ML20070H691
| ML20070H691 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 03/08/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 91-133, NUDOCS 9103140381 | |
| Download: ML20070H691 (2) | |
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YlltOINIA F.LIFTillO ANI) POWEli COMI%NY 3
H ie nt >ioxu, V HOINIA DODOl March 8,1991 U.S. Nuclear Regulatory Commission Serial No.
91 133 Attention: Document Control Desk NL&P/JDH:R4 Washington, D.C. 20555 Docket Nos.
50 338 50 339 License Nos. NPF 4 NPF 7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 LICENSE AMENDMENT ON CONTAINMENT ISOLATION VALVES On February.20,1991, the NRC issued License Amendment Nos.143 and 126, for Facility Operating License Nos. NPF-4 and NPF 7, for North Anna Power Station Units 1 and 2.
These amendments revised the specifications regarding containment isolation valves. The changes included the addition of containment isolation valves not previously listed in Table 3.6 An administrative error and an implemontation issue have been identified during our review of the amendments.-
The administrative error was the inadvertent retention of a pound sign (#) on Unit 1 Table 3.61 ' Containment isolation Valves," Section F ltem 46, Valve 1-FP-272, a fire protection system isolation check valve located inside containment. The pound sign Indicates that the valve is not subject to Type C leakage testing. The sign was proposed to be deleted in our February 23,1989 submittal, but apparently was inadvertently retained by the NRC when the page was issued as part of the license' amendments on February 20,1991. It is our intent to include this valve in the Type C test program.
The implementation issue involves this valve and its Unit 2 counterpart, 2 FP-79, listed on the Unit 2 Table 2 61, Section F ltem 47. Valve 2 FP-79 was proposed to be added to the list (without a pound sign) and thus included in the Type C test program.
Type C testing of valve 1 FP-272 has been performed during the Unit i refueling outage. However, Type C testing of valve 2-FP-79 v.as not performed during the recent Unit 2 refueling outage completed on November 2,1990, because the approved licensa smendments had not yet been-Issued when the outage testing activities were p!anr:ed and scheduled. The license amendments were subsequently issued on February 20,1991. Unit 2 is currently operating at full power and Type C testing at this time is impractical.
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9103140381 9103o9 PDR ADOCI: 05000338 r
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4 It is our intent to perform Type C testing on the Unit 2 fire protection check valve discussed above during the next scheduled refueling outage. This fire protection containment penetration also contains two manual isolation valves in series located outside containment. These manual valves are cunantly in the Type C test program and were successfully Type C tested during the 1990 Unit 2 refueling outage.
We request that the NRC issue a correction to Table 3,61 for 1 FP 272 as described above. Because of the scheduling concern associated with Type C testing valve 2 FP-79 prior to issuance of the amendment, we also request that the NRC establish the at endment implementation interval to be with!n the original 30 day period, except for check valve 2 FP 79. This valve will be incorporated into the Type C test program for Unit 2 no later than the next scheduled refuel,ng outage.
If you have any questions or require additionalinformation, please contact us.
Very truly yours,
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W. L. Stewart Senior Vice President - Nuclear cc:
U. S. Nuclear Regulatory Commission Region 11 101 Marietta Street, N.W.
Suite 2900 Atlanta, Georgia 30323 Mr. M. S. Lesser NRC Senior Resident inspecter North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219
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