ML17331B323
| ML17331B323 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/25/1994 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1118E, NUDOCS 9403310273 | |
| Download: ML17331B323 (6) | |
Text
. AC"CELERATED DISTRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
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05000315 05000316 ACCESSION NBR:9403310273 DOC.DATE: 94/03/25 NOTARIZED: NO FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
AUTH.NAME AUTHOR AFFILIATION FITZPATRICK,E.
(formerly Indiana 6 Michigan Ele RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
I SUBZECT: Provides annual submittal of LOCA model changes,per 10CFR50.46(a)(3)(ii).
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal:
General Distribution NOTES:
D RECIPIENT ID CODE/NAME PD3-1 LA HICKMAN,J INTERNAL: NRR/DE/EELB NRR/DRCH/HICB NRR/DSSA/SPLB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL: NRC PDR COPIES LTTR RECIPIENT ID CODE/NAME PD3-1 PD NRR/DORS/OTS B NRR/DRPW NRR/DSSA/SRXB
-.S/-LPJBCB REG FI 01 NSIC COPIES LTTR ENCL 1
1 1
1 D
D D
NOTE TO ALL"RIDS" RECIPIENTS:
D D
PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LIPID FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 16 ENCL
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indiana hlichigan Power Company P.O. Box 16631 Coiumbus, OH.43216 AEP'NRC'1118E 10 CFR 50.46(a)(3)(ii)
Donald C.
Cook Nuclear Plant Units 1 and 2
Docket Nos.
50-315 and 50-316 License Nos.
DPR-58 and DPR-74 REPORT OF LOCA EVALUATION MODEL CHANGES PURSUANT TO 10 CFR 50.46(a)(3)(ii)
U.
S. Nuclear Regulatory Commission Document Control Desk Washington, D.
C.
20555 Attn:
W. T. Russell March 25, 1994
Dear Mr. Russell:
Pursuant to the requirements of 10 CFR 50.46(a)(3)(ii),
this letter provides our annual submittal of LOCA model changes.,'hich was provided to us by Westinghouse Electric Corporation (Westinghouse),
describes LOCA model changes which have been permanently implemented and provides a discussion in.
general terms of the impact of these changes on calculated peak clad temperatures.
Attachment 2
contains the peak clad temperatures calculated specifically for Donald C.
Cook Nuclear Plant Units 1 and 2.
These temperatures are only slightly different from those contained in our previous submittal with the exception of the SBLOCA analyses with high head safety injection crossties closed.
The crossties closed SBLOCA analyses contain larger changes in PCT due to burst and blockage assessments.
In all cases, the calculated peak clad temperatures remain within the 10 CFR 50.46 limit of 2200 F.
In addition to the changes in peak clad temperatures associated with the licensing basis LOCA analyses, Attachment 2
also contains changes to LOCA analyses that were submitted via our letter AEP:NRC:1169, dated November 11, 1992; in support of a proposed technical specification change to increase main steam safety valve (MSSV) setpoint tolerances.
This submittal, as 9403310273'940325'DR ADOCK,.05000315 P
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Mr. W. T. Russell AEP:NRC:1118E modified by our letter AEP:NRC:1169A, dated December 17, 1993, is currently under NRC review and, therefore, the referenced SBLOCA
- analyses, which are affected, are not yet part of our licensing basis.
We have elected to prepare this annual 10 CFR 50.46 report using the analyses performed for the MSSV setpoint tolerance relaxation because these analyses include in their modeling non-discretionary changes to the SBLOCA model as defined in WCAP-13251.
The MSSV SBLOCA analyses will bound currently approved operational limits, and are, therefore, conservative.
Regarding plans for future LOCA analyses, the MSSV analyses will provide a new analysis of record for SBLOCA for each unit.
The plan for revising the Unit 1
cross-ties open SBLOCA run, discussed in our letter designated AEP:NRC:1118G, is being delayed several months to ensure that the calculation is made with planned code revisions.
Current plans also include both LBLOCA and SBLOCA reanalyses in conjunction with evaluations and analyses to support an increase in allowable steam generator tube plugging (SGTP) for Unit 1.
This work is tentatively planned to be complete and submitted to the staff prior to start of Unit 1 Cycle 16.
Plans for a new LBLOCA analysis of record for Unit 2 are tentative at this time but will not be performed until after the completion of the Unit 1 SGTP analyses.
Sincerely, E.
E. Fitzpatrick Vice President cad Attachments cc:
A. A. Blind - Bridgman G. Charnoff J.
B. Martin - Region III NFEM Section Chief NRC Resident Inspector
- Bridgman J.
R. Padgett
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