ML17332A933
| ML17332A933 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 09/18/1995 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1118J, NUDOCS 9509210084 | |
| Download: ML17332A933 (5) | |
Text
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PRIORITY (ACCELERATED RIDS PROCESSING)
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9509210084 DOC.DATE: 95/09/18 NOTARIZED: NO DOCKET g FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION R
FITZPATRICK,E.
(formerly Indiana
& Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
I
SUBJECT:
Provides notification of large break loss of accident model changes or errors reported by meeting definition of significant as defined DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL TITLE: OR Submittal:
General Distribution NOTES coolant Westinghouse, in 10CFR50.46.
SIZE:
RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNA ~FILE CENTE~
1 NEM/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
0 1
1 RECIPIENT ID CODE/NAME PD3-1 PD NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 N
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESKi ROOM OWFN 5D8 (4 15 2083)
TO ELIM1NATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DONsT NEED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 12 ENCL 11
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indiana Michigan Power Company ~
P.O. Box 16631 Columbus, OH 43216 FI September 18, 1995 AEP:NRC:1118J Docket Nos.:
50-315 50-316 U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.
C.
20555 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
REPORT OF LOCA EVALUATION MODEL CHANGES Pursuant to the requirements of 10CFR50.46(a)(3)(ii),
this letter provides notification of large break loss of coolant accident (LBLOCA) model changes or errors reported to us by Westinghouse Electric Corporation (Westinghouse) that meet the definition of significant as defined in 10CFR50.46., which was provided to us by Westinghouse, contains two letters from Westinghouse to the NRC staff.
One of these notifies the staff of a change from current Westinghouse methodology for addressing power shape to a new methodology.
The second describes a
modification to the evaluation model which, in the case of Cook Nuclear Plant, will be used to compensate for the PCT penalties associated with the change of power distribution methodologies.
The change from the Power Shape Sensitivity Model (PSSM) to the new methodology, Explicit Shape Analysis for PCT Effects (ESHAPE) methodology, is a penalty for the LBLOCA analyses of record for Cook Nuclear Plant.
Most of this penalty is offset by the evaluated benefit for hot leg nozzle gap flow which is described in the second letter from Westinghouse.
Attachment 2 contains the LBLOCA peak clad temperatures calculated specifically for Cook Nuclear Plant Units 1 and 2.
In all cases, the calculated peak clad temperatures remain within the 10 CFR 50.46 limit of 2200'F.
The modeling of small break LOCA (SBLOCA) for Cook Nuclear Plant is not affected by the changes noted above; therefore, no new SBLOCA rackups are provided in this correspondence.
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~ 4 S. Nuclear Regulatory Commission Page 2
AEP:NRC:1118J A revised Unit 1 high head safety injection (HHSI) cross-tie open SBLOCA run, addressed in our letter designated AEP:NRC:1118G, has been completed and reviewed internally.
HHSI cross-ties closed SBLOCA analyses were reviewed and approved in conjunction with Amendment 182 to Facility Operating License DPR-58 and Amendment, 167 to Facility Operating License DPR-74.
These amendments approved an increase in main steam safety valve setpoint tolerance.
The SBLOCA analyses supporting these amendments and related cross-tie open analyses became the basis for Cook Nuclear Plant 10 CFR 50.46 reports starting with the letter identified as AEP:NRC:1118H.
Although we are not specifically submitting the revised Unit 1 cross-tie open case as part of our license basis, the results of the new analysis will be used to update the UFSAR reference to a Unit 1 cross-ties open SBLOCA run. It will also provide the basis for future Unit 1 HHSI cross-ties open 10 CFR 50.46 reports.
Currently, both LBLOCA and SBLOCA reanalyses are being reviewed by NRC staff in conjunction with evaluations and analyses to support an increase in allowable steam generator tube plugging (SGTP) for Unit 1.
This work was submitted to the staff in May 1995 with our letter identified as AEP:NRC:1207.
A specific letter explaining the effect of the revised power shape on the increased SGTP LOCA analyses will be submitted in the near future.
New LBLOCA and SBLOCA analyses of record for Unit 2 will be included as part of a planned uprating effort.
The submission of the results of these new Unit 2 analyses is planned for 1996.
Sincerely, 8F p
E.
E. Fitzpatrick Vice President sic Attachments cc:
A. A. Blind G. Charnoff J.
B. Martin H. J. Miller NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
ATTACHMENT 1 TO AEP:NRC:1118J WESTINGHOUSE ELECTRIC CORPORATION DESCRIPTION OF LOCA MODEL CHANGES