ML20197H365

Informs of Completion of Commitment to Test Contromatics Butterfly Valves in Response to Violations Noted in Insp Repts 50-338/97-01 & 50-339/97-01.Subject Insp Repts Documented close-out of GL 89-10

ML20197H365
Person / Time
Site:	North Anna
Issue date:	12/22/1997
From:	Saunders R VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
50-338-97-01, 50-338-97-1, 50-339-97-01, 50-339-97-1, 97-105A, GL-89-10, NUDOCS 9712310261
Download: ML20197H365 (2)

Text

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. . . . . o VimmNI A Ei.i:CTHIC ANI) P(MTR CohWANY RieschinN , h(4NI A 23261

. Lecember 22, 1997 United States Nuclear Regulatory Commission Serial No. 97105A Attention: Document Control Desk NAPS /JHUETS Washington, D. C. 20555 Docket Nos. 50-338 50-359 License Nos. NPF-4 NPF 7 4

Gentlemen:

YJRGINIA ELECTRIC AND POWER COMPANY NORTH ANNALEQWER STATION UNIT NOS.1 AND 2 SAFETY RFILATED MOTOR-OPERATED VALVE!

IESTING AND_SMByJ,lLLANCE - GENERIC LETTER 89-10 NRC Inspection Report 50 338,339/97-01, dated March 21, 1997, documented the close-out of NRC Generic Letter 8910, Safety Related Motor Operated Valve Testing and Surveillance. The inspection Report also documented that the reliability of the methods used in determining the torque requirements for butterfly valves were not previously demonstrated. This was identified as a weakness and is being tracked as inspection Follow up Item 50 338,339/9700104.

Virginia Electric and Power Company letter dated February 20,1997 (Serial No.97-105) committed to validate the design basis calculational methodology for motor-operated butterfly valves by a combination of testing and/or performing the EPRI Performance Prediction Model. Specifically, the following commitments were made:

1) Perform instrumented differential pressure testing on one 18-inch Contromatics ,

valve and one 24 inch Contromatics valve during the 1997 Unit 1 refueling outage

2) Apply the EPRI Performance Prediction Model on four mpresentative Allis ,

~

Chalmers valves by the end of 1997 or perfom) instrumenteo differential pressure testing of the valves by the end of the Spring 1998 Unit 2 refueling outage

3) Provide the results of testing on the two Contromatics valves in validating the calculational methodology and the status of applying the EPRI Performance 7 Prediction Model on the four Allis-Chalmers valves or the need to perform instrumented differential pressure testing by December 31,1997.  !

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A .A _ ,~_.-e:. __. _ _ - . --,-._.:___.2- ._m - _ _ -- , ,AJms.- .,,i._.#-. .. m-- _-...a_.a,A ,.:.-+,. ._.a.>_ -.i -___ &-_r..-_.+ ----a.- ----Ls .--m-This letter is to inform you that instrumented differential pressure testing was completed gn one 18 inch Contromatics valve and one 24 inch Contromatics valve by the end of  ;

the 1997 Unit 1 refueling outage. The quantitative assessment of the instrumented l' dynamic differential pressure tests for Contromatics motor operated butterfly valves 1-SW MOV 121A and 1 SW MOV 123A demonstrates the adequacy of the installed equipment. Also, Contromatics torque predictions covered a span of differential  :

pressures to adequately envelope the in situ conditions which confirms the design basis calculational methodology. This completes-our commitment to test Contromatics ,

butterfly valves. '

In addition, a review was pedormed to determine whether the EPRI Performance Prediction Model can be applied to validate our design basis calculational methodology for four representative Allis Chalmers valves. Instead of pursuing the analytical ,

approach of emp'oying the EPRI Performance Prediction Model, we plan to perform ,

instrumented differential pressure testing of the valves by the end of the Spring 1998 Unit 2 refueling outage, if you have any questions or require additionalinformation, please contact us.

Very truly yours, Robert F. Saunders Vice President - Nuclear Engineering and Services Commitments made in this letter:

1. Perform instrumented differential pressure testing of the Allis Chalmers valves by the end of the Spring 1998 Unit 2 refueling outage. i cc: U. S. Nuclear Regulatory Commission Region ll j 61 Forsyth Street, S. W.

Suite 23T85 Atlanta, Georgia 30303 ,

Mr. M. J. Morgan NRC Senior Resident inspector North Anna Power Station r

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