ML17146B149
| ML17146B149 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/12/1999 |
| From: | Nerses V NRC (Affiliation Not Assigned) |
| To: | Byram R PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| GL-92-01, TAC-MA1210, TAC-MA1211, NUDOCS 9907220182 | |
| Download: ML17146B149 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.c. 2055&0001 3uly 12, 1999 Mr. Robert G. Byram Senior Vice President - Generation and Chief Nuclear Officer PP8L, Inc 2 North Ninth Street Allentown, PA 18101 SUBJECT'LOSURE OF TAC NOS. MA1210 AND MA1211 - RESPONSE TO THE REQUESTS FOR ADDITIONALINFORMATIONTO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY,"FOR THE SUSQUEHANNA STEAM ELECTRIC STATION (SSES), UNITS 1 AND2
Dear Mr. Byram:
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 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 ofFederal 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 Federal Regulations(Appendices G and H to 10 CFR Part 50).
On August 18, 1995, you submitted your initial response to GL 92-01, Rev. 1, Supp. 1. and provided the requested information refative to the structural integrity assessments for SSES, Units 1 and 2. The staff evaluated your response to GL 92-01, Rev. 1, Supp. 1, and provided its conclusion relative to your response on February 6, 1997.
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&Wfabricated 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&Wfabricated 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 9907220182 990712 PDR ADOCK 05000387 P
R. Byram y 12, 1999 May 7, 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 facilityand pressure-temperature (P-T) limits for the SSES Units 1 and 2.
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 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 facilityrelative to the requirements of,1 0 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 plants.
You provided your response to the staff's RAI for SSES Units 1 and 2 on August 11, 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 or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA1210 and MA1211. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by V,,'.",
Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 cc: See next page DISTRIBUTION:
Docket Files PUBLIC PDI-1 r/f M. O'rien V. Nerses OGC ACRS A. Lee SBajwa M. Oprendek-DOCUMENT NAME: G:)PDI-1>Susq1827GL92-01.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E" = Copy with attachment/enclosure "N" = No co OFF ICE PM: PDI -I E
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R. Byram ly 12, 1999 h
May 7, 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 facilityand pressure-temperature (P-T) limits for the SSES Units 1 and 2. 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 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 licensing bases for your plants.
You provided your response to the staff's RAI for SSES Units 1 and 2 on August 11, 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 RVIDVersion 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 or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA1210 and MA1211. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by V,'.
Victor Nerses, Sr. Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 cc: See next page DISTRIBUTION:
Docket Files PUBLIC PDI-1 r/f M. O'rien V. Nerses OGC ACRS A. Lee SBajwa M. Oprendek DOCUMENT NAME: G:EPDI-1$Susq182)GL92-01.wpd To receive a copy of this document, indicate in the box: "C" = Copy without attachment/enclosure "E"= Copy, with attachment/enclosure "N" = No co OFFICE NAME DATE PH: PDI-I VNe E
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In/'C:PDI-1 SBajwa Official Record Copy
R. Byram May 7, 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 facilityand pressure-temperature (P-T) limits for the SSES Units 1 and 2. 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 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 facilityrelative 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 plants.
You provided your response to the staff's RAI for SSES Units 1 and 2 on August 11, 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 RVIDVersion 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 or upper shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA1210 and MA1211. The staff appreciates your efforts in regard to this matter.
Sincerely, Victor Nerses, Sr. Project Manager, Section1 Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 cc: See next page
I
Susquehanna Steam El
- Station, Units 1 &2 Bryan A. Snapp, Esq.
Assoc. General Counsel PP8L, Inc.
2 North Ninth Street, GENTW3 Allentown, PA 18101-1179 Terry L. Harpster Manager - Nuclear Licensing PPLL, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Director-Bureau of Radiation Protection Pennsylvania Department of.
Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Robert F. Saunders Vice President-Nuclear Site Operations Susquehanna Steam Electric Station Box 467, NUCSA4 Berwick, PA 18603-0035 Mr. Herbert D. Woodeshick-Special Office of the President PP8L, Inc.
Rural Route 1, Box 1797 Berwick, PA 18603-0035 George T. Jones Vice President-Nuclear Engineering 5 Support PPBL, Inc.
2 North Ninth Street, GENA61 Allentown, PA 18101-1179 Dr. Judith Johnsrud National Energy Committee Sierra Club 433 Orlando Avenue State College, PA 16803 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035
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