ML18153D382
| ML18153D382 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 07/08/1993 |
| From: | STEWART W L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 93-205, GL-88-14, NUDOCS 9307150047 | |
| Download: ML18153D382 (2) | |
Text
/ L e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 8, 1993 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 SUPPLEMENTAL RESPONSE TO GENERIC LETTER 88-14 INSTRUMENT AIR SUPPL V PROBLEMS AFFECTING SAFETY-RELATED SYSTEMS Serial No. NO/ETS Docket Nos. License Nos.93-205 R2 50-280 50-281 DPR-32 DPR-37 By letter dated March 25, 1993 the staff provided their approval of our actions pursuant to Generic Letter 88-14, Instrument Air Supply System Problems Affecting Related Equipment.
Based on component operability testing and the continued implementation of preventive maintenance activities, exceptions from the requirements of Instrument Society of America (ISA) Standard 7.3, Quality Standards for Instrument Air, 1981 Revision for particulate size and dewpoint were approved.
However, your acceptance of our deviation from ISA 7.3 regarding particulate size in the Containment Instrument Air System was contingent on our notification of the staff if the particulate size increases above 20 microns. We intend to utilize system performance testing and preventive maintenance activities to monitor and maintain air quality within the Containment Instrument Air System. We have established acceptance criteria based on 20 microns for the system. Appropriate corrective actions will be taken if the particulate in the Containment Instrument Air System exceeds the established acceptance criteria.
Deviations, which are currently distributed to the NRC resident inspectors, will be identified by the deviation report process. If the air quality acceptance criteria is not met, the Containment Instrument Air System and air operated component will be evaluated for operability.
If operability of a safety-related component is affected by the Containment Instrument Air System performance, it will also be documented in a station deviation report and reported if appropriate pursuant to 1 O CFR 50.72 or 73. ADOCK-05000280-
- 9307150047 9307oari--u*,, . ' -**
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., Should you have any additional questions or require additional information, please contact us. Very truly yours, RJ J'tzu..d_
6 c,,-w. L. Stewart Senior Vice President
-Nuclear cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station