ML17321A898

Submits Info Re Exxon Nuclear Co Eccs/Loca Analysis,Per 850930 Discussion W/Nrc.Error Found in TOODEE2 Code Re Calculation of Thermal Response of Hot Fuel Rod.Peak Cladding Temp Underpredicted.Calculations Revised

ML17321A898
Person / Time
Site:	Robinson, Cook, 05000000
Issue date:	10/02/1985
From:	Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML17321A899	List: ML17321A898 ML17321A900
References
AEP:NRC:0940B, AEP:NRC:940B, NUDOCS 8510080292
Download: ML17321A898 (7)

Text

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.REGULATOR 'NFORMATION DISTRIBUTION LITEM (RIDS)

ACCESSION NBR:8510080292'OC ~ DATE: 85/10/02 NOTARIZED: NO DOCKET FACIL':50-000 Generic Docket 05000000 50-315 Donald C ~ Cook Nuclear Power Plantr Unit BYNAME, -.

1~ Indiana 8 05000315 AUTH AUTHOR AFFILIATION ALEXICH<M,PE Indiana 8 Michigan Electric Co.

RECIP ~ NAt1E RECIPIENT AFFILIATION DENTONgH ~ Re Office of Nuclear Reactor Regulationi Director~

SUBJECT:

. Submits info re Exxon NUclear Co ECCS/LOCA analysisqper 850930 discussion w/NRC,Error found in TOODEEZ code re calculation of thermal. response'f- hot fuel rod+Peak clad temp, underpredicated,Calculations revised, DISTRIBUTION CODE: A001D COPIES RECElVED;LTR ENCL 'SIZE TITLE: OR Submittal: General Distribution NOTES: 05000315 OL ~ 10/25/74 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME," LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB1 BC 01 7 7 I~TER~AL: ACRS 09. 6 6 ADM/LFMB 0, ELD/HDS3 0 NRR/DE'/MTEB 1 NRR/DL DIR 1 NRR/DL/DRAB 0 NRR/DL/TSRG 1 N METB 1 NRR/DSI /RAB 1 1 'G ILE 04 1-RGN3 1 EXTERNAL; 24X 1 1 EGE,G BRUSKEgS LPDR 03 1 NRC PDR 02 NSIC 05 1 1 TOTAL NUMBER>> OF COPIES REQUIRED

. LTTR 28 ENCL'5

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INDIANA 8 M I C H I GAN ELECTRIC COMPANY P.O. BOX 16631 COLUMBUS, OHIO 43216 October 2, 1985 AEP:NRC:0940B Donald C. Cook Nuclear Plant Unit No. 1 Docket No. 50-315 L'icense'No. DPR-58 ERROR IN EXXON LOCA/ECCS ANALYSIS Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

This letter is submitted pursuant to discussions with your staff on September 30, 1985. Attached please find the recent information regarding the ECCS/LOCA analysis for Donald C. Cook Unit 1 which was performed by the Exxon Nuclear- Company (ENC).

ENC found an error in the input to the TOODEE2 code, which calculates the thermal response of the hot fuel rod. The error consisted of the assignment of a relative decay heat power density of 0.0 in the outer ring of the fuel pellet. This resulted in an underpredicted peak clad temperature (PCT) at 48 l%1D/kg. The revised calculations have been performed by ENC using more realistic'values of the pellet density, and internal rod pressure. These calculations have resulted in a PCT of 2189 F, which is in compliance with 10 CFR 50.46.

The information contained in this letter and its attachment represents a correction of the analysis presented in the ENC report entitled, "D. C. Cook Unit 1 LOCA-ECCS Analysis for Extended Exposure" (XN-NF-83-61) and subsequent revision-transmitted via letter AEP:NRC: 0745T dated March 20, 1985.

h A further Justification for operating D. C. Cook Unit 1 with the existing LOCA/ECCS Analysis for Exxon fuel was submitted on June 26, 1985 via letter no.

AEP:NRC:0940. Exxon has verified that the sensitivity study referred to in AEP:NRC:0940 was not affected by the error reported in this letter.

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Mr. Harold R. Denton AEP:NRC:0940B Currently, Donald C. Cook Unit 1 is shut down, and is scheduled for criticality on October 12, 1985. We believe that your appr oval of the submitted information is required prior to D. C. Cook Unit 1 being in Mode 1.

Therefore, your timely prooessing of the information submitted would be greatly appreciated.

This information will be reviewed by the Plant Nuolear Safety Review Committee (PNSRC) and the Nuclear Safety and Design Review Committee (NSDRC) at their next regularly scheduled meetings.

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,

. P. Ale ich ~y, Vice President iQ cm 2'ttachments CC ~ John E. Dolan W. G. Smith, Jr. - Bridgman G. Bruchmann ~

R. C. Callen R. Charnoff NRC"Resident Inspector - 'Bridgman G."Ward, ENC - Riohland, Washington

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Fg I to AEP:NRC:0940B