ML18153C360
| ML18153C360 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/14/1990 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML18153C361 | List: |
| References | |
| 90-571, NUDOCS 9009240105 | |
| Download: ML18153C360 (3) | |
Text
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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 September 14, 1990 United States Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 2 TECHNICAL SPECIFICATION CHANGE REQUEST APPENDIX J EXEMPTION Serial No.
NO/ETS Docket No.
License No.90-571 R2 50-281 DPR-37 In accordance with 1 O CFR 50.90, we are requesting a license amendment in the form of a change to the Technical Specifications for Operating License DPR-37 Surry Unit
- 2. Section 111.D.3 of Appendix J requires Local Leak Rate Testing (LLRT) during every reactor shutdown for refueling but in no case at intervals greater than two years. Surry Unit 2 was shutdown for refueling on September 10, 1988 and remained in the refueling outage for 374 days to perform maintenance and modifications. Because of this extended outage the Type C testing requirements of 1 O CFR 50 Appendix J will be due for performance prior to the scheduled refueling date (April 5, 1991 ). This is based on an interpretation that the interval requirement is applied individually to each applicable valve. On September 14, 1990, Virginia Electric And Power Company requested a one-time exemption from 1 O CFR 50 Appendix J to perform the LLRT testing during the scheduled Cycle 1 O refueling outage. This Technical Specification change request provides for a footnote in the surveillance requirements to document this exemption.
The technical basis and justification for the our September 14, 1990 exemption request (Serial No. 90_-~570) are applicable for this Technical Specification change.
If Unit 2 were forced to go to cold shutdown and establish atmospheric conditions prior to the scheduled refueling outage, it is our intention to initiate Type C testing of the affected containment isolation valves.
Testing would be performed at a rate of approximately five penetrations per day while the Unit remained in cold shutdown with atmospheric containment conditions.
9009240105 900914 PDR ADOCK 05000281 P
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e This Technical Specification change has been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed change does not involve an unreviewed safety question as defined in 1 O CFR 50.59 or a significant hazards consideration as defined in 10 CFR 50.92. The basis for our no significant hazards consideration determination is included in Attachment 2.
Very truly yours,
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W. L. Stewart Senior Vice President - Nuclear Attachments
- 1.
Technical Specification Change - Appendix J Exemption
- 2.
Significant Hazards Consideration Evaluation 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
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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 his knowledge and belief.
Acknowledged before me this
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