ML20071H348

Application to Amend Licenses NPF-4 & NPF-7,revising Tech Specs to Add Containment Isolation Valves 36 & 37

ML20071H348
Person / Time
Site:	North Anna
Issue date:	03/01/1982
From:	Leasburg R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20071H351	List: ML20071H348 ML20071H354 ML20071H357
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-TM 095, 95, NUDOCS 8203080387
Download: ML20071H348 (4)

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IEEWirD VinornA ELEcrHIC AND POWER COMPANW 05 MI ?

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March 1,

1982 Narca. man opsmarionn Mr. Harold R. Denton, Director Serial No. 095 Office of Nuclear Reactor Regulation N0/GSS: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 Centlemen:

AMENDMENT TO OPERATING LICENSES NPF-4 AND NPF-7 NORTH ANNA POWER STATION UNITS NO. 1 AND No. 2 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 Operating Licenses NPF-4 and NPF-7 for the North Anna Power Station, Units No.

I and No. 2.

The proposed changes are enclosed.

The proposed changes revise the Table 3.6-1 by the addition of containment isolation valves 36 & 37.

It has been determined that to meet the requirements of NUREG-0737 Section II.B.3 for the Poct Accident Sampling of the containment atmosphere, a dedicated penetration be provided.

This j

dedicated penetration will require the addition of two :ontainment isolation valves per unit.

Addition of the category I Containment isolation valves meets the requirements for containment isolation integrity as specified in the FSAR.

Also, the installation of the valves satisfies the seismic design criteria for safety related systems.

The addition of this modification does not introduce the possibility of an accident or malfunction.

The margin of safety is not reduced by this change and this does not alter the basis for the Technical Specifications.

The proposed changes are requested during the refueling outages currently scheduled during March 5, 1982 - May 14, 1982 for Unit 2 and during May 21, 1982 - July 2, 1982 for Unit 1.

This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.

It has been determined i

that this request does not involve an unreviewed safety question.

We have evaluated this request in accordance with the criteria in 10CFR170.22.

It has been determined that this request requires a Class III amendment fee.

Accordingly, a voucher check in the amount of $4,400. is enclosed in payment of the required fee.

Very y urs, taQO d 4gb B203090387 820301 glp PDR ADOCK 05000338 0

. teasburg P

PDR ig 5

VtuoixA ELECTRIC AND PowEs COMPAMY TO Attachments:

1.

Proposed Technical Specification change - Unit 1 2.

Proposed Technical Specification change - Unit 2 3.

Voucher Check No. 9716 for $4,400.

cc:

Mr. James P. O'Reilly, Regional Administrator Office of Inspection and Enforcement Region II i

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i COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND

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The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by R. H. Leasburg, who is Vice President-Nuclear Operations, of the 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

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day of he-O 19 PA My Commission expires: A 4

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