ML20083H106

Application for Amend to Licenses NPF-4 & DPR-7,revising Tech Spec to Reflect Addition of New Fire Protection Sys

ML20083H106
Person / Time
Site:	North Anna
Issue date:	12/27/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20083H112	List: ML20083H106 ML20083H132
References
552A, NUDOCS 8401040424
Download: ML20083H106 (2)

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,VIRGIMIA ELECTRIC AND PowEn COMPANY Ricnwown, VIRGINIA 20261 W.L.srswimr vice r ..r===' December 27, 1983 Nucu. nam oFEMATIONS

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Mr. Harold R. Denton, Director Serial No. 552A Office of Nuclear Reactor Regulation N0/JHL: jab Attn: Mr.-James R. Miller, Chief Docket Nos. 50-338 Opefating 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 SPECIFICATIONS CHANGES In our letter dated ' October 7, 1983 (Serial No. 552), Vepco requested an amendment in the form of changes to the Technical Specifications for North

. Anna-Unit Nos. I and 2. These proposed changes would revise the Technical Specifications to reflect the addition of new fire protection systems.

This submittal will be a supplement to our above mentioned submittal, to add-the statement that hose rack stations are located at the containment entrance.

W This statement should be added to the asterisk note on Table 3.7-7. The addition of this change will aid in completing the provisions of Appendix A to Branch Technical Position APCSB 9.5-1~and to clarify where the fire hose rack

. stations are located in relation to the containment. The proposed Technical Specification change for North Anna Unit No. 1 is provided in Attachment 1.

The proposed Technical Specification change for North Anna Unit No. 2 is provided in Attachment 2. A discussion of the proposed Technical Specifications change is provided in Attachment 3.

This ~ supplemented 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 supplemental request does not involve an-unreviewed safety question as defined in 10CFR50.59 and it does not pose a significant hazards consideration as defined in 10CFR50.92.

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Vaasswu Es.acresc. Awo Powsm Conapawr To Mr. Harold R. Denton LWe'have reviewed.this supplemental request /in accordance with the criteria in 10CFR170.22. .Since. this request supplements a previous submittal,. no

-additional license amendment fees are required.

Very truly yours,

/ (,sy'p W. L. Stewart Attachments:

1. Proposed Technical Specification Change - Unit 1

-2. Proposed Technical Specification Change - Unit 2 3.l Discussion of Proposed Technical Specifications Change cc: Mr. James P. O'Reilly Regional Administrator Region-II:

.Mr. M. W. Branch

-NRC Resident. Inspector

-North Anna Power Station iMr. Charles Price Department of Health 109 Governor Street-

' Richmond, Virginia 23219 Mr. L. D. Graber LIS S

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