ML19338G071

Forwards Proposed Tech Spec Changes,Per NRC 800702,0815 & 0611 Ltrs to PWR Licensees

ML19338G071
Person / Time
Site:	North Anna
Issue date:	10/15/1980
From:	Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML19338G072	List: ML19338G071 ML19338G077
References
845, NUDOCS 8010280409
Download: ML19338G071 (3)

Text

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, VIRGINIA Ex.ucrH C AND l'OWEN COM I%NY Hrcuwown.Vamorms A 2n201 October 15, 1980 Mr. Harold R. Denton, Director Serial No. 845 Office of Nuclear Reactor Regulation LQA/WRM:ms Attn: Mr. Robert A. Clark, Chief Docket Nos. 50-338 Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555

Dear Mr. Denton:

AMENDMENT TO OPERATING LICENSE NPF-4 NORTH ANNA POWER STATION UNIT NO. 1 PROPOSED TECHNICAL SPECIFICATION CHANGE Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operat-ing License NPF-4 for the North Anna Power Station, Unit No.1. The proposed changes are enclosed.

We received the letter of July 2, 1980 from Mr. D. G. Eisenhut to all pressurized water reactor licensees ~ requesting the submittal of a license amendment application to incorporate the recommended TMI-2 Lessons Learned Category A changes for the Appendix A Technical Specifications. The proposed Technical Specification changes enclosed for North Anna Unit 1 incorporate the additional limiting conditions of operation, surveillance requirements, and bases for the areas of instrumentation, the reactor coolant system, the auxiliary feedwater system, and administrative controls as outlined in the July 2, 1980 letter. The North Anna Unit ~2 Technical Specifications already contain these new requirements. The propcsed changes being incorporated for North Anna Unit I will, to the extent possible, make the applicable Unit I requirements identical to the existing approved Unit 2 requirements.

The letter of August 15, 1980 from Mr. Thomas M. Novak to all Westinghouse pressurized water reactor licensees requested that we review the Technical Specifications and the procedures for North Anna to assure that fuel assemblies and control rods not be inadvertently exposed during refueling operations. In our letter of September 16, 1980, we provided information concerning the existing operating procedures for North Anna and Surry Power Stations. The proposed Technical Specification changes enclosed revise the requirements for maintenance of minimum water levels above fuel assemblies during refueling operations. The proposed changes are identical to th( 'ist-ing approved requirements for North Anna Unit 2.

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visoim nectaic no Powra courm to Mr. Harold R. Denton 2 The letter of June 11, 1980 from Mr. D. G. Eisenhut to all operating pressurized water reactor licensees requested that we submit proposed Tech-nical Specification changes to provide for redundancy in decay heat removal capability for all modes of facility operation. The proposed Technical Speci-4 fication changes enclosed revise the requirements for residual heat removal identified in the June 11, 1980 letter. These proposed changes will provide North Anna Unit 1 Technical Specification requirements for residual heat removal which are identical in format and content to the existing approved requirements for North Anna Unit 2.

These proposed Technical Specification changes increase the margin of safety associated with the Technical Specifications being modified by requiring operability of equipment previously not required. The probability of occurrence or the consequences of an accident or malfunction of equipment important to safety and previously evaluated in the Safety Analysis Report is not increased by the proposed changes since these changes impose additisaal restrictions on operation and require more comprehensive instrumentation and surveillance.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee. It has been determined that this request does not involve an unreviewed safety question.

We have evaluated this request in accordance with the criteria in 10 CFR 170.22. Since this request is based upon NRC positions, as outlined in the letters of June 11, 1980, July 2, 1980, and August 15, 1980, a Class III license amendment fee is required. Accordingly, a voucher check in ttie amount of $4,000.00 is enclosed in payment of the required fee.

Very truly yours, f4 -

J. H. Ferguson Executive Vice President Power Attachments:

1. Proposed Technical Specification Changes

2. Voucher Check No. 41059 for $4,000.00 cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II

COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared J. H. Ferguson, who being duly sworn, made oath and said (1) that he is Executive Vice President-Power, of the Virginia Electric and Power Company, (2) that he is duly authorized to execute and file the foregoing Amendment in behalf of

{ that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.

Given under my hand and notarial seal this 16 D day of Oclober , BBo.

My Commission expiras MouMu \9,68A .

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