ML19317F681

Safety Evaluation Supporting Amend 2 to License NPT-3

ML19317F681
Person / Time
Site:	Davis Besse
Issue date:	06/14/1977
From:	Office of Nuclear Reactor Regulation
To:
Shared Package
ML19317F674	List: ML19317F673 ML19317F678 ML19317F681 ML19317F682 ML19317F685
References
NUDOCS 8001230581
Download: ML19317F681 (2)

Text

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JIJN 141977 SAF5?lY.EVALUATICti BY ?JE GE? ICE CP K'fT V. PEACIOR SUPPCPCING Ne; Cts? !O. 2 "O.L._ICENSE 0. NP_F._3 K/LEDO EDISCH LWl."#I E_.0 MEIA:0_ Ell %'TRIC ILLUMIdATING CGLONTI 0

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CAVIS-BE_SSE MJCLEAR POWE. R STATIGI, UNIT 1-wo

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I":TCCCCIICU issued

ie stated in Section 5.2.2 of S.

polecent I to the Safety Cvaluatio nect renoval relief valve actuate prior to the actcmatic closure cf the decay on April 22, 1977, heat rexval iso',ation valves CS 11 ard m 12.

Paragraph 2C.(3)(o) of the Davis-Basse, Unit 1 facility operatirg license, No.

aEF-3, sticulates as a condition that:

" Prior to entering Mode 2 (Ctartuo), Toledo Edisen Ccreany shall succit for staff evaluation and sucsequently i:clanent the necessary r.a2ification to ensure i

l that the decay heat rercval relief valve will actuate prior to automat c c osure of tce decay neat recaval system 1. solation valves."

CISCUS3 icy By letter dated May 2,1977, the licensee stated that the a ceing raised to not less than -113 pounds per square inen gauge which is 93 pounds per scuate inch gauge above ene decay heat receval valve set of 32t] pcunus per square inch gauge.auteatic closure setpoints included ma tclerance, instrtruent drift en:) relief valve acetc.ulation.

iNALCATI0tj

'ie have evaluated the licensee's ccx:xnit: rent for the autcznatic and have determined from our review that the 93 pounds per square inch g pressure differential between tne setpoints of the isolation valves and th valve provides adequate assurance that the decay heat removal relief valve a n..

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will actuate prior to autccatic closure of the decay heat recoval system isolation valves.

Based on our review of the licensee's ccmitrent for the automatic closure set;cints as stated above, we conclude that adequate assurance will be provided for assuring that the decay heat removal relief valve will actuate prior to autccatic closure of the decay beat receval system isolation valves and this provision is acceptaole to minimize the likelibcod of exceeding the pressure limits of,%mpendix G to 10 CFR Part 50 for the first fuel cycle.

We therefore conclude that the limitations on olant oppraticns as scecified in Paragraph 2C.(3)(o) to the facility coeratire license, NPF-3, are no 1cocer necessary and that the facility operating license, MPF-3, issued on April 22, 1977 can be er,erced by rermvirr; the license conditien, stat =d in Paragrapn 2C.(3)(c) which temcorarily limited operation of Davis-desse, Unit I to nede 3 (not standby).

CWIDi.WAL CCNSIDEWCICt!

We have determined that the-amerdent does not authorize a chame in effluent types or tctal amounts nor an increase in puer level ard will not result in any significant enviremental 1. cact. Having nade this determination, we have further concluded that the amerdent involves an acticn which is insignificant frca tne standpoint of envircrantal impact and, pursuant to 10 CPR S51.5(d)(4),

that an enviromental imcoct statement or negative declaration and envircrc.ontal irract aceraisal need not be prepared in connecticn with the issuance of this SQendcent.

CCCSICri i

Ne have concluded, based on the considerations discussed above, that:

(1) i because the merxirent does not involve a significant increase in the pro-bability or wiwoences of accidents previously considered or a significant decrease in any safety margin, it does not involve a significant hazards consideration, (2) there is reasonable assurance that the health a M safety of the public will not be eMangered by operation in the proposed manner, arx1 (3) such activities will be conducted in ccmpliance with the Ccmission's regulations and the issuance of this amendment will not be inimical to the

Also, j

common defense and security or to the health and safety of the public.

we reaffirm our conclusions as otherwise stated in our safety r?/aluation Report.

Dated:

orrecs 9 suenaiss e '

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