ML20212K887

Forwards Notice of Denial of Amends to Licenses DPR-32 & DPR-37 & Opportunity for Hearing Based on Review of Util 801028,830921 & 850412 Requests to Delete Tech Spec 4.15 Re High Energy Pipe Break Insp Program

ML20212K887
Person / Time
Site:	Surry
Issue date:	03/03/1987
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
Shared Package
ML18157A168	List: ML20212K887
References
IEB-79-14, TAC-43113, TAC-43114, NUDOCS 8703090445
Download: ML20212K887 (3)

Text

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N S- 1gP Docket Nos. 50-280 DISTRIBUT 50-281 3 BGrimes NRC R JPartlow Local PDR NThompson, DNFT Mr. W. L. Stewart PD# 2 Reading CPatel Vice President - Nuclear Operations TNovak DMiller.

s Virginia Electric and Power Company OGC-Rethesda ACRS (10)

Post Office Box 26666- EJordan Gray File Richmond, Virginia 23261

SUBJECT:

HIGH ENERGY LINE RREAK INSPECTION PROGRAM FOR SURRY POWER STATION UNITS 1 A 2 By letter dated October 28, 1980, as supplemented September 21. 1983 and April 12, 1985, Virginia Electric and Power Company requested a proposed

, change to the Technical Specifications pertaining to the High Energy Pipe Rreak Inspection Procram for Surry Power Station Units 1 & 2.- The proposed i

change would delete Technical Specification 4.15 completely with the rationale

- that examinations performed under the rules of Section XI of the ASME Code are acceptable and that " continuation of the Technical Specification 4.15 represents j impractical duplication."

l- We have reviewed your request and supporting information contained in the j supplemental letters and attachments. We do not agree with your assessment of "duplicative" requirements of the Technical Specification 4.15 and those of Section XI. The number of welds sub,iect to and the frequency of examination as

, delineated in Technical Specification 4.15 significantly exceed Section XI l requirements. The basis for the augmented examinations of the welds cited in the Technical Specification is to reduce the probability of. failure of the high

j. and moderate energy fluid systems piping located outside containment. Failures

. at the break locations have been analyzed as potential causes of damage to safety systems that could result in the inability to safely shut down and maintain cold shutdown conditions of the reactor.

l Although'the sampling plan of Section XI for Class 2 piping welds might t include the welds required to be examined by Technical Specification 4.15, the frequency of examination would be one-fourth that of the Technical Specification. In order to preserve the capability of timely detection of incipient cracks and thus the structural reliability of the hiah and moderate energy fluid systems piping, we consider the proposed Technical Specification change request to be inappropriate. Therefore, the current requirements of

i. Technical Specification 4.15 should remain effective, and your request for a l change is denied.

i 8703090445 870303 PDR ADOCK 05000280 l P PDR-

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' Mr. W. L. Stewart In addition, in your letter dated October 28, 1980 (Serial No. 862), you requested several changes' to the Technical Specifications for Surry Units 1 and 2. Among the changes proposed was one pertaining to break points to be incorporated in the High Energy Pipe Break Inspection Program.

-Your letter stated that "the seismic reanalysis of safety related piping systems required for IE Bulletin 79-14 has indicated six new break points which must be incorporated in the High Energy Pipe Break Inspection Program specified in Technical Specification 4.15-A. The proposed changes will revise Specification 4.15-A to indicate that there are 26 welds to be included in the inspection program and will revise TS Figure 4.15 to indicate the location of the six additional break inspection points."

As your proposed change of deleting Technical Specification 4.15 is not acceptable to us, we would like to know about your intention for including remaining welds into the current Technical Specifications. To date, you have not provided adequate justification for not including these break points in the Technical Specifications. You should either include the additional break inspection points in the Technical Specifications or provide justification for not doing so.

Also, Technical Specification 4.15-R refers to 1972 Winter Addenda of ASME Code Section XI. You should consider making it consistent with Technical Specification 4.15-A unless there is specific reason for not doing so.

We will review your responses to this request as separate actions in the future.

The Commission has filed the enclosed Denial of Application for Amendment to Facility Operating License with the Office of the Federal Pegister for publication.

Sincerely, Lester S. Rubenstein, Director PWR Project Directorate #2 Division of PWR Licensino-A

Enclosure:

As Stated cc w/ enclosure j See next page O

CW 0 N y f

L: PM: PAD 2 R ::SB' PD: PAD 2 OGi er CPatel RB liard LRubenstein

/87 FS/87 1J/ 9 /87 1/26/87 4/jA/8

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, Mr. W. L. Stewart Virginia Electric and Power Company Surry Power Station cc:

Mr. Michael W. Maupin Attorney General Hunton and Pilliams Supreme Court Building Post Office Box 1535 101 North 8th Street Richmond, Virginia 23213 Richmond, Virginia 23?19 i

Mr. Robert F. Saunders, Manager Surry Power Station Post Office Box 315 Surry, Virginia- 23883 Resident Inspector Surry Power Station ll.S. Nuclear Regulatory Commission Post Office Box 166, Route 1 Surry, Virginia 23883 Mr. Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthause Surry, Virginia 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation Post Office Box 1197 Rici..aond, Virginia 23209 Mr. J. T. Rhodes Senior Vice President - Power Ops.

Virginia Electric and Power Company Post Office Rox 26666 Richmond, Virginia 23261 i

Regional Administrator, Region II U.S. Naclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30323 James R. Kenley, M.D., Commissioner Department of Health 109 Governor Street Richmond, Virginia 23?lo

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