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La Salle Station, License Amendment 5, Amendment Changes To Doue.STRIBUTIO (; Document bontrol (50-373) "AUG•2•7 18Z NRC PDR I Di ni tz L PDR Wjones, OA (l1) PRC ACRS (16) NSIC BPCotter, ASLBP LB#2 Reading ARosenthal, ASLAP *ocket No.: 50-373 ARournia Region III EHyl ton ASchwencer Mr. 0. CWoodhead, OELD Louis DelGeorge DEi senhut/RPurpl Director e of Nuclear Licensing TMNovak Commonwealth Edison Company JSouder P.O. Box 767 I&E Illinois Chicago, 60690 MPA Mr. TBarnhart (4) Dear DelGeorge: WMIller Subject: Amendment No. 5 to Facility Operating License No. NPF-11 - La Salle County Station, Unit 1 The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 5 to Facility Operating License No. NPF-11 for the La Salle County Station, Unit 1. This Amendment which is effective as of August 13, 1982, consists of changes to the license in response to your application dated August 11, 1982. The changes to the Technical Specifications relate to Specification 4.7.3.C.2 and Bases 3/4.7.3 to account for flow differences between the test flow path and the normal flow path required for an 18 month surveillance on the reactor core isolation cooling (RCIC) system. These changes were approved on August 13,'1982, as indicated in our letter to you on August 16, 1982. In addition, a number of pages are being transmitted to be replaced in the Technical Specifications as a result of typo-corrections made to the snubber numbers in Table 3.7.9-2 and the Y2 term in Table 4.6.1.5-2. By letter dated August 11, 1982, Commonwealth Edison proposed changes to the Technical Specifications for La Salle County Station, Unit 1 to require that - the RCIC system be demonstrated operable at least every 18 months by verifying, using the test flow path, that the system is capable of delivering a flow greater than or equal to 600 gpn to the reactor vessel when steam is supplied to the turbine at a pressure of 150 + 15 psig. A request was also included to modify Bases 3/4.7.3 to allow the use of Initial startup test data for determining. r.NN. equivalent flows in the RCIC test line and vessel injection line. The present 20 specification requires that the RCIC system be demonstrated operable at least NO00 every 18 months by verifying that the system will develop a flow greater thangr (DO equal to 600 gpm in the test flow path when steam is supplied to the turbine \ rd 0 at a pressure of 150 + 15 psig. lwox•"- O0 003 Commonwealth Edison requested these changes because excessive pressure losses I fl rdC the test line prevent the system from achieving a flow of 600 gpm in the test ow[0. path when steam pressure is 150 psig. (A flow of 590 gpm was achieved.) Commonwealth Edison calculated the driving pressure required to deliver 600 gpm to the vessel at the point where the test line and the vessel injection line\ split. Based upon this calculation and the pressure measured at this point 1\ during a test In which a test line flow of 590 gpm was achieved, it was shown, that rn v~nn inf 1;fl n~.4 4e *,u41*hl-, *hi~t= *ha h,,,e•- nada#4i *n n#•'h4au,,, €Pll.' OFFICE• gpm-to the vessel. -Suprorting analy, es have been provided whfi6s fiOw thati. SUR•AMý ...than..ihome in.•..test-..1 I;L....... 1,.4" tio4AI..a.•.9r..j ram ................ OAT yw1ou.1wtllv rtfy a flow rate to the actor of at leaqAt 600jj. I n :r w n a s..s p d . .. ................ 1.... ..... ." 1 ... ... ..... ................ NRC FORM 318 (10-80) NRiCM 0240 OFFICIAL RECORD COPY USGPO: 1981--335-960 Hr. Louis 0. DelGeorge - 2 On August 13, 1982, we reviewed your request and the supporting analyses and concluded that the reliability of the RCIC system will not be adversely affected by this change. We further concluded that this action will not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; (2) Create the possibility of an accident of a type different from any evaluated previously; or (3) Involve a significant reduction in a margin of safety. The proposed Technical Specification changes were therefore, found to be acceptable. We have determined that the Amendment does not involve a change in effluent types or total amounts nor an increase In power level and will not result In any significant environmental impact. Having made this determination, we have further concluded that the Amendment involves an action which is insignificant from the standpoint of environmental impact and pursuant to 10 CFR Section 51.5(d)(4) that an environmental Impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this Amendment. We have concluded, based on the considerations discussed above, that: (1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously considered and does not Involve a significant decrease in a safety margin, the Amendment does not involve a significant hazards consideration, (2) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this Amendment will not be inimical to the common defense and security or to the health and safety of the public. A copy of a related Notice of Issuance is also enclosed. Sincerely, A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Enclosures: 1. Amendment No. 5 to NPF-11 2. Federal Register Notice cc w/enclosures: OFFICEF..... ...... i S~~n.MSLI~~. Q.I. Q.4d iJ..A L:-1.#Bf2/?JP1: .#?~....Q...... .............E . o~Cn:kwn ABournia N.E.ASchwencer QE .A.ou.n.a.A..h.en.e............................ SUR "AME . / ......................... ./.../8. ................ S........................................................................ ........ ............. NRC~ M..31 f ...........0240.. ................ ..............O*---A RE O D C PY -- O 98- -8 NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY tISGPO. 1981--335-M6 K-, CO, 4ONWEALTH EDISON COMPANY DOCKET NO. 50-373 LA SALLE COUNTY STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-11 Amendment No. 5 1. The Nuclear Regulatory Commission (the Commission or the NRC) having found that: A. The application for amendment by the Commonwealth Edison Company, dated August 11, 1982, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth In 10 CFR Chapter 1; B. The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C. There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (I1) that such activities will be conducted in compliance with the Commission's regulations; D. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied. 2. Accordingly, the license is amended by changes to the Technical Specifications as indicated In the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-11 is hereby amended to read as follows: (2) The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 5, are hereby Incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications. 6209270064 620627 PDR ADOCK 05000373 P PDR Y OFFICE. .......... ...................... ........................| ..............,......... ............=........... SURNAME ............. ........... ...................... ........................ ...~.............=..........................°*om. DATE, .................. ... ................°mIei °° ............. ............ I n R E WMROFORM 318 (10410) NRCM 0240 OFFICIAL R CORD COPF USGPO:. 1981 --435-960 -2 3. This amendment is effective as of August 13, 1982. FOR THE NUCLEAR REGULATORY COMISSION A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing Attachments: Changes to the Technical Specifications Date of Issuance: P , 2 ! ....................PI. : F B. ... SURNAME,.•oATEý .•E..... 8..QT-... I. ..... AnUT n............................................I82.............. I .Th.o... :8/X.........."........................................... ............ .................... ....................I.................... NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY USGPO: 1981--335-260 K-' ATTACHMENT TO LICENSE AMENDMENT NO. 5 FACILITY OPERATING LICENSE NO. NPF-11 DOCKET NO. 50-373 Replace the following pages of the Appendix OA" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines Indicating the area of change. REMOVE INSERT 3/4 7-8 3/4 7-8 B 3/4 7-1 B 3/4 7-1 3/4 6-12a 3/4 6-12a 3/4 7-33 3/4 7-33 3/4 7-35 3/4 7-35 3/4 7-36 3/4 7-36 3/4 7-37 3/4 7-37 3/4 7-40 3/4 7-40 3/4 7-42 3/4 7-42 3/4 7-43 3/4 7-43 3/4 7-45 3/4 7-45 OFFICE ..................................... , SURNAME............... ........................ NRC FORM 318 (10-80) NRCM 0240 OFFICIAL RECORD COPY uwOsa.,i1-.-geo PLANT SYSTEMS SURVEILLANCE REQUIREMENTS c. At least once per 18 months by: 1. Performing a system functional test which includes simulated automatic actuation and verifying that each automatic valve in the flow path actuates to its correct position, but may exclude actual injection of coolant.into the reactor vessel. 2. Verifying that the system is capable of providing a flow of greater than or equal to 600 gpm to the reactor vessel when steam is supplied to the turbine at a pressure of 150 ± 15 psig using the test flow path.
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