ML18153C155
| ML18153C155 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/20/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-828A, NUDOCS 9003270385 | |
| Download: ML18153C155 (3) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 20, 1990 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.
89-828A NO/ETS Docket Nos.
50-280 License Nos.
DPR-32 CLARIFICATION TO TYPE C TESTING EXEMPTION REQUEST On January 8, 1990, Virginia Electric and Power Company requested an exemption from 10 CFR 50, Appendix J, Type C testing requirements. This exemption, coupled with one-time Technical Specification changes for snubber and check valve testing, will avoid a shutdown of Surry Unit 1 prior to its scheduled refueling outage solely to perform routine testing. In a telephone conference call with Mr. B. C. Buckley and other members of the NRC staff, several items of clarification were provided regarding the Type C testing exemption request. provides formal documentation of the clarification provided during the above mentioned telephone conversation. Should you have any further questions please contact us.
Very truly yours, JL~
W. L. Stewart Senior Vice President - Nuclear Attachment cc:
U. S. Nuclear Regulatory Commission Region II
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101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station 17'()():327(>3::::!=.
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ATTACHMENT 1 SURRY POWER STATION UNIT 1 10 CFR 50 APPENDIX J TYPE C TESTING EXEMPTION REQUEST CLARIFICATIONS
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e CLARIFICATIONS OF TYPE C TEST EXEMPTION REQUEST
- 1. Give the approximate date when the local leak rate tests (Type C) will be performed after reaching the refueling outage.
The Unit 1 refueling outage is currently scheduled to commence October 19, 1990 and the 'as-found' Local Leak Rate Testing (LLRTs) could be completed in approximately 3 weeks from that date, barring any unforeseen scheduling difficulties. However, due to the uncertainties associated with the start of a refueling we are requesting an exemption until December 31, 1990 to complete the LLRTs.
- 2. Give the duration (how many weeks or days) the test interval will be extended.
The test interval would be extended approximately 27 weeks if December 31, 1990, is used for the exemption. This date would not exceed two years of power operation on any of the penetrations.
- 3. Give the number of valves and penetrations to be exempted from the 24 month requirement. Are there any valves that can be tested at power or during shutdown before the scheduled Cycled 1 O refueling outage?
There are a total of 122 containment isolation valves and 63 penetrations.
LLRTs have been performed on 47 valves associated with 31 penetrations. 19 penetrations have been totally completed.
Therefore, 75 valves and 44 penetrations remain to be tested and are included in the exemption request.
Those valves associated with safety systems and safe operation of the plant cannot be tested without rendering the system or train inoperable for a period greater than Technical Specifications would permit. Auxiliary systems (i.e.,
sampling, leakage monitoring, steam generator recirculation and transfer vent and drain, service air, fire protection, and reactor cavity purification systems )
could be tested. However, unless containment entries were made only the outside valves could be tested and only limited venting and draining of the penetrations could be accomplished.
If the Unit were forced to cold shutdown prior to the scheduled refueling outage, an average of 5 penetrations (approximately 1 O valves) could be tested each day. This number is approximate and depends on the circumstances of the forced shutdown and existing plant conditions.
- 4. Provide the results of the last two LLRTs for each valve/penetration. Were the test completed on schedule and satisfactorily? Include the valve repair information for valves due to excessive leakage.
The last two Type A test reports include the LLRT results. Included in the Type Test A reports are a summary of the test results and the maintenance performed based on leakage.. The 1986 and 1988 Type A Test reports were submitted to the NRC on October 29, 1986 and November 23, 1988, respectively.