ML18153C099
| ML18153C099 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 02/01/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 89-453A, NUDOCS 9002080206 | |
| Download: ML18153C099 (2) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 1, 1990 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No.
NO/ETS Docket Nos.
License Nos.
89-453A 50-280 50-281 DPR-32 DPR-37 WITHDRAWAL OF TECHNICAL SPECIFICATION CHANGE REQUEST REQUEST FOR PRESSURIZER SAFETY VALVES On October 18, 1989, Virginia Electric and Power Company requested amendments, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32
- and DPR-37 for Surry Units No. 1 and 2, respectively.
The proposed Technical Specification change requested an increase in the pressurizer safety valve lift setpoint -
tolerance, to+/- 3% of nominal lift setpoint.
Subsequently, Surry Unit 2 was shutdown on October 23, 1898, due to a leaking Code safety valve. Because of the generic safety valve test methodology issue identified by Westinghouse, we chose to have our safety valves tested at that time. This testing confirmed that our valves were affected by the setpoint shift phenomena. Therefore, on November 10, 1989, we proposed an emergency Technical Specification change to provide modified safety valve tolerances (-1 % and +5%) for the remainder of Cycle 1 O
-operation for both units. This change was granted on November 16, 1989.
l Because of the Emergency Technical Specification change (-1 % and +5%), we are withdrawing the October 18, 1989, Technical Specification change request for increase in the pressurizer safety valve set point tolerance to +/-3%. When the generic safety valve setpoint tolerance and testing issues are resolved by the industry, we will submit an appropriate Technical Specification change request.
If you have any questions, please call.
Very truly yours, JL>J-
- w. L. Stewart Senior Vice President - Power
---.9.002080206. 90020 :l. -
PDR ADOCK 05000280 P
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cc:
U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Suite 2900 Atlanta, Georgia 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219