ML20209E734

Discusses Util Responses to GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity. Responses Acceptable.Info Revised in Reactor Vessel Integrity Database (Rvid) & Is Releasing as Rvid Version 2

ML20209E734
Person / Time
Site:	Millstone
Issue date:	07/12/1999
From:	John Nakoski NRC (Affiliation Not Assigned)
To:	Necci R NORTHEAST NUCLEAR ENERGY CO.
References
GL-92-01, GL-92-1, TAC-MA0554, TAC-MA554, NUDOCS 9907150137
Download: ML20209E734 (5)

Text

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20665 4001

.,,,/ July 12, 1999 j i

Mr. R. P. Necci - Vice President '

Nuclear Oversight and Regulatory Affairs  !

c/o Mr. David A. Smith i Northeast Nuclear Energy Company l l

. P. O. Box 128 Waterford, CT 06385-0128 l

SUBJECT:

CLOSURE OF TAC NO. MA0554 - RESPONSE TO THE REQUEST FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1,

" REACTOR VESSEL STRUCTURAL INTEGRITY," FOR MILLSTONE UNIT 3

Dear Mr. Necci:

i 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 l l addressees of the GL to -

i

( (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 '

l (2) to 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 Federal i Regulations (10 CFR 50.60 and 10 CFR 50.61), and to the requirements of Appendices l G and H to Part 50 of Title 10 of the Code of FederalRegulations(Appendices G and H l to 10 CFR Part 50).

On August 21,1995, you submitted your initial response to GL 92 01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for Millstone Unit 3. The staff evaluated your response and provided its conclusion relative to your response on August 12,1996. However, since the time of the staff's 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.

On September 29,1997, you provided your final response to the staff regarding your assessment of the information in the topical reports noted above. The staff has reviewed the information that you submitted and determined that it adequately reflects the information contained in CE Topical Reports CE NPSD-1039, Revision 2, and CE NPSD-1119, Revision 1, kg\

for CE fabricated RPV welds.

MC FU MNTER CDPV 9907150137 990712 PDR ADOCK 05000423 P PDR

e R. Necci l

l As a result of the staff's review of your responses to GL 92-01. Revision 1, and GL 92-01, Rev.1, Supp.1, the staff has revised the information in the Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. The revised database is posted on the world-wide-web at a location linked to the NRC home page (http://www.nrc. gov /NRR/RVID/inde 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 plant. No additionalinformation is necessary with regard to the structuralintegrity assessments.

Future submittals on pressure-temperature limits, pressurized therma! shock, or upper shelf energy, should reference the most current information.

This closes efforts in regardthe staff's to this matter.efforts in regard to TAC number MA0554. The staff appreciates your Sincerely,

/

John . Nakoski, Senio Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50 423 cc: See next page

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. Millstone Nuclear Power Station k Unit 3 cc:

Ms. L. M. Cuoco Mr. F. C. Rothen Senior Nuclear Counsel Vice President - Operations Northeast Utilities Service Company Northeast Utilities Service Company P. O. Box 270 P. O. Box 128 Hartford, CT 06141-0270 Waterford, CT 06385 Edward L. Wilds, Jr., Ph.D. Ernest C. Hadley, Esquire Director, Division of Radiation 1040 B Main Street

! Department of Environmental Protection P.O. Box 549 79 Elm Street West Wareham, MA 02576 Hartford, CT 06106-5127 Mr. James S. Robinson, Manager l Regional Administrator, Region i Nuclear investments and Administration l U.S. Nuclear Regulatory Commission New England Power Company 475 Allendale Road 25 Research Drive King of Prussia, PA 19400 Westborough, MA 01582 First Selectmen Mr. R. P. Necci l Town of Waterford Vice President - Nuc! ear Oversight and 15 Rope Ferry Road Regulatory Affairs Waterford, CT 06385 Northeast Nuclear Energy Company P. O. Box 128 Mr. Wayne D. Lanning, Director Waterford, CT 06385 Millstone inspections Office of the Regional Administrator Deborah Katz, President 475 Allendale Road Citizens Awareness Network King of Prussia, PA 19406-1415 P.O. Box 83 Shelburne Falls, MA 03170 Mr. M. H. Brothers Vice President - Operations Mr. A%n Johanson, Assistant Director Northeast Nuclear Energy Company Offico of Policy and Management P.O. Box 128 Policy Development and Planning Waterford, CT 06385 Division 450 Capitol Avenue - MS# 52ERN Mr. M. R. Scully, Executive Director P O. Box 341441 Connecticut Municipal Electric Hartford, CT 06134-1441 Energy Cooperative 30 Stott Avenue Ms. Terry Concannon Norwich, CT 06360 Co-Chair Nuclear Energy Advisory Council Mr. J. T. Carlin Room 4100 Vice President - Human Services Legislative Office Building Northeast Utilities Service Company Capitol Avenue I P. O. Box 128 Hartford, CT 06106 Waterford, CT 06385 i

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• Millstone Nuclear Power Station Unit 3 cc:

Citizens Regulatory Commission Mr. Evan W. Woollacott ATTN: Ms. Susan Perry Luxton Co Chair 180 Great Neck Road Nuclear Energy Advisory Council Waterford, CT 06385 128 Terry's Plain Road Simsbury, CT 06070 Mr. William D. Meinert Nuclear Engineer Mr. John W. Beck, President Massachusetts Municipal Wholesale Little Harbor Consultants, Inc. Electric Company  ;

Millstone -ITPOP Project Office P.O. Box 426  !

P.O. Box 0630 Ludlow, MA 01056 Niantic, CT 06357-0630 Mr. B. D. Kenyon Mr. L. J. Olivier President and Chief Executive Officer-Senior Vice President and Nuclear Group Chief Nuclear Officer - Millstone Northeast Utilities Service Company Northeast Nuclear Energy Company 7 >. Box 128

. P.O. Box 128 , aterford, CT 06385 Waterford, CT 06385 Mr. D. B. Amerine Mr. C. J. Schwarz Vice President - Engineering Services Director - Unit 3 Operations Northeast Nuclear Energy Company l

- Northeast Nuclear Energy Company P. O. Box 128  ;

P.O. Box 128 Waterford, CT 06385 Waterford, CT 06385 Mr. D. A. Smith Senior Reside,.it inspector Manager - Regulatory Affairs Millstone Nuclear Power Station Northeast Nuclear Energy Company c/o U.S. Nuclear Regulatory Commission P. O. Box 128 P. O. Box 513 Waterford, CT 06385 Niantic, CT 06357 Ms. Nancy Burton Nicholas J. Scobbo, Jr., Esquire 147 Cross Highway Ferriter, Scobbo, Caruso, & Rodophele, P.C. Redding Ridge, CT 00870 75 State Street,7th Floor Boston, MA 0210

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k July 12, 1999 w.

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R. Necci l 1

As a result of the staff's review of your responses to GL 92-01, Revision 1, and GL 92-01, Rev.1, Supp.1, the staff has revised the information in the Reactor Vessel Integrity Database  !

(RVID) and is releasing it as RVID Version 2. The revised database is posted on the world-wide-web at a location 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 1 plant. No additionalinformation is necessary with regard to the structuralintegrity assessments. l Future submittals on pressure-temperature limits, pressurized thermal shock, or upper shelf l energy, should reference the most current information, i This closes the staff's efforts in regard to TAC number MA0554. The staff appreciates your i effor's in regard to this matter.

1 Sincerely, ORIGINAL SIGNED BY:

John A. Nakoski, Senior Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-423 cc: See next page DISTRIBUTION:' Docket' File ? TClark OGC EAdensam (E-mail EGA1)

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