ML18152B763

Withdraws Relief Request SR-014,which Was Approved by NRC in SER Dtd 960830.Similar Relief Request in Place for Unit 2

ML18152B763
Person / Time
Site:	Surry
Issue date:	07/06/1998
From:	Hartz L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
98-371, NUDOCS 9807140125
Download: ML18152B763 (2)

Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 July 6, 1998 U.S. Nuclear Regulatory Commission Serial No.: 98-371 Attention: Document Control Desk ISI/JCP/GDM: RO Washington, D.C. 20555 Docket No.: 50-280 License No.: DPR-32 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT 1 WITHDRAWAL OF RELIEF REQUEST SR-014 Virginia Electric and Power Company submitted a request for relief from certain ASME Section XI Code requirements associated with partial examinations in our letter dated April 23, 1996 (Serial No.96-138). Relief Request SR-014 was included in this submittal and addressed welds 1-01 (terminal end welds) on seal injection piping connected to the reactor coolant pumps on all three Reactor Coolant System loops. The relief was requested because it was believed that the main flange bolts of the associated reactor coolant pump (RCP) had to be removed to make these welds accessible for performing surface examinations.

However, Surry Unit 1 was recently removed from service to repair a leak on the seal injection line connected to the "C" RCP. During the evaluation and repair of the leak, it was discovered that, although very difficult, these welds could be accessed for performing surface examinations. Therefore, Relief Request SR-014, which was approved by the NRG in their Safety Evaluation Report dated August 30, 1996, is not required and is being withdrawn.

A similar relief request is in place for Surry Unit 2. It has not yet been determined if these welds can also be examined. Therefore, the welds will be reevaluated during upcoming refueling outages, and, if it is determined that the welds can be examined without disassembly of the reactor coolant pump main flange bolting, the Surry Unit 2 relief request will also be withdrawn.

If you have any questions or require additional information, please contact us.

Very truly yours, CXY!~

L.N.Hartz r Vice President - Nuclear Engineering and Services

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cc: U.S. Nuclear Regulatory Commission Region II Atlanta Federal Center 61 Forsyth St. SW, Suite 23T85 Atlanta, Georgia 30303 Mr. RA Musser NRG Senior Resident Inspector Surry Power Station Commitment Summary

1. The Surry Unit 2 terminal end welds on the seal injection piping connected to the reactor coolant pumps on all three Reactor Coolant System loops will be reevaluated during upcoming refueling outages. If it is determined that the welds can be examined without disassembly of the reactor coolant pump main flange bolting, the applicable Surry Unit 2 relief request will also be withdrawn.