ML20076G812

Suppl to Application for Amend to Licenses NPF-4 & NPF-7, Providing Tech Specs for NUREG-0737,Item II.B.1, Reactor Vessel Head Vent. No Addl License Amend Fee Required

ML20076G812
Person / Time
Site:	North Anna
Issue date:	06/09/1983
From:	Steward W, Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20076G814	List: ML20076G812 ML20076G841
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.F.1, TASK-2.F.2, TASK-TM 333A, NUDOCS 8306160249
Download: ML20076G812 (2)

Text

r VINGINIA 13LECTRIC AND Powsu COMPANY RIcnnoNn,VIHOINIA 20261 W. L. STEWART vice I == ion"'

Nues. nam OPERATIONS June 9, 1983 Mr. Harold R. Denton, Director Serial No. 333A Office of Nuclear Reactor Regulation N0/JHL:acm 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 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated June 3, 1983, Serial No. 333, Vepco submitted proposed Technical Specification changes for North Anna Unit Nos. I and 2. These proposed Technical Specification changes were related to NUREG-0737, items II.F.1 and II.F.2. This proposed change supplements our above referenced letter by providing Technical Specifications for NUREG-0737, Item II.B.1 (Reactor Vessel Head Vent).

The proposed changes are to add Technical Specifications for the Reactor Vessel Head Vent in accordance with the requirements of NUREG-0737, Item II.B.l. The Reactor Vessel Head Vent has been installed and is considered operational but remains isolated by having the manual isolation valves closed.

Final implementation of the Reactor Vessel Head Vent Technical Specifications must be coordinated with the implementation of the revised emergency operating procedures prior to issuance of this amendment.

This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that this request does not pose an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92.

We have reviewed this request in accordance with the criteria in 10 CFR 170.22. Since this request supplements our previous license amendment application referenced above, no additional license amendment fee is required.

Very truly yours, il W. L. Stewart M 8306160249 830609 Y' PDR ADOCK 05000338 I

'I P PDR

O visorwtA Ex.zcTaic Axo Powra Counxv To Harold R. Denton Attachments:

1. Proposed Technical Specification Changes

2. Discussion of Proposed Technical Specification Changes cc: Mr. James P. O'Reilly Regional Administrator Region II Hr. M. B. Shymlock NRC Resident Inspector North Anna Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219

S ATTACIDfENT 1