ML20052A475

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Application to Amend License NPF-7,changing Tech Spec 3/4.6.3.1,Table 3.6-1 to Reflect Addition & Deletion of Containment Isolation Valves.Class II Amend Fee Encl
ML20052A475
Person / Time
Site: North Anna Dominion icon.png
Issue date: 04/23/1982
From: Leasburg R
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
Shared Package
ML20052A476 List:
References
257, NUDOCS 8204280365
Download: ML20052A475 (5)


Text

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VINGINIA EI.HCTRIC AND Powna COMPANY -

H ic u x o n o, V rnaa rs A 20261 H.H.LnAmacao v C. p...... ., April 23, 1982 NCCLEAm O smarrows Mr. Harold R. Denton, Director -

Serial No. 257 Office of Nuclear Reactor Regulation N0/JHL:acm Attn: Mr. Robert A. Clark, Chief Docket N - 39 Operating Reactors Branch No. 3 Lice ' I.11 PF Division of Licensing V U. S. Nuclear Regulatory Commission Washington, D. C. 20555 D _

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8-l Gentlemen: '

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AMENDMENT TO OPERATING LICENSE NPF-7 NORTil ANNA POWER STATION UNIT NO. 2 + J PROPOSED TECHNICAL SPECIFICATION CHANGE 9 c.n V 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 License NPF-7 for North Anna Power Station, Unit No. 2. The proposed Technical Specification changes are enclosed.

This proposed change is to modify Technical Specification 3/4.6.3.1 Table 3.6-1 for North Anna Unit No. 2 to reflect the addition and deletica of containment isolation valves. Air-operated trip valves are being replcced with direct-acting solenoid valves to improve post-accident sampling capabilities. Manual isolation valves are being replaced with remotely operated isolation valves in the post-accident containment hydrogen analysis and control equipment. Two isolation valves are being installed to provide containment integrity for the post-accident sampling system containment return line. The upgrade and installation of the containment isolation valves for post-accident sampling meets the requirements for containment isolation integrity as specified in the FSAR. The upgrade and installation of these containment isolation valves satisfies the seismic design criteria for safety

related systems. The proposed Technical Specification Change is enclosed 'in Attachment 1. A discussion of the proposed change is enclosed in Attachment 2.

l This request has been reviewed and approved by the Station Nuclear Safety and Operating Committee and System Nuclear Safety and -Operating Committee. This request was reviewed and approved while the System Nuclear Safety and

Operating Committee was still in existence. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.

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vasoix 4 Es.ECTRIC AND POWER COMPANY TO We have evaluated this . request in accordance with the criteria in 10 CFR 170.22. Since this request involves a safety issue which the staff should be abic to determine does not pose a significant hazard consideration for Unit 2, a Class III license amendment fee is required for Unit 2. Accordingly, a voucher check in the amount of $4000.00 is enclosed in payment of the required fees.

Very truly yours, o

L.S wk R.11. Leasburg Attachments

1. Proposed Technical Specification Change
2. Discussion of Proposed Technical Specification Change
3. Voucher Check No. 21005 for $4000.00 cc: Mr. James P. O'Reilly Regional Administrator Region II

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J The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart, who is Manager-Nuclear Operations and Maintenance, 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.

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Acknowledged before me this -13.cclday of M _, 19 9A .

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