ML20207H640
| ML20207H640 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/09/1999 |
| From: | Stewart Bailey NRC (Affiliation Not Assigned) |
| To: | Campbell G CENTERIOR ENERGY |
| References | |
| GL-92-01, GL-92-1, TAC-MA0540, TAC-MA540, NUDOCS 9907140023 | |
| Download: ML20207H640 (3) | |
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UNIT 2D STATES y
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NUCi. EAR REGULATORY COMMISSION i
WASHINGTON, D.C. 20666-4001
%.....+o July 9, 1999 Mr. Guy G. Campbell, Vice President - Nuclear FirstEnergy Nuclear Operating Company
(
5501 North State Route 2 3
Oak Harbor, OH 43449-9760
SUBJECT:
CLOSURE OF TAC NO. MA0540 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE DAVIS-BESSE NUCLEAR POWER STATION, UNIT 1
Dear Mr. Campbell:
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 structuralintegrity of the reactor pressure vessels (RPVs) at their nuclear plants, and (2) assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 of Title 10 of the Code of Federa/ Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requlrements of Appendices G and H to Part 50 of Title 10 of the Code of federa/ Regulations (Appendices G and H to 10 CFR Part 50).
On August 16,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structuraiintegrity assessments for Davis-Besse, Unit 1. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 13,1996. 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 Repods 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 eddition, Chicago Bridge anci 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 additional information was necessary relative to the structuralintegrity assessments for your plants.
9 On April 9,1998, the staff issued a request for additional information (RAl) in regard to the b
alloying chemistries of beltline welds, your assessment of surveillance data for your facility,
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prest,ure-temperature (P-T) limits, and pressurized thermal shock (PTS) assessment (only ar.p!, cable to PWRs) for Davis-Besse. 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 9907140023 990709 l
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I Mr. Guy G. Campbell Davis-Besse Nuclear Power Station, Unit 1 FirstEnergy Nuclear Operating Company cc:
Mary E. O'Reilly Robert E. Owen, Chief FirstEnergy Bureau of Radiological Health 76 South Main Street Ser/ ice Akron, OH 44308 Ohio Department of Health P.O. Box 118 James L. Freels Columbus, OH 43266-0118 Manager - Regulatory Affairs FirstEnergy Nuclear Operating Company James R. Williams, Executive Director Davis-Besse Nuclear Power Station Ohio Emergency Management Agency 5501 North State - Route 2 2855 West Dublin Granville Road Oak Harbor, OH 43449-9760 Columbus, OH 43235-2206 Jay E. Silberg, Esq.
Director Shaw, Pittman, Potts Ohio Department of Commerce and Trowbridge Division of Industrial Compliance 2300 N Street, NW.
Bureau of Operations & Maintenance Washington, DC 20037 6606 Tussing Road P.O. Box 4009 Regional Administrator Reynoldsburg, OH 43068-9009 U.S. Nuclear Regulatory Commission 801 Warrenville Road Ohio Environmental Protection Agency Lisle, IL 60523-4351 DERR-Compliance Unit ATTN: Zack A. Clayton Michael A. Schoppman P.O. Box 1049 Framatome Technologies incorporated Columbus, OH 43266-0149 1700 Rockville Pike, Suite 525 Rockville, MD 20852 State of Ohio Public Utilities Commission Resident inspector 180 East Broad Street U.S. Nuclear Regulatory Commission Columbus, OH 43266-0573 5503 North State Route 2 Oak Harbor, OH 43449-9760 Attomey General Department of Attomey James H. Lash, Plant Manager 30 East Broad Street FirstEnergy Nuclear Operating Company C61umbus, OH 43216 Davis-Besse Nuclear Power Station 5501 North State Route 2 President, Board of County Oak Harbor, OH 43449-9760 Commissioners of Ottawa County Port Clinton, OH 43252 l
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Mr. G. C;mpbell 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 your facility relative to the requirements of 10 CFR 50.60,10 CFR 50.61, and Appendices G and H to 10 CFR Part 50, as applicable to the liceneg sasis for your plant.
. Ycu provided your response to the staff's RAI for Davis-Besse on August 10,1998, and I
provided supplementalinformation on March 29,1999. 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 information is necessary with regard to the structuralintegrity assessments. Future submittals on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts on TAC No. MA0540. The staff appreciates your efforts on this i
matter.
Sincerely, Original signed by Stewart N. Bailey, Project Manager, Section 2 Project Directorate lli Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-346 -
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Enclosure:
As stated p
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