ML20086S689
| ML20086S689 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 07/26/1995 |
| From: | Ohanlon J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 95-331, GL-89-10, NUDOCS 9508020080 | |
| Download: ML20086S689 (3) | |
Text
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r VIRGINIA ELECTilIC AND Powrit CorOANY Ricnuonn,V norna enen July 26, 1995 United States Nuclear Regulatory Commission Serial No.95-331 Attention: Document Control Desk NL&P/MAE R4 Washington, D.C. 20555 Docket No.
50-338 50-339 License No.
NPF-4 NPF-7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 RESPONSE TO NRC GENERIC LETTER 89-10 SAFETY-RELATED MOV TESTING, AND SURVEILLANCE On June 28,1989, the NRC issued Generic Letter 89-10, entitled " Safety-Related Motor-Operated Valve Testing and Surveillance."
Virginia Electric and Power Company (Virginia Power) responded to the Generic Letteron 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 schedule and recommendations provided in the Generic Letter. Further clarification of our response was provided in letters dated February 15,1993, June 29,1993, December 3,1993, and November 16,1994 (Serial Nos.92-330, 93-333,93-664, and 94-598, l
respectively).
The Generic Letter's recommended actions were completed for North Anna Unit 2 on June 30,1995, consistent with our June 29,1993 commitment. Item m. of the Generic Letter requires NRC notification within 30 days of the completion of the recommended actions. This letter fulfills that requirement for North Anna Unit 2. (Completion of the recommended actions for North Anna Unit 1 was previously documented in our letter dated November 16,1994.)
As stated in our November 16,1994 letter, a study was initiated to resolve comments concerning the valve coefficient of friction (COF) discussed in Inspection Report Nos.
50-338/94-04 and 50-339/94-04, dated May 27,1994. As part of that study, a test program was implemented during the recent Unit 2 refueling outage to measure actual in.eita COF values for a sample of the motor operated valves (MOVs). It was determined during the test program that the measured COF values for some MOVs were not bounded by the value assumed in the Engineering calculations. The results were attributed primarily to the subjective nature of the Station Maintenance Procedures which prescribe stem inspection and lubrication. Corrective action, in the form of cleaning and lubricating the valve stems and stem nuts for the test population verified that a significant reduction of COF values from the measured values was achievable. Seventy-two (72) of eighty-two (82) Unit 2 rising stem MOVs in the Generic Letter 89-10 program were subsequently tested, cleaned and relubricated as required, and verified to be within acceptable limits for the COF. Testing of the 0100US ESA"$8888o!80$he A8di P
r remain'ng ten (10) MOVs was not performed due to configuration problems (i.e., test -
equipment could not be installed without dismantling plant equipment and/or was not available). These ten MOVs were lubricated and verified to be within acceptable thrust limits.
The Unit 1 rising stem MOVs were evaluated with COF values that bounded the actual I
values measured in Unit 2. It was determined that all of the valves would be capable of performing their design basis function even though the valve stems and stem nuts were not relubricated. The relubrication of these valves is considered to be O maintenance function. The Unit 1 valve stems and stem nuts will be relubricated i
and/or the valve COF verified to be acceptable within 30 days from the end of the next refueling outage, which is currently scheduled to begin March 2,1996.
l Should you have additional questions, please contact us.
f Very truly yours, tW f
Jarnes P. O' Hanlon Senior Vice President - Nuclear i
oc:
U.S. Nuclear Regulatory Commission Region ll i-101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 i
Mr. R. D. McWhorter NRC Senior Resident inspector l
North Anna Power Station l
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P t
COMMONWEALTH OF VIRGINIA )
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COUNTY OF HENRICO
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4 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 Rb day of
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