ML20094K341

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Forwards Core Operating Limits Rept for Remainder of Plant Cycle Nine.Several Limits Revised After Updated FSAR Chapter 15 Accident Evaluations & TS Changes & mid-cycle Rept Thus Necessary
ML20094K341
Person / Time
Site: North Anna Dominion icon.png
Issue date: 03/16/1992
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20094K336 List:
References
92-143, NUDOCS 9203200228
Download: ML20094K341 (2)


Text

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VIHoiN tA E1.1:CTHIC AN D l' owl:H COMi%NY Iticusioxu,Vunuxar ununi March 16, 1992 U.S.- Nuclear Regulatory Commission Serial No. 92143 Attention: Document Control Desk NAPS /JYR

- Washington, D.C. 20555 Docket No. 50 338 License No NPF-4 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPAtLY NORTH ANNA POWER STATION UNIT 1 CYCLE 9

,QORE OPERATING LIMITS REPORT Pursuant to Technical Specification 6.9.1.7.d, we are submitting the attaci,ed Core Operating Limits Report (COLR) for the remainder of North Anna Unit 1 Cycle 9.

This is the first issuance of a Unit 1 COLR, in accordance '-ith Amendment No.146 which was approved June 7,1991.

. North Anna Unit 1 Cycle 9 originally began operation on March 9,1991.

- However, the unit shut down on December 23,1991 to conduct a mid cycle steam generator _ tube inspection outage.

As a result of the inspection, additional steam generator tube plugging was required. The UFSAR Chapter 15: accidents were evaluated for the increased tube-plugging effects. These evaluations resulted in Technical Specification changes to support a reduced

-minimum RCS. flow rate limit for the Loss of Coolant Accident (LOCA) and a

_ temporary power reduction-for_ the remainder of the cycle.

The reduced minimum RCS flow rate limit and the temporary power reduction were approved by Amendment Nos _154 and 153, respectively.

Several core operating limits were revised as a result of the _UFSAR Chapter 15 accident evaluations and associated Technical Specification _ changes, Therefore, a mid-cycle COLR is necessary to reflect the. change in the N5) functions and the axial flux difference curves for the remainder of Cycle 9.

Should you-have any questions or require additional-information, please contact us at your earliest convenience.

1 l

Very truly yours, 0-w 1

l p r W. L. Stewart Senior Vice President - Nuclear Jo'q u

i 92o320o228 920316 I

PDR ADOCK 05000338 P

PDR

Attachment cc:

U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station

9-t I

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4 9

APPENDIX A 4

NORTH ANNA 1 CYCLE 9 CORE OPERATING LIMITS REPORT Revision 1 (Feb 92) g 5

o l

NIC9 - Core Operating Limits Report - Rev. 1 (Feb 92)

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