ML20235M801
| ML20235M801 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 02/23/1989 |
| From: | Cartwright W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20235M802 | List: |
| References | |
| 88-740, NUDOCS 8902280431 | |
| Download: ML20235M801 (3) | |
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VIROINIA }3LECTRIC AND POWEll COMi%NY RicurMoxn, VIRGINIA 2!.3 2(il j
W. II. CA NTWRIGHT Vaca Pasmansnr x== * =
February 23, 1989 United States Nuclear Regulatory Commission Serial No.88-740 Attention: Document Control Desk N0/WDC:jmj Washington, D.C.
20555 Docket Nos.
50-338 50-339 License Nos. NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY HORTH ANNA POWER STATION UNITS 1 AND 2 CONTAINMENT ISOLATION VALVES Pursuant to 10 CFR 50.90, Virginia Electric and Power Company requests an amendment, in the form of a change to the Technical Specifications, to Operating Licenses NPF-4 and NPF-7 for North Anna Units 1 and 2: respectively.
We. request the proposed amendment be approved for implementation during the next refueling outages which are currently scheduled to begin in February 1989 for Unit 2 and April 1989 for Unit 1.
The proposed amendment revises Section 3/4.6 Table 3.6-1, Containment Isolation Valves for Units 1 and 2, to identify additional valves exempt from the Type C test, to identify valves that are associated with water-filled penetrations for which a Type C test penalty will not be added to the Type A test results, to add containment isolation valves not previously listed, and j
to delete a valve incorrectly listed in the Table for Unit 1.
The proposed Technical Specification changes for Units 1 and 2 (Attachments 1 and 2), a discussion of the proposed changes (Attachment 3), and an evaluation summary (Attachment 4) are included.
In cddition, a set of reference drawings has been sent to the NRC Project Manager under separate cover to facilitate your review of this submittal.
This Technical Specification change request has been r3 viewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.
It has been determined that the request does not involve an unreviewed safety question as defined in 10 CFR 50.59 and does not involve a significant hazards consideration as defined in 10 CFR 50.92.
Very truly our,ll W. R. Cartwrig t Attachments sl 8002280431 890223 gfl PDR ADOCK 05000330 ;
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U..S. Nuclear. Regulatory Comission
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. Mr. J. L. ' Caldwell.
i NRC' Senior-Resident Inspector.
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' COMMONWEALTH OF VIRGINIA )
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. COUNTY OF HENRICO
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The foregoing document-was acknowledged before me, in and for the County. and Commonwealth aforesaid, today by W. R. Cartwright~ who is-Vice President Nuclear,.of' VirginiaE 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 cf his. knowledge and belief.
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Acknowledged before me this f2-7 day of.
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