GO2-91-123, Forwards Rev 0 to COLR 91-7, WNP-2 Cycle 7 Core Operating Limits Rept
| ML17286A891 | |
| Person / Time | |
|---|---|
| Site: | Columbia |
| Issue date: | 06/17/1991 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML17286A892 | List: |
| References | |
| GO2-91-123, NUDOCS 9106240263 | |
| Download: ML17286A891 (4) | |
Text
UTION DEMONS TlON SYSTEM ACCELERATED DIS II 4
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
SUBJECT:
Forwards Rev 0 to COLR 91-7, "WNP-2 Cycle 7 Core Operating Limits Rept."
DXSTRIBUTION, CODE:
A001D COPIES RECEIVED:LTR
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TITLE: OR Submittal:
General Distribution NOTES:
ACCESSION NBR:9106240263 DOC.DATE: 91/06/17 NOTARIZED, NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION SORENSEN,G.C.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
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RECIPIENT ID CODE/NAME PD5 LA ENG,P.L.
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NOTE TO ALL"RIDS" RECIPIENTS:
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D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISIS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
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V Sa WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968
~ 3000 George Washington Way
~ Richland, Washington 99352 June 17, 1991 G02-91-123 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn:
Document Control Desk Washington, D.C.
20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21 WNP-2 CYCLE 7 CORE OPERATING LIHITS REPORT
Reference:
- Letter, NRC to Supply System, "Issuance of Amendment No.
94 to Facility Operating License No. NPF-21 for the WPPSS Nuclear Project No.
2 (TAC No. 77311)", dated June 4,
1991 As authorized by the reference letter, enclosed is an uncontrolled copy of the WNP-2 Cycle 7 Core Operating Limits Report, COLR 91-7, Rev. 0, dated June 1991.
This report is being provided upon issuance as required by Technical Specifica-tion 6.9.3.4.
The changes in core thermal limits resulting from the analyses performed in support of the preparation of the Cycle 7
COLR have been evaluated against the criteria of 10 CFR 50.59.
That evaluation determined that neither a change in the Technical Specifications is required nor does an Unreviewed Safety question exist.
This report and the changes in core thermal limits therein have been reviewed and approved by the WNP-2 Plant Operations Committee (POC).
At the present time we expect to achieve reactor criticality, thereby starting cycle 7, no sooner than July 3, 1991.
Should you have any questions or concerns, please contact us immediately.
Very truly yours, G.
C.
- orensen, Hanager Regulatory Programs HLA/bk Attachment cc:
JB Hartin -
NRC RV (w/attach)
NS Reynolds
- Winston 5 Strawn PL Eng -
NRC DL Williams - BPA/399 NRC Site Inspector
- 901A (w/attach)-
9106240263 910617 n 'DR ADOCK 05000397 P
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