ML18139A570
| ML18139A570 | |
| Person / Time | |
|---|---|
| Site: | Surry, North Anna  |
| Issue date: | 10/06/1980 |
| From: | Sylvia VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Clark R, Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 809, NUDOCS 8010080436 | |
| Download: ML18139A570 (2) | |
Text
,.
e VIRGINtA ELECTRIC AND PowER Co>>PANY RICHMOND, VIRGIN IA. 23261 October 6, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulations Attention:
Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Denton:
Serial Number 809 Docket Nos. 50-338 50-280 50-281 License Nos. NPF-4 DPR-32 DPR-37 AUXILIARY FEEDWATER SYSTEM REQUIREMENTS NORTH ANNA UNIT 1 AND SURRY UNITS 1 & 2 We have reviewed your letter of September 28, 1979 that requests information concerning auxiliary feedwater system design basis information and pump flow verification. Our response to Enclosure 2 for North Anna Unit 1 is provided in Attachment 1.
The NRC was notified per LER 80-061/0IT-O dated July 17, 1980 that a discrep-ancy had been discovered during a review of the auxiliary feedwater system design.
It was found that we could not verify by calculation the motor driven auxiliary feedwater pump 1-FW-P-3B would be able to deliver the design basis flow of 340 gpm to its steam generator under certain accident conditions.
It was estimated that the pump would deliver a total flow of approximately 355 gpm of which 20 gpm would be recirculated to the emergency condensate storage tank and approximately 335 gpm pwould be delivered to the steam generator.
Vepco proposed as an interim modification that the recirculation from the pump would be isolated to provide an additional flow of approximately 20 gpm to the steam generator until pump tests could be run to verify flow.
Thisti.nterim modification was not done based on an interoffice NRC memorandum to Thomas M.
Novak from Paul S. Check (attached) recommending that the pump protection provided by the recirculation flow be retained until flow tests are conducted.
Testing for this pump is scheduled during the upcoming refueling outage.
You will be notified if we are unable to verify that the pump is able to deliver the design basis flow.
The Surry response to Enclosure 2 of NRC letter dated September 25, 1979 will be submitted by November 1, 1980.
This response has been delayed due to a delay in receiving design basis information from Westinghouse.
8010 08 0 f
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e VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Harold R. Denton, Director Should you have any questions or require additional information, please con-tact us.
LEN/smv: SFl cc:
Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Very truly yours, l!PpC B. R. Sylvia Manager - Nuclear Operations and Maintenance