ML20216E232
| ML20216E232 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 07/26/1999 |
| From: | Wang A NRC (Affiliation Not Assigned) |
| To: | Ted Sullivan BOSTON EDISON CO. |
| References | |
| GL-92-01, TAC-MA1206, NUDOCS 9908020188 | |
| Download: ML20216E232 (5) | |
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\\.....[t WASHINGTON, D.C. 20555 4 001 July 26,1999 Mr. Theodore A. Sullivan Vice President Nuclear and Station Director Boston Edison Company Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360
SUBJECT:
GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR PILGRIM NUCLEAR POWER STATION (TAC NO. MA1206)
Dear Mr. Sullivan:
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) 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 17,1995, Boston Edison Company (BECo/ licensee) submitted the initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for the Pilgrim Nuc! ear Power Station (Pilgrim). The staff evaluated BECo's response to GL 92-01, Rev.1, Supp.1, and provided its conclusion to your response on December 16,1996. 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 alloyir.g 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.
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l On May 14,1998, the staff issued a request for additional information (RAl) in regard to the alloying chemistries of beltline welds, BECo's assessment of surveillance data for Pilgrim, and j
their impact to pressure-temperature (P-T) limits for Pilgrim. In general, with respect to the l
contents of the RAl, the staff requested that BECo reassess the alloying chemistries for the 020128 L900020188 990726 D
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T. Sullivan beltline welds and RPV surveillance welds relative to the chemistries provided in Topical Reports CE NPSD-1039, Revision 2 and CE NPSD-1119, Revision 1, and provide the impact of any changes to the best-estimate chemistries for the beltline RPV welds on the structural integrity assessments for Pilgrim 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 the plant.
BECo provided a response to the staff's RAI on August 6,1998. 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. It should be noted that there are some variations in the data inputted by the staff, and the corresponding values reported by you in your response to the GL 92-01, Rev.1, Supp.1 RAI. The deviations between the data are explained in the reference sections for each Unit, or the individual component screen notes (i.e., each forging, plate, and weld has a specific area for notes which is a new feature of the database). They are summarized as follows:
In BECo's response to GL 92-01, Rev.1, Supp.1 dated August 6,1998, you reported thst the unirradiated RT value for the weld fabricated with weld wire heat number 21935 is -68 *F.
uor We did not include the lower value of unirradiated RTuor in the RVID because the new value cannot be substantiated. This decision has no impact on the current P/T limits because this weld is not the limiting material.
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 BECo 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 Pilgrim. No additional information is necessary with regard to the structuralintegrity 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. MA1206. The staff appreciates your efforts in regard to this matter.
Sincerely,
% Wav Alan B. Wang, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation cc: See next page L__
July 26, 1999 T Sulliv:n * '
beltline welds and RPV surveillance welds relative to the chemistries provided in Topical Reports CE NPSD-1039, Revision 2 and CE NPSD-1119, Revision 1, and provide the impact of any changes to the best-estimate chemistries for the beltline RPV welds on the structural integrity assessments for Pilgrim 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 the plant.
BECo provided a response to the staff's RAI on August 6,1998. 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 It should be noted that there are some variations in the data inputted by the staff, and the corresponding values reported by you in your response to the GL 92-01, Rev.1, Supp.1 RAl. The deviations between the data are explained in the reference sections for each Unit, or the individual component screen notes (i.e., each forging, plate, and weld has a specific area for notes which is a new feature of the database). They are summarized as follows:
In BECo's response to GL 92-01, Rev.1, Supp.1 dated August 6,1998, you reported that the unirradiated RTuoy value for the weld fabricated with weld wire heat number 21935 is -68 *F.
We did not include the lower value of unirradiated RTuor in the RVID because the new value I
cannot be substantiated. This decision has no impact on the current P/T limits because this weld is not the limiting niaterial.
The new database diskettes are posted on the world-wide-web at a location which is linked to l
the NRC home page (http://www.ntc. gov /NRR/RVID/index.html). We recommend that BECo 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 Pilgrim. No additional 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. MA1206. The staff appreciates your efforts in regard to this matter.
Sincerely, Original signed by:
Alan B. Wang, Project Manager, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation cc: See next page DISTRIBUTION:
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Docket Files PUBLIC ACRS PDl-2 r/f T. Clark C. Andersen, RI A. Wang OGC DOCUMENT NAME: G:\\PDI 2\\ Pilgrim \\gl9201.wpd TO receive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with rttachment/ enclosure "N" = No copy 0FFICE PM:PDI 2 lE LA:PDI-2, pg l6 SC:PQ/2 l
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NAMF AWang QM TClark M"
JC11fYord DATE 07/ h/99 07//b/99 07/1)* 99 Official Record Copy
e Pilgrim Nuclear Power Station cc:
Mr. Ron Ledgett Mr. C. Stephen Brennion Executive Vice President Acting Licensing Division Manager 800 Boyleston Street Boston Edison Company Boston, MA 02199 600 Rocky Hill Road Plymouth, MA 02360-5599 Resident inspector U. S. Nuclear Regulatory Commission Mr. vack Alexander Pilgrim Nuclear Power Station Manager, Reg. Relations and Post Office Box 867 Ouality Assurance Plymouth, MA 02360 Pilgrim Nuclear Power Station 600 Rocky Hill Road Chairman, Board of Selectmen Plymouth, MA 02360-5599 11 Lincoln Street Plymouth, MA 02360 Mr. David F. Tarantino Nuclear Information Manager Chairman, Duxbury Board of Selectmen Pilgrim Nuclear Power Station Town Hall 600 Rocky Hill Road 878 Tremont Street Plymouth, MA 02360-5599 Duxbury, MA 02332 Ms. Kathleen M. O'Toole Office of the Commissioner Secretary of Public Safety Massachusetts Department of Executive Office of Public Safety Environmental Protection One Ashburton Place One Winter Street Boston, MA 02108 Boston, MA 02108 Mr. Peter LaPorte, Director Office of the Attorney General Attn: James Muckerheide One Ashburton Place Massachusetts Emergency Management 20th Floor Agency Boston, MA 02108 400 Worcester Road P.O. Box 1496 Mr. Robert M. Hallisey, Director Framingham, MA 01701-0317 Radiation Control Program Massachusetts Department of Chairman, Citizens Urging Public Health Responsible Energy 305 South Street P.O. Box 2621 Boston, MA 02130 Duxbury, MA 02331 Regional Administrator, Region l Citizens at Risk U. S. Nuclear Regulatory Commission P.O. Box 3803 475 Allendale Road Plymouth, MA 02361 King of Prussia, PA 19406 John M. Fulton Assistant General Counsel Boston Edison Company 800 Boyleston St.,36th Floor Boston, MA 02199
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' Chairman Ms. Mary Lampert. Director Nuclear Matters Committee Massachusetts Citizens for Safe Energy Town Hall 148 Washington Street 11 Lincoln Street Duxbury, MA 02332 Plymouth, MA 02360 Mr. William D. Meinert Nuclear Engineer Massachusetts Municipal Wholeca!e Electric Company P.O. Box 426 Ludlow, MA 01056-0426 l
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