ML18153A559

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Submits Required Notification for Unit 1 Re GL 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance
ML18153A559
Person / Time
Site: Surry Dominion icon.png
Issue date: 12/18/1995
From: Ohanlon J
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
95-607, GL-89-10, NUDOCS 9512220250
Download: ML18153A559 (3)


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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 December 18, 1995 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

. Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 Serial No.95-607 NURPC Docket Nos. 50-280 License Nos. DPR-32 SAFETY-RELATED MOTOR-OPERATED VALVE TESTING AND SURVEILLANCE -

GENERIC LETTER 89-10 On June 28, 1989, the NRC issued Generic Letter 89-10, "Safety-Related Motor-Operated Valve Testing and Surveillance." Virginia Electric and Power Company submitted its initial response to the generic letter on December 26, 1989 (Serial No.89-530) stating that the necessary reviews, analyses, verifications, tests and inspections would be conducted in order to meet the specified schedule. Additional information was provided in letters dated June 29, 1993 and December 3, 1993 (Serial Nos.93-333 and 93-664, respectively) in order to clarify the implementation of our Motor Operated Valve (MOV) Program.

Pursuant to Generic Letter 89-10, Virginia Electric and Power Company provides the required notification concerning Surry Power Station Unit 1.

During the recent refueling outage which ended on October 21, 1995, Surry Power Station Unit 1 completed the actions described in the first paragraph of item i of Generic Letter 89-10.

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NRC Inspection Report Nos. 50-280/94-18 and 50-281/94-18, dated August 25, 1994, identified that information concerning the valve stem coefficient of friction will require further NRC evaluation prior to closure of Generic Letter 89-10.- A study including a test program and data evaluation has been completed. Plant-specific data support and justify the validity of using a 0.15 value for the coefficient of friction.

Should you have additional questions, please contact us.

Very truly yours,

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James P. O'Hanlon Senior Vice President - Nuclear 9512220250 951218 ---~-~----!

PDR ADOCK 05000280 PDR

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U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station

COMMONWEAL TH 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 J. P. O'Hanlon, who is Senior Vice President -

Nuclear, of 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 /f~ay of f4Ce&n6ul, 19 95 My Commission Expires: L/Ji~ 3/

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