ML20209E358

Discusses Util 980925 Response to GL 92-01,Rev 1,Suppl 1, Rv Structural Integrity, Issued on 950519 to Wolf Creek Generating Station

ML20209E358
Person / Time
Site:	Wolf Creek
Issue date:	07/12/1999
From:	Donohew J NRC (Affiliation Not Assigned)
To:	Maynard O WOLF CREEK NUCLEAR OPERATING CORP.
References
GL-92-01, GL-92-1, TAC-MA0584, TAC-MA584, NUDOCS 9907140216
Download: ML20209E358 (4)

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• • • • • l July 12, 1999 Mr. Otto L. Maynard President and Chief Executive Officer Wolf Creek Nuclear Operating Corporation Post Office Box 411 Burlington, KA 66839

SUBJECT:

GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR WOLF CREEK GENERATING STATION (TAC NO. MA0584)

Dear Mr. Maynard:

On May 19,1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL 92-01, Rev.1, Supp.1), " Reactor Vessel Structural Integrity,"

to holders of nuclear operating licenses. In issuing the GL the staff required addressees of the GL to:

(1) identify, collect and report any new data pertinent to the analysis of structural integrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61, and Appendices G and H to 10 CFR Part 50.

You submitted your initial response to the GL on August 17,1995, and provided the requested information relative to the structural integrity assessment for Wolf Creek Generating Station (WCGS). The staff evaluated your response to the GL and provided its conclusions in a letter on August 5,1996. However, since the time of the staffs closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B&W) Owners Group have each submitted additional data regarding the alloying chemistries of beltline welds in CE and B&W fabricated vessels. The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision 1, for B&W fabricated RPV welds. In addition, Chicago Bridge and Iron (CB&l) BWR data were submitted in Topical Report BWRVIP-46. As a result of the efforts by CE and B&W, the staff determined that additionalinformation was necessary relative to the structural integrity assessments for your plant.

j On March 26,1998, the staff issued a request for additional information (RAI) in regard to the alloying chemistries of beltline welds, your assessment of surveillance data for your facility, pressure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessment (only applicable to PWRs) for WCGS. In general, with respect to the contents of the RAI, the staff

, requested that you reassess the alloying chemistries for the beltline welds and RPV l surveillance welds relative to the chemistries provided in the applicable topical report, and provide the impact of any changes to the best-estimate chemistries for your beltline RPV welds on the structural integrity assessments for WCGS relative to the requirements of Sections

> 50.60 and 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the licensing l- basis for WCGS.

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'O j O. Maynard You provided your response to the staffs RAI on September 25,1998. As a result of the staffs review of your responses to GL 92-01, Revision 1 GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http://www.nrc. gov /NRR/RVID/index.html). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we wi;l assume that the data entered into the RVID ace acceptable for your plant. No additional information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits, PTS (only applicable to PWRs), or upper' shelf energy (USE) should reference the most current information.

You have adequately responded to the GL for WCGS and this letter closes the staffs efforts in regard to TAC No, MA0584. The staff appreciates your efforts in regard to this matter.

'ncerely, Jac N. Donohew, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-482 cc: See next page DISTRIBUTION:

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l O. Maynard {

You provided your response to the staff's RAI on September 25,1998. As a result of the staff's review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2.

1 The new database diskettes are posted on the world-wide-web at a location which is linked to the NRC home page (http //www.nrc. gov /NRR/RVID/index.html ). We recommend that you review this information. If the staff does not receive comments by September 1,1999, we will assume that the data entered into the RVID are acceptable for your plant. No additional l information is necessary with regard to the structuralintegrity assessments. Future submittals I on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information. ]

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You have adequately responded to the GL for WCGS and this letter closes the staff's efforts in i regard to TAC No. MA0584. The staff appreciates your efforts in regard to this matter. l Sincerely, s

l D. ]

f Jack N. Donohew, Project Manager, Section 2 l Project Directorate IV & Decommissioning Division of Licensing Project Management l

l Office of Nuclear Reactor Regulation j Docket No. 50-482 l l

cc: See next page J

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. Wolf Creek Generating Station cc:

Jay Silberg, Esq. Vice President & Chief Operating Officer Shaw, Pittman, Potts & Trowbridge Wolf Creek Nuclear Operating Corporation 2300 N Street, NW P. O. Box 411 Washington, D.C. 20037 - Burlington, Kansas 66839 Regional Administrator, Region IV Superintendent Licensing  ;

U.S. Nuclear Regulatory Commission Wolf Creek Nuclear Operating Corporation 611 Ryan Plaza Drive, Suite 1000 P.O. Box 411 Arlington, Texas 76011 Burlington, Kansas 66839 Senior Resident inspector U.S. Nuclear Regulatory Commission U.S. Nuclear Regulatory Commission Resident inspectors Office i P. O. Box 311 8201 NRC Road Burlington, Kansas 66839 Steedman, Missouri 65077-1032 Chief Engineer Utilities Division Kansas Corporation Commission 1500 SW Arrowhead Road Topeka, Kansas 66604-4027 Office of the Governor-State of Kansas Topeka, Kansas 66612 Attomey General Judicial Center 301 S.W.10th 2nd Floor Topeka, Kansas 66612 County Clerk Coffey County Courthouse Burlington, Kansas 66839 Vick L. Cooper, Chief Radiation Control Program Kansas Department of Health and Environment Bureau of Air and Radiation Forbes Field Building 283 Topeka, Kansas 66620