ML20094R319: Difference between revisions

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This revision to the COLR is being submitted in accordance with DBNPS Technical Specification 6.9.1.7.
This revision to the COLR is being submitted in accordance with DBNPS Technical Specification 6.9.1.7.
'      Revision 1 corrects linear heat rate limits'specified in Table 4 of the COLR to account for nonconservative assumptions discovered in the Loss of Coolant Accident (LOCA) analysis. This was reported to the Nuclear Regulatory Commission (NRC) under Licensee Event Report (LER) 95-001-00, which was                                !
'      Revision 1 corrects linear heat rate limits'specified in Table 4 of the COLR to account for nonconservative assumptions discovered in the Loss of Coolant Accident (LOCA) analysis. This was reported to the Nuclear Regulatory Commission (NRC) under Licensee Event Report (LER) 95-001-00, which was                                !
submitted by letter dated February 24, 1995 in accordance with                                        !
submitted by {{letter dated|date=February 24, 1995|text=letter dated February 24, 1995}} in accordance with                                        !
10 CFR 50.73 (a) (2) (ii) (B) and 10 CFR 50.46 (a) (3) (ii) . Revision 1 also corrects a typographical error in Table 4 of the COLR. This error was in                              I the conservative direction.                                                                            l Should you have any questions or require additional information, please contact Mr. Peter W. Smith, acting Manager - Regulatory Affairs, at (419) 249-2366.
10 CFR 50.73 (a) (2) (ii) (B) and 10 CFR 50.46 (a) (3) (ii) . Revision 1 also corrects a typographical error in Table 4 of the COLR. This error was in                              I the conservative direction.                                                                            l Should you have any questions or require additional information, please contact Mr. Peter W. Smith, acting Manager - Regulatory Affairs, at (419) 249-2366.
Very truly yours, MAR /llh                                                                                                l i
Very truly yours, MAR /llh                                                                                                l i

Latest revision as of 16:57, 24 September 2022

Forwards Davis-Besse Unit 1 Cycle 10 COLR, Rev 1
ML20094R319
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 11/27/1995
From: Stetz J
CENTERIOR ENERGY
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20094R322 List:
References
2345, NUDOCS 9512040357
Download: ML20094R319 (2)
v • d • e


Text

- ..

l CENTECHOR

..' ENERGY 300 W h John P. Sletz Toledo, OH 43652M1 V6ce Pfosident - Nuclear 419-249 2300 g Docket Number 50-346 License Number NPF-3 Serial Number 2345 November 27, 1995 United States Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Revision to Core Operating Limits Report for Cycle 10 Ladies and Gentlemen:

Enclosed is a copy of Revision 1 of the Davis-Besse Nuclear Power Station, Unit 1 (DBNPS) Core Operating Limits Report (COLR) for Cycle 10 Operation.

This revision to the COLR is being submitted in accordance with DBNPS Technical Specification 6.9.1.7.

' Revision 1 corrects linear heat rate limits'specified in Table 4 of the COLR to account for nonconservative assumptions discovered in the Loss of Coolant Accident (LOCA) analysis. This was reported to the Nuclear Regulatory Commission (NRC) under Licensee Event Report (LER) 95-001-00, which was  !

submitted by letter dated February 24, 1995 in accordance with  !

10 CFR 50.73 (a) (2) (ii) (B) and 10 CFR 50.46 (a) (3) (ii) . Revision 1 also corrects a typographical error in Table 4 of the COLR. This error was in I the conservative direction. l Should you have any questions or require additional information, please contact Mr. Peter W. Smith, acting Manager - Regulatory Affairs, at (419) 249-2366.

Very truly yours, MAR /llh l i

l Enclosure l cc: L. L. Gundrum, NRC Project Manager H. J. Miller, Regional Administrator, NRC Region III l S. Stasek, DB-1 NRC Senior Resident Inspector  !

Utility Radiological Safety Board  !

^~--

Operating Companies: --

cieveiond Electnc illuminating 9512040357 951127 I Toledo Ed: son PDR ADOCK 05000346 "

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... . . _~ . . - - . .

1 Docket Number 50-346  :

License Number NPF-3 .

I Serial Number 2345 t

Enclosure i

l CYCLE 10 I

CORE OPERATING LIMITS REPORT i

(20 Pages follow) 1 l

l i

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