ML20211H074
| ML20211H074 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/30/1999 |
| From: | Eaton R NRC (Affiliation Not Assigned) |
| To: | Necci R NORTHEAST NUCLEAR ENERGY CO. |
| References | |
| GL-92-01, TAC-M92696, TAC-MA0553, NUDOCS 9909020008 | |
| Download: ML20211H074 (5) | |
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NUCLEAR REGULATORY COMMISSION k*****[t WASHINGTON D.C. 20565 0001 August 30, 1999 Mr. R. P. Necci - Vice President Nuclear Oversight and Regulatory Affairs Northeast Nuclear Energy Company clo Mr. David A. Smith P.O. Box 128 Waterford, CT 06385
SUBJECT:
CLOSURE OF TAC NOS. M92696 AND MA0553 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, ' REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE MILLSTONE NUCLEAR POWER STATION, UNIT 2
Dear Mr. Necci:
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 periinent to the ana!ysis 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 to Part 50 of 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 21,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative the structural integrity assessment for the Millstone Unit 2. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on July 19,1996. 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. In addition, Chicago
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Bridge and Iron (CB&l) BWR data were submitted in Topical Report BWRVIP-46. As a result of g
the efforts by CE and B&W, the staff determ!.ned that additional information was necessary relative to the structural integrity assessments for your plants. On April 20,1998, 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 Millstone Unit 2. In general, with respect to the contents of the RAI, the staff requested that you h
reassess the alloying chemistries for the beltline welds and RPV surveillance welds relative to 9909020008 990830 PDR ADOCK 05000336 P
August 30, 1999 R. Necci 2
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 licensing basis for your plant.
You provided your response to the staff's RAI for Millstone Unit 2 on July 15,1998. 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 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.
This closes the staff's efforts in regard to TAC Nos. M92697 and MA0553. The staff appreciates your efforts in regard to this matter.
Sincerely, ORIGINAL SIGNED BY.
Ronald B. Eaton, Sr. Project Manager, Section 2 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-336 tRC F U FSTER CDPV.
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Millstons Nuclear Power Station Unit 2 cc:
Ms. L. M. Cuoco Ernest C. Hadley, Esquire Senior Nuclear Counsel 1040 B Main Street Northeast Utilities Service Company P.O. Box 549 P. O. Box 270 West Wareham, MA 02576 I
Hartford, CT 06141-0270 Mr. J. T. Carlin Edward L. Wilds, Jr., Ph.D.
Vice President - Human Services Director, Division of Radiation Northeast Utilities Service Company Department of Environmental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Mr. Allan Johanson, Assistant Director Regional Administrator, Region i Office of Policy and Management U.S. Nuclear Regulatory Commission Policy Development and Planning 475 Allendale Road Division King of Prussia, PA 19406 450 Capitol Avenue - MS# 52ERN P. O. Box 341441 First Selectmen Hartford, CT 06134-1441 Town of Waterford 15 Rope Ferry Road Mr. M. H. Brothers Waterford, CT 06385 Vice President - Millstone Operations Northeast Nuclear Energy Company Mr. Wayne D. Lanning, Director P.O. Box 128 Millstone Inspections Waterford, CT 06385 Office of the Regional Administrator 475 Allendale Road Mr. J. A. Price King of Prussia, PA 19406-1415 Director - Unit 2 Operations Northeast Nuclear Energy Company Charles Brinkman, Manager P.O. Box 128 Washington Nuclear Operations Waterford, CT 06385 ABB Combustion Engineering 12300 Twinbrook Pkwy, Suite 330 Mr. L. Olivier Rockville, MD 20852 Senior Vice President and Chief Nuclear Officer - Millstone Senior Resident inspector Northeast Nuclear Energy Company Millstone Nuclear Power Station P.O. Box 128 c/o U.S. Nuclear Regulatory Commission Waterford, CT 06385 P.O. Box 513 Niantic, CT 06357 Mr. F. C. Rothen Vice President - Nuclear Work Services Northeast Utilities Service Company P. O. Box 128 Waterford, CT 00385
=
Millstone Nuclear Power Station Unit 2 cc:
Citizens Regulatory Commission Ms. Nancy Burton ATTN: Ms. Geri Winslow 147 Cross Highway P. O. Box 199 Redding Ridge, CT 00870 Waterford, CT 06385 Deborah Katz, President Citizens Awareness Network P. O. Box 83 Shelburne Falls, MA 03170 Ms. Terry Concannon Co Chair Nuclear Energy Advisory Council 415 Buckboard Lane Marlborro, CT 06447 Mr. Evan W. Woollacott Co-Chair Nuclear Energy Advisory Council 128 Terry's Plain Road Simsbury, CT 06070 Little Harbor Consultants, Inc.
Millstone - ITPOP Project Office i
P. O. Box 0630 Niantic, CT 06357-0630 Attorney Nicholas J. Scobbo, Jr.
Ferriter, Scobbo, Caruso, Rodophele, PC
'75 State Street,7th Floor Boston, MA 02109 Mr. D. B. Amerine Vice President - Engineering Services Northeast Nuclear Energy Company P. O. Box 128 1
Waterford, CT 06385 Mr. D. A. Smith Manager - Regulatory Affairs j
Northeast Nuclear Energy Company P. O. Box 128
]
1 Waterford, CT 06385
R. Necci 2
the chemistries provided in the applicable topical report, and provide the impact of any changes to the best-estimate chemistnes for your beltline RPV welds on the structuralintegrity 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 basis for your plant.
You provided your response to the staff's RAI for Millstone Unit 2 on July 15,1998. 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 RVlO are 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.
This closes the staff's efforts in regard to TAC Nos. M92697 and MA0553. The staff appreciates your efforts in regard to this matter.
Sincerely, I)4Wb
. R nald B. Eaton, Sr. Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
~
Docket No. 50-336
' cc: See next page 1
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