ML20209G272
| ML20209G272 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 07/14/1999 |
| From: | Croteau R NRC (Affiliation Not Assigned) |
| To: | Wanczyk R VERMONT YANKEE NUCLEAR POWER CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-MA1212, NUDOCS 9907190111 | |
| Download: ML20209G272 (4) | |
Text
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i UNITED STATIS y"
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July 14, 1999 Mr. Robert J. Wanczyk Acting Director of Operations Vermont Yankee Nuclear Power Corporation 185 Old Ferry Road Brattleboro, VT 05301
SUBJECT:
RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE VERMONT YANKEE NUCLEAR POWER STATION (TAC NO. MA1212)
Dear Mr. Wanczyk:
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) idenHfy, 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 enalyses relative to the requirements of Sections 50.60 and 50.61 to Part 50 cf Title 10 of the Code of Federal Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements 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 15,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1. and provided the requested inforr ation relative to the structuralintegrity assessment for the Vermont Yankee Nuclear Power Station (Vermont Yankee). The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 1,1996. However, since the time of the staff's closure letter, the Goinbustion 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 additional information was necessary relative to the structural integrity assessments for your plants. On April 22,1998, 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, and pressure-temperature (P-T) limits for Vermont Yankae. In I
ganeral, with respect to the contents of the RAI, the staff requested that you resm ess the I
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R. Wanczyk 2
alloying chemistries for the beltline welds and RPV surveillance welds relative to the chemistries
= provided in the applicable topical report, and provide the impact of any changes to the best-l 6 stimate 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 licensing bases for your plant, j
j You provided your response to the staff's RAI on June 26,1998. As a result of the. staff's j
review of your responses to GL 92-01, Revision 1; GL 92-01, Rev.1, Supp.1; and the Rep 1 RAI, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) anc is releasing it as RVID Version 2.
The new database diskettes are posted on the world-wide-web at a location which is lir.ked to the NRC home page (http /www.nrc Jov/NRR/RVID/index.html ). We recommend that you 1
review this information. If the staff coes 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 i
on P-T limits or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts in regard to TAC No. MA1212. We appreciate your efforts in i
regard to this matter.
Sincerely, s
- / [r M
Richard P. Croteau, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271 cc: See next page 4
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R. Wanczyk 2
alloying chemistries for the beltline welds and RPV 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 !icensing bases for your plant.
You provided your response to the staff's RAI on June 26,1998. 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.
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 1
information is necessary with regard to the structural integrity assessments. Future submittals on P-T limits or upper shelf energy (USE) should reference the most current information.
This closes the staff's efforts in regard to TAC No. MA1212. We appreciate your efforts in regard to this matter.
Sincerely, ORIGINAL STGKi BY:
Richard P. Croteau, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-271 cc: See next page DISTRIBUTION:
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OFFICIAL RECORD COPY
a.
e Vermont Yankee Nuclear Power Station cc:
Regional Administrator, Region 1 Mr. Raymond N. McCandless U. S. Nuclear Regulatory Commission Vermont Department of Health 475 Allendale Road Division of Occupational King of Prussia, PA 19406 and Radiological Health 108 Cherry Street Mr. David R. Lewis Burlington, VT 05402 Shaw, Pittman, Potts & Trowbridge 2300 N Street, N.W.
Mr. Gautam Sen Washington, DC 20037-1128 Licensing Manager Vermont Yankee Nuclear Power Mr. Richard P. Sedano, Commissioner Corporation Vermont Department of Public Service 185 Old Ferry Road 112 State Street Brattleboro, VT 05301 Montpelier, VT 05620-2601 Resident inspector Mr. Michael H. Dworkin, Chairman Vermont Yankee Nuclear Power Station b
Public Service Board U. S. Nuclear Regulatory Commission State of Vermont P.O. Box 176 112 State Street Vernon, VT 05354 Montpelier, VT 05620-2701 Director, Massachusetts Emergency Chairman, Board of Selectmen Management Agency Town of Vernon ATTN: James Muckerheide P.O. Box 116 400 Worcester Rd.
Vernon, VT 05354-0116 P.O. Box 1496 Framingham, MA 01701-0317 Mr. Richard E. McCullough Operating Experience Coordinator Jonathan M. Block, Esq.
Vermont Yankee Nuclear Power Station Main Street P.O. Box 157 P. O. Box 566 Governor Hunt Road Putney, VT 05346-0566 Vernon, VT 05354 G. Dana Bisbee, Esq.
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Deputy Attorney General 33 Capitol Street Concord, NH 03301-0937
- Chief, Safety Unit Office of the Attorney General One Ashburton Place,19th Floor Boston, MA 02108 Ms. Deborah B. Katz Box 83 Shelburne Falls, MA 01370
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