'yo-yt Date It Jvi. eo Sample Location (-I.C,.",r 13-/t) Technician , Air Sampler Type/No. ,Awco,/ 7o,.s-r Filter Used Cc--,q-1,r,

Activity (uCi/ml) = (net cpm)x(C.F.) x (4.505 x 10-' uCi/dpm) X Fa Fa = 1.25 for Alpha (Sample volume) x (103 mIA) or (2.83 x 10' ml/ft3) Fa = 1.00 for Other Emitters

Time Sampler on Sampler off Total time X Flow Rate = Sample Volume

-- 2

,,E..2 /-\ r- Counting inst./Serial# '-,t', C.F. Y,.U MDA 4.1 ,0"O z- "0 Total Counts + Count Time = cpm cpm C'b Net cpm Activity (uCi/ml) ,. c .- /. I

Of Counting Inst./Serial_ C.F.__ MDA Total Counts - Count Time = cpm cpm Cb = Net cpm Activity (uCi/mi)

Sample Location Technician Air Sampler/# Filter Used Time Sampler on Sampler off Tota?'time X Flow Rate = Sample Volume

,3 //• Counting Inst./Serial# C.F.____ MDA Total Counts + Count Time = cpm cpm C = Net cpm Activity (uCi/ml)

Or Counting Inst./Serial# C.F.__ MDA Total Counts .i- Count Time = cpm cpm C 4 - Net cpm Activity (uCi/ml)

R;D1Df OOICAL CONTROL CONTAMINA~ )AOIATION D:ATE TIMIE ITIMEIA_____ Pt.a),c7 rn.C ?I 1 JL)L 90 START 0770D COMFIT, . PG 4CTIWY/ SURVEYOR A) DALNAL LOATOGf),,)" WM 0 CONTAMINATION AND WEKL 0 RADIATION SURVEY MNHY0 MNHY0 c4Ad~trc~j"_ rACO MMEKNTIS TMAP I D uIvrP.3PIT 13B- If 13-11 'I-IV -d~g

rERMISSIBLELE'VELS CSCAAREA CONTACT. LEVEL.S C5 OTHER

-_ dpmI00~C,,' ALPHA I/I~ W,'ALPHA (SEE COMMENTS) ______100 OpWIVIOIKY' BETA.GAMMA T mIP11-C BT-GAMMA U N0 ACTION RTEGO

SOURCECHECK DATA CONTAMINATION SURVEYS RADIATION CONTAMINATION ALPHA BETA-GAMMA SURVEY ALPHA BETA/OAMMA BETA/GAMMA INSTRUMENT TYPE'TAONO FsP_ W1 SOUCEID LJ23 -RADIATION NEUTRON BETA-GAMMA SSTIIUMFN IV~T~N VSZ- D. SnE SOURSCESTRENGTH n"' 111,1 ~ a51 - mflA,,iNnmN tr/T OM P7

INSTRUMENTRESPONSE Cpm' zvr cE"' - WRtvh. AADCONREVIEW ~ 7 ~-.-.DATE ______

KFFICIKNCY/CORRFECTION FACTOR 0.71 qIf - ALPHA BETA-GAMMA Irntn,JI SAT, UNSAT. SWIFIE/ ~eeYAOAMMA iTeM UOA - dpný d~pm * PRE EOUIV EOUjvftEM~NUTO OR ______143__ ROBE__NEUTRON LOCATION nC nON p W1NO lp'11' dPYI/ dpnl Rpm' T.C'TSOUNDC~fl, 3~- C'fl 4 '4Rj~"' RODE IV0cm PROBE Icfl VIOII

fl"ASON FOITSURVEY 0 PROCEDURE-NO. ct 4I___ fMAP______

0 SPECIAL______9______

UROUTINE WOO- IA.) P_0*rI2ýAS t~ 20______suVE nEP PtI I 7______LT I ______ALPIIA BETA-GAMMA "",' 1 ITEM______- ,r OUIV OO~U)rtR'4GAMMA U OII II011K NEUTRON 0 LOCATION ______'0 do"' 05'11 do-' do PROSE 100c., ~ POOE 100 C' "I CIO A,*,, 71

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3 ~~ ~ ~~~~~~~~~~36______w.c I I 114 m 14______I______37 ______(A 8 - IP II!KOIS & WIL CORDING OF FALSEJFý VI-ORSFRAUD LENLT-ATLMENMSIS-ALJTAIOHS 11"WoO~U~NTA CO N TAM0 NI RADIATION SURVEY REPORT CO4TNO SNEET 4

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1"" 19 JVL. le NOTE: THlE XNOWINO A WILLFUL ARECORDINO OF FALSE.FICTITIOUS. ORFRAUDULENT STATEMENTS ORENTRIEtS ON THIS DOCUMENT MAYSE PUNISHABLEAS A FELONY UNDER FEDERAL STATUTES.

A1PI'll 9ETA GAMMA mre/t ALPHA BETA-GAMMA ,nrenmih, FopFuvLS BE-qA-AMMA ITEM SWIPE/ EOUIV - EOUIV U.-3 BM¶*-OAMMA a ITEM fPOFE ():;39 HU NoPRBNETO OOUI 0LORAIO 00"" op"' pp"' dpnv NEt P 0 LOCATION NO dp"IV n dp n~ o, ETRN 0LCfO rn; I,. jOc ~ n~~ PROBIE ~oOmn,' ~ [O e nICIC Rn/r

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Midweit Office P.O. Box 293 Channahon, Illinois 60410 (815) 467-3000

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Defense Consolidation Facility P.O. Box 828 Barnwell, South Carolina 29812 (803) 259-1119

GENERAL NUCLEAR SYSTEMS, INC. (GNSI) A Chem-Nuclear Company 140 Stoneridge Drive Columbia, South Carolina 29210 (803) 256-0450 "IeanHari

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-02W Sample I.D.: W-8A Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium 0.27 +/- 0.05 pCi/l 08/17/90 908.1(h)

Notes: * Error = 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

-9 - r CleanHarbff -E

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-03W Date Received: 07/27/90 Sample I.D.: W-9A Sample Type: Water

Analysis Method Number Date and Reference Parameter Result* Units

08/17/90 908.1(h) Uranium 0.27 +/- 0.05 pCi/l

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit _11eanHatbo!3

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-04W Date Received: 07/27/90 Sample I.D.: W-11A Sample Type: Water

Analysis Method Number Date and Reference Parameter Result* Units 908.1(h) Uranium LT 0.14 pCi/l 08/17/90

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations inr.the net count rate or the procedure detection limit

X-837 Clean Harb'or Sd

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-06W Sample I.D.: W-7A Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference Uranium 0.27 +/- 0.05 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

Y _oQ] "IeanHarbors

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-07W Date Received: 07/27/90 Sample I.D.: WC-10B Sample Type: Water

Analysis Method Number and Reference Parameter Result* Units Date 908.1(h) Uranium LT 0.14 pCi/l 08/17/90

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-839 CleanHarb46

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-08W Sample I.D.: WC-10A Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error = 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-840 CleandHri'

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-09W Sample I.D.: W-6A Date Received: 07/27/90 Sample Type: Water

Analysis Method Number er Paramet4 Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-841 Plean'arbor,~

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-lOW Date Received: 07/27/90 Sample I.D.: WC-5A Sample Type: Water

Analysis Method Number Date and Reference Parameter Result* Units pCi/I 08/17/90 908.1(h) Uranium LT 0.14

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-842 1-ean~arbor

CHAS Lab #: 9007219-11W Client: Chem-Nuclear Systems, Inc. Date Received: 07/27/90 Sample I.D.: WC-5C Sample Type: Water

Analysis Method Number Date and Reference Parameter Result* Units

08/17/90 908.1(h) Uranium LT 0.14 pCi/l

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-843 [leanha

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007219-04W Sample I.D.: W-11A Date Received: 07/27/90 Sample Type: Water

DUPLICATE AND SPIKE ANALYSIS

Original Duplicate RPD Spike Recovery (%) Parameter MDL Result* Result* (M) Result*

Uranium LT 0.14 LT 0.14 0 2.3 + 0.5 95.8

Notes: ND - Below minimum detectable level (MDL) * - pCi/g Soil/solid samples based on sample dry weight.

X-844 NeanHarjor

CHAS Lab #: 9007220-01W Chem-Nuclear Systems, Inc. Client: Date Received: 07/27/90 Sample I.D.: W-2A Sample Type: Water Analysis Method Number Date and Reference Parameter Result* Units pCi/l 08/17/90 908.1(h) Uranium LT 0.14

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-849 ýIeanHariioirp ,no

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: Sample I.D.: W-3A 9007220-02W Date Received: Sample Type: Water 07/27/90

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-850 Pl~ean~abrso rb~

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-03W Sample I.D.: W-lA Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-851 p~ean albsiffj,

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-04W Sample I.D.: W-lB Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium 0.34 +/- 0.07 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-852 CleanHaP!3

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-05W Sample I.D.: W-4A Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-853 £leanHaryb,

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-06W Sample I.D.: W-4B Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-854 -cleanHariorS

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-07W Sample I.D.: M-1 / SOIL Date Received: 07/27/90 Sample Type: Soil

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.3 pCi/g 08/17/90 908.1(h)

Notes: * Error = 2 standard deviations LT - Less than 2 standard deviations in the net count rate or tWe procedure detection limit

X-855 Clean Harboi3

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-08W Sample I.D.: M-1 / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908. 1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-856 'lean iadbo!3

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-lOW Date Received: 07/27/90 Sample I.D.: M-2 / SOIL Sample Type: Soil

Analysis Method Number Date and Reference Parameter Result* Units 908.1(h) Uranium LT 0.3 pCi/g 08/17/90

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-857 CleanHadhori,

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-11W Sample I.D.: M-2 / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium 0.27 +/- 0.05 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-858 ^1a•ab!

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-12W Sample I.D.: M-3 / SOIL Date Received: 07/27/90 Sample Type: Soil

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.3 pCi/g 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standa-d deviations in the net count rate or the procedure detection limit

X-859 (lean Hatbe~

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-13W Sample I.D.: M-3 / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-860 ".'lean Farborj

CHAS Lab #: 9007220-14W Client: Chem-Nuclear Systems, Inc. Date Received: 07/27/90 Sample I.D.: M-4 / SOIL Sample Type: Soil

Analysis Method Number Date and Reference Parameter Result* Units 08/17/90 Uranium LT 0.3 pCi/g 908.1(h)

Notes: * Error = 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-861 SleanHa&

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-15W Sample I.D.: M-4 / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-862 'leanHaibor5

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-16W Date Received: 07/27/90 Sample I.D.: DS-l / SOIL Sample Type: Soil

Analysis Method Number Date and Reference Parameter Result* Units pCi/g 08/17/90 908.1(h) Uranium LT 0.3

Notes: * Error - 2 standard deviations the procedure LT - Less than 2 standard deviations in the net count rate or detection limit

X-863 £Iean Harii"i

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-17W Sample I.D.: DS-I / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-864 'Plean Baflbo!

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-18W Sample I.D.: US-I / SOIL Date Received: 07/27/90 Sample Type: Soil

Analysis Method Number Parameter Result* Units Date and Reference

Uranium 7.5 +/- 1.5 pCi/g 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-865 Clean Harbo!3 A

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-19W Sample I.D.: US-I / WATER Date Received: 07/27/90 Sample Type: Water

Analysis Method Number Parameter Result* Units Date and Reference

Uranium LT 0.14 pCi/l 08/17/90 908.1(h)

Notes: * Error - 2 standard deviations LT - Less than 2 standard deviations in the net count rate or the procedure detection limit

X-866 elean iIrbot*

Client: Chem-Nuclear Systems, Inc. CHAS Lab #: 9007220-05W Sample I.D.: W-4A Date Received: 07/27/90 Sample Type: Water

DUPLICATE AND SPIKE ANALYSIS

Original Duplicate RPD Spike Recovery Parameter MDL Result* Result* Result*

Uranium LT 0.14 LT 0.14 0 2.2 + 0.4 91.7

Notes: ND - Below minimum detectable level (MDL) * - pCi/g Soil/solid samples based on sample dry weight.

X-867 APPENDIX E MORRISON KNUDSEN & SCIENTIFIC ECOLOGY GROUP (MS & SEG) DATA APPENDIX C

APPENDIX C

Tables detailing summary tables and fraction of limit tables from the termination and characterization survey results are provided in Appendix C. Following is an index listing the tables and figures by area surveyed.

Note: Figures for Building 653, pumphouse are included in Appendix F. Burn pit soil bore logs are in Appendix D.

Off-Site Surveys Off-Site Background Soil Sample Locations Figure C- 1 Off-Site Background Exposure Rate at 1 Meter Table C-I Off-Site Background Soil Samples Gamma Spectrum Analyses Results Table C-2 Entire Site Surveys 15 x 15 Meter Grid at GSA and Property 20 Sites Figure C-2 Random Soil Sample Locations Figure C-3 GSA Site Random Soil Sample Survey Gamma Spectrum Analyses Gamma Exposure Rate Measurements Table C-3 Table C-4 Building Surveys - 1993 Direct Beta Survey Statistics Figure Gamma Survey Statistics C-4 to C-12 Figure C-13 to C-19 Building Surveys - 1994 Direct Beta Survey Statistics Figure C-20 to C-21 Gamma Survey Statistics Figure C-22 Characterization Survey Results - Summary Tables, Fraction of Limit Tables Burn Pit Soil boring Locations, 1993, 1994, Including wells Figure C-23 Soil Bore Samples Gamma Spectroscopy Analyses Results Table C-5 Locations for In Situ Measurements and Soil Samples Figure C-24 Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-6 Bulk Soil Sample Gamma Spectroscopy Sample Analyses Results Table C-7 In Situ Gamma Spectroscopy Results Fraction of Limit Table C-8 Clinker Area Locations of In Situ and Soil Samples in the Bum Pit and Clinker Areas Figure C-25 Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-9 In Situ Gamma Spectroscopy Results Fraction of Limit Table C-10

021595- P\SMA TU WI(\OSA\DRA FTDMAPPpC. D C-1 APPENDIX C

Boundary Zones for In Situ Boundary Survey Figure C-26 In Situ Gamma Spectroscopy Survey - Northeast Table C- II In Situ Gamma Spectroscopy Survey - Northwest Table C-12 In Situ Gamma Spectroscopy Survey - Southeast Table C-13 In Situ Gamma Spectroscopy Survey - Southwest Table C-14

Windborne Soil Samples Gamma Spectroscopy Sample Analyses Table C- 15

Property 20 Locations of In Situ Measurements and Soil Samples in Property 20 Figure C-27 Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-16 In Situ Gamma Spectroscopy Results Table C-17

Characterization Survey Results - Detail Tables Soil Sample Locations and Descriptors Table C-18

Burn Pit Soil Boring Locations, 1993, 1994, Including wells Figure C-28 Core Bore Sample Analysis Results Table C-19 Comparison of Total Uranium and Gamma Spectroscopy Analysis Data Table C-20 Burn Pit Locations for In Situ measurements and Soil Samples Figure C-29 Surface Soil Samples Gamma Spectroscopy Analyses Results Table C-21 In Situ Gamma Spectroscopy Analysis Results Table C-22 Bum Pit Soil Sample Density and Moisture Content Table C-23 The GSA Burn Pit are Showing Locations of Flags Placed During the Scan for DU Chips and the Areas Where Scraping Was Done Figure C-30 Bulk Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-24 C-34 Scanning for DU Chips in Scraped Areas Figure C-31 to

Clinker Area Locations of In Situ and Soil Samples in the Burn Pit and Clinker Areas Figure C-35 Table C-25 Surface Soil Samples Gamma Spectroscopy Sample Analyses Results C-26 In Situ Gamma Spectroscopy Results Table

Boundary Zones for In Situ Boundary Survey Figure C-36 In Situ Gamma Spectroscopy Table C-27 to C-30

Windborne Location Selected for Sampling for Windbome Deposition of Depleted Uranium Figure C-37 Surface and Subsurface Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-36

021595-P\SrrPAMTL\FINUGSA\DRAFTD\APP_C.D C-2 APPENDIX C

Property 20 Locations of In Situ and Soil Sample Measurements Figure C-38 Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Table C-32 In Situ Gamma Spectroscopy Sample Analyses Results Table C-33 Property 20 Soil Sample Density and Moisture Content Table C-34

Other GSA Soil from Woods North of Perimeter Fence Gamma Spectrum Analyses Table C-35

02i595-P\SmAMTI .\FI1MSA\DRA FTDAPPC. D C-3 APPENDIX b.,,

FIgure C-i Off-Site Background Soil Sample Locations

2 9 5 ( 1" "Psr\A MT\1AP SA\ DRAFMD\APPC. D C4 APPENDIX C

Table C-I Off-Site Background Exposure Rate At 1 Meter (#R/hr)

Loeadm C0d1 L[eationm meda Ma.n StdwD MN Zeibr

P05000 0.5 kim North, 14 Homier, Watetow Watertowm (city property) 10.6 0.8 21

P05030 0.5 km NNE, 18 Putamm, Waterown 12.7 0 1

PO5060 0.5 km ENE, Quisby/Cyprem istorsetio., Watetown (city prop.) 12.9 1 20

P05090 0.5 km West, NE Corner AWTL 13.4 0.5 20

P05120 0.5 kmn ESE, Arsenal Paik, Waertown 12.8 0 1

P05150 0.5 km, SSE, 46 Newton, Newton (city propeoty) 10.8 0.8 20

P05180 0.5 km South, East C MDC! Field os (ladeksbak, Newton 13 1.2 21

P05210 0.5 kin SSW, MM SkIim Rink asCldeanbk, Newton 13.2 0.8 21

P05240 0.5 kim WSW, 328 Caresbeank Rd., Watertown (city property) 11.4 0.7 20

P05270 0.5 km West, 96 B•chwood, Watertown (city property) 12.8 0.6 20

P05300 0.5 km WNW, 30 Prank, Watertown (city property) 12.2 1.2 Is

P05330 0.5 km NNW, 136 Walnut St., Watertown 14.7 1.6 21

P15000 1.5 km North, 29 Commonwealth Ave, Watertown (city property) 11.7 0.4 20

P15030 1.5 km NNE, 56 Salisbury, Watertown (city property) 9.5 0.5 20

P15060 1.5 km ENE, 133 Grove, Watertown (city propert) 11.5 0.7 40

PI5090 1.5 km, West, Old Anesenl Greeough Blvd., Watertown 11 1 40

P15120 1.5 km, ESE, 117 Murdock, Boston 11.4 0.7 20

P15150 1.5 km SSE, Peter, Park., Boston 9.5 0.4 20

P15130 1.5 km South, Haremnan Park, Boston 10.4 0.6 20

P15210 1.5 km SSW, 15 Nonamtum. Newton 12.4 0.3 20

P15240 1.5 km WSW, 9 Eldridge St., Newton (city property) 13.1 0.8 20

P 15270 1.5 km We•t. 66 Capital, Newton (city property) 12.2 0.6 19

P15300 1.5 km WNW, 91 Church St., Watertown 9.9 1.2 39

P15330 1.5 km NNW, 119 Robbins, Watertown 12.9 0.4 19

P30000 3 km North, 22 Bow Rd., Belmont (city property) 9.7 1.3 21

P30030 3 km NNE, 17 Bright, Belmont (city property) 11.3 I 21

P30060 3 km EKE, 157 Braufle St., Camridge (city property) 10.9 0.1 20

P30090 3 km East, 7 Ream St., Boston 11.8 0.5 20

P30120 3 km ESE, acros 1302 Commonwealth Ave, Boston (city property) 13.3 0.7 20

P30150 3 km SSE, MDC Pool and Park, Boston 12.3 0.6 20

P30180 3 km South, Boston College Football Field, Newton 13.8 I 41

P30210 3 km SSW, 286 Ward St., Newton 11.4 I 39

P30240 3 km WSW, Cabot Park, Newton 11.6 0.8 40

P30270 3 km West, 103 Bridge, Watertown 13.5 0.7 20

P30300 3 km WNW, 103 Chapman, Watertown (city property) 13.4 0.6 20 P30330 3 km NNW, 91 Waverly, Blmost (city property) 11.3 0.7 20

021595.-PFSrI'IAMTL\Fm'jGSA\DRAFTDýApp C.D C-5 APPENDIX C

Table C-2 Off-Site Background Soil Samples GammaS Analyses Results (pCi/g)

POS=00 13.5 1.2 0.3 3.0 0.4 0.7 0.6 0.6 1.3 0.6 P05030 13.9 0.6 0.3 1.9 0.6 0.9 0.7 0.7 0.7 2.2 0.8 0.6 POS0 14.6 1.9 0.3 0.6 0.1 0.6 0.6 0. 2.1 0.8 1.2 P05090 14.3 0.2 0.3 2.3 0.6 0.9 0.7 0.7 0.8 2.2 0.8 0.8 P05210 17.5 0.1 0.2 0.5 0.4 0.4 1.1 0.5 P05150 15.9 0.4 0.3 0.3 0.7 0.5 0.5 0.5 1.2 0.7 0.7 P05330 16.6 0.2 0.3 0.7 0.5 0.5 0.3 0.7 P03210 19.4 0.1 0.3 1.5 0.6 0.8 0.6 0.6 1.7 0.8 1.2

P05240 15.6 0.1 0.3 0.4 0.9 0.6 0.7 1.8 0.7 1.2

P057 21.9 0.1 0.4 0.6 1.2 0.8 0.9 0.9 2.5 1.0 1.7 P05300 15.4 0.3 0.3 0.4 0.8 0.6 0.6 0.4 2.2 0.7 P05330 17.7 0.1 0.3 1.9 0.3 1.0 0.7 0.7 0.6 1.7 0.9 0.8 P15O00 14.9 1.0 0.3 0.5 0.7 0.7 0.7 2.0 0.8

PI5030 14.0 0.2 0.3 2.0 0.4 0.7 0.5 0.6 0.6 1.8 0.7 0.3

P15060 15.5 0.2 0.2 2.3 0.6 0.5 0.5 1.4 0.6 0.9

P.5090 15.8 0.3 0.3 0.7 0.6 0.6 1.5 0.7

P15120 16.5 0.0 0.3 0.5 0.8 0.7 0.7 2.1 0.. 1.1

P15150 13.5 0.4 0.3 2.6 0.6 1.1 0.7 0.7 2.1 0.8 P15160 15.5 0.3 0.3 2.1 0.4 0.9 0.6 0.6 0.5 1.9 0.7

P15210 16.9 0.4 0.3 0.5 0.9 0.6 0.6 1.7 0.9 1.0 P15240 15.3 0.4 0.3 4.0 0.5 0.8 0.5 0.6 0.5 1.6 0.7 0.6

P15270 14.6 0.5 0.3 0.5 0.8 0.6 0.6 0.6 1.3 0.7 2.0 P15300 13.9 0.4 0.3 2.2 0.6 0.9 0.6 0.7 0.6 2.0 0.7 1.0

P15330 19.5 0.5 0.4 3.2 0.9 1.4 1.1 1.2 0.8 3.2 1.2 1.2

P30000 15.1 0.3 0.3 1.6 0.4 0.7 0.5 0.6 0.6 1.6 0.7 0.7 P30030 14.9 1.1 0.3 2.6 0.5 0.6 0.6 0.7 2.1 0.7 0.8

P30060 14.7 0.3 0.3 0.3 0.9 0.6 0.6 1.4 0.7 1.2

P15120 15.4 0.5 0.4 0.6 1.1 1.0 1.0 0.8 2.0 1.0 1.7

P30120 15.9 0.4 0.3 0.5 1.0 0.7 0.7 0.5 1.9 0.8 1.2 P30150 15.2 0.6 0.3 0.4 0.7 0.7 0.7 0.7 2.2 0.8

P30150 16.1 0.2 0.3 0.7 0.9 0.7 0.7 0.9 2.1 0.8 0.5

P30210 13.0 0.4 0.3 1.9 0.4 0.8 0.6 0.6 0.8 2.2 0.7 1.1

P30240 16.2 0.5 0.2 1.3 0.4 0.7 0.6 0.6 0.6 1.5 0.6

P30270 16.3 0.4 0.4 2.3 0.7 1.1 0.9 0.9 0. 2.2 0.9 1.1

P30300 17.8 0.6 0.3 2.4 0.5 0.9 0.7 0.8 0.6 1.9 0.9 0.7

P30330 15.0 0.2 0.3 2.4 0.2 0.6 0.5 0.5 1.6 0.6 0.9

Meat 15.8j 0.4 0.3 2.3 0.5 0.1 0.6 0.7 0.7 1.9 0.8 1.0

Std.ewi 1.8 0.4 0.1 0.6 0.1 0.2 0.1 0.2 0.1 0.4 0.1 0.3

Mean+ 38 21.2 1.5 0.4 4.2 0.9 1.5 1.0 2.12 .1 3.1 1.2 1.9

022 595-P\sr"AMTLWNGSA\MDRAFTD"A PPC. D C-6 C.)

+• A.' +• +•

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+ go

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I. +/+•y'+ ++ U F+++•++÷+ ++ 2 S÷ + + ++ + +

+ ++ ++++ + ...... Q

-J APPENDIX C

/Vol

',\ ...... -:-.. . CGSA SITE

, ...... RANDOM SOIL SAMPLE LOCATIONS

ii...... G6A 511lC

...... 0 .00Ml PIT.@ ...... '...... : ; 1 6- p I•. - : ;...... k ' ' . ..• ....• ..... ! ...... • .... ".... :.....:...... : II . .i ,,. .. A~X. •. • -_ .••i...... i. ..;...... i ...... i...... :..... i ...... i...... i ...... •...... i ...... S ••: ...... ~~~~~~~~~~~...... $ 3 " 9I f I It 13 14 I15 15 17 18 19 26l ZI ZZ Z"' 14 M Z6I ZT tA ' 1 1 32h 333 3.1]. 35 3G I', •" I • I 7 I 56 i i 1 1 1 S ? A 9 O Z 3 e~ ZA 9 30 31

Figure C-3. Random soil sample locations

021595-P\S( TL\FIN\OSA\DRAFTD\APP_C.D C-8( ( APPENDIX C

Table C-3 GSA Site Random Soil Sample Survey Gamma Spectrum Analyses (pCi/g)

LAnde. Gild K46 Cs-t37 WINu IW-23 Fb-212 31414 rW1l 344 R" -224 j Ae-122 71,h2M4 Mrface A-17 1.5 0.3 0. O. mb-md A-17 20.7 0.3 0.7 0.6 0.3 0.5 mdace A-22 7.9 1.5 0.2 0.5 1.0 0.9

mb-mad A-22 9.4 0.3 0.7 0.5 0.2 0.9 msrtae A-24 12.4 0.6 0.4 0.9 1.5" 1.30

slb-emd A-24 9.9 0.3 0.7 0.1 1.1 0.9

ndutce B-09 15.7 1.3 0.5 0.6 0.6 -b&.d B-09 17.3 0.3 0.6 0.5 0.6

ad'ac. B-10 15.3 0.2 0.5 0.4 0.6

mb-4md B-10 13.9 0.3 0.7 0.7 0.7

MBdace 8-13 19.2 0.2 0.5 0.5 0.4 0.9

smb-md B-13 13.8 0.2 0.7 0.6 0.5 mrfce B-17 13.2 1.1 0.4 0.9 1.4- 1.6" 1.0

mb-md B-17 17.3 0.3 0.6 0.7 0.7

mduce 1.-19 15.1 0.7 0.3 0.6 0.6 0.7

-b.md B-19 16.5 0.6 0.4 0.5

u.,.a=e 8-20 11.0 0.2 0.7 0.5 0.5

rfb-gud 8-20 11.7 0.5 0.5 0.8 sudra B--33 13.6 0.3 0.9 0.9 1.0

sub-sud B-33 7.3 0.5 0.6 0.7

,dwace C-09 13.5 0.3 0.6 0.6 0.3 0.8 sub-sud C-09 15.9 0.3 0.6 0.7 0.7

maface C-IS 17.5 0.2 0.5 0.5 0.4 mub-mud C-15 17.5 0.3 0.6 0.5 0.5

umdace C-17 12.0 0.2 0.5 0.9 2.00 2.2* 2.20 4.5* 1.7* 2.60 mb-md C-17 16.1 0.2 0.6 0.5 0.6

urface C-24 6.2 0.5 0.2 0.5 0.6 0.6

mb-sud C-24 7.0 0.2 2.70 0.4 0.4

dra.ce C-26 11.4 2.1 0.2 0.6 0.6 0.7 6.30 0.7 14.90 mb-mPd C-26 17.1 0.2 0.3 0.6 0.5 0.5

urfdue C-23 9.9 0.3 0.6 0.5

mob-mod C-28 12.2 0.4 0.3 0.9 0.9

suface C-32 15.7 0.3 0.6 0.7 0.6

mb-mud C-32 13.9 0.3 0.3 0.3 0.9

idudce C-33 9.6 0.6* 1.50 1.30 1.30 7.2* 1.7" 3.70

mub-mud C-33 0.6* 1.6* 3.7- 4.0 10.0" 1.60 6.2*

msdace D-10 19.0 0.5 0.3 0.5 mub-sumd D-10 14.2 0.2 0.4 0.4

021595-.P.SrT'A MTh\I1NDcSA\DRAFTD\APPC.D C-9 APPENDIX C

Table C-3 GSA Site Soil Survey Gamma Spectruim Analyses (pCli/g) (continued)

I.b-214 Ia-224 3*-4lI AC-22 71-2U L-ea--sm. GrM _40 CA-137 n1-2 3-212 IPb-l2 -.214 1.3 1.30 3.81 1.1 mgface D-17 12.2 0.3 0.4 1.2 0.5 mabmd )D-17 IM. 0.3 0.6 0.6 0.5 msrfac D-21 15.6 0.2 0.4 0.5 0.6 mb-.md D121 15.2 0.3 0.4 0.6 0.6 suface D-23 11.8 0.4 0.6 0.6 0.5 0.5 0.S5 ub-wmfd D-23 13.9 3.3* surface D-28 14.9 0.4 0.6 0.7 0.6 m.-md D.21 15.7 0.3 0.5 0.5 0.6

0.6 surface D30 31.3 0.4 0.6 0.7 0.6 msb-suri D30 15.5 0.3 0.6 0.7 0.5 mrface E-07 15.6 0.3 0.4 0.6 msb-surf E.07 16.9 0.4 0.5 0.7 msfade E-13 12.7 0.3 0.6 0.6 0.5 mb-mad E-13 11.1 0.3 0.4 0.6 1.40 madae E-16 11.6 1.1 0.3 1.1 1.30 mb-urf P-16 10.5 0.2 0.5 0.4 0.S 2.00 2.t Mu,,oC E-17 13.7 0.4 0.4 1.0 Mb.-mf 1-17 15.7 0.3 0.9 0.6 0.8 1.30 0.8 msrfa• -1I& 13.6 0.9 0.4 0.7 t.2" 0.8 mb-mad E-I11 12.0 0.5 0.7 0.6 0.9 msface E-19 17.0 0.5 0.9 1.0 0.7 mab-401t E-19 6.8 0.2 0.5 0.6 9.20 1.9* E-20 15.9 0.7 0.7 2.20 4.40 4.90 marface 1.30 1.40 1.0 rob-mad E-20 11.3 0.3 0.9 0.7 surface E-31 13.3 0.3 0.8

E-31 20.0 0.4 1.0 0.8 0.9 msb-fdt 0.9 1.0 1 .60 surfatce E-33 13.7 0.3 0.50 1.2 1.80 2.10 mab..=If E-33 6.9 0.6 0.4 0.8

surface F-07 15.7 0.7 mab-mad P-07 12.9 0.3 067 0.6 0.7 0.8 surface P-14 11.7 0.8 0.2 0.5 0.1 0.1 su-. s-r,, F-14 0.8 0.9 0.9 surfac~e F-12 iI. 1 0.6 0.3 0.6

sub-surf P-16 12.4 0.6

1.0 2.1" 2.30 surface F-22 13.1 0.5 0.4 0.6 0.7 0.7 m•-srf P-22 17.0 0.2

mdsace P-23 11.5 09~l 120.. 7o-a-23 I 13. 'It" zim

C-10 021 59 5 -sP'SrMTL\F[N\OSA\DRAAFrD\APP_C D APPENDIX C

Table C-3 GSA Site Soil Survey Gamma Spectrum Analyses (pCi/g) (continued)

L"m GCAd K-"o C.-37 Tn-2a1 31412 Pb-212 31414 P'b-214 R3*24 3ao226 Ac-228 Tb,-234 Mtfmcc 1-24 13.4 0.4 0.4 0.7 1.30 1.20 mb-nd P-24 4.9 0.1 0.4 0.3 0.4

mrafe 1-27 11.0 0.9 0.5 0.6 6.7 11.60 mb-mud 1-27 11.3 0.8 1.0. 0.8 5.40

mwace 0-05 15.6 0.9 0.3 0.9 0.5 0.9 mb-md G-5 16.3 0.3 0.3 0.6 0.6 0.6

mfaoc 0-23 14.0 0.2 1.0 0.7 0.7 0.9 mb-.Auf 0-23 5.3 0.3 0.7 0.7 0.8

indaoe 0-26 15.3 0.7 0.4 0.7 1.0 0.9

mb-md 0-26 15.6 0.9 2.3 2.7 mfda0e 0-28 15.3 0.4 nab-Mdf 0-28 16.9

iAdacc H-07 15.9 0.2 0.4 0.3 0.4

mb-durf H-07 15.7 0.3 0.6 0.7 0.6 0.8

madae H-13 10.5 0.5 0.6

ab-md H-13 10.1 0.4 0.6 0.5

mrface H-16 12.6 0.9 0.5 0.9 0.7 mb-mrf 1H-16 13.5 0.2 0.7 0.8

mafi.e 1H-17 16.4 0.3 0.8 0.9 0.8 0.9 mb-mdf H-17 12.2 0.3 0.7 0.8 0.9

mrface 1-04 14.0 0.3 0.3 0.6 0.5 0.6

mb-surf 1-04 12.0 0.6 0.5 0.6 murface 1-06 10.1 0.8 0.2 0.7 1.1 0.9

mb-mdrf I-0 9.7 0.8 0.8 0.9 0.8 milace 1-09 11.1 0.9 0.4 0.8 1.20 1.5*

nab-mrf 1-09 7.5 0.3 0.6 0.6 0.8 msuface 1-10 11.2 1.5 0.9 1.20 1.1

mb-mrf 1-10 8.5 0.3 0.9 1.0 1.0

mrface J-03 9.3 0.5 0.5 0.5 mb-mdf J-03 15.1 0.5 0.9 0.9 0.8

midac• 1-09 9.9 0.7 0.3 0.7' 0.6

mb-mrf J-09 12.7 0.4 0.3 0.6 0.7 0.8 mrface K-04 15.1 0.3 0.7 0.7 0.8

sub-mdf K-04 6.4 1.0 0.8 0.9 1.40 mrface L-O3 23.60 0.50 1.3 1.0 1.1 1.6

ab-murf L-03 5.5 0.2 0.4 0.6 0.6

* Indicates remila in cxceu of off-site mean + 3s.

BA--k MeOind-ow t,-, bkmlw "-4d d . Aaovk (C) dmom ,mcts.boni 3 .aed,1 d~it~ ~hIi•o(

021595-P\S I'AMTL\FI1\OSA\DRA FTD\APP_C0D C-11 APPENDIX C

Table C4 GSA Site Gamma Exposure Rate Measurements*

Grid A B C D E F G H I J K L

2 12.8

3 12.6 14.6 19.1

4 15.3 15.1 12.5 14.6

5 10.1 15.3 14 15

6 11.8 12.5 15.4 13.4 12.3

7 10.3 12.5 13.7 16 14.7 12.6

8 11.7 12.8 16 14.2 13.1

9 14 15.7 12.9 12.3 15.6 14.1 15.1

10 13.7 13 13.2 15.3 14.9

11 13.7 14.3 14.3 15.2 13.2 13.8 12.8 12 13.6 14.7 12.8 12.2 13.6 12.1

13 13.6 15.9 13.7 11.9 12.6 14 14.4 14.7 14.3 14 13.2 10.7

15 14.8 14.1 14 13.8 14.3 13.6 11.7 10.8 16 14.2 14.7 15.5 14.6 18 13.2 12.4 12.7

17 13.7 17 17.5 15.4 17.9 14.3 12.5 12.4

18 13.5 16.4 16.4 15.8 17.3 14.4 13.5 12.8 19 14 13.3 13 12.1 16.1 14 13.8 14.3

20 14.2 12.2 12.5 12.3 18.8 13.6 13.6 14.7

21 11.3 11.6 12.3 13.8 14 16 13.9 14.4

22 12 11.4 11.5 12.7 15.7 14.4 15.2

23 13.5 12.7 13.3 13.3 12 13.8 14.5 24 13.9 12.6 12.4 13 13.2 15.2 13

25 12.5 14.4 14.6 14.8 15 15.1 14.1 26 11.5 15.2 15 14.7 14.7 13.8 12.1

021595-P\SMAMTL\FIN\GSA\DRAFTD\.A PPC. D C- 12 APPENDIX C

Table C-4 GSA Site Gamma Exposure Rate Measurements* (Continued)

Grid A B C D E F G H I J K L

27 12.4 12.5 13.6 13.7 12 11.9

28 13.1 12.3 13 13.6 12.4 12.1 14.3

29 12.7 13.1 13.5 13.3 13.8

30 13.2 13.9 12.9 13.9 15.3

31 15.5 13.1 12.8 12.3 14.4

32 13.3 13.6 13.8 13.8 14.8

33 14.4 17.9 15.9 15.5

Average dose rate uR/hr at 1 meter 13

* This sheet is the data for the gamma radiation measurements made at the GSA site in 1993. These have been ordered by grid intersection location so they can be plotted in 3D.

021595-PN['IXA MTL\FIN'OSA\DRAFTD\A PP C. D C- 13 APPENDEiX C

GSA, Bldg 235, Room 101, Floor, 1 of 2 Direct Beta Survey

15

,vJul1

50v

0

Z26101 O101 Z261 O10101 Z261 O10CF01 Z261 01:C01 Z261 01 CF01 Z261C01 0O11 Z261 01 CF01 Z26101 c0OI Z261 01 OF01 Survey Meosurement Location Codes

Direct Beta Survey Statistics

Figure C-4 GSA Building 235 floor (1 of 2) (dpm/100 cm 2)

021595- SrrmAMTL\FIN\GSA\DRAFTD\APP C.D C- 14 APPENDIX C

GSA, Bldg 235, Room 101, Floor, 2 of 2 Direct Beta Survey

15

10 g

5

AL 0

-5 I i Z261 01 OF01 Z2610101rO1 Z261 01 F0O1 Z261 O01r01 Z 26101 OF01 Z261 01 OF01 Z261 01 OF01 Z261 01 O01 Z261 01 Ol01 Survey Measurement Location Codes

Direct Beta Survey Statistics

Figure C-5 GSA Building 235 floor (2 of 2) (dpm/100 cm 2)

021595- P\SrrAMTL\FINU\GSA\DRAFTD'APP C.D C- 15 APPENDIX C

GSA, Bldg 235, Room 101, Walls Direct Beta Survey

15

10

5

C , 1 1, -,I

Z261O01OW01 Z261 01 OWOl Z26101;0W02 Z26101 0W03 Z261 01'0W04 Z261 01 OW01 Z 26101 OW01 Z261 01 0W03 Z26101 0W03 Survey Measurement Locotion Codes

Direct Beta Survey Statistics

Figure C-6 2 GSA Building 235 walls direct measurement results (dpm/100 cm )

a21595- mrr\A MTL\FINMGSA\DRA FTDAPP_C D C- 16 APPENDIX C

GSA, Bldg 235, Room 101, Ceiling Direct Beta Survey

15

10 9

5

- 5 ' I I I r I Z261 01 0001 Z261 01 0001 Z261010C01 Z261 010C01 Z261 01 0002 Z261 01 0001 Z261010(01 Z261 01 0001 Z261010C02 Survey Measurement Locotion Codes

Direct Beta Survey Statistics

Figure C-7 GSA Building 235 ceiling direct measurement results (dpm/100 cm 2)

0C21595-P\'rfAMTL\FINOSA\DRAFTD\APP C D C-17 APPENDIX C

GSA, Bldg 235, Room 101, Vents Direct Beta Survey

15

10 g

5

-5 1 Z26101 OV01 Z261 01 OVol Z261 01 OVOI Z261 01 0V03 Z261010V01 Z261010V01 Z261010V02 Survey Meosurement Location Codes

Direct Beta Survey Statistics

Figure C-8 GSA Building 235 vents direct measurement results (dpm/100 cm 2)

021595- rrI'•AMTLFIN'GSA\DRAFrD\APP_C. D C-18 .APPENDIX C

GSA, Bldg 235, Room 101, Structures Direct Beta Survey

15

10 g

5

-5, . ,...... ,,• -•l . .. • ,., .,. . , ....J...1.....

Z261 01 0501 Z261 010S06 Z 26101O009 Z261 010513 Z261 010S15 Z26101 0503 Z26101 0S07 Z261010S12 Z261 010S1 4 Survey Meosurement Locotion Codes

Direct Beta Survey Statistics

Figure C-9 2 GSA Building 235 structures direct measurement results (dpm/100 cm )

021595-PSrr\AMTLAFI•OSA\DRAFTD',APPC. D C- 19 APPENDIX C

GSA, Eldg 237, Room 100, Floor Direct BE•ta Survey

15

10

ip

Z281000FO1 Z281000F01 Z281000F01 Z28100l Ol Z28100CF01 Z28100001 Z28100CF01 - Z28100CF01 Z28100(C01 Survey Meosurement Locotion Codes

Direct Beta Survey Statistics

Figure C-10 GSA Building 237 floor direct measurement results (dpm/100 cm 2)

021595 -MSR'A MTL\FIN\GSA\DRA FrDA PPC. D C-20 APPENDIX C

GSA, Bldg 237, Room 100, Walls Direct Beta Survey

15

10 g

5

0

-51 r .. --- ....---- .... - 11--'.. .--- . . Z281000W01 Z281X00WO1 Z281 00V02 Z281 00w03 Z281000W04 Z281 00OW01 Z281 00OW01 Z281 000W03 Z281 000W03 Survey MeVo.srement Location Codes

Direct Beta Survey Statistics

Figure C-Il GSA Building 237 walls direct measurement results (dpm/100 cm 2)

021595- P•\I'AMTL\FIhJOSA\DRAFTD\APPC.D C-21 APPENDIX C

GSA, Bldg 237, Room 100, Ceiling Direct Beta Survey

15

10

5

Z2B1000CO1 Z281000CO1 Z281000CO1 Z281000C02 Z28100OC02 Z281000C01 Z281000C01 Z281000C01 Z281000C02 Survey Measurement Location Codes

Direct Beta Survey Statistics

Figure C-12 2 GSA Building 237 ceiling direct measurement results (dpm/100 cm )

021595-P•ITAMTL\FrN\GSA\DRAFTD'APP_C D C-22 APPENDIX C

GSA, Bldg 235, Room 101, Floor Gamma uR/hr at 1 Meter

35

30

25

20

15

10

5

0 Z261 010F:0l Z261 01 F011 Z261 01 0F01 Z261 01 X001 Z261 01 OF01 Z261 01 C0I1 Z261 01 Ot'1 Z261 01 0F01 Z261 01 CF01 Survey Measurement LocatKon Codes

Gamma Survey Statistics

Figure C-13 GSA Building 235 floor gamma exposure rate results (uR/hr)

021595-MPSTlA MTL\FIN\0SA \D RA FTDA PPC. D C-23 APPENDIX C

GSA, Bldg 235, Room 101, Walls Gamma uR/hr at 1 Meter

35

n•

RP -11.R..I, pN~mmonI IpNIWR Z 26101 OW01 Z 26101 OW01 Z 26101 0W02 Z 26101 0w03 Z261 01 0W04 Z261 01 OW01 Z261 01 OWO1 Z26101 0W03 Z261 01 0W03 Survey Meosurement Location Codes

Gamma Survey Statistics

Figure C- 14 GSA Building 235 walls gamma exposure rate results (AR/hr)

tU21595 C•sfI\AM'II\IINGIA\I)RAI-'IY•PP" I1) C-24 APPENDIX C

GSA, Bldg 235, Room 101, Ceiling Gamma uR/hr at 1 Meter

35

30

25

LUJ 15

10

5

0 Z261 01 C01 Z261010CO1 Z261 O10C01 Z261 010C01 Z261O10COI Z26101(201 Z261010C01 Z261010C01 Survey Meoasurement Location Codes

Gamma Survey Statistics

Figure C- 15 GSA Building 235 ceiling gamma exposure rate results (tLR/hr)

(Y21591P',SI-5AMTI.TMIN(;.'A DRAJ'I D) ANI' C I1 C -25 APPENDIX I-

GSA, Bldg 235, Room 101, Vents uR/hr at 1 Meter Gamma /

35

25

20 ck

Z26101 OV01 Z26101OV0I Z261 01 OVO1 Z26101 0V02 Z26101 OVOl Z261 10VO1 Z261 O10V02 Z261 010V03 Survey Meosurement Locotion Codes

Gamma Survey Statistics

Figure C- 16 GSA Building 235 vents gamma exposure rate results (j.R/hr)

1r21 S,5 PmSn\AMTI.\P1N\(iSAIJHRAV. DhA|I' C-1)I) C-26 APPENDIX C

GSA, Bldg 237, Room 100, Floor Gamma uR/hr at 1 Meter

Of:3

0' Z281000O1 Z28100FO01 Z281000FOl Z2810(X001 Z28100CF01 Z28100X0OI Z2810(C0OI Z281000FO1 Z28100X0F1 Survey Mesurernent Locotion Codes

Gamma Survey Statistics

Figure C-17 GSA Building 237 floor gamma exposure rate results (txR/hr)

(129S P'£pDM ITI 'C(DA\)RAk-AFp " I) C-27 APPENDIX C

GSA, Bldg 1237, Room 100, Walls Gamma uR/hr at 1 Meter

0 Z281000W01 Z28100OW01 Z281000W03 Z281 00W03 Z281000W01 Z 281 000W01 Z281 000W03 Z 281 00W03 Survey Meosurement Location Codes

Gamma Survey Statistics

Figure C-18 GSA Building 237 walls gamma exposure rate results (p4R/hr)

(P2Is5. P.IMAMTI.ýFl-N'.(;SA\I)ftAIr-TI),rA'P C C7-28() APPENDIX C

GSA, Bldg ý•37, Room 100, Ceiling Gamnma uR/hr at I Meter

-c

Z281 0001CO Z281000C01 Z2810CX0CO1 Z281000C01 Z281000C01 Z281000C01 Z281000COI Z281000Cl01 Survey Meosurernent Location Codes

Gamma Survey Statistics

Figure C-19 GSA Building 237 ceiling gamma exposure rate results (p.R/hr)

f215 .1.'SrPAWMTI.\FIN'WSA,.I)RAFFI)'APP C 1) C -2-9 APPENDIX C

GSA, Bldg 235, Anne> ýý-~ Vk-~ PENI C- Direct Beta Survey

I-') I

10

5

ch,1111ijkli . ARi i A" I UMftUj'.A - , 1- 11 ý ý. 'A .1 4 0 I WTTJ IVTI-- IT - ---r - t, -

l Z261 01 F"01 Z26101 CF01 Z261 01 0F01 Z261 01 F01 Z26101 OW01 Z26101 FO1 Z261010101 Z261010FOl Z261 01 OW01 Survey Meosurement Location Codes

Direct Beta Survey Statistics

Figure C-20 GSA Building 237 Annex resurvey direct measurement results (dpm/100 cm 2)

1W21595- P'SII',AM' I J IN',( AI)RAI'ATI)APP C 1) C-30 APPENDIX C

Direct Beta Survey Statistics

Figure C-21 GSA Building 653 pumphouse direct measurement results (dpm/100 cm 2)

(421•9 I•,fsrr'AMiI I INg,.A I)RAI I},,PP ( I) C-31 APPENDIX C

(A\ lBl(lg 653, Pumnp Iloit.se ('-,innia uR/hr at 1 Meter

25

20 C% :3 15

10

5

0. Z29100X•FO1 Z291000S02 Z291 000W02 Z 291 000W03 Z29100OW044 Z291000FO1 Z291 00OW01 Z 291 000W03 Z 291 000W04 Survey Measurement Location Codes

Gamma Survey Statistics

Figure C-22 GSA Building 653 pumphouse gamma exposure rate results (fiR/hr)

1009 f", I"PAM I I 'IIN ; ,A I I RA Ii X1i' ( I) C- 32 i(

APPENDIX C

Figure C-23. Soil boring locations, 1993, 1994, including wells

iý'P ý',IMII I IN 6S&\ DRAFTDIAPI' U"D C-33 APPI x C

Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCi/g)

497000 '695000 + + Concentration - PCi/g Northing Easting

Land Sand Mass Sample Sample Survey Massachusets Grid Elevation Estimated Corrected Estimated Fraction of Limit File Number grams ID I Sample ID 2 ID 3 Point Feet Ra-226 Th-234 U-235 Material

GSAOSISs 1201 Burn Pit Bore 32 No. 1 0.1 57.0 1.09 DU 239

GSA0523S 328 Burn Pit Bore 32 No. 2 6.1 75.6 1.44 U+d 15.87

GSA0524S 943 Burn Pit Bore 32 No. 3 2.2 35.0 0.67 U+d 7.28 DU 1.49 GSA0525S 261 Burn Pit Bore 32 No. 4 -11.2 35.6 0.68 0.73 GSA0526S 160 Bum Pit Bore 32 No. 5 -5.5 17.5 0.33 DU DU 1.04 GSA0527S 132 Bum Pit Bore 32 No. 6 -7.8 24.7 0.47

GSAO519S 1113 Bum Pit Bore 33 No. 1 1513 292.7 125.2 7.6 -25.6 81.4 1.55 DU 3.42 DU 1.79 GSA0522S 981 Burn Pit Bore 33 No. 2 1513 292.7 125.2 7.6 -13.4 42.5 0.81 0.36 GSA0520S 1638 Burn Pit Bore 33 No. 3 1513 292.7 125.2 7.6 0.3 8.7 0.16 DU

GSAO533S 635 Burn Pit Bore 33 No. 4 1513 292.7 125.2 7.6 -3.0 9.7 0.18 DU 0.41

GSA0528S 134 Bum Pit Bore 33 No. 5 1513 292.7 125.2 7.6 3.0 -9.7 -0.13 U+d -1.65

GSA0521S 950 Bum Pit Bore 34 No. 1 -29.0 92.2 1.76 DU 3.87

GSA0529S 395 Bum Pit Bore 34 No. 2 -17.2 54.8 1.04 DU 2.30

GSAO53OS 751 Bum Pit Bore 34 No. 3 2.6 31.0 0.59 U+d 6.52

GSAO53IS 524 Bum Pit Bore 34 No. 4 4.0 12.2 0.23 DU 0.51

021595- P\SFLA MTL\FIN\OSA\DRAFTD\A PPC D C-34 ( ( APPF

Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCi/g) (Continued)

497000 695000 + + Concenration - PCUS Norhing Easting Sand I Land Sand Mass Sample Saimple Survey Massachusetts Grid EJevation Estirmated Corrected Estimated Fraction File Number grams ID I Sample ID 2 ID 3 Point Feet Ra-226 Th-234 U-235 Material of Limit

GSA0532S 282 Burn Pit Bore 34 No. 5 -4.0 12.6 0.24 DU 0.53

GSA0536S 1224 Burn Pit Bore 35 No. 1 1520 297.7 142.6 7 -11.4 63.0 1.20 DU 2.65

GSA0535S 571 Burn Pit Bore 35 No. 2 1520 297.7 142.6 7 0.2 41.6 0.79 DU 1.75

GSA0534S 1431 Burn Pit Bore 35 No. 3 1520 297.7 142.6 7 1.7 14.0 0.27 U+d 2.99

GSA0538S 616 Burn Pit Bore 35 No. 4 1520 297.7 142.6 7 10.5 -1.4 -0.03 U+d 0.77

GSA054OS 144 Burn Pit Bore 35 No. 5 1520 297.7 142.6 7 18.5 13.0 0.25 U+d 4.47

GSA054IS 1731 Burn Pit Bore 36 No. 1 -0.8 2.5 0.05 DU 0.10

GSA0537S 97 Burn Pit Bore 36 No. 2 33.4 -6.5 -0.12 U+d 2.01

GSA0542S 490 Burn Pit Bore 36 No. 3 6.8 5.4 0.10 U+d 1.77

GSA0543S 302 Burn Pit Bore 36 No. 4 11.8 3.7 0.07 U+d 1.93

GSA0539S 145 Burn Pit Bore 36 No. 6 17.2 6.3 0.12 U+d 3.00

GSA0544S 1267 Burn Pit Bore 37 No. 1 1514 315.6 131.4 8 1.8 5.3 0.10 U+d 1.25

GSA0550S 548 Burn Pit Bore 37 No. 2 1514 315.6 131.4 8 4.0 1.6 0.03 U+d 0.71

GSA0547S 1174 Burn Pit Bore 37 No. 3 1514 315.6 131.4 8 0.1 -0.3 -0.01 U+d -0.05

GSA0546S 1068 Burn Pit Bore 37 No. 4 1514 315.6 131.4 8 0.1 -0.4 -0.01 U+d -0.07

021595S-P\SI''AMTL\FI!•GSA\DRAF'TD\APP_C D C-35 APPE -C

Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCi/g) (Continued)

497000 695000 + + Concentration - pci/g Nodhing Esaing_ L.And Sand Corteted Estimated Fraction Mass Sample Sample Survey Massachusetts Grid Elevation Eatimated Feet Ra-226 Th-234 U-235 Material of Limit File Number grama ID I Sample ID 2 ID 3 Point 131.4 8 4.6 0.5 0.01 U+d 0.56 GSA0551S 467 Bu_ Pit Bore 37 No. 5 1514 315.6 0.03 U+d 0.63 GSA0552S 860 Burn Pit Bore 37 No. 5A 1514 315.6 131.4 8 3.2 1.5

6.8 0.0 0.0 0.00 DU 0.00 GSA0545S 1658 Bum Pit Bore 38 No. 1 1519 303.8 152 6.8 0.3 -1.1 -0.02 U+d -0.18 GSA0561S 719 Burn Pit Bore 38 No. 2 1519 303.8 152 152 6.8 -1.0 3.3 0.06 DU 0.14 GSA0574S 1359 Bum Pit Bore 38 No. 3 1519 303.8 6.8 -0.1 0.2 0.00 DU 0.01 GSA0548S 670 Bum Pit Bore 38 No. 4 1519 303.8 152 6.8 4.7 2.5 0.05 U+d 0.97 GSA0563S 287 Bum Pit Bore 38 No. 5 1519 303.8 152 6.8 4.2 -1.4 -0.03 U+d 0.14 GSA0549S 620 Bum Pit Bore 38 No. 6 1519 303.8 152 -27.9 88.9 1.69 DU 3.73 GSA0558S 1177 Bum Pit Bore 39 No. 1 1521 296.1 144.6 7.6 -24.7 78.6 1.50 DU 3.30 GSA0562S 404 Bum Pit Bore 39 No. 2 1521 296.1 144.6 7.6 7.6 2.2 14.3 0.27 U+d 3.11 GSA0557S 1213 Bum Pit Bore 39 No. 3 1521 296.1 144.6 7.6 5.9 7.7 0.15 U+d 2.14 GSA0585S 486 Burn Pit Bore 39 No. 4 1521 296.1 144.6 9.8 0.19 DU 0.41 GSA0582S 246 Bum Pit Bore 39 No. 5 1521 296.1 144.6 7.6 -3.1 8.1 -25.6 81.5 1.55 DU 3.42 GSAO060S 1302 Burn Pit Bore 40 No. 1 1512 289.5 119.8 -0.7 2.3 0.04 DU 0.10 GSA0579S 1660 Bum Pit Bore 40 No. 2 1512 289.5 119.8 8.1

U21595-.MSfTA MTL\FIMJSA\DRA FTD\A PP_C. D C-36 ( ( ( APPIF ( Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCi/g) (Continued)

497000 695000 + + Conentration - pci/S Northing Easting

LAnd Sand Mass Sample Sample Survey Massachusen- Grid Elevation Esimated Cofetetd Estimated Fraction File Number grama ID I Sample ID 2 ID 3 Point Feet Ra-226 Th-234 U-235 Material of ULmit

GSA0559S 1401 Burn Pit Bore 40 No. 3 1512 289.5 119.8 8.1 1.0 6.2 0.12 DU 0.26

GSA0566S 1127 Bum Pit Bore 40 No. 4 1512 289.5 119.8 8.1 2.4 -0.4 -0.01 U+d 0.17

GSA0571S 773 Bum Pit Bore 40 No. 5 1512 289.5 119.8 8.1 3.4 2.4 0.05 U+d 0.83

GSA0594S 1065 Burn Pit Bore 41 No. 1 1518 317.3 164.1 7.5 -54.2 172.6 3.29 DU 7.25

GSAO573S 1379 Burn Pit Bore 41 No. 2 1518 317.3 164.1 7.5 0.0 -0.1 0.00 U+d -0.02

GSA0577S 512 Bum Pit Bore 41 No. 2 1518 317.3 164.1 7.5 0.6 -1.9 -0.04 U+d -0.32

GSA0602S 1255 Burn Pit Bore 41 No. 3 1518 317.3 164.1 7.5 0.1 -0.2 0.00 U+d -0.04

GSA0575S 991 Burn Pit Bore 41 No. 4 1518 317.3 164.1 7.5 0.2 -0.5 -0.01 U+d -0.09

GSA0569S 897 Burn Pit Bore 41 No. 5 1518 317.3 164.1 7.5 0.2 -0.7 -0.01 U+d -0.12

GSA0565S 934 Burn Pit Bore 41 No. 6 1518 317.3 164.1 7.5 0.2 -0.6 -0.01 U+d -0.11

GSA0592S 261 Burn Pit Bore 41 No. 7 1518 317.3 164.1 7.5 1.4 -4.5 -0.09 U+d -0.77

GSA0568S 1125 Burn Pit Bore 42 No. 1 1517 327.7 132.9 7.8 0.1 -0.4 -0.01 U+d -0.06

GSA0570S 375 Burn Pit Bore 42 No. 2 1517 327.7 132.9 7.8 7.0 -1.1 -0.02 U+d 0.47

GSA0567S 1372 Burn Pit Bore 42 No. 3 1517 327.7 132.9 7.8 0.0 -0.1 0.00 U+d -0.03

GSA0564S 1578 Burn Pit Bore 42 No. 4 1517 327.7 132.9 7.8 0.0 0.0 0.00 U+d 0.00

021S95-P\SIT•A MTL\FINO(SA13DRAýTDýAPP_(" D) C-37 APPI x C

Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCl/g) (Continued)

497000 695000 + + Conciratno - pci/s Nothing Enfring_'_ _

Land Sand C;octed Estimated Fraction Mass Sample \ Sample Survey Massachusetts Grid Elevation Estimated Ra-226 Tn-234 U-235 Material of Limit File Number gramn [1 1 Sample ID 2 ID 3 Point Feet

8.4 -4.6 -0.09 U+d -0.08 GSAO597S 259 Burn Pit Bore 42 No. 5 1517 327.7 132.9 7.8 -1.4 24.6 0.47 DU 1.03 GSA0583S 1181 Bum Pit Bore 43 No. 1 1516 322.8 109.2 8.6 3.0 14.3 0.27 U+d 3.18 GSA0589S 634 Bum Pit Bore 43 No. 2 1516 322.8 109.2 8.6 2.1 13.1 0.25 U+d 2.86 GSA0595S 848 Bum Pit Bore 43 No. 3 1516 322.8 109.2 8.6 8.6 4.4 -0.5 -0.01 U+d 0.35 GSA0587S 1056 Burn Pit Bore 43 No. 4 1516 322.8 109.2 11.4 -0.4 -0.01 U+d 1.06 GSA0612S 235 Burn Pit Bore 43 No. 5 1516 322.8 109.2 8.6 8.8 2.2 6.8 0.13 U+d 1.59 GSA0581S 1486 Bum Pit Bore 44 No. 1 1510 279.5 101.1 0.0 0.1 0.00 DU 0.00 GSA0598S 1727 Bum Pit Bore 44 No. 2 1510 279.5 101.1 8.8 0.0 0.0 0.00 U+d 0.00 GSA0586S 1551 Bum Pit Bore 44 No. 3 1510 279.5 101.1 8.8 5.9 -1.3 -0.03 U+d 0.32 GSA0596S 643 Bum Pit Bore 44 No. 4 1510 279.5 101.1 8.8 7.7 0.15 DU 0.32 GSA0593S 1230 Bum Pit Bore 44 No. 5 1510 279.5 101.1 8.8 -2.4 1.3 0.02 DU 0.05 GSA0591S 219 Bum Pit Bore 44 No. 6 1510 279.5 101.1 8.8 -0.4 104.9 2.00 DU 4.41 GSA0611S 356.1 Bum Pit Pit Bottom 1 No. 1 1522 300.1 139 8.3 -33.0 129.3 2.46 DU 5.43 GSA0683S 880.8 Burn Pit Pit Bottom 2 No. 1 1523 298.7 140.4 8.3 -30.4

140.4 8.3 7.9 10.2 0.19 U+d 2.84 GSA0614S 287.3 Bum Pit Pit Bottom 2 No. 2 1523 298.7

021595- P\SIA MTL\FN•OSA\DRA FTD'A PP_C. D C-38 ( ( APPE n Table C-5 Soil Bore Samples Gamma Spectroscopy Analyses Results (pCi/g) (Continued)

497000 695000 + + Concentrtion - pCi/g Noflhing Eaating

Land Sand Fraction Mass Sample Sample Survey Masaachusetts Grid Elevation Estimated Cortected Estimated of Limit File Number grams ID I Sample ID 2 ID 3 Point Feet Re-226 7n-234 U-235 Material

2.54 GSA0588S 513 Burn Pit Pit Bottom 3 No. 1 1524 297.5 135.5 8.4 -19.0 60.5 1.15 DU 5.02 GSA0608S 358.1 Burn Pit Pit Bottom 4 No. 1 1525 300.1 134.1 8.4 7.0 21.4 0.41 U+d 1.50 DU 3.30 GSA0613S 106.1 Burn Pit Pit Bottom 4 No. 2 1525 300.1 134.1 8.4 -24.7 78.6 DU 6.39 GSA0600S 853 Burn Pit Pit Bottom 12 No. 1 -47.8 152.2 2.90 2.21 DU 4.88 GSA0572S 376 Burn Pit Pit Wall 5 No. 1 1526 301 135.2 8.4 -36.5 116.1 U+d -0.21 GSA0578S 671 Bum Pit Pit Wall 8 No. 1 1529 295.9 137 8.4 0.4 -1.2 -0.02 DU 3.85 GSA0590S 290 Burn Pit Pit Wall 9 No. 1 1530 296.7 139.1 8.4 -15.4 91.6 1.75 2.96 GSA0609S 542.5 Burn Pit Pit WalllO No. 1 1531 298.9 140 8.3 -22.1 70.4 1.34 DU DU 2.28 GSA0610S 550 Burn Pit Pit Wall I No. 1 1532 301 139.2 8.3 -17.1 54.3 1.03 _ _ - 1.- m---ws1. -.

C-39 (7 1) O2tS9S021595- p\SrThAMTt.\FtN\OSA\DRAFTD\APP\SIT\A MTI.\FI•G\SA\DRA FrD\APP C D) C-39 APPENDIX C

Burn Pit In Situ Gamma Spectroscopy and Surface Soil Samples

FENCE FS FS1F ...... * A......

FS47 . F? ikFS49 FS4F FS0 FS25 ~ FS27 AFS50 FS21 E

FS28

F FS19 D

FS51 tI ASSc

AS35 FS3? A ESS? A FS341 FS52 FS2 33 B

FS53 A A so

A , .- '' A ...... F...... F5731 ...

24 25 26 27 28

LEGEND

A Soil Sample only 0 In Situ Measurement and Soil Sample II

Figure C-24. Burn pit locations for in situ measurements and soil samples

(U21595 P \FII\(ISA\DRA-TI) AI' CMT'CMTI" (4 C-40 APPEV

Table C-6 Burn Pit - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (pCi/g)

Coocentration - pCQS 497000 695000 + + Sawd Eatima•d lNrwction File Masi Sample Sample Sample Land Nor'thing FAtin"g Elevation Estimated Correced Th-234 U-235 Material of Limit Number gram [D) ID 2 ID 3 Survey Fed Ra-226 Point MaesachuaeUt Grid

6.7 0.13 DU 0.28 GSA0685S 1734 Burn Pit FS-20 1506 259.5 71.3 a -2.1

3.2 11.4 0.22 U+d 2.63 GSA0687S 1690 Burn Pit FS-21 1509 274.1 95.8 9

0.6 24.9 0.48 U+d 5.10 GSA0689S 1671 Burn Pit FS-22 1503 192.6 226.2 7.8

2.5 14.5 0.21 U+d 3.19 GSA0691S 1636 Burn Pit FS-23 1505 230.3 9".6 3.7

-26.5 34.4 1.61 DU 3.54 GSA0693S 1281 Burn Pit FS-24 1537 325.9 77.2 7.9

7.3 2.0 11.3 0.23 U+d 2.59 GSAO695S 1218 Burn Pit FS-25 1515 311 120.4

4.0 7.9 0.15 U+d 1.99 GSA0764S 962.2 Burn Pit Surface FS-27 1712 369.2 149.3 7.4 Soil

-1.5 4.9 0.09 DU 0.20 GSA0762S 396.3 Burn Pit Surface FS-23 1713 335.6 177.3 7.7 Soil

7.9 2.0 4.2 0.01 U+d 1.05 GSA076OS 1097 Burn Pit Surface FS-29 1714 302.8 213.7 Soil

7.7 -1.7 5.5 0.11 DU 0.23 GSA0758S 882 Burn Pit Surface FS-30 1715 270.9 231.7 Soil

203.3 8.1 1.4 32.3 0.61 U+d 6.65 GSA0752S 1253 Burn Pit Surface FS-31 1716 246.9 Soil I

231.4 8 1.3 16.1 0.31 U+d 3.43 GSA0750S 1242 Burn Pit Surface FS-32 1717 219.5 Soil I I II

021595 -PSIr\A MTL\FIN\OSA\DRA FTMDXAPP_C. D C-41 APPE" ' C

Table C-6 Burn Pit - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (pCin/) (Continued)

/Co¢ntertioo - pCi/g

497000 695200 + + sand File Mass Sample Sample Sample Land Northing Eauting Elevation Etimated Correnid Estimated Fraction Number grams ID 1 ID 2 ID 3 Survey Fed Ra-226 Th-234 U-235 Mateial of Limit Point Massachusaett Grid

GSA074SS 997 Burn Pit Surface FS-33 1718 204.5 248.8 8.1 -3.0 9.5 0.15 DU 0.40 Soil I

GSA0754S 1007 Burn Pit Surface FS-34 1719 223 244. 8 0.2 4).5 -0.01 U+d 4).09 Soil

GSA0756S 1289 Burn Pit Surface FS-35 1720 232.7 233.7 8.1 2.2 7.8 0.15 U+d 1.79 Soil

GSA0774S 829.9 Burn Pit Surface FS45 1711 338 58.4 7.5 -1.0 3.2 0.06 DU 0.13 Soil

GSA0772S 584 Burn Pit Surface FS-46 1710 313.6 37.1 7.7 -3.1 9.7 0.19 DU 0.41 Soil

GSA0770S 923 Burn Pit Surface FS-47 1709 281.2 5.8 7.7 0.2 4-.6 4-.01 U+d 40.11 Soil I

0.00 GSA0767S 1839 Burn Pit Surface FS-48 1708 239.4 35.9 8.4 0.0 0.1 0.00 DU Soil

GSA0768S 1743 Burn Pit Surface FS-49 1707 231.1 8.1 8.3 4).9 2.9 0.05 DU 0.12 Soil

40.02 GSA0776S 1393 Burn Pit Surface FS-50 1706 209.8 51.2 8.3 0.0 40.1 0.00 U+d Soil

0.00 GSA0778S 1647 Burn Pit Surface FS-51 1705 171.6 114.6 8.7 0.0 0.0 0.00 DU Soil 1

GSA078OS 1865 Bum Pit Surface FS-52 1704 138.1 172.1 8.1 2.2 4.9 0.09 U+d 1.20 Soil I IIIII

021595-P\SIT\AMTL\FIN\GSA\DRAFTD\APPC D C-42 ( C APPENT

Table C-6 Burn Pit - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (pCi/n) (Continued)

I I I Concentnrtion - pCi/g 497000 695000 + + Suod File Mass Sample Sample Sample Land No1nhing Eastin Elevation Eatimisd Corrcted Eaimm dFracton Number grams ID 2 ID 3 Survey Feet Ra-226 Th-234 U-235 Material of Limit Point Massachuseatt Grid

GSA0782S 1707 Burn Pit Surface FS-53 1703 190.2 246.4 7.8 -1.2 3.9 0.07 DU 0.16 Soil

GSA08i6S 652 AreaA25_A28 Surface FS-70 0.4 -1.3 -0.02 U+d -0.22 Soil

GSA08I8S l011 Area A25A29 Surface FS-71 2.1 26.0 0.49 DU 1.09 Soil I

GSA0820S 1032 Area A23A28 Surface FS-72 -1.2 4.0 0.06 DU 0.17 Soil I I I _ 1

GSA0622S 890 Area A25A28 Surface FS-73 3.5 15.3 0.29 U+d 3.44 Soil

C-43 C I) (Y2159O2Ii9S 5- P\Srr\AP\SIT'AMTL\FIN\tTISA\DRAFTD'.APP M'"L\ FIN\,GSA \ DRA FrD\APP_(" 1) C-43 APPENT C

Table C-7 Burn Pit - Bulk Soil Samples Gamma Spectroscopy Sample Analyses Results (pCl/g)

Concentration - pCi/g

497000

Sand Land Northing EUlwnsg Corrctod Estimted Fraction Sample Sample Survey Elevation F3timat4d File Mass Sample Th-234 U-235 Material of Limit ID 2 ID 3 Point Massachusetta Feet RA-226 Number grams ID I

Sample #I Lower 1508 279.5 93.3 9.9 0.0 0.1 U.UU iVU U.VV Bum Pit GSA0706DD 1780 Coarse 0.00 DU 0.00 Sample #I Lower 1508 279.5 93.3 8.8 0.0 0.1 Bum Pit GSAO708DD 1702 Fines 0.00 DU 0.01 Semple # I Lower 1508 279.5 93.3 8.8 0.0 0.1 Pit GSAO707DD 1901 Bum Middlinq 32.37 DU 72.48 Sample # I Upper 1508 279.5 93.3 8.8 -542.4 1725.8 GSA0727S 2.5 Bum Pit 0.00 DU 0.00 Semple #I Upper 1508 279.5 93.3 8.8 0.0 0.0 1685 Bum Pit GSA0703DD Coarse 1.85 93.3 8.8 2.0 3.2 0.16 U+d HIl Upper 1508 279.5 GSA0705DD 1481 Burn Pit :S a :pmf le 0.00 DU 0.00 Sample # 1 Upper 1508 279.5 93.3 8.8 0.0 0.1 GSA0704DD 1754 Burn Pit Middlin 1g0 0.62 Semple #2 Lower 1507 266.5 66.4 7.9 6.0 0.1 0.03 U+d 1800 Burn Pit GSA0712DD Coarse 1.66 Sample #2 Lower 266.S 66.4 2.9 6.6 0.13 U+d Burn Pit 1507 GSA0714DD 1738 Fines 0.05 0.65 Sample #2 Lower 1507 266.5 66.4 7.9 1.3 2.6 U+d GSA0713DD 1936 Bum Pit Middlierigs .1 ____ 1 1 4 1 t I I 0.39 7.9 3.8 0.0 0.00 U+d Semple #2 Upper 1507 266.5 66.4 7.9 3.8 0.0 0.00 U+d 0.39 1695 Bum Pit GSA0709DD Coarse 1 .1 1 9 1 1 I 1.48 7.9 2.5 6.1 0.12 U+d 1507 1.48 Sample #2 Upper 266.5 66.4 7.9 2.5 6.1 0.12 U+d GSA071IDD 1602 Burn Pit - L Fines 1 ______.1 1 1

C-44 (Y21595- P\SITA MTL\FINGSA\DRAFTD\A PP_C. D ( ( APPEN

Table C-7 Burn Pit - Bulk Soil Samples Gamma Spectroscopy Sample Analyses Results (pCi/g) (Continued)

Concentraton - pCi/l 497000 • + 695000 + Land Northing Eastin Sand Eimnated Corrected Etimated Fraction File Mass Sample Sample Sample Survey Elevation Ra-226 Th-234 U-235 Materwa of Limit Number grams ID I ID 2 ID 3 Point Masuchuetts Grid Feet

7.9 -0.9 2.9 0.06 DU 0.12 GSA071ODD 1914 Bum Pit Sample 12 Upper 1507 266.5 66.4 Middlings

4.0 0.1 0.00 U+d 0.42 GSA0718DD 1734 Bum Pit Sample #3 Lower 1504 191.9 230.9 7.4 Coarse

7.4 0.0 0.1 0.00 DU 0.00 GSA0720DD 1721 Bum Pit Sample #3 Lower 1504 191.9 230.9 Fines

3 7.4 0.0 -0.1 0.00 U+d -0.02 GSA0719DD 1400 Bum Pit Sample # Lower 1504 191.9 230.9 Middlings

0.2 -0.5 -0.01 U+d -0.09 GSA0715S 1022 Bum Pit Sample #3 Upper 1504 191.9 230.9 7.4 Coarse

-33.1 121.1 2.31 DU 5.09 GSA0717DD 1837 Bum Pit Sample #3 Upper 1504 191.9 230.9 7.4 Fines

7.4 3.6 4.7 0.09 U+d 1.32 GSA0716S 1690 Bum Pit Sample #3 Upper 1504 191.9 230.9 Middlings

C-45 B 021595-021595 P\SrTAP\SIT\AMTL\FIN\OSA\DRAFTD\APPC MTI"L\ FIN\GSA\DRA F-lMDA PP_C. D C-45 APPENDIX r I Table C-8 Burn Pit In Situ Gamma Spectroscopy Results Fraction of Limit

Results Calculated

Location Code Material (pci/g) (pCiogn Fraction of Limit

FS-20 U+d 10.3 3.7 1.03 0.39 FS-21 DU 3.6 13.610.5 2.9 0.30 DU FS-22

FS-23 DU 13.1 3.6 0.38 FS-24 DU 18.7 4.7 0.53 FS-25 DU 12.3 3.3 0.35

I

021595- P\SIFlSA MTLFMSA \DDRA FTMA pp +.D C-46 (

APPENDIX C

GSA Site In Situ Gamma Spectroscopy and Surface Soil Samples

G

F

E

LEG END D

A SOIL SAMPLE ONLY 0 IN SITU MEASUREMENT AND SOIL SAMPLE C SCI IAIACI EfIZATION SCAN OF AREAS COMPLETED B

A

16 17 18 19 20 21 22 23 24 25 26 27 28

r tigure C-25. Locations of in situ and soil samples in the Bum Pit and Clinker Areas

021595-PýSIT\AMTL\FtN\OSA\DRAFrD\APPC D C-47 APPF X C

Table C-9 Clinker Area - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Fraction of Limit

497000 695O00 Coceardih. - pCi/t

Nothing Easiag A

Land Musachuset•s saw Estimatel PfEmtion File Mas Sample Sample Sample Survey Elevation Estimated Corrected U-235 Material o" Limit Number grums ID I ID 2 ID 3 Point Feet Ra-226 Th-234

0.51 U+d 5.55 GSA0697S 1077 Clinker surface FS-26 1.9 26.6 Area Soil

-o.1 0.00 U+d 0.55 GSA0786S 1387 Clinker Surface FS-55 5.8 Area Soil

0.2 0.00 DU 0.01 GSA0788S 2027 Clinker Surface FS-56 -0.1 Area Soil

9.8 0.19 U+d 2.23 GSA079OS 1657 Clinker Surface FS-57 2.5 Area Soil

0.0 0.00 U+d -0.01 GSA0792S 1535 Clinker Surface FS-58 0.0 Area Soil

0.00 U+d -0.01 GSA0794S 1538 Clinker Surface FS-59 0.0 0.0 Area Soil GSA0796S 1378 Clinker Surfce FS-60 0.0 -0.1 0.00 U+d -0.02

Are~a Soil I _70001 Surface FS-61 GSA0799S 1754 Clinker 00 U00 Area Soil GSA0800S 1225 Clinker Surface FS-62 5.0 19,5 0.37 U+d 4.43 Area Soil______t S i 5 .0 20.5 0.37 DUd 0.43

GSA0802S 1626 Clinker Surface FS-63 0.0 20.1 0.80 DU 0.85 Area Soil

021595-P\SIT\AMTL\FIN\OSA\DRAFiTDAPP_C.D C-48 ( ( APPE?

Table C-9 Clinker Area - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Fraction of Limit (Continued)

497000 695000 CooMa6,oo - pCiig + + Northing I _Eautiq

Land Massachusas Grid sand File Mass Sample Sample Sample Survey Elevation Estimtod Correctad Eatimawl Ptuctiom Number grams ID 1 ID2 ID 3 Point Feet Ra-226 Th-234 U-235 Material of Limit

GSA0697S 1077 Clinker Surface FS-26 1.9 26.6 0.51 U+d 5.55 Area Soil

GSA0804S 1730 Clinker Surface FS-64 3.0 36.9 0.97 U+d 7.73 Ame Soil I

GSA0806S 1471 Clinker Surface FS-65 7.9 25.7 0.49 U+d 5.98 Area Soil

GSA0808S 1612 Clinker Surface FS-66 4.8 0.0 0.00 U+d 0.48 Area Soil

GSA08 1OS 1396 Clinker Surface FS-67 0.0 -0.1 0.00 U+d -0.02 Area Soil

GSA08I2S 1396 Clinker Surface FS-68 0.0 -0.1 0.00 U+d -0.02 Area Soil

GSA014S 1396 Clinker SURFAC FS-69 0.0 -0.1 0.00 U+d -0.02 Area E SOIL

021595-P\Srr\-.AMTL\FINOSA\DRAF"D•APP_C D C-49 APPENDIX C

Table C-10 Clinker Area In Situ Gamma Spectroscopy Results Fraction of Limit

Calculated Results

Concentration 2 Sigma Error LocaFion Code Material (PCi/l) (pCi/g) Fraction of Limit FS-26 DU 78.65 17.53 2.25

021595- PSrIT'A MTL\F?4\GSA \D IA FTDA PP_C. D C-50 APPENDIX C

SOUTHWEST GSA PROPERTY SITE BOUNDARY ZONES SURVEYED

+

K+ + +

1+

0+ + If+ -+ + + + + + +

GA+ +

F + +

4+ + + + + + + + + + + .+ + + + + + . . . . 84-E+ +

D+ +

C+ + + + + + - + - + + -4 + + - + + +. + . + + + + + + + + + B+ + 4- + -4- + + -+ + + + - + + + + A+ + I 3 4 5 6 7 7 8 9 Is II lZ 13 14 15 16 17 18 19 tO ZI ZZ Z3

SOUTHEAST

NORlIHEAS'I

Figure C-26. Zones for in situ boundary survey

1 P \SSSIT'AMTI-',FIN\OISADRAFTI)\APP C I) C-51 APPENDIX C

1

Table C-11 GSA Boundary In Situ Gamma Spectroscopy Survey Northeast Fraction of Limit Concentration (pCi/g)

Sample ID, Location Sample 2-sigma Fraction EIi T 112 I1D3 Iocro of jl 1 =1 MMaterial (pCi/g) (pCi/g) Limit A 27 DU 0.0 0.0 0.00 B 27 U+d 8.7 3.2 0.87 B 27 CI DU 2.5 2.2 0.07 C 27 DU 15.5 3.5 0.44 C 27 CI DU 1.9 2.0 0.05 A 28 DU 0.0 0.0 0.00 B 28 DU 0.0 0.0 0.00 B 28 CI DU 0.0 0.0 0.00 C 28 DU 2.5 2.0 0.07 C 28 CI U+d 2.1 1.3 0.21 D 28 DU 6.0 2.1 0.17 D 28 CI U+d 4.4 1.8 0.44 A 29 U+d 1.5 1.1 0.15 B 29 DU 0.0 0.0 0.00 C 29 U+d 5.4 3.4 0.54

I

0f21595- P\STMAMTL\FMtNA\CD RA FTD\APP 0CC.-D C-52 APPENDIX C

Table C-12 GSA Boundary In Situ Gamma Spectroscopy Survey - Northwest Fraction of Limit Concentration (pCi/g)

Sample ED, Location Sample 2-sigma Fraction Conc. Error of IDI [ ID2 ID3 Material (pCi/g) (pCi/g) Limit

F 31 U+d 1.8 1.2 0.18 F 32 CI DU 0.0 0.0 0.00 F 32 C2 DU 1.6 2.4 0.05 F 32 U+d 1.8 1.1 0.18 F 33 CI U+d 2.1 1.4 0.21 G 28 DU 0.0 0.0 0.00 G 31 CI DU 0.0 0.0 0.00

(Y21595 -.FSrnA MTLkFIN4GSA\DRA FT' PPFC. D C-53 APPENDIX C

Table C-13 GSA Boundary In Situ Gamma Spectroscopy Survey Southeast Fraction of limit Concentration (pCi/g)

Sampe M, Location Sample 2-sigma Fraction Coonc. Error of mD in2 i Materiai (Pci/9) (Pci/0) Limit B 15 DU 2.0 2.1 0.06 B 15 CI U+d 2.6 1.4 0.26 A 16 DU 0.0 0.0 0.00 B 16 U+d 4.1 3.2 0.41 B 16 CI DU 0.2 2.7 0.00 A 17 DU 0.0 0.0 0.00 B 17 U+d 4.1 2.8 0.41 B 17 CI DU 0.3 1.8 0.01 A 18 U+d 2.1 1.0 0.21 B 18 U+d 1.2 1.1 0.12 B 18 C1 U+d 2.2 1.3 0.22 A 19 DU 0.0 0.0 0.00 B 19 DU 0.0 0.0 0.00 B 19 CI DU 4.3 3.0 0.12 A 20 U+d 2.1 1.3 0.21 B 20 U+d 4.1 3.0 0.41 B 20 C1 DU 4.2 2.4 0.12 A 21 DU 0.0 0.0 0.00 B 21 DU 0.0 0.0 0.00 B 21 CI U+d 1.4 1.1 0.14 A 22 DU -0.3 -2.2 -0.01 B 22 U+d 1.3 1.1 0.13 B 22 C1 DU 0.0 0.0 0.00 A 23 DU 0.0 0.0 0.00 B 23 DU 0.0 0.0 0.00 B 23 CI DU 0.0 0.0 0.00

A 24 U+d 1.3 1.1 0.13 B 24 U+d 1.9 1.0 0.19 B 24 Cl DU 0.0 0.0 0.00 A 25 DU 3.6 2.8 0.10

021595-P\SrSTA MTL\FUN\OSA\DRAFTD\APPC. D C-54 APPENDIX C

Table C-13 GSA Boundary In Situ Gamma Spectroscopy Survey - Southeast Fraction of Limit Concentration (pCi/g) (continued)

Sample ID, Location Sample 2-sigma Fraction ID I Conc. Error of ______ID Material (pCi/) Wipflk/) Limit B 25 DU 0.0 0.0 0.00 B 25 CI DU 3.8 2.5 0.11 A 26 DU 0.0 0.0 0.00 B 26 U+d 9.9 3.5 0.99 B 26 CI U+d 1.4 0.9 0.14 A 27 DU 0.0 0.0 0.00 B 27 U+d 8.7 3.2 0.87 B 27 CI DU 2.5 2.2 0.07 A 28 DU 0.0 0.0 0.00 B 28 DU 0.0 0.0 0.00 B 28 CI DU 0.0 0.0 0.00 A 29 U+d 1.5 1.1 0.15 B 29 DU 0.0 0.0 0.00 B 29 CI DU 0.0 0.0 0.00 B 30 DU 0.0 0.0 0.00 B 30 CI DU 0.0 0.0 0.00 B 31 U+d 6.9 3.9 0.69 B 31 CI DU 0.0 0.0 0.00 B 32 DU 0.0 0.0 0.00 B 32 Cl U+d 1.8 1.3 0.18 B 33 DU 0.0 0.0 0.00 B 33 C1 U+d 7.7 3.6 0.77 C 33 CI DU 4.3 3.8 0.12 B 34 U+d 1.3 1.0 0.13 B 34 C1 DU 0.0 0.0 0.00

021595-PPTAMTL\FINWOSAD RAFTD\APPpC D C-55 APPENDIX C

Table C-14 GSA Boundary In Situ Gamma Spectroscopy Survey - Southwest Fraction of Limit Concentration (PCi/g)

Sample ID, Location Sample 2-sigma Fraction Conc. Error of IDI 2 I D3 Material (pC) (pCi/g) Limit I 5 DU 0.0 0.0 0.00

0.00 I 6 DU 0.0 0.0 I 7 U+d 1.3 1.2 0.13 0.00 I 7 C1 DU 0.0 0.0 0.00 I 8 DU 0.0 0.0 I 8 CI U+d 1.8 1.5 0.18 0.14 I 9 U+d 1.4 1.3 I 9 CI U+d 2.5 1.3 0.2_5 J 3 DU 2.6 2.5 0.07 J 3 CI DU 0.0 0.0 0.00 0.00 J 4 DU 0.0 0.0 C1 DU 0.0 0.0 0.00 J 4 0.20 J 5 U+d 2.0 1.4 0.16 J 6 U+d 1.6 1.1 0.00 K 6 C1 DU 0.0 0.0 DU 0.0 0.0 0.00 7 C1 0.00 K 3 DU 0.0 0.0 0.00 Kf 3 C1 DU 0.0 0.0 0.00 K 4 DU 000.0

D 021 595.ISITr\AMTL\PI\GSA\DRAFTD\APP_C. C-56 ( ( APPENDIX C

Table C-15 Windborne - Soil Samples Gamma Spectroscopy Sample Analyses (pO/g)

Cowe.mzuaioa - PCi/8 497000 695000 + + File Mas Sample Sample Sample Survey Elevation Estimated Corrected Eatimatd Fraction

Number grams ID I ID 2 I) 3 Point Massachuen- Grid Feet Ra-226 Th-234 U-235 Material of Limit

GSA0584S 834 East of Windborne I No. I 1540 110.8 396.7 11.8 0.3 -0.3 -0.02 U+d -0.14 Greenough I

GSA0601S 1178 East of Windborm 2 No. 1 1539 195.4 643.5 11.5 0.1 -0.3 -0.01 U+d -0.05 Greenough

GSA0603S 1060 East of Windbome 2 No. 2 1539 195.4 643.5 11.5 0.1 -0.4 -0.01 U+d -0.0o Greenough

GSA0604S 982 East of Windborne 3 No. I 1565 291.7 541.2 10.8 0.2 -0.6 -0.01 U+d -0.09 Greenough

GSA0599S 949 East of Windborne 3 No. 2 1565 291.7 541.2 10.8 0.2 -0.6 -0.01 U+d -0.10 Greenough

GSA0559S 1181 East of Windborm 4 No. I 1564 372.4 606.4 11 0.1 -0.3 -0.01 U+d -0.05 Greenough

GSAO607S 967.8 East of Windbome 4 No. 2 1564 372.4 606.4 11 0.2 -0.6 -0.01 U+d -0.10 Greenough

GSA0605S 797 East of Windbome 5 No. 1 1563 439.2 663.9 5.4 0.3 -0.9 -0.02 U+d -0.15 Greenough

GSA0606S 673.7 East of Windborne 5 No. 2 1563 439.2 663.9 5.4 0.4 -1.2 -0.02 U+d -0.21 Greenough

021595-P\SrrTAMTL\FII\GSA\DRAFTD\APP C D C-57 APPENDIX C

GSA, PROPERTY In Situ Gamma S pectroscopy APPENDIXC and Soil Sample Locations F

"ifb E

FS9 GSA D FS39-A

FS 0 C A FSZ

FS37 Ar? B

LEG END 130ut.,.. sA A AFS42 FS43 FS36 A Soil Sample only 31 32 33 34 35 36 37 * In Situ measurement and Soil Sample

Figure C-27. Locations of in situ meaurements and soil samples in Property 20

)21'•Qs p, sr L\FrN\GSA'DRAFTD\APP C D ( APPVJ'

Table C-16 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Fraction of Limit

497000 695000 Coocentratioa - pCitl + + Northing Easting Land Sand File Mass Sample Sample Sample Survey Massachusetts Grid Elevation Estimated Corrected Estimated Fraction Number I rams ID 1 ID 2 ID 3 Point Feet Ra-226 Th-234 U-235 Material of Limit

GSA0616S 1541 Area 20 FS-01 1547 438.4 445.5 10.1 15.6 13.0 0.25 U+d 4.13

GSA0618S 1335 Area 20 FS-02 1542 463.1 413 I1.1 4.4 16.1 0.31 U+d 3.70

GSA0620S 1446 Am&20 FS-03 1545 484.2 444.3 10 5.7 7.6 0.14 U+d 2.11

GSAO624S 1632 Ares 20 FS-04 1543 482.9 419.1 10.8 4.6 18.2 0.35 U+d 4.14

GSA0622S 1415 Area 20 FS-05 1548 486.4 393.5 10.7 -30.9 98.4 1.37 DU 4.13

GSA0626S 1337 Area 20 FS-06 1550 506.2 417.9 10.4 3.5 4.7 0.09 U+d 1.31

GSA0664S 1459 Area 20 FS-07 1546 451.4 459.7 9.5 18.7 9.7 0.18 U+d 3.,3

GSA0628S 1249 Area 20 FS-08 1549 531 394.7 9.8 3.4 7.3 0.14 U+d 1.81

GSA0630S 1040 Area 20 FS-09 1551 522.2 351.7 11.2 0.1 -0.5 -0.01 U+d -0.08

GSA0632S 1371 Area 20 FS-10 1552 556.8 371.3 10.2 0.0 -0.1 0.00 U+d -0.03

C-59 Cl) 021595-U2IS9S P\SIT\AP\SIT AMTI.\ILN\OSA\DRAFTI)\API' MTIA\ F MOVSA\DRA F-I'DA P_(", 1) C-59 APPET"' C

Table C-16 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Fraction of Limit (Continued)

497000 695000 Conc.etration - PCi/x

INohing Eaingsan Corrected Estimated Fractioa File Mass Sample Sample Sample Survey Massachusetts Grid Elevation Estimated of Limit uID Feet Ra-226 Th-234 U-235 Material Number I grants ID I!- I[D 2 3 , Point

8.3 0.0 -0.2 0.00 U+d -0.03 GSA0666S 1367 Area 20 FS-I I 1557 543.4 473.4

6.8 0.0 -0.1 0.00 U+d -0.02 GSA0682S 1434 Area 20 FS-13 1562 583.8 593.3

9 0.1 -0.3 -0.01 U+d -0.05 GSA0670S 1228 Area 20 FS-14 1553 510 473.1

8.6 7.0 3.7 0.07 U+d 1.45 GSA0672S 1324 Area 20 FS-15 1559 490.9 496.5

9.4 <3 -0.2 <.2 DU -0.01 GSAO674S 1313 Area 20 FS-16 1556 529.5 450.4

9.6 0.0 -0.2 0.00 U+d -0.03 GSAO676S 1358 Area 20 FS-17 1554 565.9 424.3

7.3 0.1 -0.3 -0.01 U+d -0.05 GSA0679S 1172 Area 20 FS-18 1555 563.5 450.4

7.2 0.1 -0.5 -0.01 U+d -0.08 GSAO680S 1043 Area 20 FS-19 1561 614.5 546.5

7.9 0.1 -0.4 -0.01 U+d -0.07 GSA0736S 1098 Area 20 Surface FS-36 1722 420.4 467.5 Soil

0.0 -0.1 0.00 U+d -0.01 GSA0738S 1488 Area 20 Surface FS-37 1723 409.8 434.3 9.9 Soil

021595 P\S-I'I'A MTL\FDGSA\DRA FrD\A PP_C 1) C-60 ( ( APPF'

Table C-16 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results Fraction of Limit (Continued)

497000 695000 Concentration- pCi/g

Northing Eaatinu Land Sand File Mass Sample Sample Sample Survey Massachusetts Grid Elevation Estimated Corrected Esimated Fraction Number Irams ID I [D 2 ID 3 Point Feet Ra-226 Th-234 U-235 Material of Limit

GSA0746S 1155 Area 20 Surface FS-38 1728 437 402.2 10.6 0.1 -0.3 -0.01 U+d -0.06 Soil

GSA0744S 1242 Area 20 Surface FS-39 1727 466.1 370.7 10.8 0.1 -0.3 0.00 U+d -0.04 Soil I

GSA0742S 1601 Area 20 Surface FS-40 1726 506.1 378.3 II 6.1 3.1 0.06 U+d 1.24 Soil I I

GSA0740S 1375 Area 20 Surface FS-41 1725 532.9 365.8 11.3 5.1 5.0 0.09 U+d 1.51 Soil III

GSA0734S 1174 Area 20 Surface FS-42 1724 439.9 481.5 7.3 5.2 -0.3 -0.01 U+d 0.46 Soil

GSA0733S 1725 Area 20 Surface FS-43 1730 472.2 513.4 8 0.0 0.1 0.00 DU 0.00 Soil

GSA0731S 799.5 Area 20 Surface FS-44 1729 507.5 505.7 4.7 0.3 -0.9 -0.02 U+d -O 15 Soil

C-61 (' 1i 021595-P\SIrýAAI1TLL\FIN\(iSA\DRAI-"DýAPP_("021 S95 l'\srrAMTL\1N\(SA\DRAI-TD\)PP 1) C-61 APPENDIX C

I-• Table C-17 Property 20 In Situ Gamma Spectroscopy Results Fraction of Limit

Sample ID Code* Material Fraction of Limit FS-01 U+d 1.50 FS-02 DU 0.30 FS-03 U+d 1.03 FS-04 U+d 2.30 FS-05 U+d 1.44 FS-06 DU 0.10 FS-07 DU 0.13 FS-08 DU 0 FS-09 DU 0 FS-10 DU 0 FS-1I DU 0 FS-12 U+d 0.13 I FS-13 DU 0 FS-14 U+d 0.14 FS-15 U+d 0.15 FS-16 U+d 0.11 FS-17 DU 0.08 FS-18 DU 0 FS-19 DU 0

* See map for locations

I

021595-PSIT MTL\FI4G)SA\DRA FrDAPP_C. D C-62 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors

497000 + 695000 Nordhia h +

Maw Sample Survey Massachusetts Grid Elevation Sample No. grams Location Bote Nunmer Number Point Feet

GSAOS4MS 334 East of Windbonue 1 No. 1 1340 110.3 396.7 11.3 rOeenough

OSA0601S 1178 Eat of Wi'dbom e2 No.1 1539 195.4 643.5 11.5 Greenough

GSA0603S 1060 Eaot of Wi'dborne 2 No. 2 1539 195.4 643.5 11.5 Greenough

GSA0604S 932 Eat of Windbome 3 No. 1 1565 291.7 541.2 10.8 Greenough

GSA0599S 949 East of Windbome 3 No. 2 1565 291.7 541.2 10.3 Greenough

GSA0559S 1181 Eas of Windborne 4 No. 1 1564 372.4 606.4 II Greenough

GSA0607S 967.8 East of Windbomne 4 No. 2 1564 372.4 606.4 it Greenough

GSA0605S 797 East of Windborne 5 No. 1 1563 439.2 663.9 5.4 Greenough

GSA0606S 673.7 East of Windborne 5 No. 2 1563 439.2 663.9 5.4 Greenough

GSA0616S 1541 GSA Area 20 FS-01 1547 438.4 445.5 10.1

GSA061S 1335 GSA Area 20 FS-02 1542 463.1 418 11.1

GSA0620S 1446 GSA Area 20 FS-03 1545 484.2 444.3 10

GSA0624S 1632 GSA Area 20 FS-04 1543 482.9 419.1 10.8

GSA0622S 1415 GSA Area 20 FS-05 1548 486.4 393.5 10.7

GSA0626S 1337 GSA Area 20 FS-06 1550 506.2 417.9 10.4

GSA0664S 1459 GSA Area 20 FS-07 1546 451.4 459.7 9.5

GSA0629S 1249 GSA Area 20 FS-08 1549 531 394.7 9.8

GSA0630S 1040 GSA Area 20 FS-09 1551 522.2 351.7 11.2

GSA0632S 1371 GSA Area 20 FS-10 1552 556.8 371.3 10.2

GSA0666S 1367 GSA Are 20 FS-! I 1557 543.4 473.4 8.3

GSA0682S 1434 GSA Area 20 FS-13 1562 583.3 593.3 6.8

GSA0670S 1223 GSA Aea 20 FS-14 1558 510 473.1 9

GSA0672S 1324 GSA Area 20 FS-15 1559 490.9 496.5 8.6

GSA0674S 1313 GSA Area 20 FS-16 1556 529.5 450.4 9.4

GSA0676S 1358 GSA Area 20 FS-17 1554 565.9 424.8 9.6

021595-PMSM MTL\F1NioSA \DRA FTD\APP_C D C-63 APPENDIX C

--.A Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 Nonhing + Easing Ma" Sample Survey M Elevation Sample No. Vm-- Location Bore Number Number Point Feet

0SA0676$ 1172 GSA Area 20 FS-18 1555 563.5 450.4 7.3

OSA06IOS 1043 GSA Area 20 FS-19 1561 614.5 546.3 7.2

GSAOS I 1201 IBum Pit Boc, 32 No. I

OSA0523S 325 Burn Pit Bor 32 No. 2

GSA0524S 943 Bum Pit Bore 32 No. 3

GSA0525S 261 Bum Pit Bore 32 No. 4

GSA0526S 160 Burn Pit Bore 32 No. 5

GSA0527S 132 Bum Pit Bore 32 No. 6

GSA0519S 1113 Burn Pit Bore 33 No. 1 1513 292.7 125.2 7.6

GSA0522S 981 Bum Pit Bore 33 No. 2 1513 292.7 125.2 7.6

GSA0520S 1638 SUL Pit Bore 33 No. 3 1513 292.7 125.2 7.6

GSA0533S 635 Bum Pit Bore 33 No. 4 1513 292.7 125.2 7.6

GSAO52SS 134 Bum Pit Bore 33 No. 5 1513 292.7 125.2 7.6

GSA0521S 950 Burn Pit Bore 34 No. I

GSA0529S 395 Bum Pit Bore 34 No. 2

GSA0530S 751 Burn Pit Bore 34 No. 3

GSA0531S 524 Bum Pit Bore 34 No. 4

GSA0532S 282 Burn Pit Bore 34 No. 5

GSA0536S 1224 Burn Pit Bore 35 No. 1 1520 297.7 142.6 7

GSA0535S 571 Burn Pit Bore 35 No. 2 1520 297.7 142.6 7

GSA0534S 1431 Burn Pit Bore 35 No. 3 1520 297.7 142.6 7

GSA0533S 616 Bum Pit Bore 35 No. 4 1520 297.7 142.6 7

GSA054OS 144 Burn Pit Bore 35 No. 5 1520 297.7 142.6 7

GSA0541S 1731 Bum Pit Bore 36 No. 1

GSA0537S 97 Burn Pit Bore 36 No. 2

GSA0542S 490 Bum Pit Bore 36 No. 3

GSA0543S 302 Bum Pit Bore 36 No. 4

GSA0539S 1453 . Pit Bore 36 No. 6

GSA0544S 1267 Bum Pit Bore 37 No. 1 1514 315.6 131.4 8

021595- P\S TA MTL\WIN\OSA\DRA FTD\APPC.D C-64 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 Northiag + Easting

Mam Sample Survey Massachusetta Grid Elevation Sample No. grams Location Bore Number Number Poit Feet

OSA0550S 548 Bum Pit ore 37 No. 2 1514 315.6 131.4 a

GSA0547S 1174 Bum Pit ore 37 No.3 1514 315.6 131.4 8

GSA0546S 1068 BUM Pit ore 37 No. 4 1514 315.6 131.4 8

OSA055IS 467 Bum Pit Bore 37 No. 5 1514 315.6 131.4 8

GSA0552S 860 Bum Pit Bore 37 No. 5A 1514 315.6 131.4 3

GSA0545S 1653 Bum Pit Dore 38 No. 1 1519 303.3 152 6.8

GSA0561S 719 Bum Pit Bore 38 No.2 1519 303.8 152 6.8

OSA0574S 1359 Bum Pit Dore 38 No.3 1519 303.3 152 6.8

GSAO549S 670 Bum Pit Bore 38 No. 4 1519 303.8 152 6.8

GSA0563S 287 Burn Pit Bom 38 No.5 1519 303.8 152 6.8

GSA0549S 620 Bum Pit Bore 38 No.6 1519 303.3 152 6.8

GSA05589S 1177 Bum Pit Bore 39 No.1 1521 296.1 144.6 7.6

GSA0562S 404 Bum Pit Bore 39 No. 2 1521 296.1 144.6 7.6

GSA0557S 1213 Bum Pit Bore 39 No.3 1521 296.1 144.6 7.6

GSA0585S 486 Bum Pit Bore 39 No. 4 1521 296.1 144.6 7.6

GSAO582S 246 Bum Pit Bore 39 No.5 1521 296.1 144.6 7.6 "GSA'"6OS 1302 Bum Pit Bore 40 No.1 1512 289.5 119.8 8.1

GSA0579S 1660 Bum Pit Bore 40 No.2 1512 289.5 119.8 8.1

GSA0559S 1401 Bum Pit Bore 40 No.3 1512 289.5 119.8 8.1

GSA0566S 1127 Bum Pit Bore 40 No.4 1512 289.5 119.8 8.1

GSA0576S 773 Bum Pit Bore 40 No.5 1512 289.5 119.8 8.1

GSA0594S 1065 Bum Pit Bore 41 No.1 1518 317.3 164.1 7.5

GSA0573S 1379 Bum Pit Bore 41 No.2 1518 317.3 164.1 7.5

GSA0577S 512 Bum Pit Bore 41 No.2 1518 317.3 164.1 7.5

GSA0602S 1255 Bum Pit Bore 41 No.3 1518 317.3 164.1 7.5

GSA0575S 991 Bum Pit Bore 41 No.4 1518 317.3 164.1 7.5

GSA0569S 897 Bum Pit Bore 41 No. 5 1518 317.3 164.1 7.5

GSA0565S 934 Bum Pit Bore 41 No.6 1518 317.3 164.1 7.5

GSA0592S 261 Bum Pit Bore 41 No. 7 1518 317.3 164.1 7 5

021595-PRS'AMTL\FI•fOSA\DRAFTD\APP C.D C-65 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 NSothiW + Eauting

Mae"n Survey Mssaclhusett Grid Elevation Sample No. gtum Location Bore Numbcr Number Point Feet

OSAO56IS 1125 Burn Pit Bore 42 No. 1 1517 327.7 132.9 7.8

GSA0570S 375 Bum Pit Bore 42 No. 2 1517 327.7 132.9 7.8

OSAO67S 1372 Burn Pit Bore 42 No. 3 1517 327.7 132.9 7.8

GSAO564S 1578 Bum Pit Bore 42 No. 4 1517 327.7 132.9 7.8

OSA0597S 259 Burn Pit Bore 42 No. 5 1517 327.7 132.9 7.8

OSA053S 1181 Bum Pit Bore 43 No. 1 1516 322.8 109.2 8.6

GSA0589S 634 Bum Pit Bore 43 No. 2 1516 322.3 109.2 8.6

GSA0595S 84 Buum Pit Bore 43 No.3 1516 322.8 109.2 3.6

GSA0587S 1056 Born Pit Bore 43 No. 4 1516 322.3 109.2 8.6

GSA0612S 235 Bum Pit Bore 43 No. 5 1516 322.8 109.2 3.6

GSAOS8IS 1486 Bum Pit Bore 44 No.1 1510 279.5 101.1 .83

GSA0598S 1727 Bum Pit Bore 44 No. 2 1510 279.5 101.1 8.3

GSA0586S 1551 Bum Pit Bore 44 No.3 1510 279.5 101.1 8.8

GSA0596S 643 Bum Pit Bore 44 No. 4 1510 279.5 101.1 8.8

GSA0593S 1230 Bum Pit Bore 44 No.5 1510 279.5 101.1 8.8

GSA0591S 219 Bum Pit Bore 44 No.6 1510 279.5 101.1 8.8

GSA0555S 1000 Burn Pit Bum Pit Burn Pit water

GSA61IS 356.1 Bum Pit Pit Bottom 1 No.1 1522 300.1 139 8.3

GSA0683S 330.3 Burn Pit Pit Bottom 2 No. 1 1523 293.7 140.4 3.3

GSA0614S 287.3 Burn Pit Pit Bottom 2 No. 2 1523 293.7 140.4 8.3

GSA0589S 513 Burn Pit Pit Bottom 3 No. 1 1524 297.5 135.5 8.4

GSA0609S 353.1 Burn Pit Pit Bottom 4 No. 1 1525 300.1 134.1 8.4

GSA0613S 106.1 Burn Pit Pit Bottom 4 No.2 1525 300.1 134.1 8.4

GSA0600S 353 Burn Pit Pit Bottom 12 No. !

GSA0572S 376 Burn Pit Pit Wall 5 No. 1 1526 301 135.2 8.4

GSA0578S 671 Bum Pit Pit Wall 8 No. 1 1529 295.9 137 8.4

GSA0590S 290 Born Pit Pit Wall 9 No. I 1530 296.7 139.1 8.4

GSA0609S 542.5 Burn Pit Pit Wall 10 No. I 1531 298.9 140 8.3j1I

021595-PSrIAMTL\FIN\GSA\DRAFrPDAPPC D C-66 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 Norhing + Eaeting

Mass Sample Survey Masschusett Grid Elevation Sample No. grams Location Bore Number Number Point Feet

OSA06106 550 Burn Pit Pit Wail I No. 1 1532 301 139.2 8.3

OSA0553S 1000 Bum Pit Well B-25 No. 1511 310.1 87 8.5 B-25-W-1

OSA0554S 1000 Bum Pit Well B-31 No. B-3 I-W- I

GSA0685S 1734 Burn Pit FS-20 1506 259.5 71.3 8

GSA0687S 1690 Burn Pit FS-21 1509 274.8 95.8 9

GSA0689S 1671 Burn Pit FS-22 1503 192.6 226.2 7.8

GSA0691S 1636 Burn Pit FS-23 1505 230.8 98.6 8.7

GSA0693S 1281 Bum Pit FS-24 1537 325.9 77.2 7.9

GSA0695S 1218 Burn Pit FS-25 1515 311 120.4 7.8

GSA0697S 1077 Clinker Area FS-26

GSA0706DD 1780 Bum Pit Bulk Sample Lower 1508 279.5 93.3 8.8 #1 Coarse

GSA07ODD 1702 Burn Pit Bulk Sample Lower Fines 1508 279.5 93.3 8.8 #1

GSA0707DD 1901 Burn Pit Bulk Sample Lower 1508 279.5 93.3 8.8 #1 Middlings

GSA0727S 2.5 Bum Pit Bulk Sample Upper 1508 279.5 93.3 8.8 #1

GSAO703DD 1685 Burn Pit Bulk Sample Upper 1508 279.5 93.3 8.8 #I Coarse

GSAO705DD 1481 Bum Pit Bulk Sample Upper Fines 1508 279.5 93.3 8.8 #1

GSA0704DD 1754 Bum Pit Bulk Sample Upper 1508 279.5 93.3 8.8 #1 Middlings

GSA0712DD 1800 Burn Pit Bulk Sample Lower 1507 266.5 66.4 7.9 #2 Coarse

GSA0714DD 1738 Bum Pit Bulk Sample Lower Fines 1507 266.5 66.4 7.9 #2

GSA0713DD 1936 Burn Pit Bulk Sample Lower 1507 266.5 66.4 7.9 1#2 Middlings I

GSA0709DD 1695 Burn Pit Bulk Sample Upper 1507 266.5 66.4 7.9 1#2 Coarse

021595- PSr•A MTLFINMOSA\DRA FTrDA PP_C D C-67 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 Northiag + Easting

MaNs Sample Survey M usetts Grid Elevation Sample No. grams Location Bove Number Number Point Feet

OSA071IDD 1602 Burn Pit Bulk Sample Upper Fumes 1307 266.5 66.4 7.9 12

OSAO71ODD 1914 Burn Pit Bulk Sample Upper 1507 266.5 66.4 7.9 12 Middtisp

GSA071IDD 1734 Bum Pit Bulk Saymple Lower 1504 191.9 230.9 7.4 13 Coarse

GSA072ODD 1721 Bum Pit Bulk Sample Lower Funes 1504 191.9 230.9 7.4 /3

GSA0719DD 1400 BamPit Bulk Sample Lower 1504 191.9 230.9 7.4 #3 Middlings,

GSA0715S 1022 Burn Pit blWk Sample Upper 1504 191.9 230.9 7.4 #3 Coarse

OSA0717DD 11237 Bum Pit BWlk Sample Upper Fines 1504 191.9 230.9 7.4 #3

GSA0716S 1690 Bum Pit Bulk Sample Upper 1504 191.9 230.9 7.4 #3 Middlings

GSA0764S 962.2 Burn Pit Surface Soil FS-27 1712 369.2 148.3 7.4

GSA0762S 896.3 Burn Pit Surface Soil FS-28 1713 335.6 177.8 7.7

GSA0760S 1097 Bum Pit Surface Soil FS-29 1714 302.8 213.7 7.9

GSA0758S 882 Burn Pit Surface Soil FS-30 1715 270.9 231.7 7.7

GSA0752S 1253 Burn Pit Surface Sod FS-31 1716 246.9 203.3 8.1

GSA0750S 1242 Bum Pit Surface Sod FS 2 1717 219.5 231.4 8

GSA0748S 997 BuM Pit Surface Sod FS-33 1718 204.5 248.8 8.1

GSA0754S 1007 Burn Pit Surface Soil FS-34 1719 223 244.8 8

GSA0756S 1219 burn Pit Surface Sod FS-35 1720 232.7 233.7 8.1

GSA0736S 1098 GSA Area 20 Surface Soil FS-36 1722 420.4 467.5 7.9 9.9 GSA0738S 1481 GSA Area 20 Surface Soil FS-37 1723 409.8 434.3

GSA0746S 1155 GSA Area 20 Surface Soil FS-38 1728 437 402.2 10.6

GSA0744S 1242 GSA Area 20 Surface Sod FS-39 1727 466.1 370.7 10.8

GSA0742S 1601 GSA Area 20 Surface Soil FS-40 1726 506.1 378.3 11

GSA0740S 1375 GSA Area 20 Surface Soil FS-41 1725 532.9 365.8 11.3

GSA0734S 1174 GSA Area 20 Surface Soil FS-42 1724 439.9 481.5 7.3

GSA0733S 1725 GSA Area 20 Surface Soil FS-43 1730 472.2 513.4 8

021595-PMS1"' MTL\FU4IGSA\DRAFFDA PP_C. D C-68 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 695000 Nordhing + Eusting

Mad Sample Survey Massachusetat Grid Elevation Sample No. grmM Location Bore Number Numbe Point Feet

GSA0731S 799.5 GSA Area 20 Surface Soil FS-44 1729 507.5 505.7 4.7

GSA0774S 329.9 Bum Pit Surface Soil FS-45 1711 335 58.4 7.5

GSA0772S 534 BurnPit Surface Soil FS-46 1710 313.6 37.1 7.7

GSA0770S 923 Bum Pit Surface Soil FS-47 1709 281.2 5.8 7.7

OSA0767S 1839 Bum Pit Surface Soil FS-48 1701 239.4 35.9 8.4

GSA076US 1743 Bum Pit Surface Soil FS-49 1707 231.1 8.1 8.3

GSAO776S 1393 Bum Pit Surface Soil FS-50 1706 209.8 51.2 8.3

GSAO779S 1647 Bum Pit Surface Soil FS-51 1705 171.6 114.6 8.7

GSA0738S 1365 Bum Pit Surface Sodl FS-52 1704 138.1 172.1 8.1

GSA0782S 1707 Bum Pit Surface Soil FS-53 1703 190.3 246.4 7.8

GSA0786S 1387 Clinker Area Surface Soil FS-55

GSA0798S 2027 Clinker Area Surface Soil FS-56

GSA0790S 1657 Clinker Area Surface Soil FS-57

GSA0792S 1535 Clinker Area Surface Soil FS-58

GSA0794S 1538 Clinker Area Surface Soil FS-59

GSA0796S 1378 Clinker Area Surface Soil FS-60

GSA0798S 1754 Clinker Area Surface Soil FS-61

GSAO800S 1225 Clinker Area Surface Soil FS-62

GSAO8O2S 1626 Clinker Area Surface Soil FS-63

GSA0804S 1730 Clinker Area Surface Soil FS-64

GSA006S 1471 Clinker Area Surface Soil FS-65

GSAO8O8S 1612 Clinker Area Surface Soil FS-66

GSAOSIOS 1396 Clinker Area Surface Soil FS-67

GSA0812S 1396 Clinker Area Surface Soil FS-68

GSAO814S 1396 Clinker Area Surface Soil FS-69

GSA0816S 652 Area Surface Soil FS-70 A25A28

GSA081SS 011 Area Surface Soil FS-71 A25 A28 I III

021595-P\SI'\A MTL\F1N\GSA\DRAFTD\APP_C D C-69 APPENDIX C

Table C-18 Soil Sample Locations and Descriptors (Continued)

497000 + 693000 NorbW + Easting

vaton Man Sampie Survey Machuses Grd Feet Sample No. gra Locaton Bore Number Number PoMCt

GSA7020S 1032 At" Surface Soil FS-72 A25_A2S

GSA0622S 590 Area Surface Soil FS-73 A25A28

OSA0624S 1523 ABR/BS 1060 ABB BS-106 FS-74 12 FT II _ I_1_

021595-.PSTMr MTL\FIN•GSAMDRAFTDAPP C. D C-70 APPENDIX C

8.17 w60 440 y4444 a Fenced 4 4e Area C WjA o°' ° 4•• APPENDIX %5

o-ý916 4 0 i F*F o" e-4 ---. * 4 5-,

General Area

8404 Detail Sampllng In Burn Pit a-p7 0-4

Bi.3,..1o- la "4"4 B..3 •% e-4 4 8ej

P.1 B-J2 P 4 P~s 40 2 0 FEET _-' %4 %.3 SA

B - Soil Boring Locations 1-4 17 BS - Bulk Sample Locations i -•4 ]- - 4- a P - Hand Auger Locations Within Burn Pit W & WC - Previously Existing Water Sampling Wells

rigure C-25. Soil bonng locations, 199•3, 1)94, including wells

021 s9S P',S-,AMrI.\FIN\(OSA\DRAF'TD\APP C D C-71 APPENDIX C

Table C-19 GSA Bumn Pit Core Bore Sample Analysis Results (pCi/g)

Numbe 1y K-M Ce-137 ln-M i3-212 Pb-l12 3-114 214 Ra-324 -224 At-=8 TV-234 U-235

B-21 0-1' 22.50' 0.36 0.30 0.79 0.77 0.U 0.96 55.780 1.06

1'-3' 16.01 0.14 0.23 0.60 0.68 0.73 8.39* 0.91 21.730

3'-5' 21.12 0.24 0.45 0.60 0.62 3.13* 0.66 4.200 5'-7' 20.99 0.28 0.79 0.71 0.80 301.440 2.06* 5.45* 4.01 3.910 15.27' 5.43 S70.88* 0.34 1.61* 1.10 0.86 8' pea 291.560 2.04' 4.21" 4.73' 3.020 3.310 9.64* 4.92*

B-22 0-1' 33.61' 0.610 1.14 1.26* 1.•5

1'-3' 52.29' 0.83' 1.54' 1.61' 1.78'

V-5' 10.67 0.29 0.75 0.4 0.66

5-7' 18.98 022 0.65 0.67 0.59

ik 42.71 0.45* 0.87 0.78

u. p"M 48.55' 0.31 0.99 0.66

L pem 93.40-' 0.47* 1.27 1.07

8-23 0-1" 7.66 0.26 0.58 0.48 0.65 2.99

5'-7' 39.16' 0.45' 0.88 0.98 0.70 5.24*

uik 18.25 0.28 0.67 0.59 0.65

u peat 110.87' 0.73* 2.18 1 1.00 1.12' 2.35'

I pat 26.46' 0.30 0.77

B-24 0-1' 8.26 0.27 0.58 0.82 0.80 5.77*

1-3' 7.29 0.24 0.68 0.68 0.63 2.95 4.40*

3'-5' 11.92 0.22 0.51 0.50 0.64

5'-7' 20.99 0.55

U C-p 13.98 0.27 0.52 053

u. peat 83.99' 0.71' 1.85' 1.65* 1.71* 2.52*

1. pea 51.990 1.15 0.89

021595 -ISIT\MTL\FIGSA\DRAFTDA PP_C. D C-72 u

0

0 0 0;6 C ci d

Asu

0 0 0 ci 0 . i - I 0 - 0 0 0 0 0 0 APPENDIX C

Table C-19 GSA Burn Pit Core Bore Sample Analysis Results (pCl/g) (continued)

Number Trpe i-0 C..137 1 -2 1 312 Vb-212 3214 b-214I R--M U 6 J Th-234 1[•t &-29 0-1 5.95 0.56 0.73 0.76

V-5' 15.00 0.30 0.57 0.64 0.71

.a 9.76 0.26 0.51 0.30 0.51 0.59

pew 21.06' 0.58

&-30 0-1' 6.99 0.33 0.89 0.96 0.88 6.210 11.36*

1'-31 20.62 0.39 0.88 6.34'

V'.5' 34.47 0.86 0.92 0.77

5'-7' 12.90 0,28 0.54 0.72 0.73 2.610

ik 29.88' 0.37 1.00 0.84 0.91

u. pe 37.22* 0.36

L pe 190.4* 1.77' 3.38' 4.430 3.41' 3.480 13.39' 5.00' 4.710

&-31 0-1' 7.52 0.38 0.78 0.86 0.79 0.75

V-3' 13.36 0.46 0.63 0.66

3-5' 11.17 0.28 0.69 0.60 0.63

5°-7' 121.62' 1.02' 2.01' 2.12' 2.513 3.78'

ilt/tarn 12.95 0.39 0.96 1.09' 1.0' 1.06

peat 58.45- . 1.12- 2.053 1.92* 2.30'

Blank cel imcatlm s the nclide w not detected.

*Imlical resuits in excess of off-lste mrem + 3s.

021595-P\S ITAMTL\FMT:4\SA\DRAFTD\AP PC.D C-74 APPENDIX C

Table C-20 GSA Soil Bore Samples Comparision of Total Uranium and Gamma Spectroscopy Analyses Data

Total Uranium Gamma Spectral Analysis Analysis

Sample Core Depth/ Total Uranum dU ih-234 dU Number Number Lac (V/g) (WU&) ug) (pCi/g)

287 21 0-1' 109.00 53.65 55.78 81.79 288 21 1'-3' 29.00 14.27 21.73 31.86 289 21 3U-5f 5.30 2.61 4.20 6.16 302 23 5'-7' 3.00 1.48 5.42 7.94 306 24 0-1' 9.10 4.48 5.77 8.45 307 24 1'-31 6.90 3.40 4.40 6.44 313 25 0-1' 18.50 9.11 5.71 8.37 314 25 1'-3' 3.00 1.48 4.09 6.00 322 26 0-1i 6.80 3.35 4.42 6.49 328 27 0-1' 18.40 9.06 15.50 22.72 329 27 1'-3' 13.60 6.69 13.29 19.49 330 27 3'-5' 1.60 0.79 1.86 2.73 336 28 0-1' 3.90 1.92 4.70 6.90 338 28 3'-5' 0.90 0.44 4.08 5.98 347 30 0-1' 17.40 8.56 11.36 16.65 348 30 1'-3 9.80 4.82 6.34 9.29 3.83 350 30 5'-7' 3.30 1.62 2.61 353 30 I. peat 8.20 4.04 4.71 6.91

Note 1: Total Uranium Analysis dU = Total Uranium (ug/g) * 0.4922 (pCilug)

Note 2: GaCma Spectral Analysis dU = Th-234 (pOlg) / 0. 682 (Th-234/dU)

021 595-P\SrlRAMTL\F!N\GSA\DRA FTMhAPPC D C-75 APPENDIX C

Burn Pit. In Situ Gamma Sp ectroscopy Burn Pit In Situ Gamma Spectroscopy and Surface Soil Samples

...... FENCE-...... G

FS4 7 t FS49 F.F.S4 .. F

FS48A FS.FR FS25 FS2 AFS 5 F S 21F E _8 FS2

FoT FS9 D

51 C

FS5 B

A7A ...... A . 2jS F S73 ......

27 28

SLEG END

A = Soil Sample only - In Situ Measurement and Soil Sample

Figure C-29. Burn pit locations for in situ measurements and soil samples

021595 P\SIT\AMTI'\FI/\OSA\DRAPTD\APP C" 1) C-76 APPENDIX C

Table C-21 Burn Pit - Surface Soil Samples Gamma Spectroscopy Analyses Results

Concentration - pCi/g Not Sand

497000 695000 Corrcted + + Land Northing Easting Elevation File Man Sample Sample Sample Survey Feet Number grams ID I ID 2 ID 3 Point Moaachuacts Grid K-40 T1-208 Cs-137 Ac-228 Pa-234m Ra-226 Th-234 U-235

- = I = =- -I GSAO685S 1734 Bum Pit FS-20 1506 259.5 71.3 A 7.0 0.29 0.33 1.07 <3 6.63 0.21

GSA0687S 1690 Bum Pit FS-21 1509 274.8 95.8 9 9.9 0.37 0.2 0.92 6.30 11.40 0.41

GSA0689S 1671 Bum Pit FS-22 1503 192.6 226.2 7.3 13.4 0.27 1.08 0.93 54.3 8.47 24.90 0.51

GSA0691S 1636 Bum Pit FS-23 1505 230.8 98.6 8.7 9.3 0.27 0.33 0.69 7.10 14.50 0.43

GSA0693S 1281 Bum Pit FS-24 1537 325.9 77.2 7.9 10.3 0.21 0.92 120.12 <3 34.60 3.11

GSA0695S 1218 Burn Pit FS-25 1515 311 120.4 7.3 11.1 0.29 5.70 12.10 0.35

GSA0764S %2.2 Bum Pit Surface FS-27 1712 369.2 148.3 7.4 16.7 0.4 0.63 0.00 6.51 8.45 0.40 Soil

GSA0762S 896.3 Burn Pit Surface FS-28 1713 335.6 177.3 7.7 13.4 0.3 0.51 0.00 0.00 5.46 0.00 Soil

GSA0760S 9TU97 Bum Pit Surface FS-29 1714 302.8 213.7 -- 7-9 15.5 0.3 0.40 1.11 3.31 4.60 0.21 Soil

GSA0758S 882 Bum Pit Surface FS-30 1715 270.9 231.7 7.7 13.0 0.52 0.00 0.00 6.24 0.00 Soil

GSA0752S 1253 Burn Pit Surface FS-31 1716 246.9 203.3 3.1 10.6 1.25 0.00 65.23 11.50 32.53 0.70 Soil

GSA0750S 1242 Bum Pit Surface FS-32 1717 219.5 231.4 $ 15.2 1.35 0.00 6.87 16.36 0.42 Soil

GSA0748S 997 Bum Pit Surface FS-33 1718 204.5 243.8 8.1 18.6 0.3 1.55 0.00 0.00 10.08 0.00 Soil

021 sq5-P\SrI'A Mr I,\FMNCSA \DRA F-D\APPC.D C-77 APY. X C

Table C-21 Burn Pit - Surface Soil Samples Gamma Spectroscopy Analyses Results (Continued)

Concentration - Pcilg Nt4~ Sand C(fCted 497000 695000 + + Northing Easting Elevation L.and I Feet Sample Sample Survey U-235 File Mass Sample Ca-137 AC-225 Pa-234m Ra-226 Th-234 Point Massachuaetls Grid K-40 TI-205 Number grams ID I ID 2 ID 3

<3 6.63 0.21 259.5 71.3 8 7.0 0.29 0.33 1.07 GSA0685S 1734 Burn Pit FS-20 1506 0.00 0.00 0.00 223 244.1 $ 13.1 0.52 0.00 GSA0754S 1007 Burn Pit Surface FS-34 1719 SoilI

4.62 1.03 0.21 232.7 233.7 8.1 13.2 0.44 0.00 GSA0756S 1289 Burn Pit Surface FS-35 1720 Soil

0.00 0.00 0.00 420.4 467.5 7.9 15.1 0.00 0.00 GSA0736S 1091 GSA Surface FS-36 1722 Area 20 Soil

0.00 0.00 0.00 409.8 434.3 9.9 13.5 0.3 0.00 0.00 GSA0739S 1488 GSA Surface FS-37 1723 I Area 20 Soil 0.00 0.00 0.00 437 402.2 10.6 15.1 0.00 0.00 GSA0746S 1155 GSA Surface FS-38 1728 Area 20 Soil

0.00 0.00 0.00 466.1 370 7 10.3 12.1 0.3 0.00 0.00 GSA0744S 1242 GSA Surface FS-39 1727 Soil Area 20 7.07 3.13 0.43 506. I 371.3 11 6.2 0.5 0.41 1.42 GSA0742S 1601 GSA Surface FS-40 1726 Soil Area 20 6.67 5.11 0.41 365.8 11.3 7.6 0.4 0.55 1.35 GSA0740S 1375 GSA Surface FS-41 1725 532.9 Area 20 Soil 5.12 0.00 0.31 439.9 481.5 7.3 7.6 0.3 0.35 0.97 GSA0734S 1174 GSA Surface FS-42 1724 Soil Arma 20 0.00 0.00 0.00 513.4 a 14.2 0.2 0.16 0.74 GSA0733S 1725 GSA Surface FS-43 1730 472.2 Arm& 20 Soil IIII IIII

P\SITAMTL\FIN\GSA\DRA F-D\APPC D C-78 021595- ( ( C

APPENDIX APPENDIX C

Table C-21 Burn Pit - Surface Soil Samples Gamma Spectroscopy Analyses Results (Continued)

Cocentratio - pCi/g No San 497000 695000 Corcted + + Land Northing Eauting Elevation File Mass Sample Sample Sample Survey Feet Number grams ID I ID 2 ID 3 Point Massachusets Grid K-40 T1-208 Ce-137 Ae-228 Pa-234m Ra-226 1T-234 U-235

GSA0685S 1734 Bum Pit FS-20 1506 259.5 71.3 S 7.0 0.29 0.33 1.07 <3 6.68 0.21

GSA0731S 799.5 GSA Surface FS-44 1729 507.5 505.7 4.7 6.3 1.09 0.00 0.00 0.00 0.00 Area 20 Soil I I

OSA0774S 829.9 Bum Pit Surface FS-45 1711 338 58.4 7.5 15.8 0.3 1.35 0.00 0.00 4.00 0.00 Soil

GSA0772S 584 Burn Pit Surface FS-46 1710 313.6 37.1 7.7 11.7 4.50 0.00 0.00 11.26 0.00 Soil 3j

GSA0770S 923 Bum Pit Surface FS-47 1709 281.2 5.8 7.7 12.5 0.3 1.70 0.00 0.00 0.00 0.00 Soil I III

GSA0767S 1839 Burn Pit Surface FS-48 1708 239.4 35.9 8.4 10.2 0.3 0.34 0.89 0.00 0.00 0.00 Soil I_ II

GSA0768S 1743 Bum Pit Surface FS-49 1707 231.1 8.1 8.3 12.4 0.3 0.49 0.97 0.00 2.80 0.00 Soil

GSA0776S 1393 Bum Pit Surface FS-50 1706 209.8 51.2 8.3 9.8 0.3 0.60 0.00 0.00 0.00 0.00 Soil I

GSA0778S 1647 Bum Pit Surface FS-51 1705 171.6 114.6 8.7 13.8 0.00 0.00 0.00 0.00 0.00 Soil I III

GSA0780S 1865 Bum Pit Surface FS-52 1704 138.1 172.1 8.1 10.6 0.3 0.00 0.00 3.69 4.73 0.22 Soil I I

GSA0782S 1707 Bum Pit Surface FS-53 1703 190.8 246.4 7.8 16.4 0.2 0.46 0.00 0.00 3.80 0.00 Soil

021595-P\STl-rAMTL\FMNOSA\DRAFTDýAPP_(7 1) C-79 K, APPENDIX C

Table C-21 Burn Pit - Surface Soil Samples Gamma Spectroscopy Analyses Results (Continued)

Concentrtion - pCi/g Not Sand 497000 695000 Cofrected + +

Land Northing Lasting Elevation File Mass Sample Sample Sample Survey Feet Number grams ID I ID 2 ID 3 Point Massachuseta Grid K-40 Th-208 Ca-137 Ac-228 Pa-234m RA-226 Th-234 U-235

GSA0685S 1734 Bum Pit FS-20 1506 259.5 71.3 8 7.0 0.29 0.33 1.07 <3 6.63 0.21

GSA0816S 652 Area Surface FS-70 18.5 0.68 0 0 0 0 A25A28 Soil

GSA08IRS l011 Area Surface FS-71 15.1 0.35 1.14 0 10.29 26.5 0.625 A25 A28 Soil

GSA0820S 1032 Area Surface FS-72 10.2 0.31 0 0 4.44 0 A25 A28 Soil I

GSA0822S 890 Area Surface FS-73 13.7 0.26 1.03 0 3.31 16.03 0.504 A25_A28 Soil

0215qi-P\srl\AM'r GSA\DRAFtD\APPC.D C-80( ( ( ( APPENDIX C

Table C-22 Burn Pit In Situ Gamma Spectroscopy Analyses Results (pCli/g)

I ReortedSampleI Reported Reported Estimated Estimated Cose. Fraction Location K-40 Cs-137 Ac-228 Pb-214 Bi-214 Ra-226 Pa-234m Th-234 U-235 U-2350 Ra-226" Material (ICi/g) of Limit FS-20 9.13 0.14 1.00 1.06 1.29 0.00 0.00 4.12 0.20 0.08 2.0 U+d 10.3 1.03 FS-21 10.55 0.13 1.01 1.00 1.10 0.00 8.38 7.17 0.21 0.14 -2.3 DU 10.5 0.30 FS-22 13.41 0.36 0.84 0.94 0.94 0.00 7.60 9.27 0.25 0.18 -2.9 DU 13.6 0.39 FS-23 11.01 0.14 0.96 1.21 1.20 0.00 6.71 8.94 0.23 0.17 -2.8 DU 13.1 0.38 FS-24 12.40 0.25 0.63 0.53 0.63 0.00 24.14 12.74 0.25 0.24 0.1 DU 18.7 0.53 FS-25 9.01 0.12 0.64 0.60 0.62 0.00 5.41 8 39 0.13 0.16 -2.6 DU 12.3 0.35

*From alinsrst.wbl - Ra-226 Critical Level Test

Note 1: This shows the in situ gamma spectroscopy results for the Burn Pit. It is a subset of GSINSALL.WB1. OSINSALL is a composite from INSFRAC2 and ALINSRST. Raw results come from INSFRAC2. The results for Estimated Ra-226 and Estimated U-235 come from ALINSRST. These results are derived through the Ra-2Y6 Critical Level test (see technical basis in GSA report appendix).

Note I - The results for Measured Ra-226 (reported) are all zero. This is because the energy offset for each spectrum was adjusted so that the - 186 keV peak/s were all assigned to U-235. Estimates for Ra-226 and U-235 were then based on the Ra-226 CL test. As the spectroscopy system cannot properly distinguish between the Ra-226 and U-235 peak energies, and there are no confirming lines for either nuclide, this is the most satisfactory method for estimating these nuclides.

C-81 D'.APP (' I) 0"21595-P'SIT\AMTL\FI(¢;SA\DRAF-II),,AppQ2I S9SP'srr\A MTL\ItN\GSA\DRAF1 C"1) C-81 APPENDIX C *

Table C-23 Burn Pit Soil Sample Density and Moisture Content

IDegmty " Moistu-e Location (glcc) Content % FS20 2.3 12.0 FS21 2.2 26.8 FS22 1.7 9.0 FS23 2.0 11.3 FS24 1.8 29.5 FS25 1.5 12.7 Average 1.9 16.9 SMpI Var 0.1 78.3 Smpi SD 0.3 8.8 Max 2.3 29.5 Min 1.5 9.0

021595-P\STLA MTL\FtIOSA\DRAFT''APPYC D C-82 ( V APPENDIX C

G

F SCRAPE SCAN GRID LOCATION

a) D25/EZ5 SCRAPE SCAN BOUNDARY ()- C25 SCRAPE SCAN (3 C26 SCRAPE SCAN E D - EZ5 SCRAPE SCAN E26 SCRAPE SCAN

DU FLAG LOCATIONS D AND SCRAPED AREAS OF BURN PIT

LEC END

{C Chsrlet rlz.ilOn C SC-satd At... •J Scraped Ares

Scraped 0 ArielD~r from

F11lag Locstlons

* Is St. Seeple

B H-bsm•fOrslcb .yr P I e -h.

"STt RW t*TOC 5. CA& L"Týi ?LC GEmi.**l

Figure C-30. The GSA bum pit area showing locations of flags placed during the scan for DU chips and the areas where scraping was done.

C-83 'FIN\GSA\DRAFT!)\APP C r) 021S9S-P',Srr'AMTI.\F[NýGSA\DRAFT)ýAPPCG2IS9 PSITAMT1 D C-83 (_._ _ _APPE: C

Table C-24 Burn Pit - Bulk Soil Samples Gamma Spectroscopy Sample Analyses Results

- = - m i - - I C-Oncratio..-PCi/g Not sawd 497000 695000 Corrcted + I + E~asting Lad Northing LandI Ra- Th- U File Maas Sample Sample Sample Survey Massachusetts Grid Elevation TI- C- Ac- Pa- 234 235 Number grams ID I D) 2 [D 3 Point Feet K-40 206 1371 228 234m 226

<3 <2 < .2 GSA0706DD 1780 Bun No. #1 Lower 1506 279.5 93.3 1.8 15.5 0.98 2.95 Pit Coarse

<2 < 1 <.2 GSA070ODD 1702 Burn No. #1 Lower 1506 279.5 93.3 8.8 10.4 0.22 Pit Fines

<2 < I <.I GSAO707DD 1901 Burn No. #1 Lower 1506 279.5 93.3 8.8 10.7 0.32 0.87 II Pit Middlings I

0.00 2290.00 0.00 GSA0727S 2.5 Burn No. #1 Upper 1506 279.5 93.3 8.8 0.0 2287.1 0.00 0.00 Pit

<3 <2 <.2 GSA0703DD 1685 Burn No. #i Upper 1506 279-5 93.3 8.6 17.1 0.7 1.61 Pit Coarse

4.57 8.23 0.28 GSA0705DD 1481 Burn No. #1 Upper 1508 279.5 93.3 8.8 9.9 0.4 0.28 1.07 Pit Fines I

<2 <.2 GSA0704DD 1754 Burn No. #I Upper 1506 279.5 93.3 8.8 12.9 0.3 <3 Pit Middlings

2.75 6.02 <2 0.36 GSA0712DD 1800 Burn No. #2 Lower 1507 266.5 66.4 7.9 13.7 1.0 Pit Coarse

5.06 6.69 0.31 GSAO714DD 1738 Burn No. #2 Lower 1507 266.5 66.4 7.9 8.0 0.3 0.29 0.65 Pit Fines I II

2.10 2.40 0.13 GSA0713DD 1936 Burn No. #2 Lower 1507 266.5 66.4 7.9 9.3 0.3 0.77 Pit Middlings I I I

3.36 <2 0.23 GSA0709DD 1695 Burn No. #2 Upper 1507 266.5 66.4 7.9 14.5 1.02 2.47 Pit Coarse

021595- PS•SAMTL\FIMOSA\DRAFTD\APP_C. D C-84 ( f APPEý ",

Table C-24 Burn Pit - Bulk Soil Samples Gamma Spectroscopy Sample Analyses Results (Continued)

Comoentruio.- PCI/g Nat Saud 497000 695000 Corrected + I + Easting IAd Northing

Th- U File Mass Sample Sample Sample Survey Massachusetts Grid Elevation TI- Cs- Ac- Pa- Ra- 234 235 Number grams EDI 1) 2 1) 3 Point Feet K-40 206 137 228 234m 226

<3 <2 <.2 GSAOO6DD 1780 Burn No. #I Lower 1508 279.5 93.3 •.8 15.5 0.98 2.95 II Pit Coame

4.46 6.06 0.27 GSA071IDD 1602 Burn No. f2 Upper 1507 266.5 66.4 7.9 3.6 0.3 0.21 0.10 Pit Fines

<2 2.77 <.2 GSA0710DD 1914 Burn No. 92 Upper 1507 266.5 66.4 7.9 12.0 0.4 1.10 Pit Middlings I _I

4.07 0.00 0.25 GSA0718DD 1734 Burn No. 93 Lower 1504 191.9 230.9 7.4 14.3 0.1 0.00 2.14 Pit Coarse I

<2

<2 <.2 GSAOI9DD 1400 Burn No. #3 Lower 1504 191.9 230.9 7.4 1.0 0.4 0.00 0.00 <3 Pit Middlings

<2 <.2 GSA0713S 1022 Burn No. 03 Upper 1504 191.9 230.9 7.4 20.4 0.4 0.00 1.86 <3 Pit Coarse

<3 121.00 2.31 GSAO717DD 1837 Burn No. 03 Upper 1504 191.9 230.9 7.4 13.7 0.3 0.12 0.72 225.0 Pit Fines 4

5.10 4.68 0.31 GSAO716S 1690 Burn No. #3 Upper 1504 191,9 230.9 7.4 17.1 0.3 0.12 1.24 Pit Middling.

C-85 C 1) 071595021595 P\SrTAMTt-\FltN\GSA\DRAFTD\APP_CP\SIT'AMTL\FIN\C3SA\t)RAFTD\APP D C-85 APPENDIX C

DEPLETED URANIUM SCAN RESULTS FOR SCRAPED AREA OF BURN PIT

S CZ RZ .JF= E DI5E25 . . -- 3 INCHEI-IS

1 I.

- I

0 *m - - - inm... .Km..UILULJEIJEEEIlEEEinIKUUEU

-- I S2 4 6-: 6 10 12 1 '16 20 22 22 26 e2 S;Cm jf, nm•. W.,,tm

c EAX E r - i-c :E-: E

I~ I-, I' -I. - - - m ------m - - - m - in . i lu

. 21 2 1 2. 20MW 2.. 5- es 1. 11 12 I 17 2. 6 26 2 4. 6 6 1I0 1•2" '4 16 16 0 22 2 S o..,na,1 r.,tr

c F A.T : r - I m- G I-I 5

'Sr

-I-

0 EU K EE EU •K . - - - .m =L -,. U-m m M EMAu._ KK

.4 2', ' 2 7 9L ' I ' ' 2' 7 1 9 21 2 2 2 2" 2' 22 2 6 6 10 1m2 16es6 20 22 24 28 26 20

Figure C-31. Large area detector scanning for DU at successive depths. Chips are observed for readings over about 2000 dpm/100 cm2 .

021595 -P\Sf\AMTL\FU N\GSA\DRAFTD\APPC.D C-86 APPENDIX C

Figure C-32. At this location chips are observed at all depths.

,595-P','Ir'\AhSTI,\::f\GSA\DRAIý7-D)APP CD C-878 APPENDIX C

DEPLETED URANIUM SCAN RESULTS FOR SCRAPED AREA OF BURN PIT

A-r -3 INTGI-1FLs

'0

0

- - i n, , , - -

-- 6 I 2 5 9 6 8 '0 '2 I -r S ,-,-t-

I

0

5

0 - - - ILm - - -

I 5 5 .7 9 'I '.5 1 5 7 6 8 '0 '2

Figure C-33. No chips are seen at -3 inches, but -6 inches has chips in two square meters. I

021595 •sI'rTAMT'.FIN\•(SA\I)RA|.l')',APP C I) C-88 APPENDIX C

DEPLETED URANIUM SCAN RESULTS FOR SCRAPED AREA OF BURN PIT

Figure C-34. All data was lost for this location for -3 and -6 inches because of instrument failure

021595-P\SITrAMTL\F1\GSA\DRAFTD',APPC D C-89 APPENDIX C

_G

FS rS27 E

•i9D

C

_ 1B

70

8

Figure C-35. Locations of in situ and soil samples in the burn pit and clinker areas -N( ()'I SQSt" ri \FrNGSAJ)PAFTD\APP C 1) APPEI

Table C-25 Clinker Area - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results

497000 695000 Co-ceLrlo - pCi/g HNotSamn Cortcgtlad + + Northing Eaging

Land Elevatio File Mas Sample Sample Sample Survey Co-137 Ac-2n P.-234m Ra-226 Th-234 U-235 Number granum ID I ID 2 ID 3 Point Massachusetts Grid Feet K-40 TI-206

1.41 44.64 10.23 27.00 0.62 GSA0697S 1077 Clinker Surface FS-26 14.48 0.33 Area Soil

0.5 0.44 1.31 5.75 0.00 0.35 CSA0796S 1337 Clinker Surface FS-35 12.2 Area Soil

0.2 0.19 0.00 0.00 0.00 0.00 GSA0798S 2027 Clinker Surface FS-56 14.2 Area Soil

0.2 0.29 0.00 5.60 9.77 0.34 GSA0790S 1657 Clinker Surface FS-57 9,9 Area Soil

0.00 0.73 0.00 0.00 0.00 GSA0792S 1535 Clinker Surface FS-58 13.5 Area Soil

0.3 0.00 0.00 0.00 0.00 0.00 GSA0794S 1538 Clinker Surface FS-59 12.0 Area Soil

0.2 0.00 0.00 0.00 0.00 0.00 CUSA0796S- - 1378 Clinker Surface FS-60 "1g 11.9 Area Soil GSA0798S 1754 Clinker Surface FS-61 14.0 0.30 0.00 0.00 0.00 0.00

Area Soil GSA080OS 1225 Clinker Surface FS-62 11.3 0.2 1.17 0.00 34.26 11.10 19.77 0.67

Area Soil

12.4 0.47 0.00 32.36 0.00 20.14 0.80 GSA0O02S 1626 Clinker Surface FS-63 Area Soil

12.0 0.2 0.34 0.48 53.00 2.93 36.38 0.97 GSA0804S 1730 Clinker Surface PS-64 Area Soil

i0215.5 -I'\SrTA MT L\ FI](SA \DRA l-rDA PP_C D C-91 APPI, x C

Table C-25 Clinker Area - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (Continued)

497000 695000 ComAntration - pciig Not Sand Comesed + + Northing Eastting

Land File Mass Sample Sample Sample Survey Elevation Number grams ID I ID 2 ID 3 Point Mas.achu.tut Grid Feet K-40 TI-206 C&-137 Ac-228 Pa-234m Ra-226 Th-234 U-235

GSA0697S 1077 Clinker Surface FS-26 14.48 0.33 1.41 44.64 10.23 27.00 0.62 Area Soil

GSA0806S 1471 Clinker Surface FS-65 11.3 0.2 0.57 0.70 45.30 15.95 25.79 0.97 Area Soil

GSA080S 1612 Clinker Surface FS-66 11.1 0.6 0.08 1.16 4.73 0.00 0.29 Area Soil

GSAO8 IOS 1396 Clinker Surface FS-67 13.3 0.5 0.00 1.85 0.00 0.00 0.00 Area Soil I

GSA0812S 1396 Clinker Surface FS-68 16.1 0.4 0.33 0.00 0.00 0.00 0.00 Area Soil I

GSA0814S 1396 Clinker Surface FS-69 14.3 0.3 0.00 0.57 0.00 0.00 0.00 Area Soil IIII

(Y21595-.\sITMAMTI.\FIN\GSA\DRAF--I)\APP_(- 1) C-92 ( ! C APPENDIX APPENDIX C

Table C-26 Clinker Area In Situ Gamma Spectroscopy Results

8"**• Frattm Reporuld Reported Eu_.natad Eadumatad Cao,. of Location K-40 C.-137 Ac-223 Pb-214 BI-214 P-234mPa-226 Th-234 U-235 U-235* IRt-2260 Mat al ($Ig/t) Uimit

FS-26 1 10.01 0.44 0.48 0.58 1 0.61 0.00 49.72 53.50 1.49 1.49 0.0 DU 7".7 2.25

*From alinsrst.wMl - Ra-226 Critical Level Test

Note I - This shows the in situ gamma spec. results for the Clinker Area. It is a subset of GSINSALL.WBI. OSINSALL is a composite from INSFRAC2 and ALINSRST. Raw results come from INSFRAC2. The results for Estimated Ra-226 and Estimated U-235 come from ALINSRST. These results are derived through the Ra-226 Critical Level test (see technical basis in GSA report appendix).

Note 2 - The results for Measured Ra-226 (reported) are all zero. This is because the energy offset for each spectrum was adjusted so that the - 186 keV peak/s were all assigned to U-235. Estimates for Ra-226 and U-235 were then based on the Ra-226 CL test. As the spectroscopy system cannot properly distinguish between the Ra-226 and U-235 peak energies, and there are no confirming lines for either nuclide, this is the most satisfactory method for estimating these nuclides.

C-93 (' 1) 021595-P\SI'TAMTL\F1N\GSA\DRA021 S9SP\Srr\AM-rLFIN\GSA\DRAETD\APP M-M~kPP C"1) C-93 APPENDIX C

Figure C-36. Zones for in situ boundary survey

021 595-p"," ft \FDN\GSA\DRAPTD\APP C D APPENDIX C

Table C-27 GSA Boundary In Situ Gamma Spectroscopy Survey - Northeast Concentration pCi/g

Sample, L AO,&

EDI ED2 1 D3 K-40 Cs-137 Ra-226 Pa-234m Th-234 U-235

A 27 13.1 0.1 0.0 0.0 0.0 0.00 B 27 CI 9.2 0.2 0.9 0.0 1.7 0.00 C 27 10.9 0.3 3.2 10.3 10.5 0.00 C 27 CI 11.5 0.1 1.1 0.0 1.3 0.00 A 28 13.4 0.2 0.7 0.0 0.0 0.04 B 28 10.6 0.2 0.7 1.9 0.0 0.04 B 28 CI 9.7 0.1 0.0 -1.8 0.0 0.00 C 28 12.5 0.2 0.0 0.0 1.7 0.12 C 28 Cl 11.7 0.1 2.1 0.0 0.0 0.13 D 28 10.4 0.2 2.0 0.0 4.1 0.00 D 28 CI 11.3 0.1 4.4 0.0 0.0 0.27 A 29 12.7 0.1 1.5 0.0 0.0 0.09 B 29 7.7 0.2 0.0 0.0 0.0 0.00 C 29 8.6 0.2 2.9 0.0 1.4 0.00

021595-P•\Sn'IAMTL\FIN\GSA\DDRAFTD\APPC D C-95 APPENDIX C

Table C-28 GSA Boundary In Situ Gamma Spectroscopy Survey - Northwest Concentration pCi/g

Samp_- _I IDI 1D2 ID3 K-40 Cs-137 Ra-226 Pa-234m Th-234 U-235

G 28 16.4 0.0 0.5 0.0 0.0 0.03 F 31 15.8 0.0 1.8 0.0 0.0 0.11 G 31 CI 16.0 0.1 0.0 0.0 0.0 0.00 F 32 14.9 0.0 1.8 0.0 0.0 0.11 F 32 CI 16.3 0.1 1.3 0.0 0.0 0.08 F 32 C2 15.9 0.1 0.0 0.0 1.1 0.00 F 33 Cl 17.3 0.1 2.1 0.0 0.0 0.13

C-96 if21595- PMHMA MTL\F1n'•SA\DRA FTDA PP C. D C-96 APPENDIX C

Table C-29 GSA Boundary In Situ Gamma Spectroscopy Survey - Southeast Concentration pCi/g

Sampe, LocaofM IDI !1D2 1D3 K-40 Cs-137 Ra-226 Pa-234m Th-234 U-235 B 15 12.8 0.4 0.0 0.0 1.4 0.00 B 15 CI 12.7 0.4 2.6 0.6 0.0 0.16 A 16 11.2 0.6 0.0 0.0 0.0 0.00 B 16 12.6 0.4 2.4 0.0 1.0 0.00 B 16 Cl 10.9 0.4 0.0 0.0 0.1 0.09 A 17 8.9 0.4 0.0 0.0 0.0 0.00 B 17 11.9 0.5 3.2 0.0 0.5 0.00 B 17 CI 13.5 0.4 0.0 0.0 0.2 0.12 A 18 8.7 0.6 2.1 0.0 0.0 0.13 B 18 11.3 0.6 1.2 0.0 0.0 0.07 B 18 CI 12.1 0.4 2.2 0.0 0.0 0.13 A 19 8.9 0.4 0.6 0.0 0.0 0.04 B 19 12.6 0.3 0.8 0.0 0.0 0.05 B 19 C1 11.7 0.4 2.0 0.0 3.0 0.12 A 20 9.0 0.3 2.1 0.0 0.0 0.13 B 20 10.6 0.3 1.9 0.0 1.3 0.00 B 20 Cl 9.7 0.4 0.0 0.0 2.8 0.00 A 21 5.8 0.2 0.0 0.0 0.0 0.00 B 21 9.8 0.3 0.0 0.0 0.0 0.00 B 21 CI 7.7 0.3 1.4 0.0 0.0 0.09 A 22 5.3 0.3 0.6 0.0 -0.2 0.04 B 22 7.4 0.2 1.3 0.0 0.0 0.08 B 22 C1 6.0 0.2 0.0 0.0 0.0 0.00 A 23 6.9 0.3 0.0 0.0 0.0 0.00 B 23 9.6 0.3 0.9 0.0 0.0 0.06 B 23 Cl 8.3 0.2 0.0 0.0 0.0 0.00 A 24 8.6 0.2 1.3 1.6 0.0 0.08 B 24 10.3 0.3 1.9 0.0 0.0 0.12 B 24 Ci 8.6 0.3 1.3 0.0 0.0 0.08 A 25 11.7 0.3 1.9 0.0 2.4 0.11 B 25 12.2 0.1 0.4 0.0 0.0 0.03

021595. PSrRAMTL\F\oGSAA\DRAPTD\A PP_C. D C-97 APPENDIX C

Table C-29 GSA Boundary In Situ Gamma Spectroscopy Survey - Southeast Concentration pCi/g (continued)

Sampie, Location MD1IU2'3 - -4 Cs-137 1 Ra-226 JPa-234m. Th-234 U_____ B 25 CI 11.1 0.3 2.0 0.0 2.6 0.00 A 26 10.9 0.3 0.1 0.0 0.0 0.00 B 26 11.4 0.3 4.1 0.0 3.4 0.00 B 26 Cl 6.2 0.3 1.4 0.0 0.0 0.08 A 27 13.1 0.1 0.0 0.0 0.0 0.00 B 27 10.2 0.4 2.5 0.0 3.6 0.00 B 27 CI 9.2 0.2 0.9 0.0 1.7 0.00 A 28 13.4 0.2 0.7 0.0 0.0 0.04 B 28 10.6 0.2 0.7 1.9 0.0 0.04 B 28 C1 9.7 0.1 0.0 -1.8 0.0 0.00 A 29 12.7 0.1 1.5 0.0 0.0 0.09 B 29 7.7 0.2 0.0 0.0 0.0 0.00 B 29 C1 10.7 0.1 0.0 0.0 0.0 0.00 B 30 11.9 0.2 0.0 0.0 0.0 0.00 B 30 CI 12.1 0.2 0.0 0.0 0.0 0.00 B 31 10.4 0.1 3.6 0.0 2.0 0.00 B 31 Cl 12.5 0.2 0.0 0.0 0.0 0.00 B 32 10.4 0.2 0.0 0.0 0.0 0.00 B 32 C1 9.3 0.1 1.8 0.0 0.0 0.11 B 33 9.4 0.2 0.0 0.0 0.0 0.00 B 33 Cl 7.3 0.1 2.6 0.0 3.0 0.16 C 33 C1 5.1 0.0 0.0 0.0 2.9 0.30 B 34 10.3 0.2 1.3 0.0 0.0 0.08 B 34 CI 7.2 0.2 0.0 0.0 0.0 0.00

021595-PP'SITLM\k\FOSA\DRAFTD\A PP C. D C-98 APPENDIX C

Table C-30 GSA Boundary In Situ Gamma Spectroscopy Survey - Southwest Concentration pCi/g

Sample, LoIation IDI ID2 ID3 K-40 Cs-1D7 Ra-226 Pa-234m Th-234 U-235

H 10 17.4 0.1 1.7 0.0 0.0 0.10 H 11 12.0 0.3 1.5 0.0 0.0 0.09 H 11 R 9.5 0.2 1.0 0.0 0.0 0.06 I 5 13.8 0.1 0.0 0.0 0.0 0.00 I 6 14.3 0.0 0.0 0.0 0.0 0.00 I 7 11.0 0.1 1.3 0.0 0.0 0.08 I 7 C1 11.7 0.3 0.0 0.0 0.0 0.00 I 8 10.2 0.1 0.0 0.0 0.0 0.00 I 8 CI 10.8 0.2 1.8 0.0 0.0 0.11 1 9 8.3 0.2 1.4 0.0 0.0 0.09 I 9 CI 10.7 0.2 2.5 0.0 0.0 0.15 J 3 13.0 0.1 0.0 0.0 0.0 0.00 J 3 C1 11.9 0.1 0.0 0.0 0.0 0.00 J 4 11.9 0.1 0.0 0.0 0.0 0.00 J 4 CI 12.5 0.2 0.0 0.0 0.0 0.00 i 5 11.0 0.2 2.0 0.0 0.0 0.12 1 6 11.4 0.1 1.7 0.0 0.0 0.10 J 6 CI 9.7 0.2 0.0 0.0 0.0 0.00 J 7 CI 9.6 0.2 0.0 0.0 0.0 0.00 K 3 13.7 0.1 0.0 0.0 0.0 0.00 K 3 Cl 14.3 0.0 0.0 0.0 0.0 0.00 K 4 13.4 0.0 0.6 0.0 0.0 0.03 L 2 14.4 0.1 0.0 0.0 0.0 0.00 L 2 CI 16.9 0.1 3.9 0.0 0.0 0.24

021595- PSIT\AMTL\F1F\GSA\D RAFTD-APPC D C-99 APPENDIX C

C;SA WINBOPNE LOCATIONS

/ GSA PROPERTY PROPERTY SITE / P R / / / /

SwBt ~o 0]I S08 W3 04W5

Figure C-37. Location selected for sampling for windborne deposition of depleted uranium

02159• PSIT V\FIN\CGSA"DRAFTDAPPC D CM I " K , APPENDIX C

Table C-31 Windborne - Surface and SubSurface Soil Samples Gamma Spectroscopy Sample Analyses Results

49700o 695000 Co-cmai-ou - PCi/g Not Saed Coryccted + + Northing Eauing

File Mas Sample Sample Sample Survey Elcvaioo Pa No. grams ID I ID 2 ID 3 Point M-achuscm Grid Feet K-40 TI-208 C4-137 Ac-221 234m Ra-2.6 Th-234 U-235

GSA0584S 834 East of Wndborne I No. i 1540 110.8 396.7 1!. 15.1 0.23 0.77 0.91 <2 <1

GSA0601S 1178 East of Windbor-t 2 No. 1 1539 195.4 643.5 11.5 1.3 0.28 <3 <2 <.2 Greenough

GSA0603S 1060 Ear of Wilndborne 2 No. 2 1539 195.4 643.5 11.5 7.1 0.2 0.29 <3 <2 <.2 Greenough I I

GSAO0O4S 982 ERa of Windborne 3 No. 1 1565 291.7 541.2 10.S 15.4 0.27 <3 <2 <.2 Greenough _ I I

GSA0599S 949 East of Windborne 3 No. 2 1565 291.7 541.2 10.3 15.5 0.34 <3 <2 <.2 Greenough

GSA0559S 1181 Euitof Windborne 4 No. 1 1564 372.4 606.4 11 11.8 0.23 <3 <2 <.2 Greenough

GSA0607S 967.8 East of Wiadborne 4 No. 2 1564 372.4 606.4 11 16 0.34 <3 <2 < .2 ______Greenough ______

GSA0605S 797 East of Windborne 5 No. I 1563 439.2 TQ.9 5.4 14.2 1.04 <3 <2 < .2 Greenough 2_ GSA0606S 673.7 East of Windborne 5 No. 2 1563 439.2 663.9 5.4 9.8 2.36 <2 < I <.I

Greenough I I I___II___F

02I595-P\SITrAMTI \FIN\GSA\DRAFrD',APP C 1) C-101 C

APPENDIX C

GSA. PROPERTY 20 In Situ Gammra Spectroscopy and Soil Sample Locations / APPENDIX • E

FS9 S I GSA 40 S FS17 PROPERTY 20 I~~ )* I FF1 D

0 FS4 • 0t C

FS37 F FSI5' B _ •,,N• • ' LWBE ...... A A LEGEND FS4Z FS43 FS36 A Sod Sample only 31 32 33 34 35 36 3? * In Situ measurement and Soil Sample I

Figure C-38. Property 20 - Locations of in situ and soil sample measurements

02095-,p "TL',FGSA\DRAFTD)APP-Cr D C-l) ( APP"

Table C-32 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results

497000 695000 Cossotraoo.- pCi/g Not Sud + + Comeind Land Northing Eaning_ File Mass Sample Sample Sample Survey Elevation Number grams ID I ID 2 ID 3 Point Massachusetts Grid Feet TI- CO- Ac- Pa- Ra- T11- U K-40 206 137 221 234m 226 234 235

GSA0616S 1541 GSA Surface FS-01 1547 438.4 445.5 10.1 0.63 1.66 19.70 13.00 1.20 Area 20 Soil_ _ _

GSA0618S 1335 GSA Surface FS-02 1542 463.1 418 I1.1 7.5 0.35 1 31.43 9.50 16.30 0.58 Area 20 Soil I I

GSA0620S 1446 GSA Surface FS-03 1545 484.2 444.3 10 3.93 0.29 0.2 8.10 7.70 0.49 Area 20 Soil

GSA0624S 1632 GSA Surface FS-04 1543 482.9 419.1 10.8 2 0.73 2.39 42.24 10.30 13.20 0.63 Area 20 Soil

GSA0622S 1415 GSA Surface FS-05 1548 486.4 393.5 10.7 3.14 0.52 1.51 191.13 0.00 91.50 2.39 Area 20 Soil

GSA0626S 1337 GSA Surface FS-06 1550 506.2 417.9 10.4 3.94 0.37 0.9 5.00 4.90 0.30 Area 20 Soil

GSA0664S 1459 GSA Surface FS-07 1546 451.4 459.7 9.5 0.74 1.6 21.30 9.79 1.32 ""-U,, Area 20 Soil 1)3 1

GSAU628S 1249 GSA Surface FS-08 1549 531 394.7 9.3 9.07 0.33 0.22 1.03 5.69 7.50 0.35 Area 20 Soil IIII

GSA0630S 1040 GSA Surface FS-09 1551 522.2 351.7 11.2 12.17 0.24 0.21 0.00 0.00 0.00 Area 20 Soil I I_ II

GSA0632S 1371 GSA Surface FS-10 1552 556.8 371.3 10.2 15.0 0.32 <3 <2 <.2 Area 20 Soil I_1 _1

GSA0666S 1367 GSA Surface FS-II 1557 543.4 473.4 8.3 14.9 0.22 0.13 0.96 <3 <2 <.2 Area 20 Soil

C-103 C D 021595-021595 P\SrFI'AP\Sfl MTITIAFIN\OSA\DRAlTD\APP .\ F I•SAN\D RA I-'DýA PPC.D C-103 K APPENDIX C

Table C-32 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (Continued)

497000 6950 COOcrsriom- pCi/g Not Sod + + Comffeed Land Northing I Eadinm File Mas Sample Sample Sample Survey Elevation Number grams ID I ID 2 1) 3 Point MUSachuseus Grid Feet TI- Cs- Ao- Pa- Ro- TI- U K-40 208 137 228 234m 226 234 235

GSA0682S 1434 GSA Surface FS-13 1562 583.8 593.3 6.8 11.9 0.73 0.34 1.68 <3 <2 <.2 Area 20 Soil

GSA0670S 1228 GSA Surface FS-14 1558 510 473.1 9 13.9 0.36 <3 <2 <.2 Area 20 Soil

GSA0672S 1324 GSA Surface FS-15 1559 490.9 496.5 8.6 9.8 0.34 0.1 1.52 8.18 3.90 0.50 Area 20 Soil

GSA0674S 1313 GSA Surface FS-16 1556 529.5 450.4 9.4 16.0 0.23 0.342 0 <3 <2 <.2 Area 20 Soil I II

GSA0676S 1358 GSA Surface FS-17 1554 565.9 424.8 9.6 13.7 0.29 0.16 <2 <2 <.2 Area 20 Soil II

GSA0678S 1172 GSA Surface FS-18 1555 563.5 450.4 7.3 11.5 0.16 <3 <2 <.2 Area 20 Soil I I

GSA0680S 1043 GSA Surface FS-19 1561 614.5 546.5 7.2 16.8 0.3 <3 <2 <.2 Area 20 Soil I II

GSA0736S 1098 GSA Surface FS-36 1722 420.4 467.5 7.9 15.1 0.00 0.00 0.00 0.00 0.00 Area 20 Soil

GSA0738S 1488 GSA Surface FS-37 1723 409.8 434.3 9.9 13.5 0.3 0.00 0.00 0.00 0.00 0.00 Area 20 Soil

GSA0746S 1155 GSA Surface FS-38 1728 437 402.2 10.6 15.1 0.00 0.00 0.00 0.00 0.00 Area 20 Soil

GSA074AS 1242 GSA Surface FS-39 1727 466.1 370.7 10.9 12.1 0.3 0.00 0.00 0.00 0.00 0.00 Area 20 Soil

021595-P\S rL\FIN\GSA\DRA F"D.A PP_C 1) c lo( ( (

APPENDIX C

Table C-32 Property 20 - Surface Soil Samples Gamma Spectroscopy Sample Analyses Results (Continued)

497000 69550" C-9-6 - pCig No Saad + + Conm Law No EiEan gti File Mass Sample Sample Sample Survey Elevation Number grams ID I ID 2 ID 3 Point Maaachusctts Grid FNot TI- Ca- Ac- Pa- Ra- TIV U K-40 206 137 228 234m 226 234 235

GSAO742S 1601 GSA Surface FS-40 1726 506.1 371.3 1 6.2 0.5 0.41 1.42 7.07 3.13 0.43 Area 20 Soil

GSA074OS 1375 GSA Surface FS-41 1725 532.9 365.8 11.3 7.6 0.4 0.55 1.35 6.67 5.11 0.41 Area 20 Soil

GSA0734S 1174 GSA Surface FS-42 1724 439.9 481.5 7.3 7.6 0.3 0.35 0.97 5.12 0.00 0.31 Area 20 Soil

GSA0733S 1725 GSA Surface FS-43 1730 472.2 513.4 8 14.2 0.2 0.16 0.74 0.00 0.00 0.00 Area 20 Soil

GSA0731I 799.5 GSA Surface FS-44 1729 507.5 505.7 4.7 6.3 1.09 0.00 0.00 0.00 0.00 Area 20 Soil

C-105 \I-IN\GSA\DRAFTE)'A PP C 1) 0"21Y'95-P\SITRAMTI.\F1•GSA\I)RA021 S9S.P\S[T'AMTI FTD•A PP_ 1") C- 105 APPT X C

Table C-33 Property 20 In Situ Gamma Spectroscopy Sample Analyses Results

Reported R.lrud Edmautd Fjimalad Cer. Frecdon Locatioo K-40 Co-137 Ac-225 Pb-214 BI-214 Ra-226 Pa-234m Tr-234 U-23S U-2350 R1s-226* Matajal (PGid[) of Iimt

FS-01 5.34 0.15 1.03 2.77 3.20 0.00 16.05 4.27 0.47 0.06 6.4 U+d 15.0 1.50o I

FS-02 6.34 0.10 0.79 1.55 1.77 0.00 15.38 7.20 0.35 0.14 -2.3 DU 10.6 0.30 FS-03 7.89 0.18 0.88 1.92 2.03 0.00 0.00 350 026 0.07 3.2 U+d I0.3 1.03

FS-04 5.85 0.11 1.21 2.09 2.39 0.00 7.44 9.82 0.38 0.19 3.2 U+d 23.0 2.30

BS-O5 6.07 0.19 0.78 1.58 1.78 0.00 13.75 6.16 0.24 0.12 1.9 U+d 14.4 1.44

FS-06 9.18 0.13 0.86 1.49 1.56 0.00 1.74 2.27 0,00 0.04 -0.7 DU 3.3 0.10

FS-07 4.93 0.14 0.93 2.61 3.17 0.00 0.00 3.11 0.26 0.06 -1.0 DU 4.6 0.13

FS-O8 9.28 0.17 0.67 1.01 1.33 0.00 0.00 0.00 0.16 0.00 0.0 DU 0.0 0.00

FS-09 10.32 0.22 1.08 0.79 1.03 0.00 0.00 0.00 0.16 0.00 0.0 DU 0.0 0.00

FS-IO 14.22 0.08 0.61 0.55 0.63 0.00 0.00 0.00 0.00 0.00 0.0 DU 0.0 0.00

FS-Ii 12.11 0.12 0.54 0.50 0.50 0.00 0.00 0.00 0.00 0.00 0.0 DU 0.0 0.00

FS-12 10.31 0.16 0.66 0.59 0.55 0.00 0.00 0.00 0.06 0.00 1.3 U+d 1.3 0.13

FS-13 12.12 0.12 0.49 0.48 0.52 0.00 0.00 0.00 0.00 0.00 0.0 DU 0.0 0.oo

FS-14 11.37 0.19 0.64 0.58 0.67 0.00 0.00 0.00 0.09 0.00 1.4 U+d 1.4 0.14

FS-15 11.19 0.13 0.70 0.64 0.74 0.00 0.00 0.00 0.09 0.00 1.5 U+d 1.5 0.15

FS-16 12.52 0.17 0.63 0.55 0.60 0.00 0.00 0.00 0.07 0.00 1.1 U+d 1.1 0.11

FS-17 13.44 0.12 0.73 0.56 0.63 0.00 0.00 0.00 0.00 0.03 .0.6 DU 2.7 0.08

FS- 18 12.47 0.18 0.65 0.62 0.78 0.00 0.00 0.00 0.06 0.00 0.9 DU 0.0 0.00

S-1 9 12.69 0.16 0.59 0.47 0.52 0.00 0.00 0.00 0.00 0.00 0.0 DU 0.0 0.00

021595- P\Srr\A MTL\FIN\GSA \)RAI-D\A PP C 1) C-106 ( ( APPENDIX C

Table C-33 Property 20 In Situ Gamma Spectroscopy Sample Analyses Results (Continued)

*From alinarst.wi - Ra-226 Critical Le'vel Test

Note I - This shows the in situ gamma spec. results for the Property 20 measurements. It is a subset of GSINSALL.WB1. OSINSALL is a composite from INSFRAC2 and ALINSRST. Raw results come from INSFRAC2. The results for Estimated Ra-226 and Estimated U-235 come from ALINSRST. These results are derived through the Ra-226 Critical Level test (see technical basis in GSA report appendix).

Note 2 - The results for Measured Ra-226 (reported) are all zero. This is because the energy offset for each spectrum was adjusted so that the - 186 keV peak/s were all assigned to U-235. Estimates for Ra-226 and U-235 were then based on the Ra-226 CL test. As the spectroscopy system cannot properly distinguish between the Ra-226 and U-235 peak energies, and there are no confirming lines for either nuclide, this is the most satisfactory method for estimating these nuclides.

C-107 C [) (Y21595-021595 PNsrrAP\S[T\AMTL\FIN\GSA\DRAVfI)\APP MTI-\FM]GSA\ DRA F'TIA PP-C. D C- 107 APPENDIX C

Table C-34 Property 20 Soil Sample Density and Moisture Content

"In-earth" Densty MoSMre Location (g/cc) Content %

FSI 1.4 4.5 FS2 1.5 10.4 FS3 1.5 9.2 FS4 1.9 6.4 FS5 1.6 9.2 FS6 1.5 10.1 FS7 1.5 14.6 FS8 1.4 7.9 FS9 1.4 16.9 FSIO 1.6 8.2 FSII 1.0 8.8 FSI2 1.6 29.7 FSI3 1.3 -0.1 FSI4 1.4 -1.0 FS15 1.2 0.8 FS16 1.5 6.7 FSI7 1.8 9.3 FS18 1.6 16.8 FS19 1.1 10.7

Average 1.5 9.4 Smpi. Var 0.0 48.4 Smpl SD 0.2 7.0 Max 1.9 29.7 Min 1.0 -1.0

0r21595-P\SmTAMTL\FIN'\OSA\DRAFTD\APPC D C-108 APPENDIX C

Table C-35 GSA Soil from Woods North of Perimeter Fence Gamma Spectrum Analyses (pCi/g)

Sample Number Location K-40 Cs-137 11-208 Bi-212 Pb-212 Bi-214 Pb-214 Ra-224 Ra-226 Ac-228 Th-234

GSA271S l@surf 0.69 2.46 9.03 9.15 18.06 1.84 5.22

GSA272S 1@18- 0.59 1.13 2.27 8.42 8.25 18.87 1.66 5.70

GSA276S 1@3' 0.26 1.04 2.64 2.68 6.14

GSA273S 20surf 0.32 1.54 6.56 6.87 13.34 1.35

GSA274S 2@!8' 0.46 1.83 5.52 5.90 10.65 1.08 6.26

GSA275S 2@3' 2.76 0.50 0.66 1.60 5.53 5.01 1.17 6.90

C-109 C I) O2159•i-P\SIT',AMTI-\FNI•GSA\DRAýTII)•,APPO2I9S P\SrEAN4TL\FIN'USA\DRAVTfl'APP C" ) C- 109 APPENDIX F

"PENDEK F

TOUMINATION SURVEY AIFMODS

(121595-PýSrrýAMTLkFMGSAkDRAf-TDýAI'P F 1) APPENDIX F

APPENDIX F TERMINATION SURVEY METHODS

Final (termination) surveys were performed in Building 237, in the annex of Building 235, in Building 653 (Pumphouse), and in several manholes, to determine acceptability for unrestricted use. This task required the performance of surveys on building surfaces for removable and fixed contamination, and gamma exposure rate measurements at one meter from the building surface. Sludge samples were taken from the manholes. The final survey was performed using procedures established for the MTL facilities decommissioning in AM7L Termination Surveys Work Planfor Decommissioning, Demolition and Site Restoration of the Research Reactor and Decommissioning of the Radiation Facilitiesat the U.S. Army Materials Technology Laboratory, Watertown, Massachusetts.

1. BUILDING FINAL SURVEY METHODS

The building termination surveys consisted of:

* Dividing the floor and walls up to two meters above the floor of Building 235 annex into one-meter grids.

0 Dividing the floor and walls of Building 237 (the shed) into one-meter grids.

Performing a 100 percent beta scan of all surfaces.

* Collecting five surface alpha/beta measurements, one gamma exposure rate measurement at one-meter from the surface, and one smear from each grid.

* Collecting 250 alpha/beta measurements, 50 gamma exposure rate measurements, and 50 smears on the ceiling and overhead horizontal surfaces in the annex of Building 235.

* Collecting 50 alpha/beta measurements, 15 gamma exposure rate measurements, and 15 smears on the ceiling and overhead horizontal surfaces in Building 237. * Collecting ten alpha/beta measurements in front of the overhead door on the north side of

Building 235 annex.

The gridding for the buildings is shown in figures ? through ?.

021595-P\SIT\AMTL\FINGSA\DRAF--TD\APP F D F-1 APPENDIX F

^. ..' i ...... :. .- .. y...... , ...... , , , . i , .. . A or ...... , • 3 4' 6 7 8 9 1011 1Z 13,14 5 16 17,18 9 •Q ZI Z•2.4.Z Z5 WALL I SJMVEYD 1M M4 A^FECTEM Z2610IOW01 7OLLOSIG WKMNFIT MAXCSOIL ANALSIS AREA

RUA EXISTNG

A a 9 H :RMA: : a : -: :! : ...... ; . :

G 3 F' 4 5 E 5, 4 3 A Z

BA 1 . 3 4 567?8910 I lItI 13 14 15 16 17 18 19 Z0Z1&• 3 Z4 Z5

WALL 4 FLOOR Z261010W04 WALL 2 Z2610101FOI Z26101OW02

Z5 Z4 !3 ZZ ZI ZO 19 IS 17 16 5 14 13 1Z 11 10 9 8 7 6 5 4 3 Z 1 A

WALL 3 Z261010W03

GSA (GRIDS)

Figure F-1. Building 235 Annex grids

0f22595- PS/TlAMTLUL1OSA\DRAPTD\APP F D F-2 APPENDIX F

Ae 1 I 3, 4 5 6 7 6 9 14 II U 13 14 15 16 I IS 19 20I Zl 2223 4 45

WALL I

A a

HI 3 -7 £ 4 6 F" S U U 6 4 D 7 3 C 2 8 9 I. I Aw 5 A I Z 3 4 S 6 7 1 g1 11 013 14 15 1617 14 19 ESZi ZZ 3 Z4

WALL 4 FLOOR WALL Z

25 Z4 Z3 ZZ1E 19 is 17 16 15 14 13 1Z It 10 9 1 7 6 5 4 3 . I

WALL 3

STRUCTURE 8 STRUCTURE 11 Z26101eS0t6 -6101@S11 ...... :$..:::i.

STRUCTURE 4 STRUCTURE 3 STRUCTURE I STRUCTURE 6 Z2610101" / 261010O54 5 2.6101S44 ZZ61010S03 Z.261010SO6 STRUCTURE E[i

VENT I STRUCTURE Z VENT 3 Z261010SO2 2261010 VO3

CEILING V6114Ses7 226104510S 2261010COI LEGEND -VMrS GSA Sw'JCT'.E (STRUCTURES & VENTS)

Figure F-2. Building 235 Annex structures & vents

O21595-P\Sr'AMTL\PINF OSA[)PRAF-Trl)ýAPP F I) F-3 APPENDIX F

STRUCTURE 16 STRUCTURE 15 STRUCTURE 14 STRUCTURE 13 STRUCTURE 12 Z261010S16 Z261010S15 Z261010S14 Z261010S13 Z.6101SI2

CEILING Z261010C01

GSA (CEILING)

Figure F-3. Building 235 Annex ceiling

021595-P\SI'rAMTL\kPN\OSA\DRA FrD\APP F. D F-4 APPENDIX F

__ I II B I I A 1 2 3 4 5 6 7 8 9 10 11

WALL I Z?8100OW01

A B 13 C i 2 Bi 3

B A 1 2 3 4 5 6 7 8 9 10 11 FLOOR WALL 2 WALL 4 Z281000W02 Z281000W04 Z281000F01

11 10 9 8 7 6 ' 5 4 3 2 1 B;

WALL 3 Z28100OW03

N

CEILING GSA Z281000I01 (GRIDS)

Figure F-4. Building 237, room 100 grids

O21 95,-P\SrI'rA TL\FIN\GSA\DRA FTI)A PP F D F-5 APPENDIX F

2. BUILDING 653 (PUMPHOUSE) FINAL SURVEY METHODS

Gamma Exposure Rate measurements were made at 57 locations.

Direct alpha/beta measurements were made at 369 locations.

Gridding for the pumphouse final survey is shown in Figure F-5.

APPENDIX F Survey Unit ID GSA

SUMP PUMP AND PIPING Sol

WALL I WALL 3

SUMP COVER PLATE MANHOLE INTO SUMP WALL 4

ELECTRIC CEILING PANEL S03

GSA BLDG 653 PUMP HOUSE

Figure F-5. Gridding for Building 653 pumphouse

021595-P\SrflAMTL\FINGSA\DRAFrD\APP F D F-6 APPENDIX F

3. MANHOLE FINAL SURVEY METHODS

The manhole survey consisted of:

0 Collecting and analyzing two sediment samples from two unlabeled sewer manholes outside of Building 235. These samples were not dried due to potential biological hazards. 0 Collecting and analyzing one water sample from manhole #147; sediment was not

available due to flowing water in this manhole.

Locations of the manholes are shown in Figure F-6.

GSA PROPERTY SITE

+ + + + MANHOLES

+ + ++

\ + . .. +•'4...•. . . • 4 - 4

+ / + + ...... PR......

r+ +

t+ + + . . .#• . .. . . -4+ + + + + 4- + .. • +++ + + + + + 0+ + c + + + ++ + + + 4+ . . . .- . .. .• . ._ .• . .• ...... + ++ 9+ +

A- + + 1 NI 11

#147

NOTE i5xISN GRID LAYOUT SW0IN BUT NOT TO SCALE FILE. SEC ASSTLkII4 C\C1D06\GCD\GSA\SI"E1hAPS\MAI4IOIIS GCl)

Figure F-6. Locations of manholes at the GSA site

(721595-P•SfT'IAMTI.\FIN'OSA\DRAI-TD\APP P 1) F-7 APPENDIX F MK & SEG: METHOD FOR CALCULATING DEPLETED URANIUM OR URANIUM PLUS DAUGHTERS BASED ON TH-234, RA-226, AND U-235 APPENDIX J

APPENDIX J METHOD FOR CALCULATING DEPLETED URANIUM OR URANIUM PLUS DAUGHTERS BASED ON TH-234, RA-226, AND U-235

1.0 PURPOSE

The purpose of this document is to describe the logical process used to determine the amount of depleted uranium or uranium plus daughters in a sample of depleted uranium. The process is based on analysis of the 186 keV peak in a gamma spectrum. The result will be assigned to either uranium-235 or radium-226.

2.0 DISCUSSION

The concentrations of Th-234, U-235 and Ra-226 in samples of soil bearing DU or U+d can be analyzed with a high resolution gamma spectrometer (laboratory or field based).

If the concentration of DU and/or U+d in the sample is low, the gamma spectrometer cannot differentiate between Ra-226 and U-235 in the sample. Unfortunately, this occurs near the acceptable limits of concentration.

The confusion occurs because Ra-226 and U-235 both emit their most significant gamma ray at a peak energy of "186 keV. Ra-226 has no other significant gamma peak; U-235 has other peaks of low yield at 143.5 and 16. keV. When the concentrations of the nuclides are low, the 186 keV peak result is often reported as both Ra-226 and U-235, though it can be reported as either one.

When the concentration of U-235 in the sample is high enough, the gamma spectrometer can identify and quantify the 143.8 keV (and sometimes the 163.3 keV peak), thus providing a mechanism to properly split the 186 keV result between U-235 and Ra-226, giving correct answers for both nuclides.

If the 143.8 keV peak is not detected in the spectrum, the question is, how to tell whether the sample contains only U-235, only Ra-226, or both?

In DU, the ratio of Th-234 to U-235 is fixed and known. The concentration of Th-234 can be measured independently of the U-235. Thus it is possible to calculate the expected result for U-235 once the concentration of Th-234 is measured.

Subtracting this value for U-235 from the result reported via the 186 keV peak measurement, gives us the amount of the 186 keV peak to assign to Ra-226, and the concentration of Ra-226, when an appropriate yield factor is introduced. Thus we can assign the area of the 186 keV peak to U-235, or Ra-226, or a mixture of the two, by measuring the Th-234 and the 186 keV line.

021 55-P'SrrmA FIN\OSFA\DRAFrD'AP I J.JD J-1 APPENDIX J

3.0 BASIS FOR DECISION

If the analysis of the 186 keV peak is not determined to be U-235 by virtue of the existence of a 143.5 keV peak, then the decision of whether the peak area should be assigned to Ra-226 or U-235 will be based on the value of an estimated Ra-226 result if it exceeds the error in the estimated Ra 226 (exceeding Critical Level).

4.0 DECISION PROCESS

The decision process is a function of the analysis techniques and reporting practices of the gamma spectroscopy software employed for sample analysis. This document is based on the use of Canberra Industries Genie-PC gamma spectroscopy software. The gamma spectroscopy software configuration can produce reports for the 186 keV peak which identify it in the following ways:

* As U-235 and Ra-226 when both are present in the sample;

* As U-235 and Ra-226 when only one nuclide is present. This is the most common form of report;

* As U-235 (verified by the presence of the 143.5 keV peak);

* As U-235 when the source really is U-235 (but the 143.5 keV peak is not reported);

* As U-235 when the source really is Ra-226;

• As Ra-226 when the source really is Ra-226;

* As Ra-226 when the source really is U-235;

Table J-1 shows the actions needed to generate an appropriate result when the nuclides of interest are reported with values above zero, in their various combinations. Not all permutations of the variables are shown here, because some of them are not viable under these circumstances, and are irrelevant to the discussion.

021595-PISrrAKMTLWINOGRA\DRAFTDDAPPI.D J-2 APPENDIX J

Table J-1 - Actions Required to Produce an Appropriate Answer for DU and U+d Calculations

Nuclides reporting > zero Uranium Action required to assign 186 keV peak to concentration verified by Ra-226, U-235, or both 143.5 keV peak

Th-234 Ra-226 U-235

Y N Y Y Use values as reported.

Y Y Y Y Use values as reported.

Y N Y N Calculate estimated U-235, Ra-226, and their errors. Perform Critical Level test for Ra 226 to assign portions of the 186 keV peak area.

Y Y N N Calculate estimated U-235, Ra-226, and their errors. Perform Critical Level test for Ra 226 to assign portions of the 186 keV peak area.

y Y Y N Calculate estimated U-235, Ra-226, and their errors. Perform Critical Level test for Ra 226 to assign portions of the 186 keV peak area.

Y N N N Use values as reported.

N Y N N Use values as reported.

N N N N Use values as reported.

N N Y N Calculate Ra-226 concentration and error values from the U-235 values. Report Ra 226 values and set U-235 to zero.'

N Y Y N Use Ra-226 concentration and error values as reported. Set U-235 to zero.

02 1 5-P\SrrA.MMlT LA\DRAFTAPJ). D J-3 APPENDIX J

The logical steps required to implement the actions described in Table J-1 are described below, in gross form. The calculation of estimated values for U-235, Ra-226, and their uncertainties (errors) is described later, with the Ra-226 Critical Level test.

Logic to Generate Results from Gamma Spectrum Analysis If a U-235 143.5 keV peak is present then use reported values for nuclides;

otherwise, If there is no 143.5 keV peak available, then

If no thorium-234 result is present, then

If both Ra-226 and U-235 are reported then, do not report U-235 (set it to zero),

Otherwise, if only U-235 is reported, then

Calculate and report equivalent Ra-226, set U-235 to zero,

otherwise, only Ra-226 is reported, then

Use reported values for Ra-226

otherwise, Thorium-234 was reported, then

Calculate estimated U-235 and Ra-226, Perform Ra-226 Critical Level test and calculate amount of material, and Use computed values for nuclides.

The processes required to perform the functions to:

Calculate Estimated U-235 and Ra-226; Perform Ra-226 Critical Level test and calculate amount of material are described below:

021595- P•L%.•sAcrLF\GSA\DRAFrDDAPP J.D J-4 APPENDIX J

4.1 Calculate Estimated U-235 and Ra-226

The inputs to this calculation are the reported concentrations of Th-234 and Ra-226.

Calculate the Estimated U-235, based on the Th-234 value reported by Genie-PC, i.e.

(Th-234/52.5);

Convert the reported Ra-226 to interim U-235, by dividing Ra-226 by 16.43;

Subtract the Estimated U-235 from the Interim U-235 to obtain the Excess U-235;

Convert the Excess U-235 back to Estimated Ra-226 by multiplying Excess U-235 by 16.43;

Compute the error for the Estimated U-235 and Estimated Ra-226 by the square root of the sum of the squares of the errors method.

4.2 Perform Ra-226 Critical Level Test and Calculate Amount of Material

The inputs to this calculation are the Th-234 value, the Estimated U-235 and Estimated Ra-226 values and their errors, from the above calculations.

The Critical Level is the 95 % confidence level error associated with the result for Estimated Ra-226.

If the Estimated Ra-226 exceeds the Critical Level, then calculate and assign the material as U+d, otherwise calculate the material as DU;

If the material is DU, then calculate the amount of DU as, 1.47 x Th-234;

If the material is U+d, then calculate the amount of U+d from, 2 x Th-234 + Estimated Ra 226 + Estimated U-235;

If the material is DU, then calculate the error in the amount of DU from, 1.47 x Th-234 error;

If the material is U+d, then calculate the error in the amount of U+d from:

Square Root of { [Estimated Ra-226-error]f2 + [2 * Th-234-error]f2 + [Estimated U-235-error]^2 };

Note: The errors reported by the Genie PC are at the 95% confidence level.

(1). U-235 cannot exist without Th-234 being present. Thus, if U-235 is reported with zero Th-234, then we conclude that it is really Ra-226.

02t 595- PSrrAMATLUJ7IN\O8A \DRA TD\.APP i .D J-5 APPENDIX G

ATSDR PUBLIC HEALTH ASSESSMENT (SELECTED PAGES) PUBLIC HEALTH ASSESSMENT

MATERIALS TECHNOLOGY LABORATORY (U.S. ARMY)

WATERTOWN, MIDDLESEX COUNTY, MASSACHUSETTS

CERCLIS NO. MA0213820939

ARMY SECTION FEDERAL FACILITIES ASSESSMENT BRANCH DIVISION OF HEALTH ASSESSMNENT AND CONSULTATION AGENCY FOR TOXIC SUBSTANCES AND DISEASE REGISTRY DEPARTMENT OF HEALTH & HUMAN SERVICES Public Health Service

Agency for Toxic Substances and Disease Registry Atlanta GA 30333 December 26, 1995

Mr. Dennis Waskiewicz U.S. Army Corps of Engineers 424 Trapelo Road Building 112S Waltham, MA 02254-9149

Dear Mr. Waskiewicz: Enclosed please find a copy of the Agency for Toxic Substances and Disease Registry (ATSDR) Public Health Assessment-Public Comment Release for the Materials Technology Laboratory (U.S. Army), dated December 26, 1995. This document is ATSDR's evaluation of data and information on the release of contaminants into the environment from the Materials Technology Laboratory (U.S. Army), Watertown, Middlesex County, Massachusetts. The purpose of this document is to assess any current or future impact on public health. The ATSDR will accept written comments from the public until February 12, 1996. Comments should be addressed to: Chief, Program Evaluation, Records, and Information Services Branch, Division of Health Assessment and Consultation, ATSDR, 1600 Clifton Road NE, Mailstop E-56, Atlanta, Georgia 30333. If you have any questions, please do not hesitate to call Lorna Bozeman, the health assessor, at (404) 639-6070. Sincerelyurs,

ax M. Howie, Jr. Chief Program Evaluation, Records, and Information Services Branch Division of Health Assessment and Consultation

Enclosures EXPLANATION THE ATSD"LUBLIC HEALTH ASSESSMENT: A NOTE OF

pursuant to the Comprchtsv Environment.l This Public Health Assessmcnt-Public Comment Release was prepamdby ATSDR 104 (iX6) (42 U.S.C. 9604 (%)(6), and in Response. Compensation, and Liability Act (CERCLA or Superfund) section In preparing this documcntL ATSDR has collected relevant accordancewith our implementing regulations 42 C.F.R. Pant 90). the Environmental Protection Agency (EPA). itatc and data, environmental data, and community health concerns from health responsible parties, where appropriate. This dpcumcnt local helth and environmcnul agencies, the community, and potentially to fulfill the statutory criteria set out in CERCLA represents the Agency's best efforts, based on currently avaikablc i•ormation, it presents an assessment of the potential risks to human section 104 ()(6) within a limited tirme-am,. To the extent possible, by CERCLA, may be undertaken to prevent heaMlh. Actions authorizcd by CERCLA section 104 (1 (11). or othcrwise authorized ATSDR will ufti this document to dtcermine if follow-up or migtate human exposure or risks to human health. In addition, health actions are appropriate at this time. an isitial release, as required by CERCLA section 104 This document has been provided to EPA and the affected state in becn revised in response to comments or additional relevant (i)(6(H) for their information and rcvicw. Where necessary, it has now been released for a 30 day public comment period. information provided by them to ATSDR. This revised document has all public comments and revise or append the document as Subsequent to the public comment pciod, ATSDR will address assessment process for assessment will then be reissued. This will conclude the public health appropriate- The public health id the Agency's opinion, indicates a need to revise or this site, unless additional information is obtained by ATSDR which, append the conclusions previously issued.

Satchcr, M.D., Ph.D., AdmiisL•-ator and Disease Registry ...... David Agency for Toxic Substacr, "BarryL. Johnson, Ph.D., Assistant Admiris-ator Division of Heal.h Assessm¢-t and ConsulUa:on ...... Roben C. Williams, P.E., DEE, Di--tor Juan J. Rcyes, Deputy Di-•:er

Edvnrd 1. Skowronski, Ac.'--g Chief Exposure lnves-i.-pions and Consultationsr-neh ...... Sandra G. Isaics, Acting Chief Federal Facilities ,Asssse.-ne.t Branch ...... Cynthia M. Harris, Ph.D., Chief Petitions Response Branch ...... Sharon Wifiams-Flccwod, Ph.D., Chief Superfund Site Assessment Branch ...... Jr., Chief Branch ...... Max M. Howie, Program Evaluation, Records, and Infor-atdon Services U.S. not constitute endorsement by the Public Health Service or t&. Use of t•adc names is for idcndrication only and does Dcparmnt of Health and Human Services.

Please address comments regarding this report to: Agency for Toxic Substances and Disease Registry Division of Health Assessment and Consultation Services Branch, E-56 Atn: Chief. Program Evaluation, Records, and Information 1600 Clifton Road, N.E., Atlanta, Georgia 30333 FOREWORD

Toxic Substances and Disease Registry, ATSDR, is an The Agency for by of the U.S. Public Health Service. It was established agency Response, Congress in 1980 under the Comprehensive Environmental and Liability Act, also known as the Superfund Compensation, our law. This law set up a fund to identify and clean up hazardous waste sites. The Environmental Protection country's investigation Agency, EPA, and the individual states regulate the and clean up of the sites. a public Since 1986, ATSDR has been required by law to conduct health assessment at each of the sites on the EPA National List. The aim of these evaluations is to find out if Priorities if so, people are being exposed to hazardous substances and, that exposure is harmful and should be stopped or whether is reduced. (The legal definition of a health assessment on the inside front cover.) If appropriate, ATSDR also included concerned conducts public health assessments when petitioned by Public health assessments are carried out by individuals. from the environmental and health scientists from ATSDR and states with which ATSDR has cooperative agreements. As the first step in the evaluation, ATSDR scientists Exposure: at a environmental data to see how much contamination is review contact with site, where it is, and how people might come into environmental it. Generally, ATSDR does not collect its own but reviews information provided by EPA, other sampling data is agencies, businesses, and the public. When there government report will not enough environmental information available, the indicate what further sampling data is needed. data shows Health Effects: If the review of the environmental hazardous that people have or could come into contact with ATSDR scientists then evaluate whether or not there substances, report be any harmful effects from these exposures. The will on the community focuses on public health, or the health impact than on individual risks. Again, ATSDR as a whole, rather can makes use of existing scientific information, which generally epidemiologic include the results of medical, toxicologic and the data collected in disease registries. The studies and and science of environmental health is still developing, information on the health effects of certain sometimes scientific will is not available. When this is so, the report substances needed. suggest what further research studies are of The report presents conclusions about the level Conclusions: to threat, if any, posed by a site and recommends ways health plan. ATSDR stop or reduce exposure in its public health action these reports is primarily an advisory agency, so usually by EPA, identify what actions are appropriate to be undertaken parties, or the research or education divisions other responsible threat, A.SDR of ATSDR. However, if there is an urgent health health advisory warning people of the &nger. can issue a public studies of ATSDR can also authorize health education or pilot full-scale epidemiology studies, disease health effects, specific registries, surveillance studies or research on hazardous substances. Interactive Process: The health assessment is an interactive solicits and evaluates information from numerous process. ATSDR for city, state and federal agencies, the companies responsible the site, and the community. It then shares its cleaning up to an early conclusions with them. Agencies are asked to respond the report to make sure that the data they have version of of ATSDR's provided is accurate and current. When infomed recommendations, sometimes the agencies will conclusions and report. begin to act on them before the final release of the ATSDR also needs to learn what people in the area Community: about its know about the site and what concerns they may have health. Consequently, throughout the evaluation impact on their from the process, ATSDR actively gathers information and comments live or work near a site, including residents of the people who groups. area, civic leaders, health professionals and community report responds to the community's health To ensure that the for an early version is also distributed to the public concerns, public are their comments. All the comments received from the responded to in the final version of the report. questions or Comments: If, after reading this report, you have comments, we encourage you to send them to us.

Letters should be addressed as follows: Chief, Program Evaluation, Records, and Information Attention: and Disease Services Branch, Agency for Toxic Substances GA 30333. Registry, 1600 Clifton Road (E-56), Atlanta, Materials Technology Laboratory (U.S. Army) - Public Comment Release

SUM M ARY ...... 1

BACKGROUND ...... ' .. 4

CONTAMINATION / PATHWAYS ANALYSES / PUBLIC ENVIRONMENTAL 8 HEALTH IMPLICATIONS ...... I. POTENTIAL HEALTH HAZARDS - POSSIBLE EXPOSURE SITUATIONS ...... 8 A. Subsurface Contamination (FUDS Parcel, now the Arsenal Marketplace) ...... 10 Conclusions for Subsurface Contamination ...... 16 Public Health Action Plan for Subsurface Contamination .. 17 Public Health Action Plan for Subsurface Contamination .. 18 B. Suspected Fish Contamination (Charles River) ...... 19 Conclusions and Public Health Action Plan ...... 21 I1. NO APPARENT HEALTH HAZARDS ...... 22 A. Past Air Releases of Depleted Uranium ...... 22 Conclusions and Public Health Action Plan ...... 32 B. Future Land Use (MTL and GSA site) ...... 33 Conclusions and Public Health Action Plan ...... 34

COMMUNITY HEALTH CONCERNS EVALUATION ...... 35

PREPARERS OF REPORT ...... 44

REFERENCES ...... 45 54 A PPENDICES ...... Comment Release Materials Technology Laboratory (U.S. Army) - Public SUMMARY

(MTL) was added to the O.S. The U.S. Army Materials Technology Laboratory Priorities List (NPL):on May Environmental Protection Agency's Superfund National was originally the Watertown 30, 1994. The 37 acre MTL facility is part of what Massachusetts, approximately Arsenal, established in 1816. MTL is in Watertown, on the NPL was largely based on 5 miles west of Boston. The facility's inclusion the Charles River, which is about the potential for site contaminants to migrate into involvement at MTL stems 100 yards south of the installation border. (1) ATSDR by community members that from the facility's inclusion on the NPL and requests former Watertown Arsenal and our agency evaluate public health issues at the health concerns raised by other sites in Watertown (see Appendix A). Specific Health Concerns section of Watertown residents are discussed in the Community this report. former Arsenal properties, Environmental contamination at MTL, and associated manufacturing and related resulted from a long history of munitions and arms other contaminated former operations, and materials research. (1,2) Although they are considered in our public Arsenal properties are not included on the NPL, Formerly Used Defense Site health assessment. Those properties include the referred to as the Arsenal (FUDS) parcel, which is now the Arsenal Mall (also Services Administration (GSA) site. Marketplace) and Arsenal Park, and the General for all properties comprising the ATSDR evaluated the environmental information A describes our evaluation of original Watertown Arsenal (Figure 1). Appendix several potential situations these parcels. As a result.of this review, we identified could be exposed to where people currently could be exposed to contaminants, exposed to site contaminants site contaminants in the future, or could have been relate to: 1) contaminated in the past. These potential exposure situations parcel; 2) suspected fish subsurface soil and building remnants on the FUDS air releases of depleted uranium. contamination in the Charles River, and; 3) past might result from future use of Other situations were evaluated where exposures exposure situations are grouped properties that are currently contaminated. These Categories, which are below by ATSDR Public Health Assessment Conclusion defined in Appendix B. MORE DATA NEEDED POTENTIAL (INDETERMINATE) HEALTH HAZARDS: public health hazards: We conclude that two situationspose potential currently being exposed to 1) Subsurface Contamination - People are not exposures are possible if workers contaminants on the FUDS parcel, but future

1 Materials Technology Laboratory (U.S. Army) - Public Comment Release

unearth contaminatedsubsurface soils and building remnants potentially containing radiologically-contaminatedpiping. Further, it has not yet been determined if portions of the sewer system that were once connected to former Arsenal buildings 34, 41 and 421 are radiologicallycontaminated and if these area! are accessible to public works employees. A TSDR recommended that the Army implement measures to ensure that people are not exposed to potentially hazardous levels of residual radiologic and chemical contamination, which resulted from former Arsenal activities, on what is now the FUDS parcel. (5,6)

2) Fish in the Charles River - Chemicals known to bloaccumulate in edible fish sources species have entered the Charles River from multiple industrialand urban caught in the Watertown area, including the former Arsenal. People who eat fish in urban stretches of the Charles River could, therefore, be exposed to river, contaminants in fish tissue. A TSDR recommended fish sampling In the (3,4,5) which the Massachusetts Department of EnvironmentalProtection conducted during the fall of 1995 in coordination with the state fish toxics program. (7,8) The Massachusetts Department of Public Health, the agency if responsible for issuing fish advisories, will review that data to determine followup public health action is needed. (8)

NO APPARENTHEALTH HAZARD hazard: A TSDR concluded that two other situations were no apparentpublic health Arsenal 1) In the situation where depleted uranium was burned at the Watertown of health in the past, possible exposure to airborne contaminants was below levels showed concern. Radiation dose estimates, based on very protective assumptions, levels. a lifetime cancer risk less than that expected from backgroundradiation (e.g., 2) In the situation regardingMTL and GSA land use, current site conditions would be access by the generalpublic is restricted)make it unlikely that people these exposed to contaminants at levels of health concern. Moreover, before up to properties can be released for reuse, residual contamination must be cleaned by state levels consideredprotective of public health according to guidelines set and federal regulatory agencies.

2 !

FIGURE 1: Former Watertown Arsenal, Watertown, MA

M'~ Materials Technology Laboratory (U.S. Army) - Public Comment Release

II. NO APPARENT HEALTH HAZARDS

A. Past Air Releases of Depleted Uranium past, thb Although depleted Uranium (DU) was burned at the Arsenal in the harmful to amount of DU released to air was unlike/v to be at levels considered community residents of the surroundingcommunity. There were few, if any, airborneDU members living close enough to the Arsenal to have been exposed to dose in the past. Very conservative assumptions were used in the radiation per year, for a estimates. We assumed burning occurred 8 hours a day, 365 days risk was maximum of 20 years. Based on these assumptions, the lifetime cancer The l than the risk of cancer expected from background levels of radiation. MDPH review of cancer incidence for Watertown (34) showed no observed increase in cancer ratesplausibly associated with radiationexposure. the Controlled incineration of depleted Uranium chips was done because of the chips pyrophoric properties of the metal. The incineration not only prevented requiring from spontaneously igniting but also reduced the volume of DU waste after 1974 disposal at Atomic Energy Commission (AEC) licensed facilities and, DU was initially 1975, Nuclear Regulatory Commission licensed facilities. (36) The areas. burned in a remote part of Watertown (GSA site), away from residential from a Later, DU was incinerated in building 43 (MTL) where air releases occurred DU burn stack near the east end of the building. Detailed information about activities at both the GSA site and building 43 are provided below.

GSA site - Northeast Area: area at the Incineration Practices: Depleted Uranium was incinerated in a fenced (Figure 6). (13) Northeast Area, which is now the GSA site, from 1955 to 1967 area, away During the time period when the burn pit was used it was in a remote of personnel from residences. Procedures were implemented to prevent exposure D-1. (36) A to airborne radioactivity. These procedures are described in Appendix Energy December 23, 1966 letter from the Arsenal (AMRA) to the Atomic procedures. Commission (AEC) reported air sampling results for Uranium oxidation average Although numerical data were not provided, the letter indicates that limits set in Uranium concentrations in smoke generated by oxidation were below limit for air the federal regulations in place at that time. (13) The 1966 AEC which is the releases in unrestricted areas was 5 x 10"12 pCi/ml for Uranium-238, and insoluble predominant isotope in DU. This level is applicable for both soluble in place bt that Uranium compounds and assumes constant exposure. The limit to the time would result in a whole-body dose of 0.5 rem/year (500 mrem/y) in the group. general populace and considers the potential presence of children

22 - Public Comment Release Materials Technology Laboratory (U.S. Army) the GSA site were not at levels of Based on these data, air releases of DU from health concern.

23 FIGURE 6. GSA Site

~~~ .~-......

ltepol.L 126 1 nsfGrunc"i I*I'o*cIi I- It.- I IL-0111 Vijj'Ire B-1, REPadio Iogica I Survey Comment Release Materials Technology Laboratory (U.S. Army) - Public were exposed to Human Exposure: We do not expect that people off site The residential areas that significant concentrations of airborne Uranium oxides. built after burning border the western edge of the GSA property, were now site vicinity. (13) Aerial photographs from 1968 show no housing in the ceased. quickly settle to DU is extremely dense, particles carried in smoke would Because very small in the general proximity of the burn pit. Conceivably, the ground However, could disperse at greater distances from the source. particulates and consequently, deposition of these fine particles would be widely scattered, areas distant from the measurable amounts of DU would not occur in localized DU particulatesin smoke would source. Therefore, significant amounts of fugitive in the unlikely event that people not be expected to have drifted far off site. Even have been rare and, based on off site did inhale DU particulates,exposures would the lung would have been below available air dispersion data, the resulting dose to health concern. at the GSA property Radiological surveys to determine the extent of contamination results reported thus far confirm that radiologic contamination are in progress. The is not confined to surface soil in discrete, on-site areas. Contamination is primarily for unrestricted use. widespread and buildings on the GSA land meet requirements (37) and adjoining Property20 Residual soil contamination on both the GSA property areas adjacent to the site. does not pose a health threat to people who live in by fences surrounding the Access to potentially contaminated areas is restricted of Property 20 where fill was burn pit, the GSA property boundary and the portion complete the evaluation and placed. (38) Additional survey work is planned to soils exceed the health-based portions of the GSA property where DU levels in standard of 35 pCi/gram will be cleaned up. (37)

Building 43 - Foundry on MTL depleted Uranium in an Incineration Practices: The Arsenal began burning 7) after the GSA property was incinerator in the MTL Foundry (building 43) (Figure could not be located that no longer used for that purpose. Although records DU burns occurred in the 1970s indicate when the incinerator was first used, most the amount of DU released to the and early 1980s. Engineering controls to reduce until 1981. By the mid to late outside air were not installed on the incinerator 1992, DU was no longer burned 1980s, DU was burned infrequently, and by July DU fires also occurred in the at the Arsenal. (39,40) In the past, uncontrolled Foundry building.

25 ( ( scale FIGURE 7. MTL Buildings inmter 3 ISO ofool $00 015%-l 1101n

I

ors

Senior Officer's Quarters

a

jjkI A..tjeiicet m.odified from vig~ure 4-7, Westo[I RI (10)

C rls

4,,I. C, - Public Comment Release Materials Technology Laboratory (U.S. Army) radiation dose resulting from DU Human Exposure: To estimate the potential available air sampling data. The Arsenal released from building 43, we reviewed from 1981 to 1991 (Appendix D-2). had limited stack monitoring data, spanning from the stack dropped dramatically. After 1981, the amounts of DU released made several assumptions prior fo Because the data were not complete, we data were used in the dose estimates. calculating dose estimates. The 1981 air of material released from the stack These data represent the greatest amounts (41) considering no earlier data could be found. 8 hours per day, every day of the year. We also assumed that DU burns occurred the actual duration and rate of However, these values probably overestimate indicate that DU bums usually lasted burning. Arsenal records from 1972 to 1977 a month. (42) The reported volume of about 2 hours and occurred 5 times or less 400 to 1265 ftW per minute. (43) air handled by the system ranged from about the total amount of DU and products From these very conservative assumptions, estimated totals for 1981 were released from the stack was estimated. The Uranium-238 and 217 to 685 mCi of between 84 and 267 millicuries (mCi) of Thorium-23 4 (a decay product of U-238). released were estimated, ATSDR Once the total amounts of radioactive materials 10,000 trials, to estimate the most performed a probability analysis, based on the stack. These values were then probable amount of material released from assessment software package. (44) entered into the CAP88-PC radiological radionuclides released through the air. CAP88-PC estimates the risk and dose from of Federal Regulations], in compliance Its use is required in 40 CFR 61.93(a) [Code radiation doses to the public. with the Clean Air Act, when calculating dose equivalent (EDE) resulting The results indicate that the maximum effective per year (mrem/y), whole body, to from DU incineration was less than 200 mrem 43 in 1981. As the distance one an individual living within 200 meters of building dose decreased. The maximum lived from the Arsenal increased, the effective the 500 mrem/y federal limit in place in calculated whole body dose was within limit is 100 mrem/y, (45) we do not 1981. (24) Even though the current federal hazard since very protective margins consider the estimated doses to be a health and in the dose calculations. The 100 of safety were used in setting these limits general public is exposed to these levels mrem/y limit assumes a member of the mrem/y is still permitted for infrequent every day for 70 years; however, 500 annual limit is 5000 mrem/y and no known exposures. Moreover, the occupational at that level. (45) adverse health effects have been reported develops cancer risk estimates related to Cancer Risk: The CAP88-PC model also for all radionuclides entered into the the estimated radiological dose summed the major radionuclides present in DU. model, in this case, U-238 and Th-234, systems and the whole body. Uranium The estimates are given for several organ is considered to be uniformly 238, for the purposes of radiation dosimetry,

27 Materials Technology Laboratory (U.S. Army) - Public Comment Release distributed throu-ghout the bone. Thorium-234, however, is considered to be uniformly distributed over the bone surface (46). Therefore, the critical organs affected would be both the bone surface and the red marrow within the bone interior, and the lungs which are the point of entry. However, lung cancer would comprise virtually all the risk from this form of exposure. The data from o r CAP88-PC calculations indicates that the exposure to the entire body was less than 200 mrem per year. This equates to a lifetime cancer mortality risk that is 10 times LM than the risk expected from 70 years of exposure to natural radiation in the environment. (47)

Pooulation Exposed: Based on the modeling, maximum exposure would have been to people living within 200 meters of building 43. The nearest residential areas, which are about 200 meters from building 43, are on MTL and on the FUDS parcel to the east.

Figure 8 (1980) and Figure 9 (1990) show population estimates within 100, 250 and 500 meters of building 43. These estimates are based on census data, assume even distribution of the population within each census subgroup, and extrapolate the percentage of the census subgroup within each concentric circle. These figures probably underestimate the actual number of people who live closest to building 43. Condominiums and apartments, built on redeveloped former Arsenal property-, are within 200 meters east of building 43. However, these residential areas were not built until the early 1980s, by which time air releases of depleted uranium from building 43 were significantly reduced. The condominium complex is comprised of an original Arsenal building (building 212) that was renovated and two newer buildings. The Arsenal Apartments, housing for the elderly, includes a five-story apartment building and several renovated former Arsenal buildings (buildings.71, 72 and 73). (13)

The three buildings on the MTL facility that were used for housing are roughly 250 meters or more from building 43. (Figure 7) Building 111 was the Installation Commander's residence, building 117 was a four-bedroom senior officer's quarters, and building 118 comprised five two-bedroom family units. The average length of residence in any of these military housing units was 2 to 3 years. (48)

28 FIGURE 8. Population Estimates Around the Former Watertown Arsenal Source: 1980 U.S. Census

190 U.S. Ck

/ Distance Tolal LEGEND 100 M 56 IL 250m 297 353 STrad 3702 (rFtlh Pop. - 9223) 500 m 1078 1431 ED Tract 3703 Crcul Pbp. - 5585)

I L] Trac 3704 Crotal Pop. - 5791)

F] Ferxm(MTL Watatown and FUDS) Araaial TSDR G Spada Ambiris AzOviry

29 FIGURE 9. Population Estimates Around the Former Watertown Arsenal Source: 1990 U.S. Census

SM

/ • 1990 U.s. Cm

-250 324 3

100m 1154 1539

[--t 370o4 (r'ot,! Pop. - 5426)

PpldFmWmoDm

30 Release Materials Technology Laboratory (U.S. Army) - Public Comment penetrate different regions of Health Effects of Particulates: Inhaled particulates referred to as activity mean the respiratory tract based mainly on their size (also particulates released to air that aerosol diameters [AMAD]). It is the very small DU because they can be inhaled are of greatest concern from an exposure standpoint, deep into the lung (Table 2). (46) Table 2. Respiratory Deposition of Uranium Oxide Particulates

Percent Deposition by Respiratory Deposition Particle Size (u) 51p 111 0. 3/ 9 FNasophaaryngeea (Noe 74 30 TrachealI Bronchrocial Tree (Throat) 8 8 8 Pulmonaryrarenchyma Paenum (Lung) 9 25 143

U0 and U3 02; relatively The airborne material produced from burning DU is 2 class Y compounds, which insoluble uranium oxides. These uranium oxides are than 100 days because they are have an estimated lung retention time of greater they stay in the lungs for an not very soluble in lung fluids. (46) This means that the body. The extended period of time before being distributed throughout deep in the lung are smaller than majority of uranium oxide particulates deposited add to the lung burden, but to 0.3 p. Particles ranging in size from 0.3ji to 5p also with AMAD greater than 5 a lesser extent. And finally, less than 10% of particles deposited in the nose and p penetrate into the deep lung region. (46) Particles and ingested. Because these throat are usually expelled-from the upper air ways relatively insoluble, they pass ingested particulates are uranium oxides, which are rapidly. through the digestive system and are excreted fairly model is from the time The 1981 air data used in the radiation dose estimation of DU released to outside air. period after engineering controls reduced the amount than 0.3 microns [p]) to air during However, releases of fine DU particulates (less to earlier years. Although burning in 1981 and after, were most likely comparable filters on the incinerator decreased the use of high efficiency particulate air (HEPA) in size, fine particulates continued to air releases of particulates greater than 0.3 p the greatest amounts of be emitted. As discussed earlier, using data representing assumptions that are very material released from the stack and incorporating radiation dose was not at protective of public health, the maximum estimated levels which pose a public health hazard.

31 Materials Technology Laboratory (U.S. Army) - Public Comment Release

Conclusions and Public Health Action Plan for Past Air Releases of Depleted Uranium

1. The amount of depleted Uranium (DU) released to air from MTL and the GSA site was unlikely to be at levels considered harmful to residents of the surrounding community. Few, If any, residents lived close enough to sites to have been exposed. Further, radiation dose estimates, based on very protective assumptions, showed a lifetime cancer risk less than that expected from background radiation levels.

2. Members of the general public are not likely to contact residual DU conrtamination at either the GSA site or the MTL property because access to contaminated areas is restricted.

Completed Actions:

1. The Army has restricted access to areas of the GSA and MTL properties where there is residual DU contamination.

Planned Actions:

1. The Army is continuing radiation survey work at the GSA site and is planning to cleanup DU levels in soil to the health-based standard of 35 pCi/gram. Cleanup of MTL building 43, which housed the DU incinerator, is also being completed to meet applicable Nuclear Regulatory Commission requirements.

32 Comment Release Materials Technology Laboratory (U.S. Army) - Public

B. Future Land Use (MTL and GSA site)

GSA site (see concerning future land use of MTL and the Public health issues ProC.edures importance and are being actively addressed. Figure 1) are of utmost general and cleanup activities to protect both the are implemented during sampling can hazards. Further,before the land and remediation workers from possible public cleanup actions must be completed. be transferredfor reuse, all necessary and cleanup at MTL and the GSA site The Army is conducting site investigations of Massachusetts Departments of under the guidance of the Commonwealth Public Health (MDPH), the U.S. Environmental Protection (MDEP) and and the Nuclear Regulatory Commission Environmental Protection Agency (EPA) levels that are protective of public (NRC). These regulatory agencies set cleanup are planned. ATSDR supports these considering the land reuse options that health public health issues as by providing technical assistance concerning activities Risk Assessment for We reviewed the "Human Health Radiological requested. the 10 mrem dose limit 21E Sites" for MDEP and concur that Massachusetts health. (49) We have also for cleanup at MTL is protective of public proposed activities at the former Arsenal reviewed documentation regarding environmental and provided comments to the Army and properties (GSA site and FUDS parcel) of public health importance. (5,6,38,50) regulatory agencies concerning issues expressed concern about who live next to MTL and the GSA site Residents they see on-site workers wearing being exposed to contaminants because possibly and cleanup activities. protective equipment (PPE) during sampling personal does not necessarily mean that a the use of PPE by remediation workers However, precautionary measure to hazardous; rather, PPE is a required site is extremely field investigations. from possible hazards encountered during protect workers prevent exposures during the course of site cleanup that Other actions are taken residual include restricting access in areas where from occurring. These security public health concern. Fencing and/or contamination is at levels of access. GSA site which effectively limit site measures are in place at MTL and the are developed which detail proper safety Finally, Site Health and Safety Plans work. These plans include containment measures to be followed during all site and cleanup activities which prevent methods to be used during sampling moving away from the site. contaminated dusts, vapors, etc from

33 Materials Technology Laboratory (U.S. Army) - Public Comment Release

Conclusions and Public Health Action Plan for Future Land Use of MTL and GSA site

1. Neither MTL nor the GSA site pose a public health threat to members of the general public because exposure to contamination Is not likely to occur. The Army has restricted access to areas where there is residual contamination.

2. Actions planned by the Army, in collaboration with state and federal regulatory agencies, will ensure that neither site will pose a future public health hazard. Before the properties can be transferred for reuse, all necessary cleanup will be completed following strict health and safety guidelines.

34 - Public Comment Release Materials Tecdnology Laboratory (U.S. Army)

COMMUNITY HEALTH CONCERNS EVALUATION members their health concerns with ATSDR staff Watertown residents discussed Information 1993 (31) and January 1994 (57). during meetings held in December from members of the Watertowr Board about health concerns was also gathered Departments of Environmental Protection of Health, the Army, the Massachusetts Protection Agency. Concerns 1-3 and Public Health, and the U.S. Environmental Arsenal properties, while the other concerns relate directly to MTL or other former in Watertown as a whole. center around environmental contamination

Concerns associated with tihe Arsenal: Uranium occur from past exposure to depleted 1. Could long term health effects (DU) that was burned at the Arsenal? Uranium at MTL to air during past burning of depleted The amount of DU released residents of the to be at levels considered harmful to and the GSA site was unliely adverse significant exposures were not expected, surrounding community. Since 32 of reader is referred to pages 22 through health effects would not occur. The of past air releases of DU. this report for a detailed discussion workers could have been exposed to 2. There is concern that former Arsenal of beryllium and depleted Uranium. - harmful levels on minimizing worker exposures hygiene practices at the Arsenal focused Industrial the health risks associated with materials. (58,59,60) Consequently, to these Studies among beryllium-exposed with beryllium and DU were reduced. working the prevalence of chronic the industry as a whole, have shown workers, within little opportunity for to be only 5%. (61) Since there was beryllium disease (CBD) developing CBD beryllium at the Arsenal, their risk of workers to be exposed to sound With regard to depleted Uranium workers, was even further reduced. of a practices coupled with the results industrial hygiene and health physics of health suggest exposures occurred at levels medical surveillance program do not concern. (59,62)

Beryllium: with beryllium is inhalation, glove principal safety hazard in dealing Because the areas where beryllium work collection systems were in place for boxes and exhaust greatly reduce industrial hygiene practices would was carried out. (58) These that a former metal. Community members stated possible worker exposures to the (63,64), but details regarding the circumstances Arsenal worker died of berylliosis of disease and the subsequent development which lead to the worker's exposure were unavailable. (58,59,62)

35 Materials Technology Laboratory (U.S. Army) - Public Comment Release

There are two types of diseases associated with inhalation exposure to beryllium: acute beryllium disease and chronic beryllium disease. Acute beryllium disease, which is a chemical pneumonitis, can result from breathing high concentrations of soluble beryllium. However, since the implementation of the Atomic Energy Commission's 1950 recommendations calling for a 99% reduction of berytllum concentrations in the work environment, acute beryllium pneumonitis was completely eliminated. (61,65)

Chronic beryllium disease (CBD), an immunologic disease, only occurs in a small number of people who are exposed to both soluble and Insoluble forms of the metal. This finding was reported in studies of industry workers who were exposed to beryllium. CBD is an Immunologic lung disease, characterized by chronic hypersensitivity, for which there is no effective treatment. (66,67) Sensitized Individuals develop granulomas in their lungs, which are clusters of immune cells (lymphocytes) that accumulate around beryllium particles In the alveoli of the lungs. (61) Studies suggest that there are at least two risk factors for CBD; exposure to the metal and inheritance of a genetic marker linked with susceptibility to the disease. (61,68)

It is also known that the onset of CBD may occur up to 10 to 20 years after exposure. (66,67) A blood test, the beryllium lymphocyte proliferation test (BeLT), can be .one to detect early CBD or to make a specific diagnosis of CBD. If an individual has been sensitized to beryllium, their blood lymphocytes will proliferate when cultured in the laboratory in the presence of beryllium salts. (61)

Deoleted Uranium: Industrial hygiene practices at the Arsenal focused on minimizing worker exposure to DU, which could occur through inhalation, ingestion, or through skin lesions. DU is a byproduct of the nuclear industry that is less radioactive than the naturally occurring uranium. All operations involving DU complied with safety and health physics standards applicable at that time and individual radiation exposures were monitored to ensure that allowable exposure doses to workers were kept well within permissible limits. (60)

The most likely route of occupational exposure to DU is via inhalation. However, when an individual breathes in uranium dust, most of it leaves the lungs when the person coughs or breathes out. (69) Some of the more soluble compounds of DU that remain in the lung are taken into the blood stream. Once in the blood stream, the soluble DU may result in significant deposits in the kidneys, where chemical toxicity occurs. (70) However, DU is eliminated from the kidneys at a rate of about half every two weeks. Moderately severe damage to the kidney as a result of acute exposure is repairable, and a return toward normal kidney function may occur even during continued exposure. (60) Any insoluble DU compounds that are deposited in the respiratory system are mobilized slowly. Although these insoluble DU compounds pose a radiation hazard to the lungs, adverse health effects on the

36 Materials Technology Laboratory (U.S. Army) - Public Comment Release exposure doses at respiratory system are not expected to occur because individual the Arsenal were well within permissible limits. soluble uranium (U) is If exposure occurred via ingestion, only about 1 % of the of insoluble U is aýbsorbed absorbed from the digestive system and less than 0.2% the bloodstream would into the bloodstream. (71) Depleted Uranium that enters would be excreted in the be deposited primarily in bone and the kidney, and some from the body in the urine. Unabsorbed compounds would be quickly eliminated feces. exposure to eyes, Hazards associated with handling DU metal is beta radiation recommended for hands and fingers. Thermoluminescent dosimeters were protective equipment, such monitoring DU exposures to the extremities. Personal 50%. (60) DU could also as leather gloves, reduced exposures to the hands by enter the blood stream through contaminated wounds. to reduce occupational In addition to implementing safety procedures designed program to check workers exposure, the Arsenal maintained a medical surveillance the concentration for uptake of DU. Urine testing was done quarterly to determine detects soluble DU, was of DU excreted by workers. (59,60) Urine testing, which used as an indicator of chronic exposure. pulmonary function Also, exit physicals were available to workers, which included (59,62) Clinic tests, and kidney function tests as well as other evaluations. in workers that might be medical staff remarked that there were no abnormalities were provided copies of associated with occupational exposures. (59,62) Workers no longer worked at the their medical records upon request. Once an employee Personnel Records Arsenal, that individual's records were sent to the National the individual's name, Center in St. Louis, Missouri. These records are filed by the agency where they had date of birth, social security number and the name of worked. (59) in the community? 3. Were any nuclear materials from the Arsenal buried nuclear materials from the The information that we reviewed does not suggest that described in the Arsenal were buried in the community. Disposal procedures (13) indicate that no Former Watertown Arsenal Preliminary Investigation landfills or the town radioactive or hazardous wastes were discarded in Watertown incinerator. the MTL facility is being Extensive investigations and environmental cleanup at radiological contamination conducted at this time. Much of the cleanup of residual been completed. Moreover, from past industrial activities at that site has already necessary remedial actions, the property cannot be transferred for reuse until all Agency, the Nuclear which are regulated by the Environmental Protection

37 Release Materials Technology Laboratory (U.S. Army) - Public Comment Environmental Regulatory Commqlssion, and the Massachusetts Departments of Protection and Public Health, are taken. the Arsenal There is residual radiologic contamination on the FUDS parcel, now Marketplace (11,13) and the GSA site (37,51), which were both part of ti.e a health haiard to original Watertown Arsenal. However, these sites do = pose restricted. members of the general public because access to contaminated areas is (FUDS Parcel, The reader is referred to sections entitled Subsurface Contamination Area, pages now the Arsenal Marketplace), pages 10-18 and GSA site - Northeast 22-25 for detailed discussions regarding these areas.

Other Concerns in Watertown: community Is higher 4. Watertown residents believe that cancer Incidence In their sources of than expected. They are particularly concerned that multiple to cancer environmental pollution in their community could be contributing occurrence. in the community, To address concerns about multiple sources of contamination hazardous ATSDR evaluated the likelihood of people coming in contact with the Arsenal, Arsenal materials in particular areas in Watertown. These included: the neighborhoods Park, United Parcel Service, Watertown municipal landfills, and and Parker Street. of Frank Street, North Beacon Street, Bay Street, Palmer Street levels of We consider it unlikely that residents could be exposed to hazardous based on observations contaminants in any of these areas. Our conclusions are by community we made during tours of areas that were brought to our attention data relating to members, and on our review of all the applicable environmental evaluation of specific specified waste sites in Watertown. Details regarding our sites are provided in Appendix A. exposures. People have strong fears about cancers caused by environmental everything Although the term "environmental" causes of human cancer includes about 2% of cancer other than genetic factors, it has been estimated that only cancer cases that are deaths are attributed to environmental pollution. (72) Often, exposed to linked to chemical exposure afflict individuals who were occupationally occupational exposures high concentrations of particular types of chemicals. Such The presence of appear to account for about 5% of all cancer deaths. (73) necessarily mean that environmental contamination in a community, does not hazardous materials to people are coming into contact with sufficient quantities of that people have not cause disease. Again, we emphasize that it is our opinion come into contact with contamination. very common illnesses It is widely recognized that cancers, like heart disease, are of individual cancer that occur in all communities. In order to put the number be made to the occurrence cases in Watertown into perspective, comparisons must

38