ML18153A880

Application for Amends to Licenses DPR-32,DPR-37,NPF-4 & NPF-7,modifying Surveillance Frequency of Nozzles in Containment & Recirculation Spray Sys in Accordance W/Gl 93-05, Line-Item TS Improvements to Reduced Srs....

ML18153A880
Person / Time
Site:	Surry, North Anna
Issue date:	02/25/1994
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18153A881	List: ML18153A880 ML18153A882
References
94-033, 94-33, GL-93-05, GL-93-5, NUDOCS 9403110107
Download: ML18153A880 (6)

Text

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e e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 25, 1994 U.S. Nuclear Regulatory Commission Serial No.94-033 Attention: Document Control Desk NL&P/ETS: RO Washington, DC. 20555 Docket Nos. 50-280 50-281 50-338 50-339 License Nos. DPR-32 DPR-37 NPF-4 NPF-7 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 NORTH ANNA POWER STATION UNITS 1 and 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGES CONTAINMENT SPRAY SYSTEMS NOZZLE SURVEILLANCE FREQUENCY Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests amendments, in the form of changes to the Technical Specifications, to Facility Operating License Nos. DPR-32, DPR-37, NPF-4, and NPF-7 for Surry Power Station Units 1 and 2 and North Anna Power Station Units 1 and 2, respectively. The proposed changes will modify the surveillance frequency of the nozzles in the Containment and Recirculation Spray Systems in accordance with Generic Letter 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993.

• Discussions of the proposed Technical Specifications changes for Surry and North Anna are provided in Attachment 1. The proposed Technical Specifications changes are provided in Attachment 2 for North Anna and Attachment 3 for Surry. It has been determined that the proposed Technical Specifications changes do not involve an unreviewed safety question as defined in 10 CFR 50.59 or a significant hazards c consideration as defined in 10 CFR 50.92. The basis for our determination that these changes do not involve a significant hazards consideration is provided in Attachment

4. The proposed Technical Specifications changes have been reviewed and approved by the Stations' Nuclear Safety and Operating Committees and the Management Safety Review Committee.

,AD1)1 I

Should you have ~my questions or require additional information, please contact us.

Very truly yours,

\JL~

W. L. Stewart Senior Vice President - Nuclear Attachments cc: U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, N.W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRG Senior Resident Inspector Surry Power Station Mr. R. D. McWhorter NRG Resident Inspector North Anna Power Station Commissioner Department of Health Room 400 109 Governor Street Richmond, Virginia 23219

e e COMMONWEALTH OF VIRGINIA )

)

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 Jsfltay of , J,,1u,fd//1J , 19 9t/.

My Commission Expires: 1 ll141t 3/ , 1s_p,t'.

fu, ~!!ult Notary Public -

(SEAL)

Attachment 1 Discussion of Changes Surry and North Anna Power Stations

e Discussion of Changes Introduction As documented in Generic Letter (GL) 93-05, "Line-Item Technical Specifications Improvements to Reduce Surveillance Requirements for Testing During Power Operation," dated September 27, 1993, the NRG has completed a comprehensive examination of surveillance requirements in technical specifications that require testing at power. In addition, several changes in surveillance intervals for tests performed during shutdown were recommended. Specifically, GL 93-05 recommended a reduction in nozzle test frequency for stainless steel spray systems. Consistent with GL 93-05, Virginia Electric and Power Company is requesting a change to the surveillance frequency from five years to ten years for the spray nozzles in the Containment Spray and Recirculation Spray Systems at Surry and the Quench Spray and the Recirculation Spray Systems at North Anna. These systems will subsequently be referred to as the "Spray Systems."

Background

NUREG-1366, "Improvements to Technical Specifications Surveillance Requirements,"

dated December 1992, evaluated testing of spray nozzles in pressurized water reactor's Containment Spray Systems with stainless steel piping. The NUREG concluded that the corrosion of stainless steel piping is negligible during the extended surveillance interval, since the Spray Systems are maintained dry and there are no additional mechanisms that could reasonably cause blockage of the Spray Systems' nozzles.

NUREG-1366 concluded that the surveillance interval could be increased from five to ten years without any decrease in plant safety. In confirmation of that conclusion, no clogging of the nozzles in the Spray Systems during the surveillance tests performed to date has been observed at either Surry or North Anna.

Specific Changes Surry The surveillance intervals for the spray nozzles in the Containment Spray System and the Recirculation Spray System in Technical Specifications 4.5.A.3 and 4.5.B.3 are being changed from five to ten years. In addition, the Basis Section is being changed to reflect the changes in surveillance frequency.

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e e North Anna The surveillance intervals for the spray nozzles in the Quench Spray System and the Recirculation Spray System in Technical Specifications 4.6.2.1.d and 4.6.2.2.d, respectively, are being changed from five to ten years for both Units 1 and 2. The test frequency of the nozzles is not discussed in the basis of North Anna's Technical Specifications.

In addition, an editorial change is being made to Specification 4.6.2.2.1.c.2 for both Units 1 and 2.

Safety Significance The proposed changes to the surveillance requ_irements for the Spray Systems' nozzles are consistent with the intent of Generic Letter 93-05. NUREG-1366 concluded that the corrosion of stainless steel piping is negligible during the proposed extended surveillance interval, since the Spray Systems are maintained dry and there are no additional mechanisms that could reasonably be postulated to cause blockage of the Spray Systems' nozzles. Therefore, the proposed reduced testing of the Spray Systems nozzles remains adequate to ensure operability of the nozzles to mitigate the consequences of a Design Basis Accident.

The proposed changes to the surveillance frequency have no impact on the probability of an accident occurrence, nor do they create a new or different type of accident.

Therefore, there is no increase in the probability of a malfunction of the Spray Systems or the consequences of any Design Basis Accident. The surveillance requirements do not affect the margin of safety in that the operability requirements of the Spray Systems are not changed. Therefore, the margin of safety is not reduced by the proposed changes.

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