ML17319B418

First Suppl to 820407 Application for Cycle 4 Reload & Uprate License Amend.Results of Exxon Nuclear Co Analyses of ECCS Exxon Fuel & Plant Transients Will Be Submitted Separately

ML17319B418
Person / Time
Site:	Cook
Issue date:	07/08/1982
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:0637B, AEP:NRC:637B, NUDOCS 8207140257
Download: ML17319B418 (6)

Text

REGULATORY .FORMATION DISTRIBUTION S't M (RIDS)

AOCESSION NBR:82071<0257 DOC,DATE: 82/07/08 NOTARIZED: NO DOCKET FACIL:50-316 Donald C-. Cook Nuclear Power Plant~ Uni,t 2i Indiana 8 05000316 AUTH ~ NAME AUTHOR AFFILIATION HUNTERiR ~ S> Indiana L Michigan Electric Co ~

(R EiC IP ~ NAME RECIPIENT AFFILIATION DENTONg H,R ~ Of fice of Nucl ear Reactor Regul ationi Director SUBJEGT: First suppl ito 820007 application for Cycle 4 reload 8 uprate license amend, Results of Exxon Nuclear iCo analyses of ECCS Exxon fuel 8 p)ant;transients will 'be submitted separately, DISTRIBUTION CODE: A001S, COPIES "RECEIVED:LTR, TITLE: General Distr ibution for af tor Issuance

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INDIANA It MICHIGAN ELECTRIC COMPANY P. Oo BOX I8 BOWLING GREEN STATION NEW YORK, N. Y. 10004 July g, 1982 AEP:NRC'0637B Donald C. Cook Nuclear Plant, Unit No. 2 Docket No. 50-316 License No. DPR-74 UNIT 2 CYCLE 4 SAFETY ANALYSES Mr. Harold R. Denton, Director Office of Nuclear Rector Regulation U.. S. Nuclear Regulatory Commission Washington, D. C. 20555

Dear Mr. Denton:

This letter is the first supplement to our "Application for Cycle 4 Reload and Uprate License .Amendment" contained in letter No.

AEP:NRC:0637A dated April 7, 1982.

Exxon Nuclear Company (ENC) has completed their safety analyses for Cycle 4 operation of the Donald C. Cook Nuclear Plant, Unit No. 2. The analyses were performed at a reactor (core) thermal power level of 3425 MWt. However, for Cycle 4, scheduled to begin in December of 1982, we have applied to operate at a reactor thermal power level of 3411 MWt.

The results of the analyses for the Emergency Core Cooling System (ECCS) as it relates to ENC fuel and of the more limiting plant transients have been documented by ENC in Report Nos. XN-NF-82-35 and XN-NF-82-32(P) entitled "Donald C. Cook Unit 2 LOCA ECCS Analysis Using Exem/PWR Large Break Results" and "Plant Transient Analysis for the Donald C. Cook Unit 2 Reactor at 3425 MWt," respectively. ENC is transmitting twenty-five (25) copies of each of these reports under separate cover. American Electric Power Service Corporation (AEPSC) is currently reviewing these reports.

As stated in our letter No. AEP:NRC:0637A, AEPSC is also conducting an independent review of the effects of uprating on the various plant safety systems, components, and structures. This review has not yet been completed. However, we have not, to date, identified any aspects of the uprating which would prevent safe and reliable 8207140257 820708 PDR 'ADOCK '05000316 P . PDR

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Mr. Harold R. Denton AEP:NRC: 0637B operation of Cycle 4 of Unit No. 2; We will inform you of our final conclusion upon completion of our review. In addition, we will be submitting additional Technical Specification changes in support of Cycle 4 operation in the near future.

This document has been prepared following Corporate Procedures which incorporate a reasonable 'set of controls to insure its accuracy and completeness prior to signature by the undersigned.

Very truly yours, R. S. Hunter RSH /os Vice President cc: John E. Dolan R. W. Jurgensen W. G. Smith, Jr. Bridgman R. C. Callen G. Charnoff Joe Williams, Jr.

NRC Resident Inspector at Cook Plant Bridgman

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