ML20070S800

Application to Amend License NPF-5 Adding Tech Specs for Instruments Installed in post-accident Monitoring Instrument Table

ML20070S800
Person / Time
Site:	Hatch
Issue date:	02/03/1983
From:	GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML20070S802	List: ML20070S800 ML20070S809
References
NUDOCS 8302080020
Download: ML20070S800 (4)

Text

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' Georgia Power Corroany 333 P>edmont Avenue Ananta. Georgia 303C8 Telephone 404 526-7020 Marting Address-Post Off:ce Box 4545 Atlanta, Georg!a 30302 Georgia Power J. T. Beckham, Jr. February 3, 1983 the Southem eleCfnC System Vice President and Ge cral Yanager Nuc! ear Gereration Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO AMEND TECHNICAL SPECIFICATION POST-ACCIDENT MONITORING INSTRUE NT LIST Gentlemen:

In accordance with the provisions of 10 CFR 50.90, Georgia Power Company (GPC) hereby proposes an amendnent to the Edwin I. Hatch Unit 2 Technical Specifications (Appendix A to the Operating License). This change would add specifications for instruments which have been recently installed in Unit 2 to the post-accident monitoring instrument table (3.3.6.4-1). The number of available post-accident monitoring channels for suppression chamber water level, suppression chamber pressure, and drywell pressure would be increased fran two to four by this amendment. A result of this addition would be a decrease in the number of reportable occurrences due to failure to meet minimum operable channel requirements.

Application of these proposed Technical Specification changes would in no way constitute an unreviewed safety question as determined by the Plant Review Board and the Safety Review Board. The probability of occurrence and the consequences of an accident or malfunction of safety-related equipment would not be increased above those analyzed in the FSAR due to this change because present safety-related equipment would not be affected. The possibility of an accident or malfunction of a different type than analyzed in the FSAR would not result from this change because no new modes of operation or failure would be introduced. The margin of safety as defined in the Technical Specifications would not be reduced by this change because the requirement for minimum number of operable post-accident instrumentation channels would remain unchanged.

Instructions for incorporation of these changes along with copies of affected Technical Specification pages are enclosed.

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Georgia Powerkh Director of Nuclear Reactor Regulation Attention: Mr. John Stolz, Chief Operating Reactors Branch No. 4 February 3, 1983 Page Two Included with this proposal is a determination of amendment class. We have determined this to be one Class II amendment, and have enclosed the appropriate payment.

J. T. Beckham, Jr. states that he is Vice President of Georgia Power Company and is authorized to execute this oath on behalf of Georgia Power Company, and that to the best of his knowlecge and belief the facts set- forth in this letter are true.

GEORGIA POWER COMPANY By:

y J. T. Beckham, Jr.

Sworn to scrib be this third day of February,1983.

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Notary Public Notary Public, Georgia State at Large My Commission Expires Sept. 20,1983 CBS/mb Enclosures xc: H. C. Nix Senior Resident Inspector J. P. O'Reilly (NRC-Region II) 700775

ATTACHE NT 1 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EIMIN I. HAICH NUCLEAR PIANT UNIT 2 REQUEST TO MEND TECHNICAL SPECIFICATION POST-ACCIDENT MONITORING INSFRIMENT LISP The proposed changes to ~ Technical Specifications (Appendix A to Operating License NPF-5) would be incorporated as follows:-

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ATTACHieff 2 '

NRC DOCIGTP 50-366 TERATING LICDISE NPF-5 s

.EDfIN I. HA'ICH NUCLEAR PIANP UNIT 2 REQUEErr 'IO ABEtO TECHNICAL SPII3IFICATION POST-ACCIDENT ICNI'10RIIG INSPRGENT LISP Pursuant to 10 CFR -170.22, Georgia Power Coupany has evaluated the attached proposed amendment to Operating License NPF-5 and has determined that:

a. The proposed amendment does not require evaluation of a new Safety Analysis Report and rewrite of the facility license;

b. The proposed amendment does not require evaluation of several couplex issues, involve ACRS review, or require an environmental inpact statement;

c. The proposed amendment does not involve a couplex issue or more than one environmental or safety issue;

d. The proposed amendment does not involve a single environmental or safety issue;

e. The proposed amendment is administrative in nature,- namely the listing of new post-accident monitoring instrumentation;

f. The proposed amendment is therefore a Class II amendment.

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