ML20087B822

Application for Amend to License NPF-4,revising TS Table 2.2-1, Reactor Trip Sys Instrumentation Trip Setpoints & Table 3.2-1, DNB Parameters to Reduce Min RCS Flow Rate Limit to Support Increased SG Tube Plugging Level

ML20087B822
Person / Time
Site:	North Anna
Issue date:	01/08/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20087B825	List: ML20087B822 ML20087B828
References
92-018, 92-18, NUDOCS 9201130320
Download: ML20087B822 (3)

Text

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VIHOINIA ISLI CTHIC ANil t'OWI?H COMI'ANY lhCHMOND,YlHU1NIA 20061 January 8, 1992 k

'J.S. Nuclear Regulatory Commission Serial No.92-018

.sitention: Document Control Desk NL&P/JBL: R0 '

Washington, D.C. 20555 Docket Nos. 338 License Nos. NPF-4 Gentlemen:

-VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER -STATION UNIT 1 PROPOSED TECHNICAL SPECIFICATION CH ANGE BEDUCED MINIMUM RCS FLOW RATE LIMIT TO SUPPORT INCREASED STEAM GENERATOR TUBE PLUGGING LEVEL Pursuant to 10 CFR 50.90, the VirgH" Electric and' Power Comp iy requests amendments, in the form of changes to the Technical Specifications, to Operating License Number NPF 4 for North Anna Power Station Unit-1. The proposed Technical-Specifications changes revise Table 2.2-1, Reactor Trip System Instrumentation Trip Setpoints, of Specification 2.2,1 and Table 3.21,- DNB Parameters, of Specification 3.2.5 to reduce the limit for Reactor Coolant System Total Flow Rate for the remaining operating period until the North Anna Unit 1 steam generators are replacad in 1993.

- The proposed reduction in the minimum measured reactor coolant system (RCS) flow is necessary to accommodate the interim system effects associated with the extended steam generator tube plugging as a result of the current Unit 1 mid cycle inspection outage.

The proposed Technical Specifications changes are presented in Attachment 1. A discussion of the proposed changes is provided in Attachment 2 and a safety evaluation is provided in Attachment 3. This . request has been reviewed and approved by _the Station Nuclear Safety and Operating- Committee. and the i Management Safety Review Committee. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant .

- hazards consideration as defined in 10 CFR 50.92. The basis for our determination that this change does not involve a significant hazards consideration is provided in Attachment 4.

North Anna Unit 1 is scheduled to conclude the steam generator inspections and commence unit startup_ on February 19,1992. We request your approval of these proposed Technical Specifications changes prior to this scheduled startup date.

9201130320 9201o8 00 P

PDR ADOcr: 05ooo338 PDR- ( l' I-

Should you have any questions or require additional information, please contact us immediately.

I Ver oly y ur,,

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W. L. tevfart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specifications Changes

2. Discussion of Proposed Changes

3. Safety Evaluation 4.10 CFR 50,92 No Significant Hazards Consideration Evaluation cc: U.S. Nuc:.c. ' 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 Commissioner Department of Health Room 400 109 Governor Street Richmod. Virginia 23219 l

COMMONWEALTH OF VIRGINIA )

)

COUNTYOF HENRICO _)

The foregoing document was acknowledged before me, in and - for the County and Commonwealth aforesaid,-today- by E, W. _Harrell, who is-Vice President - Nuclear Operations, for .W;zL.? Stewart, who -is Seni_or Vice

-President - Nuclear, of ' Virginia Electric and - Power Company. _He it duly authorized to execute and--file the foregoing : document -in: behalf ofsthat Company,: and the1 statements in the_. document are true to Lthe best of his-knowledge and belief.

Acknowledged before me .this ' day of - NdALLiou , 19'72. ,

My Commission- Expires: ( -

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' Notary 'Public o

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