ML20084Q944
| ML20084Q944 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/01/1995 |
| From: | Bowling M VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 87-184A, GL-87-06, GL-87-6, NUDOCS 9506090131 | |
| Download: ML20084Q944 (4) | |
Text
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VIHOINIA ELecTh1C AND POWEH COMI%NY Rics Monn,VIROINIA 202 61 June 1, 1995 United States Nuclear Regulatory Commission Serial No.
87-184A Attention: Document Control Desk NL&P/EJW Washington, D.C. 20555 Docket No.
50-338 License No.
NPF-4 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT 1 SUPPLEMENTAL RESPONSE TO GENERIC LETTER 87-06 PERIODIC VERIFICATION OF LEAK TIGHT INTEGRITY OF l
P_BESSURE ISOLATION VALVES Generic Letter 87-06, " Periodic Verification of Leak Tight integrity of Pressure Isolation Valves," dated March 13,1987 requested a list of all pressure isolation valves for the Reactor Coolant Pressure Boundary (RCPB) and a description of the periodic tests or other measures performed to assure the integrity of the valves as an independent barrier at the RCPB along with the acceptance criteria for leakage, operational limits, and frequency of test performance. The requested information was provided by letter (VEPCO Serial No.87-184) dated June 12,1987. However, a subsequent review of the North Anna Unit 1 Technical Specifications and Inservice Testing (IST) Program and Plans has revealed that the information on our June 12,1987, letter related to testing the Unit 1 Accumulator Discharge Check Valves needs to be corrected.
Previously, it was indicated that a periodic leak test was performed on the Unit 1 Accumulator Discharge Check Valves. However, a periodic leak test is not performed on these valves. Instead, the integrity of the RCPB is tested in accordance with the Technical Specifications, the IST Program, and the Inservice Inspection Program.
The corrected information is provided in Attachment 1, " Pressure Isolation Valve List and Testing Criteria for North Anna Unit 1." If you have any questions, please contact us.
Very truly yours, hk M. L. Bowling, Manager Nuclear Licensing and Programs l
Attachment 1.
Pressure isolation Valve List and Testing Criteria for North Anna Unit 1 y
'Di 3
9506090131 950601 PDR ADOCK 05000338 I
P PDR
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cc:
U. S. Nuclear Regulatory Commission Region il 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. R. D. McWhorter NRC Senior Resident inspector North Anna Power Station i
i I
Pressure Isolation Valve List i
and Testing Criteria for North Anna Unit 1 l
l
NORTH ANNA UNIT 1 Valve Number Description Test Type Test Freq. Accept. Criteria 1 -SI-195 Lo Head Si to Leak Test
- C9 Leak Rate 51 GPM l-SI-197 Cold Legs IAW T.S.
or 1 -SI-199 4.4.6.2.2 Note 1 1-SI-83 Si to Cold Legs Leak Test
- C9 Leak Rate 51 GPM l-SI-86 (Low and High IAW T.S.
or 1-SI-89 Heads) 4.4.6.2.2 Note 1 MOV-1867C BIT Outlet to Type "C"
- R24 Leak Rate 50.92 MOV-1867D Cold Legs Leak Test SCFH @ 45 psig l
(Note 3)
MOV-1836 Alt Charging Type "C"
- R24 Leak Rate 50.92 To Cold Legs Leak Test SCFli @ 45 psig l
(Note 3)
MOV-1890C Lo llead Si to Type "C"
- R24 Leak Rate $1.8 MOV-1890D Cold Legs Leak Test SCFH @ 45 psig l
(Note 3) 1-SI-185 lii head Si to Type "C"
- R24 Leak Rate <0.92 1-SI-79 Cold and Hot Leak Test SCFH C 45 psig l
l-SI-201 legs 1 -SI-90 1-SI-206 Lo liead Si to Type "C"
- R24 Leak Rate 51.8 l-SI-207 Hot Legs Leak Test SCFH @ 45 psig MOV-1869A Ili llead Si to Type "C"
- R24 Leak Rate 50.92 MOV-1869B Hot Legs Leak Test SCFH @ 45 psig l
MOV-1890A Lo llead Si to Type "C"
- R24 Leak Rate 51.8 MOV-1890B Hot Legs Leak Test SCFH @ 45 psig 1
1-SI 125 Accumulator None Note 2 1
1-SI-127 Discharge 1 -SI-142 Check Valves 1-SI-144 1-SI-159 l-SI-161 MOV-1700 RilR Supply None Note 2 MOV-1701 Isolation MOV-1720A RHR Return None Note 2 MOV-1720B lsolation
- C9-Each Cold Shutdown but not more often than every 9 months.
- R24 - Each Refueling Outage and at least every 24 months.
Note 1 -
>l GPM but 55 GPM if the latest measured leak rate has not exceeded the previous leak rate by an amount that reduces the margin between the previous measured rate and the max. permissible value (5 GPM) by 507c.
Note 2 - The integrity of the primary coolant pressure boundary is periodically tested in accordance with Technical Specifications and ASME Section XI hydrostatic test requirements. This testing verifies the integrity of the boundary with the interfacing systems but not the integrity of the individual valves which form the boundary.
Note 3 -
1-S!-83. 86 and 89 are tested as PlVs in lieu of these motor operated valves.