ML17319A795

Application to Amend License DPR-58,changing Tech Specs to Increase Core Peaking Factor Limits.Class III Amend Fee Encl

ML17319A795
Person / Time
Site:	Cook
Issue date:	03/26/1981
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17319A796	List: ML17319A795 ML17319A798 ML19350C391
References
AEP:NRC:0538, AEP:NRC:538, NUDOCS 8104010357
Download: ML17319A795 (6)

Text

REGULATORY FORMATION DISTRIBUTION SY:M (RIBS)

ACCESSION NBR:8100010357 DOC ~ DATE: 81/03/26 NOTARIZED: NO DOCKET FACIL:50-315 Donald C ~ Cook Nuclear Power Planti Unit 1E Indiana 8 05000315 AUTH, NAME AUTHOR AFFILIATION HUNTERER ~ ST Indiana 8 Michigan Electric Co ~

RECIP ~ NAME RECIPIENT AFFILIATION DENTONEH ~ RE Office of Nuclear Reactor Regulationp Director<

SUBJECT:

Application to amend License DPR-58<changing Tech Specs to increase, FQ core peaking factor limits. Class III amend fee LLq<ug ~

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TITLE: General Distribution for after Issuance of Operating License NOTES:ISE:3 copies a11 motet ia'I. Il/6'ffEE/('/YAHOO'5000315 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME. LTTR ENCL'. ID CODE/NAME LTTR ENCL ACTION: VARGA S, 04 13,13 INTERNALe D/DIR EHUll FAC08 1 1 DIRE DIV OF LIC 1 1 I8,E 06 2 2 NRC PDR 02 1 1 11 1 ...0 OR ASSESS BR 10 1 0 01 1 1 EXTERNAL: ACRS 09 16 16 LPDR 03 1 1 "NSIC 05 1 1 gPR 8 1981 Vo TOTAL NUMBER OF COPIFS REQUIRED+ LTTR ENCL

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CA March 26, 1981 co we/ rr AEP:NRC:0538 ~~CCA tC 4'At Donald C. Cook Nuclear Plant Unit No. 1

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Docket No. 50-315 License No. DPR-58 F Technical Specification Change Request Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

Attachment 1 to this letter contains a proposed Technical Specification change for Unit 1 of the Donald C. Cook Nuclear Plant. We are requesting that the current Fq core peaking factor limit be increased.

A new plant ECCS reanalysis justifying the proposed change has been performed by Exxon Nuclear Company (ENC) using their NRC approved ECCS evalu-ation model. The general methodology and initial analysis results were discussed with members of your staff in a meeting held on January 14, 1981'.

Attachment 1 to this letter contains the proposed Technical Specification.,

revisions. 'ttachment 2 to this letter provides the technical basis and our safety evaluation of the proposed change. Attachment 3 to this letter is the ENC report (No. XN-NF-81-07) which provides the ECCS re-analysis results. This Technical Specification change has been reviewed. by both the PNSRC and the required membership of the AEPSC NSDRC in accordance with the provisions of our Technical Specifications. These reviews concluded that the subject change will not adversely affect the health and safety of the public.

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H. R. Denton, Director AEP:NRC:0538 This Technical Specification change deals with a single safety issue, which does not involve a significant hazard issue. Therefore, pursuant to paragraph 170.22 of 10 CFR 170, a check in the amount of $ 4,000.00 is also attached.

Very truly yours, R. S.

Vice President cc: R. C. Callen G. Charnoff John E. Dolan R. W. Jurgensen D. V. Shaller - Bridgman Resident NRC Region III Inspector - Bridgman

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