ML18153C564
| ML18153C564 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/08/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 88-790C, NUDOCS 9103140138 | |
| Download: ML18153C564 (2) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 8, 1991 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 REQUEST FOR ADDITIONAL INFORMATION SERVICE WATER SYSTEM DESIGN Serial No.
NURPC Docket Nos.
License Nos.
88-790C R2 50-280 50-281 DPR-32 DPR-37 By letter, Serial No. 88-790B, dated May 5, 1989, Virginia Electric an.d Power Company submitted a summary report of an analysis which demonstrated that, in the event of a hurricane and the associated loss of offsite power to both units, sufficient service water flow is available for equipment necessary to ensure a safe hot shutdown.
Included in that report were the analytical results and necessary actions with times to achieve and maintain cold shutdown in the event of a hurricane. That report also addressed a concern identified during the Safety System Functional Inspection with regard to the ability of the Service Water (SW) system to perform its safety function during a hurricane as required by 1 O CFR 50, General Design Criterion (GDC) 2.
On July 12, 1989, a meeting was held between our staffs to discuss the summary report. During the meeting, it was specifically requested that we verify that there would be no adverse impact in isolating component cooling water to the Containment Air Recirculation Coolers in terms of an increase in containment temperature and subsequent ability to maintain the reactor at hot shutdown.
Further analysis has been performed to evaluate the ability of the SW System to perform its safety function during a hurricane as required by GDC 2. This analysis encompassed the specific concern addressed above and determined that the SW system is capable of performing its safety function with appropriate operator actions.
Abnormal Procedure, AP-37.01, "Abnormal Environmental Conditions" provides the appropriate guidance and actions to ensure a safe hot shutdown as well as to achieve and maintain cold shutdown in the event of a hurricane. As a result of the additional
. evaluation performed, AP-37.01 was determined to require further revision. AP-37.01 will be replaced by an upgraded procedure, O-AP-37.01, which addresses the containment cooling issues resulting from the GDC 2 analysis.
The upgraded procedure has completed the technical review process, is currently being validated via walk-down and will be formally issued by April 1, 1991.
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'*t,i The specific concern identified during the July 12, 1989, meeting has been addressed.
Upon issuance of 0-AP-37.01, no further actions will be required on this subject.
Should you have any questions concerning this response, please contact us.
Very truly yours,
~\\_~
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. W. E. Holland NRC Senior Resident Inspector Surry Power Station