ML18153C276

Application for Amends to Licenses DPR-32 & DPR-37, Requesting That Setpoint Tolerance of Tech Spec 3.1.A.3.c Remain as Modified in Amend 135 for Next Cycle of Operation

ML18153C276
Person / Time
Site:	Surry
Issue date:	06/25/1990
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153C277	List: ML18153C276 ML18153C278
References
90-283, NUDOCS 9007050034
Download: ML18153C276 (3)

Text

e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 June 25, 1990 United States Nuclear Regulatory Commission Serial No.90-283

• . Attenti.on: Document Contrql Desk NO/ETS Washington, D. C. 20555 Docket Nos. 50-280 50-281 License Nos. DPR-=-32 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 PRESSURIZER SAFETY VALVE SETPOINT TECHNICAL SPECIFICATION CHANGE REQUEST Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of a change to the Technical Specifications, to Operating Licenses No. DPR-32 and DPR-37 for Surry Power Station Units 1 and 2, respectively.

We are requesting that the setpoint tolerance of Technical Specification 3.1.A.3.c remain as modified in Amendment 135, dated November 16, 1989, for the next cycle of operation (Cycle 11) for both units. The expanded tolerance,-1 %,+5%, will ensure that RCS pressure will remain within the design envelope during transient/accident conditions. The requested Technical Specification change is provided in Attachment 1.

Since a generic resolution to this issue has not yet been determined by industry or the NRG, we have no basis for modifying the safety valves or the loop seals at this time.

After a generic resolution is developed, we will modify our valve testing or operations and request the appropriate Technical Specification change.

Although no additional measures are necessary, based on the safety analysis performed with the setpoint tolerance proposed, compensatory measures will be taken to provide added assurance that primary pressure can not exceed 2750 psig (110% of system design). These measures, which will apply to each unit, are the same measures that are currently being taken in support of the existing interim specification.

They include the continued operability of at least one of the two Power Operated Relief Valves (PORV) and the anticipatory reactor trip on turbine trip circuitry. With these measures in place, any analyzed UFSAR transient would result in peak pressure remaining below 2750 psig, even if the setpoints were to shift to a value higher than the +5% proposed limit.

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e In addition, we will continue to work with the NRC, industry and Owners groups to determine a satisfactory resolution to this potential generic issue in order to support the end of Cycle 11 application of this proposed Technical Specification change.

These requests have been reviewed and approved by the Station Nuclear Safety and Operating Committee. It has been determined that the proposed Technical Specification change does not involve an unreviewed safety question as defined in 10 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 .

Should you have any additional questions, please call.

Very truly yours,

\)00 W. L. Stewart Senior Vice President - Nuclear Attachments

1. Proposed Technical Specification Change

2. Discussion of Proposed Change and Significant Hazards Consideration 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

e COMMONWEALTH OF VIRGINIA )

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COUNTY OF HENRICO )

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 Z5 day of -~~IJ....,/k"""-1-,.___-

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