ML18143B451
| ML18143B451 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/10/1985 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Harold Denton, Varga S Office of Nuclear Reactor Regulation |
| References | |
| 85-621, NUDOCS 8509160271 | |
| Download: ML18143B451 (2) | |
Text
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e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS
- September 10, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NO. 1 10 CFR 50 APPENDIX R MODIFICATION SCHEDULE Serial No.85-621 RRC:psj:2004N Docket No. 50-280 License No. DPR-32 The purpose of this letter is to provide information on the status of certain Unit 1 modifications related to 10 CFR 50 Appendix R.
On November 30, 1984 (Serial No. 692), we submitted schedules for completion of various Appendix R items for Surry Unit Nos. 1 and 2.
This submittal included schedules for modifications to be completed during the Fall 1985 maintenance outage.
On August 4, 1985 Unit 1 was inadvertently tripped. Since we were within the window for the required snubber inspection outage, the Fall 1985 maintenance outage was started. This was approximately eight (8) weeks earlier than previously planned.
The modification described below, numbered in accordance with Volume II, Chapter 6 of the Surry Appendix 11 R 11 reanalysis dated November 30, 1984, has been rescheduled as noted.
4KV Pump Motor Control Isolation (Section I, Item #13)
A postulated fire in the Control Room could render the 4KV pumps in the residual heat removal and component cooling water systems inoperable. This modification will provide a transfer switch for each of the affected pumps which will isolate the contrql circuit from the control room.
Due to the advanced maintenance outage, materials were not available to complete this work.
The completion of this design change will take place before the end of the 1986 refueling outage.
B5091b0271 850910 PDR ADOCK 05000280 F _ __,
e Should you have any questions or require additional information, please contact us.
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W. L. Stewart cc: Dr. J. Nelson Grace Regional Administrator NRC Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J. D. Neighbors Operating Reactors Branch No. 1 Division of Licensing Mr. T. Conlon NRC Region II