ML20125D194

Forwards Amend to License NPF-7,consisting of Proposed Change,Revising TS Table 2.2-1,RCS Instrumentation Trip Setpoints of TS 2.2.1 & Table 3.2-1,DNB Parameters of TS 3.2.5 to Allow Reduction in RCS Flow Rate

ML20125D194
Person / Time
Site:	North Anna
Issue date:	12/04/1992
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20125D197	List: ML20125D194 ML20125D213
References
92-721, NUDOCS 9212150045
Download: ML20125D194 (3)

Text

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VInOINIA ELECTHIC AND Powen COMPANY Ricit>iOND, VIHOINI A 23201 December 4,1992 U.S. Nuclear Regulatory Commission Serial No.92-721 Attention: Document Control Desk NL&P/JBL: R0 Washington, D.C. 20555 Docket Nos. 50-339 License Nos. NPF-7 Gentlemen: .

1 VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES REDUCTION IN MINIMUM MEASURED RCS FLOW RATE Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Facility Operating License NPF-7 for North Anna Power Station Unit 2. The proposed changes will revise Table 2.2-1, Reactor Trip System Instrumentation Trip Setpoints, of Specification 2.2.1 and Table 3.2-1, DNB Parameters, of Specification 3.2.5 to allow a reduction in the minimum measured reactor coolant system flow rate. This change is necessary to accommodate the system effects associated with increasing steam generator tube plugging. This proposed change is consistent with and essentially the same as the change requested for North Anna Unit 1 in letter dated January 8,1992 (Serial No.92-018) and approved by the NRC by letter dated March 3,1992.

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 Management Safety Review Committee. It has been determined that this request does not involve an unreviewed safety tyastion 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 .

North Anna Unit 2 is scheduled to conclude Cycle 9 operations and begin a refueling /

steam generator inspection outage in September 1993. It is expected that this inspection will result in plugging additional steam generator tubes. Therefore, we request approval of these proposed Technical Specifications changes prior to startup from this outage which is currently scheduled for completion on November 16,1993.

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

Very truly yours, W.' L.QStewar}t

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Senior Vice President - Nuclear 1

Attachments

1. Proposed Technical Specifications Changes

2. Discussion of Changes

3. Safety Evaluation .

4.10 CFR 50.92 No Significant Hazards Consideration Evaluation 3 cc: U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 g Mr. M. S. Lesser NRC Senior Resident inspector North Anna Priwer Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

r COMMONWEALTH OF VIRGINIA )

)

COUNTY OF HENRICO )

The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L Stewart who is Senior Vice President -

Nuclear, of Virginia Electric and Power Company. He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.

Acknowledged before me this Mf_ day of Nfad,d_,1991 My Commission Expires: (-, //A 3/ ,19M.

$6 Y/bij Notary P0blic (SEAL)

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