ML18141A078

Forwards Suppl to 830805 Proposed Tech Spec Change Re Administrative Extension to Visual Insp Period for Inaccessible Snubbers.Suppl Revises Previous Disscusion of Proposed Change

ML18141A078
Person / Time
Site:	Surry
Issue date:	08/09/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, Varga S Office of Nuclear Reactor Regulation
References
439A, NUDOCS 8308150234
Download: ML18141A078 (3)

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VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART VICE PRES'.rDENT NUCLEAR OPERATIONS August 9,1983 Mr. Harold R. Denton, Director Serial No. 439A Office of Nuclear Reactor Regulation NO/WDC:acm Attn: Mr. Steven A. Varga, Chief Docket No. 50-280 Operating Reactors Branch No. 1 License No. DPR-32 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Gentlemen:

AMENDMENT TO OPERATING LICENSE DPR-32 SURRY POWER STATION UNIT NO. 1 SUPPLEMENT TO PROPOSED TECHNICAL SPECIFICATION CHANGE In our letter dated August 5, 1983 (Serial No. 439), the Virginia Electric and Power Company requested an amendment, in the form of changes to the Technical Specifications, to Operating License DPR-32 for the Surry Power Station Unit No. 1. The proposed change pertains to an administrative extension to the visual inspection period for inaccessible snubbers in Unit 1. Attached is a supplement to revise Attachment 2, the Discussion of the Proposed Change, of the amendment referenced above.

This supplement has been reviewed and approved by the Surry Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control Staff.

It has been determined that this supplement does not pose a significant safety hazards consideration as defined in 10 CFR 50. 92 or an unreviewed safety question as defined in 10 CFR 50.59.

Very truly~)};rs/_

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W. L. Stewart

Attachment:

cc: Mr. James P. O'Reilly Regional Administrator Region II Mr. D. J. Burke NRC Resident Inspector Surry Power Station Mr. J, Don Neighbors NRC Project Manager -Surry Operating Reactors Branch No.I Division of Licensing flo*I

(~8308150234 830809 - -

Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219 PDR ADOCK 05000280

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• e e COMMONWEALTH OF VIRGINIA)

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CITY OF RICHMOND )

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by W. L. Stewart who is Vice President -

Nuclear Operations, of the 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.

-t;L, Acknowledged before me this '1 day of ~ , 19 ~3 My Commission expires: _ _ _4_.:.__-_.2._b__ , 19 'as Notary Public (SEAL)

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... e e DISCUSSION OF PROPOSED TECHNICAL SPECIFICATION CHANGE This proposed Technical Specification change revises Specification 4.17.A for an administrative extension of the visual inspection period for inaccessible snubbers in Unit 1. The Unit 1 snubber visual inspection period is currently required to be completed on August 31, 1983. A 21 day*extension will allow continued operation of Surry Unit 1 until Surry Unit 2 returns to power following an extended refueling outage.

Due to unanticipated additional large bore snubber overhaul and testing at an offsite facility, as well as extensive turbine bearing work, the Surry Unit 2 refueling outage has slipped past the original scheduled completion date. An extension of 21 days to September 21, 1983 for the Unit 1 snubber visual inspection period is necessary to prevent a dual unit outage during a peak load period.

The first inspection after Surry Unit 1 entered a refueling outage in February, 1983 revealed five inoperable snubbers. All inoperable snubbers were repaired or replaced as necessary during the outage. The inspection performed on June 15, 1983 just prior to startup revealed no inoperable snubbers. As a result of these inspection findings the present visual inspection interval is 62 days+/- 25%. Although this proposed change involves a relaxation in the limiting condition for operation, it is -not likely to involve- a significant hazards consideration because an -administrative extension of 21 days will not have significant impact on the ability of the inaccessible snubbers to respond and perform satisfactorily during a seismic event or under accident conditions.