ML20126F474

Forwards SE Granting Relief from ASME Code Requirements for Repair of RWCU Equalizing Line Until Next Refueling Outage, Contingent Upon Util Performing VT-2 Visual Insps of Repair During Plant Shutdowns in Which Containment Deinerted

ML20126F474
Person / Time
Site:	FitzPatrick
Issue date:	12/23/1992
From:	Capra R Office of Nuclear Reactor Regulation
To:	Ralph Beedle POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
Shared Package
ML20126F476	List: ML20126F474 ML20126F477
References
TAC-M85147, NUDOCS 9212300332
Download: ML20126F474 (6)

Text

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\., . . . . . p' December 23, 1992 Docket No. 50-333 Mr. Ralph E. Beedle Executive Vice President, Nuclear Generation Power Authority of the State of New York 123 Main Street White Plains, New York 10601

SUBJECT:

RELIEF REQUEST FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE REQUIREMENTS FOR REPAIR OF REACTOR WATER CLEANUP EQUALIZING LINE - JAMES A. FITZPAT11CK NUCLEAR POWER PLANT (TAC NO M85147)

During a hydrostatic test on the Reactor Water Cleanup (RWC) system, the Power Authority of the State of New York (PASNY) detected a through-wall defect on the 1/2" equalizing line to valve bonnet weld for RWC suction isolation valve 12RWC-46. A preliminary root cause analysis of the defect determined that the most likely cause of the failure was thermal fatigue due to differential expansion between the stainless steel equalizing line and the carbon steel valve body. PASNY designed a pipe assembly to encapsulate the component that has the through-wall defect. This design ensures that the repair is capable of meeting all primary and secondary stresses. Powever, this-encapsulation repair method does not remove the pipe defect as required by the Section XI of the ASME Code. Therefore, by letter dated December 14, 1992, PASNY submitted a request for relief from ASME Code, 1980 Edition through Winter 1981 Addenda,Section XI, IWA-5250(a)(2) and IWA-4130(a)(2).

PASNY has provided information to support determinations that repair as specified by the Section XI of the ASME Code would result in hardship or unusual difficulties without a compensating increase in the level of quality-and safety and that the proposed alternative repair provides an acceptable level of quality and-safety. Specifict.lly, removal of the pipe defect in accordance with the ASME Code would require the RWC line be drained. Two methods of isolating this pipe were considered; installing a freeze seal and installing a plug into the Recirculation System' suction line. Insthllation of a freeze seal was determined to be impossible due to the piping configuration.

, Installing a plug into the Recirculation System suction line would require

! disassembly of the reactor vessel, removal of the reactor internals, and offload of over one-third of the fuel from the reactor core. This would result in a significant increase in person-rem exposuu and extend the refuel-outage approximately 16 days. Furthermore, the level of quality and safcty r l- will be maintained with the alternative repair since the encapsulated pipe ' f assembly restores structural integrity to the pipe containing the defect.

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lMr. Ralph E.'Beedle- December 23, 1992 .

As noted in the enclosed safety evaluation, the staff has reviewed the submittal: and concludes- that the encapsulation repairJimplemented by FASN. is acceptable for service until the next refueling outage. Pursuant to 10 CFR 50.55a(a)(3)(i) and (ii), the staff concludes that completely _ satisfying;the requirements of IWA-5250(a)(2) and IWA-4130(a)(2) would~ result in hardship or unusual difficulties without a compensating increase in the level of quality and safety and the proposed alternative provides an adequate' level of quality

• and safety. Also, pursuant to 10 CFR 50.55a(a)(3)(1) and (ii),_the staff-concludes that. the proposed . repair is an acceptable alternative to' completely satisfying the requirements of IWA-7220. Therefore,-relieffis granted until the next refueling. outage. At that_ time, repair or,r6 placement-to the Code requirements shall be made. The granting of thir relief ~1s contingent upon PASNY performing VT-2 visual inspections of the repair during all plant shutdowns in which containment is-deinerted.

This completes our action related to TAC No. M85147.

Sincerely,-

Original Signed BY:

Robert A.-Lapra, Director Project Directorate-1-1

I Division of Reactor Projects - 1/II .

Office of Nuclear Reactor Regulation-

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Enclosure:

Safety Evaluation cc w/ enclosure:

See next page  ;

DIS _TRIBUTION: ,

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Mr. Ralph E. Beedle December 23, 1992 As noted in the enclosed safety evaluation, the staff has reviewed the submittal and concludes that the enchpsulation repair implemented by PASNY is acceptable for service until the next refueling outage. Pursuant to 10 CFR 50.55a(a)(3)(1) and (ii), the staff concludes that completely satisfying the requirements of IWA-5250(a)(2) and IWA-4130(a)(2) would result in hardship or unusual dif ficulties without a compe.' .ating increase in the level of quality and safety and the proposed alternative provides an adequate level of quality and safety. Also, pursuant to 10 CFR 50.55a(a)(3)(i) and (ii), the staff concludes that the proposed repair is an acceptable alternative to completely satisfying the requirements of IWA-7220. Theiefore, relief is granted until the next refueling outage, At that time, repair or replacement to the Code -

requirements shall be made. The granting of this relief is contingent upon <

PASNY performing VT-2 visual inspections of the repair during all plant shutdowns in which containment is deinerted.

This completes our action related to TAC No. M85147.

Sincerely, c

wa. C Robert A. Capra, Director

. Project Directorate I-l Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation -

cc w/ enclosure:

See next page t

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I Mr. Ralph E. Beedle December 23, 1992 As noted in the enclosed safety evaluation, the staff has reviewe6 the submittal and concludes that the encapsulation repair implemented by PASNY is acceptable for service until the next refueling outage. Pursuant to 10 CFR 50.55a(a)(3)(1) and (ii), the staff concludes that completely satisfying the.

requirements of IWA-5250(a)(2) and IWA-4130(a)(2) would result in hardship or unusual difficulties without a compensating increase 1n the level of quality and safety and the proposed alternative provides an adequate level of quality and safety. Also, pursuant to 10 CFR 50.55a(a)(3)(i) and (ii), the staff concl;Jes that the proposed repair is an acceptable alternative to completely a satisfying the requirements of IWA-7220. Therefore, relief is granted until the next refueling outage. At that time, repair or replacement to the Code requirements shall be tr.ade. The granting of this relief is continge,1t upon "SNY performing VT-2 visual inspections of the repair during all plant shutdowns in which containment is deinerted.

This completes our action related to TAC No M85147.

Sincerely, Original Signed BY:

Robert A. Capra, Director Project Directorate 1-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Safety Evaluation cc w/ enclosure:

See next page DISTRIBUTIOJ:

See next page

• See previous concurrence j orricE PDI-1:LA PDI-1:PM . *0GC PDI-1:D_, ,

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OFFICIAL RECORD COPY FILENAME: G:\FITZ\flT85347.REL L

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1 Mr. Ralph E. Beedle James A.-FitzPatrick~ Nuclear-- l Power Authority-of the State of New York Power Plant I

cc:

Mr. Gerald C. Goldstein- Ms. Donna Ross 4

' Assistant General Counsel New York State Energy Office Power Authority of the State 2 Empire State Plaza of New York 16th Floor 1633 Broadway Albany, New York 12223-New York, New York 10019 -

Resident Inspector's Office U. S. Nuclear Regulatory Comission Post Office Box 136 Lycoming, New York 13093 Mr. Harry P. Salmon, Jr.

Resident' Manager

' James A. FitzPatrick Nuclear Power Plant Post Office Box 41 Lycoming, New York 13093 Mr. J. A. Gray, Jr. L Director Nuclear' Licensing - BWR Power Authority of the State of New York 123 Main Street White Plains, New York 10601 Supervisor Town of Scriba Route 8, Box 382 Oswego, New York 13126 Mr, John C. Brons, President Power Authority of the' State

- of New York 123 Main Street ~

White Plains, New York 10601 l

Charles Donaldson, Esquire L . Assistant Attorney. General New York Department of Law 120 Broadway New York, New York 10271 p

L Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406-L

4 DATE: December 23. 1992

SUBJECT:

RELIEF REQUEST FROM THE AMERICAN SOCIETY OF MECHANICAL ENGINEERS (ASME) CODE REQUIREMENTS FOR REPAIR OF-REACTOR WATER CLEANUP-EQUALIZING LINE - JAMES A. FITZPATRICK NUCLEAR POWER PLANT (TAC N0. M85147)

Distributign:

< Docket $ File NRC & Local PDRs PDl-1 Reading .i TMurley/FMiraglia,12/G/18 JPartlow,12/G/18 BGrimes, 9/A/2 JLieberman, 7/H/5 -

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