ML20044A080

Clarifies NRC Position & Reporting Requirements in Generic Ltr 88-01 Re Approval of Flaw Evaluations Prior to Resumption of Plant Operation.Weld Overlay Repair Considered Noncode Repair & Requires NRC Approval

ML20044A080
Person / Time
Site:	Peach Bottom, Limerick
Issue date:	06/11/1990
From:	Butler W Office of Nuclear Reactor Regulation
To:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
GL-88-01, GL-88-1, TAC-69143, TAC-69144, TAC-69150, TAC-69151, NUDOCS 9006280043
Download: ML20044A080 (3)

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UNITED $TATEs

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NUCLEAR REGULATORY COMMISSION WAaHINGTON, D. C. 20666 y'

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June 11, 1990 Docket Nos. 50-277 50-278 50-352 50-353 Mr. George A. Hunger, Jr.

Director-Licensing,ic Company Mc 5-2A 5 Philadelphia Electr Nuclear Group Headquarters Correspondence Control Desk P. O. Box No. 195 Wayne, Pennsylvania 19087-0195

SUBJECT:

CLARIFICATION OF THE STAFF POSITION ON REPORTING REQUIREMENTS IN GENERIC LETTER 88 01 ON NRC REVIEW AND APPROVAL OF FLAW EVALUATIONS PRIOR TO RESUMPTION OF OPERATION, LIMERICK GENERATING STATION, UNITS 1 AND 2 (TAC N05. 69143 AND 69144) PEACH BOTTOM ATOMIC POWER STATION, UNITS 2AND3(TACN05.69150AND69151)

A licensee recently misinterpreted Generic Letter (GL) 88-01 and started up the plant without first obtaining NRC ap)toval of flaw evaluations and/or repairs although their response to the 6. indicated that they would comply without exception with the Staff Position on Reporting Requirements.

PEco's response of August 2, 1988 to the GL Attachment, page 15, states that "NRCapprovalofthedispositionforeachflewexceedingthecriteriawillbe obtained before operation is resumed."

By way of clarification, the staff's GL 88-01 position is restated below along with the applicable ASME,Section XI requirements, it should also be noted that weld overlay repair is considered a non-Code repair and requires NRC approval.

1.

GL 88-01, dated January ?5,1988, Attachment A. Page 6 Staff Position on Reporting Requirements.

If any cracks are identified that do not meet the criteria for continued operation without evaluation given in Section XI of the Code, NRC approval of flaw evaluation and/or repairs in accordance with IWB 3640 and IWA 4130 is required before resumption of operation.

2.

ASME Code,Section XI, IWB 3640 " EVALUATION PROCEDURES AND ACCEPTANCE CRITERIA FOR AUSTENITIC PIPING"

" Piping containing a flaw exceeding the allowable flaw standards of IWB-3514.3 may be evaluated to determine its 3t /g\\\\

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9006280043 900611 ADOCK 0500 7

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Mr. George A. Hunger, Jr.

Limerick Generating Station Philadelphia Electric Company Units 1 & 2 i

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i Troy B. Conner, Jr., Esquire Mr. Thomas Gerusky, Director Conner and Wetterhahn Bureau of Radiation Protection j

1747 Pennsylvania Ave.66 P. O.pt. of Environmental Resources N.W.

PA De i

Washington, D. C.

200 Box 2063 i

Mr. Rod Krich 52A-5 Philadelphia Electric Company Single Point of Contact 955 Chesterbrook Boulevard P. O. Box 11880 Wayne, Pennsylvania 19087 5691 Harrisburg, Pennsylvania 17108-1880 Mr. Graham M. Leitch, Vice President Mr. Philip J. Duca Limerick Generating Station Support Manager l

Post Office Box A Limerick Generating Station Sanatoga, Pennsylvania 19464 P. O. Box A Sanatoga, Pennsylvania 19464 Mr. Marty J. McCormick, Jr.

I Plant Manager Mr. Garrett Edwards Limerick Generating Station Superintendent-Technical P.O. Box A Limerick Generating Station Sanatoga, Pennsylvania 19464 P. O. Box A Sanatoga, Pennsylvania 19464 Mr. Larry Doerflein U.S. Nuclear Regulatory Commission Mr. Gil J. Madsen Region 1 Regulatory Engineer i

475 Allendale Road Limerick Generating Station l

King of Prussia, PA 19406 P. O. Box A Sanatoga, Pennsylvania 19464 Mr. Thomas Kenny Senior Resident inspector US Nuclear Regulatory Comission P. O. Box 596 Pottstown, Pennsylvania 19464 l

Mr. John Doering l

ProjectManager Limerick Generating Station P. O.~ Box A Sanatoga, Pennsylvania 19464 Mr. Larry Hopkins Superintendent-Operations Limerick Generating Station P. O. Box A Sanatoga, Pennsylvania 19464

Mr. George A. Hunger, dr.

-2 June 11, 1990 acceptability for continued service in accordance with the evaluation procedures and acceptance criteria of IWD 3641 or IWB 3642. The evaluation procedures and acceptance criteria shall be subject to approval i

of the regulatory authority having jurisdiction at the plent site.'

Sincerely, 1

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v! alter R. Butler, Director Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation ec: See next page 1

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