NRC Generic Letter 1981-04

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NRC Generic Letter 1981-004: Implementation of NUREG-0313, Rev.1, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping (Generic Task A-42.).
ML031210168
Person / Time
Issue date: 02/26/1981
From: Eisenhut D G
Office of Nuclear Reactor Regulation
To:
References
NUREG-0313, Rev 1, USI A-42 GL-81-004, NUDOCS 8103170225
Download: ML031210168 (3)


  • I REQ IAUNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D. C. 20555February 26, 1981ALL BWR LICENSEES(EXCEPT HUMBOLDT BAY AND LACROSSE)RE: IMPLEMENTATION OF NUREG-0313, REV. 1, TECHNICAL REPORT ON MATERIALSELECTION AND PROCESSING GUIDELINES FOR BWR COOLANT PRESSURE BOUNDARYPIPING (GENERIC TASK A-42)(Generic Letter 81-04)Enclosed for your action is the final NUREG-0313, Rev. 1, Technical Reporton Material Selection and Processing Guidelines for BWR Coolant PressureBoundary Piping,' dated July 1980, which incorporates the public commentson the wFor Commento edition of the same subject report published in October1979. This final report constitutes the staff's resolution of the NRC'sGeneric Technical Activity A-42, Pipe Cracks in Boiling Water Reactors,"which was an mUnresolved Safety Issue' pursuant to Section 210 of the EnergyReorganization Act of 1974.This report, NUREG-0313, Rev. 1, identifies NRC requirements resultingfrom the recent publication, NUREG-0531, "Investigation and Evaluationof Stress-Corrosion Cracking in Piping of Light Water Reactor Plants,*by the NRC Pipe Crack Study Group (PCSG). The Study Group was specificallychartered to reexamine our previous conclusions and recommendations onthis subject In view of cracks recently discovered in large diameter pipes,to evaluate the significance of safe end cracking at Duane Arnold relativeto similar material and design aspects at other facilities, and to examinedetection capabilities.NIUREG-0313, Rev. 1 sets forth the NRC staff's revised acceptable methodsto reduce the intergranular stress corrosion cracking susceptibility ofBWR ASME Code Class 1, 2, and 3 pressure boundary piping and safe ends.For plants that cannot fully comply with the material selection, testingand processing guidelines of this report, varying degrees of augmentedinservice inspection and leak detection requirments are presented.We request that you review all of the ASME Code Class 1 and 2 pressureboundary piping, safe ends, and fitting material, including weld metal,at your facility to determine if it meets the material selection, testing,and processing guidelines set forth in the enclosed report. You shouldidentify to us ayw materials that do not meet these guidelines and proposeappropriate changes to your Technical Specifications to incorporate theaugmented inservice inspection requirements specified in Section IV ofthe enclosed report. In the case of 'service sensitive" lines you shouldalso provide your plans and schedule for the replacement, to the extentpracticable, of nonconforming materials with those that conform to thestaff's guidelines.d o3176<

-2-In addition, we request that if it is needed, you propose appropriate changesto your Technical Specifications to bring them into conformance with theenclosed report and the affected portion of the model Technical Specificationsdenoted with an asterisk in the margin of the text.You should respond to this letter by July 1, 1981. In your response, youshould propose a schedule to accomplish the above requested actions or adescription, schedule and justification for alternative actions to accomplishthe objectives of this program.This request for information was approved by GAO under a blanket clearancenumber R0072 which expires November 30, 1983. Comments on burden and dupli-cation may be directed to the UbS. General Accounting Office, RegulatoryReports Review, Room 5106, 441 G Street, N.W., Washington, D.C. 20548.The response to this request should reference this letter by title andnumber.

Sincerely,UarI 1senDivison Licensing

Enclosures:

1. NUREG-0313, Rev. 12. Model Technical Specificationscc: Service Lists, w/o Enclosure 1

-AI-ASI- 6t~e,,enCIf 4'Ctyd,Docket No. 50-293Pilgrim Unit 1Docket No. 50-325Brunswick Unit 1Docket No. 50-324Brunswick Unit 2Docket No. 50-10Dresden 1Docket No. 50-237Dresden 2Docket No. 50-249Dresden 3Docket No. 50-254Quad-Cities Unit 1Docket No. 50-265Quad-Cities Unit 2Docket No. 50-155Big Rock PointDocket No. 50-409Lacrosse ro c)Docket No. 50-321Edwin I. Hatch Unit 1Docket No. 50-366Edwin I. Hatch Unit 2Docket No. 50-331Duane ArrnoldDocket No. 50-219Oyster CreekDocket No. 50-220Nine Mile Point Unit 1BOILING WATER REACTOR LICENSEES-( lDocket No. 50-245Millstone Unit 1Docket No. 50-263MonticelloDocket No. 50-133Humboldt BayDocket No. 50-277Peach Bottom Unit 2Docket No. 50-278Peach Bottom Unit 3Docket No. 50-333FitzPatrickDocket No. 50-259Browns Ferry Unit 1Docket No. 50-260Browns Ferry Unit 2Docket No. 50-296Browns Ferry Unit 3Docket No. 50-271Vermont YankeeDocket No. 50-298Cooper Statione

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