ML20209D551
| ML20209D551 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/06/1999 |
| From: | Vissing G NRC (Affiliation Not Assigned) |
| To: | James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| GL-92-01, GL-92-1, TAC-MA1190, NUDOCS 9907130161 | |
| Download: ML20209D551 (5) | |
Text
..,
nn UNITED STATES.
4 g
j NUCLEAR REGULATORY COMMISSION I
g WASHINGTON, D.C..mman anaq July 6, 1999 Mr. James Knubel '
Chief Nuclear Officer Power Authority of the State of New York 123 Main Street White Plains, NY 10601
SUBJECT:
CLOSURE OF TAC NO. MA1190 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, _" REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE JAMES A. FITZPATRICK NUCLEAR POWER PLANT
Dear Mr. Knubel:
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 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 FederalRegulations (Appendices G and H to 10 CFR Part 50).
On August 16,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1. and l
provided the requested information relative the structural integrity assessment for the James A.
FitzPatrick Nuclear Plant. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on September 6,1996. 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 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 k
additional information was necessary relative to the structural in+egrity assessments for your D
plants. On June 1,1998, the staff issued a request for additional information (RAl) 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 James A. FitzPatrick Nuclear Plant. In general, with respect to the contents of the RAI, the staff requested that you reassess the alloying chemistries for the Y\\
beltline welds and RPV surveillance welds relative to the chemistries provided in the applicable y topical report, and provide the impact of any changes to the best-estimate chemistries for your l
beltline RPV welds on the structural integrity assessments for your facility relative to the I
l 9907130161 990706 PDR ADOCK 05000333 P
PDR s
J. Knubel
- 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 the James A. FitzPatrick Nuclear Plant on August 31,1998. 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 witn regard to the structuralintegrity 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. MA1190. The staff appreciates your efforts in regard to this matter.
Sincerely, original Signed by:
Guy S. Vissing, Senior Prcject Manager, Section 1 Project Directorate l Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333 cc: See next page DISTRIBUTION:
Docket File S. Little ACRS PUBLIC G. Vissing M. Oprendek PDI-1 R/F OGC A. Lee DOCUMENT NAME: G:\\PDl-1\\FITZ\\MPAM1190.WPD To r ceive a copy of this document, Indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy I
with attachment / enclosure "N" = No copy 0FFICE PM:PDI-1 lE LA:PDI 1 j ()
l SC:PDl 1 f(/h l
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NAME GVissing/rsl Slittle 4V SBajwa F'W DATE 07/ 6 /99 07/ (p /99 07/[j/99 Official Record Copy
)
J. Knubel 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 the James A. FitzPatrick Nuclear Plant on August 31,1998. 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 VesselIntegrity 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, MA1190. The staff appreciates your efforts in regard to this matter.
Sincerely, jf:'; (
Guy. Vissing, Senior Project Manager, Section 1 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-333 cc: See next page
I J. Knubel 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 the James A. FitzPatrick Nuclear Plant on August 31,1998. 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 tbs 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 j
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 regcrd to TAC No. MA1190. The staff appreciates your efforts in regard to this matter.
Sincerely, original signed by:
Guy S. Vissing, Senior Project Manager, Section 1 Project Directorate 1 3
Division of Licensing Project Management i
Office of Nuclear Reactor Regulation I
i Docket No. 50-333 cc: See next page i
& Q ikW Vu u DISTRIBUTION:
Docket File S. Little ACRS PUBLIC G. Vissing M. Oprendek PDI-1 R/F OGC A. Lee DOCUMENT NAME: G:\\PDl-1\\FITZ\\MPAM1190.WPD I
To rece!ve a copy of this document, indicate in the box: *C" = Copy without attachment / enclosure "E" = Copy with ettachment/ enclosure "N" = No copy 0FFICE PM:PDI-l lE LA:PDI 1 A ()
l SC:PDI-1 fp/Jh l
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j NAME GVissing/rsl Slittle {V SBajwa [7 ' W DATE 07/ 4/99 07/(p/99 07/fo/99 Official Record Copy 130020
Jamts A. FitzPatrick Nucisar Pow r PI:nt Mr. Gerald C. Goldstein Mr. F. William Valentino, President Assistant General Counsel New York State Energy, Research, Power Authority of the State and Development Authority of New York Corporate Plaza West 1633 Broadway 286 Washington Avenue Extension New York, NY 10019 Albany, NY 12203-6399 Resident inspector's Office Mr. Richard L. Patch, Director U. S. Nuclear Regulatory Commission Quality Assurance P.O. Box 136 Power Authority of the State Lycoming, NY 13093 of NewYork i
123 Main Street Mr. Harry P. Salmon, Jr.
White Plains, NY 10601 Vice President - Engineering Power Authority of the State Mr. Gerard Goering of NewYork 28112 Bayview Drive 123 Main Street Red Wing, MN 55066 White Plains, NY 10601 Mr. James Gagliardo Ms. Charlene D. Faison Safety Review Committee Director Nuclear Licensing 708 Castlewood Avenue Power Authority of the State Arlington,TX 76012 of NewYork 123 Main Street Mr. Arthur Zaremba, Licensing Manager White Plains, NY 10601 James A. FitzPatrick Nuclear Power Plant Supervisor P.O. Box 41 Town of Scriba Lycoming, NY 13093 Route 8, Box 382 Oswego, NY 13126 Mr. Paul Eddy i
New York State Dept. of Mr. Eugene W. Zeltmann Public Service President and Chief Operating 3 Empire State Plaza,10th Floor Officer Albany, NY 12223 Power Authority of the State of New York Michael J. Colomb 99 Washington Ave., Suite No. 2005 Site Executive Officer Albany, NY 12210-2820 James A. FitzPatrick Nuclear Power Plant P.O. Box 41 Charles Donaldson, Esquire Lycoming, NY 13093 Assistant Attorney General New York Department of Law Mr. Eric Beckjord 120 Broadway 2909 29* St. NW New York, NY 10271 Washington, DC 20008-3416 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406