ML18153B960
| ML18153B960 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 10/30/1989 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153B961 | List: |
| References | |
| 89-411, NUDOCS 8911070394 | |
| Download: ML18153B960 (4) | |
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 October 30, 1989 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.
CLARIFICATION OF PROPOSED TECHNICAL SPECIFICATION AUXILIARY FEEDWATER CROSS-CONNECT 89-411 50-280 50-281 DPR-32 DPR-37 On October 11, 1988 (Letter No.88-455), Virginia Electric and Power Company
. requested amendments in the form of changes to the Technical Specifications, to Facility Operating licenses DPR-32 and DPR-37 for Surry Power Station Units 1 and 2 respectively.
That change defined the operability requirements for the Auxiliary Feedwater System and the power sources of the shutdown unit.
Based on discussions with your staff, we are providing clarification of the operability requirements for the offsite and emergency power sources for a shutdown unit. provides the Technical Specification change request. This Technical Specification change request supercedes our October 11, 1988 request in its entirety.
Two additional changes have been included in this request: 1) the bases of Section 3.16 has been corrected to include the Auxillary Feedwater Pump in the list of Engineered Safeguards Equipment powered by the emergency diesel generators; and, 2) in Section 3.6-G, the protected condensate storage tank associated with the opposite unit has been provided with an allowed outage time consistent with the specification for the AFW cross-connect piping. Attachment 2 provides a discussion of the revised Technical Specification impact on the original Probability Risk Assessment.
This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff. It has been determined that the supplemental changes do not create an unreviewed safety question as defined in 1 O CFR 50.59, nor involve a significant hazards consideration as defined in 1 O CFR 50.92. Also, these changes do not have any significant impact on the original safety evaluation and significant hazards evaluation
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If you have any further questions, please contact us.
Very truly yours,
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W.L~te~~
Senior Vice President - Power Attachments
- 1. Technical Specification Change Request
- 2. Discussion of Risk Impact for revised Technical Specification 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
COMMONWEAL TH OF VIRGINIA )
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COUNlY OF HENRICO
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The foregoing document was acknowledged before me, in and for the County and Commonwealth aforesaid, today by W. L. Stewart who is Senior Vice President - Power, of Virginia Electric and Power Company.
He is duly authorized to execute and file the foregoing document in behalf of that Company, and the statements in the document are true to the best of his knowledge and belief.
Acknowledged before me this 30 day of rfi!g~, 1911..
My Commission Expires: ~./J/ur!J~ d5, 19'9.tl.
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Notary Public (SEAL)
ATTACHMENT 1 AUXILIARY FEEDWATER TECHNICAL SPECIFICATION CHANGE REQUEST