ML20084U766
| ML20084U766 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/16/1991 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20084U769 | List: |
| References | |
| 91-164, NUDOCS 9104220287 | |
| Download: ML20084U766 (3) | |
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VinatNIA F.Li:cTuic Ann Pown:n Co nwxy Ricunoxu.Vnunxir ununi April 16, 1991 l
U.S. Nuclear Regulatory Commission Serial No.:
91 164 Attention: Document Control Desk NL&P/RMN Washington, D.C. 20555 Docket Nos.: 50 338 50 339 License Nos.: NPF-4 NPF 7 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS.1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES ELECTRICAL POWER SYSTEMS SHUTDOWN Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Operating License Numbers NPF 4 and NPF 7 for North Anna Power Station Units 1 and 2, respectively.
The proposed changes to the North Anna Units 1 and 2 Technical Specifications concern electrical power systems during shutdown. The applicability sections of these specifications are being expanded to include handling spent fuel or any loads over spent fuel when the reactor is defueled. The specifications are being clarified and
-made consistent with Standard Technical Specifications. The changes also delete the requirement to establish containment integrity if a required bus is lost. We have determined that this requirement is not necessary and can divert operator attention from more critical bus restorat!on activities.
This proposed change-is consistent with our MERITS submittal, therefore a MERITS change is not attached. The proposed changes are provided in Attachments 1 and 2.
A discussion of the proposed changes with the technical justification and safety evaluation of the proposed changes is provided in Attachment 3.
This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Management Safety Review Committee. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our determination that no significant hazards consideration is involved is presented in.
9104220287 910416 g0 PDR ADOCK 05o00338 P_
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Because of the unusually large number of procedures involved, please allow us 60 days to implement these changes from the date of issuance. Should you have any questions or require additional information, please contact us at your earlier
- convenience.
Very truly yours, k
) T W. L. Stewart Senior Vice President - Nuclear Attachments 1.
Proposed Technical Specification Change for Nonh Anna Unit 1 2.
Proposed Technical Specification Change for North Anna Unit 2 3.
Discussion of Proposed Changes 4.
10 CFR 50.92 Evaluation cc:
U.S. Nuclear Regulatory Commission Region 11 101 Marietta Street N.W.
Suite 2900 Atlanta, GA 30323 Mr. M. S. Lesser NRC Senior Resident inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia. 23219 i
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COMMONWEALTH OF VIRGINIA )
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COUtCYOFHENRICO
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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 - Nuclear, 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 I
his knowledge and belief.
Acknowledged before me this /67 ay of AI/
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d My Commission Expires:
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S.W Notary P blic (SEAL)
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