ML17321A498
| ML17321A498 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/20/1985 |
| From: | Alexich M INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| AEP:NRC:0745T, AEP:NRC:745T, NUDOCS 8503270238 | |
| Download: ML17321A498 (6) | |
Text
REOULATtlAtNFORMATION DISTRIBUTION 4TEM (RIBS)
ACCESSION NBR:8503270238 DOC ~ DATE: 85/03/20 NOTARIZED'O DOCKET"'0 FACIL:50 31'5 Donald C.
Cook. Nuclear Power Plant~
Unit 1~ Indiana 8
05000315 AUTH-,NAME AUTHOR AFFILIATION ALEXICH<M,P, Indiana 8 Michigan Electric Co ~
RECIP ~ NAME RECIPIENT AFFILIATION DENTONgH,RE Office of Nuclear Reactor Regulationi Director
SUBJECT:
Informs of codiing er ror found in pr ogram used for LOCA"ECCS analysis submitted in XN NF 83,6ig "DC ~Cook Unit 1
LOCA EGGS Analysis for Extended Exposur e," Exxon r epenformed analysis w/coding error corrected, DISTRIBUTION CODE:
A001D COPIES RECEI VED: L'TR ENCL SIZES TITLE:
OR Submittal:
Gener al Distribution NOTES:
OL; 10/?5/70 05000315 RECIPIENT ID CODE/NAME-NRR ORB1 BC 01 INTERNAL; ACRS 09 ELD/HDS3 NRR/DL DIR NRR/DL/TSRG NRR/DSI/RA9 RGN3 COPIES LTTR ENCL RECIPIENT.
ID CODE/NAME ADM/LFMB NRR/DE/MTEB NRR/DL/DRAB
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ETB 0P COPIES LTTR ENCL EXTERNAL: LPDR NSIC 03 05 NRC PDR 02 i TOTAL NUMBER OF COPIES REQUIRED:
LTTR 26 ENCL
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INDIANA8 MICHIGAN ELECTRIC COMPANY P.O. BOX I663I COLUMBUS, OHIO 43216 March 20, 1985 AEP:NRC:0745T Donald C. Cook Nuclear Plant Unit No.
1 Docket No. 50-315 License No. DPR-58 REVISION TO ANALYSIS WHICH SUPPORTED A TECHNICAL SPECIFICATION CHANGE Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Denton:
Exxon Nuclear Company informed AEP of a coding error in their LOCA-ECCS analysis.
This ooding error was found in a program used for the LOCA-ECCS analysis of the D. C.
Cook Nuclear Plant Unit 1.
The analysis in question was submitted to NRC in XN-NF-83-61, "D. C. Cook Unit 1 LOCA-ECCS Analysis for Extended Exposure," for an exposure of 48,000 MWD/MTU.
The error was in the TOODEE2 oode whioh is used for the reflood/heatup calculation.
The error resulted in an increase in the heat transfer coefficient during reflood, thus underpredioting the peak cladding temperature (PCT).
Exxon has informed us that the analysis has been reperformed for this high burnup case with the coding error oorrected.
They indicated that the revised PCT is 1785 F, which is an increase of 49 F..
This revised PCT still satisfies the requirements of 10CFR50.46.
Therefore, we believe that there is no further action required on this matter.
Exxon Nuclear Company has advised us that they will inform you of the coding error formally as required by 10 CFR 21.21.
They have further advised us that this ooding error does not affeot the analyses performed for D. C.
Code Nuclear Plant Unit 2.
This dooument has been prepared following Corporate procedures which incorporate a reasonable set of controls to insure its 'acouracy and completeness prior to signature by the undersigned.
Very truly yours, JLB:wg M. P.
exioh o b~
Vice President 8503270238 850320 PDR ADOCK 050003i5 P
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Mr. Harold R. Denton, Director March 20, 1985 cc'ohn E. Dolan M. G. Smith, Jr. - Bridgman George Bruchmann R. C. Callen R. Charnoff NRC Resident Inspector - Bridgman G. F. Owsley, ENC - Riohland, MA
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