ML17265A695
| ML17265A695 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/06/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| References | |
| GL-92-01, GL-92-1, TAC-MA0546, TAC-MA546, NUDOCS 9907120255 | |
| Download: ML17265A695 (6) | |
Text
gfkIt RE0(
O ce n
++*++
Dr. Robert C. Mecr'edy Vice President, Nuclear Operations Rochester Gas and Electric Corporation 89 East Avenue Rochester, NY 14649 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-(001 July 6, 1999
SUBJECT:
CLOSURE OF TAC NO. MA0546-RESPONSE TO THE REQUESTS FOR ADDITIONALINFORMATIONTO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, "REACTOR VESSEL STRUCTURAL INTEGRITY,"FOR THE R. E. GINNA NUCLEAR POWER PLANT
Dear Dr. Mecredy:
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 ofFederal Regulations (Appendices G and H to 10 CFR Part 50).
CS1)>
On August 11, 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 R. E.
Ginna Nuclear Plant. The staff evaluated your response to GL 92-01, Rev. 1, Supp. 1, anrl provided its conclusion relative to your response on August 1, 1996. iHowever, since the time of the staff's closure letter, the Combustion Engineering (CE) Owners Group and the Babcock and Wilcox (B8W) Owners Group have each submitted additional data regarding the alloying chemistiies of beltline welds in CE and B&Wfabricated vessels.
The additional alloying data were submitted in Topical Reports CE NPSD-1039, Revisiorl 2, CE NPSD-1119, Revision 1, for CE fabricated RPV welds, and BAW-2325, Revision 1, for BKWfabricated 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 88W, the staff determined that additional information was necessary relative to the structural integrity assessments for your plants.
On April3, 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 the R. E. Ginna Nuclear Plant.
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 9'g)07i 20255 gI'g)0706 PDR ADOCK 05000244 P
R. Mecredy duly 6, 1999 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 the R. E, Ginna Nuclear Plant on August 25, 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/RVIDfindex.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 No. MA0546. The staff appreciates your efforts in regard to this matter.
Sincerely, or iginal signed by:
Guy S. Vissing, Senior Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear'Reactor Regulation Docket No. 50-244 cc: See next page DISTRIBUTION:
Docket File S. Little PUBLIC G. Vissing PDI-1 R/F OGC ACRS M. Oprendek A. Lee DOCUMENT NAME: GAPDI-1>GINNAFMPAM0546.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 PH: PDI -I E
LA:PDI-1 SC: PDI-1 GV1ssing/rsl DATE 07/
/99 SLittl 07/
/99 SBa3wa 077
/99 Official Record Copy
R. Mecredy 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 the R. E. Ginna Nuclear Plant on August 25, 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 No. MA0546. The staff appreciates your efforts in regard to this matter.
Sincerely, Guy S. Vissing, Senior Pro ect Manager, Section 1
Project Directorate I
Division of Licensing Project Management
'ffice of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page
R.E. Ginna Nuclear Power Plant Peter D. Drysdale, Sr. Resident Inspector R.E. Ginna Plant U.S. Nuclear Regulatory Commission 1503 Lake Road Ontario, NY 14519 Regional Administrator, Region I
U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Charles Donaldson, Esquire Assistant Attorney General New York Department of Lalw 120 Broadway New York, NY 10271 Nicholas S. Reynolds Winston 8 Strawn 1400 S Street N.W.
Washington, DC 20005-3502 Ms. Thelma Wideman, Director Wayne County Emergency Management Office Wayne County Emergency Operations Center 7336 Route 31 Lyons, NY 14489 Ms. Mary Louise Meisenzahl Administrator, Monroe County Office of Emergency Preparedness 111 West Falls Road, Room 11 Rochester, NY 14620 Mr. Paul Eddy New York State Department of Public Service 3 Empire State Plaza, 10th Floor Albany, NY 12223
l'
4 e
R. Mecredy Ouly 6, 1999 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 the R. E. Ginna Nuclear Plant on August 25, 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 No. MA0546. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by:
Guy S. Vissing, Senior Project Manager, Section 1
Project Directorate I
Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-244 cc: See next page DISTRIBUTION:
Docket File PUBLIC PDI-1 R/F S. Little G. Vissing OGC ACRS M. Oprendek A. Lee DOCUMENT NAME: GAPDI-15GINNAEMPAM0546.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 PH: PDI-I E
LA:PDI-1 SC: PDI-1 DATE GVissing/rsl 07/
/99 SLitt1 07/
/99 SBajwa 07/
/99 Official Record Copy