ML20210N199
| ML20210N199 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 08/09/1999 |
| From: | Wharton L NRC (Affiliation Not Assigned) |
| To: | Gambhir S OMAHA PUBLIC POWER DISTRICT |
| References | |
| GL-92-01, TAC-MA0545, NUDOCS 9908110043 | |
| Download: ML20210N199 (4) | |
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UNITED STATES g
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NUCLEAR REGULATORY COMMISSION U
wasuinovow, o.c. seenwooi August 9, 1999 Mr. S. K. Gambhir -
Division Manager - Nuclear Operations Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 399 Hwy. 75-North of Fort Calhoun Fort Calhoun, NE 68023-0399
SUBJECT:
CLOSURE OF TAC NO. MA0545 - RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1,*
SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY," FOR THE FORT CALHOUN STATION, UNIT 1
Dear Mr. Gambhir:
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 4
(2) to assess the impact of that data on their RPV integrity analyses relative to the requirements of Sections 50.00 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, you submitted your initial response to GL 92-01, Rev.1, Supp.1. and provided the requested information relative to the structural integrity assessment for the Fort Calhoun Station. The staff evaluated your response to GL 92-01, Rev.1, Supp.1, and provided its conclusion relative to your response on August 2,1996. 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 wolds in CE and B&W fabricated vessels. The additiona! alloying data i
were submitted in Topical Reports CE NPSD-1039, Revision 2, CE NPSD-1119, Revision 1, for O
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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 i
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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
- July 23,1998, the staff issued a request for additional information (RAl) in regard to the alloying
/p chemistries of beltline welds, your assessment of surveillance data for your facility, pressure-temperatute (P-T) limits, and pressurized thermal shock (PTS) assessment (only applicable to PWRs) for the Fort Calhoun Station. In general, with respect to the contents of the RAI, the 6
9908110043 990009 PDR ADOCK 05000285 P
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- S. Gambhir 1 August 9, 1999 istaff requested that you reassess tiie alloying chemistries for the beltline welds and RPV l:
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 bettiine RPV welds on the structural integrity assessments for the Fort Calhoun Station 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 RAls for the Fort dalhoun Station on September 28, 1998. As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, i
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 E.
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 RV!D are acceptable for the Fort Calhoun Station. 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. MA0545. The staff appreciates your efforts in regard to this matter.
Sincerely, ORIG L. Rayn. SIGN ED BYard Wharton, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-285 cc: See next page PSTRIBUTION Docket File CMarschall, RGN-IV PUBLIC SRichards PDIV-2 Reading KWichman OGC Aloe ACRS To recews a copy or mis cocumem, incicate c in tne Dox ll OFFICE PDIV-2/PM C PDIV-2/LA C PDIV-2/SC g NAME-arton:rb EPey8nf SDembeM h
DATE 6 / 4 '/99 8 / fo /99 8 / Y'/99 i
DOCUMENT NAME: G:\\PDIV-2\\FortCalhoun\\LTR0545.wpd OFFICIAL RECORD COPY 1 c.om
S. Gambhir - ;
staff requested that you reassess the alloying chemistnes 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 J
on the structural integrity assessments for the Fort Calhoun Station relative to the requirements of 10 CFR 50.60,10 CFR 6161, 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 staffs RAls for the Fort Calhoun Station on September 28, i
1998. As a result of the staffs review of your responses to GL 92-01, Revision 1, GL 92-01, Rev.1, Supp.1, and the Supp.1 RAl, the sta# 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 i
assume that the data entered into the RVID are acceptable for the Fort Cathnun Station. No additional information is necessary with regard to the structural integrity assessments. Future submittais on P-T limits, PTS (only applicable to PWRs), or upper shelf energy (USE) should reference the most current information.
1 This closes the staffs enorts in regard to TAC No. MA0545. The staff appreciates your efforts in regard to this matter.
l Sincerely, L. Raynard Wharton, Project Manager, Section 2 Project Directorate IV & Decommissioning Division of Licensing Project Management ONice of Nuclear Reactor Regulation Docket No. 50-285 cc: See next page
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Ft. Calhoun Station, Unit 1 i
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' Wmston & Strawn
- ATTN: Perry D. Robinson, Esq.
1400 L Street, N.W.
i l.
Washington, DC 20005-3502 l
Mr. Jack Jensen, Chairman i
Washington County Board of Supervisors Blair, Nebraska 68008 Mr. Wayne Walker, Resident inspector
.U.S. Nuclear Regulatory Commission.
Post Office Box 309 Fort Calhoun, Nebraska 68023
' Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Ms. Cheryl Rodgers, LLRW Program Manager Environmental Protection Section i
Nebraska Departmer>t of Health 301 Centennial Mall, South n Neb aska 68509-5007 Mr. J. M. Solymossy Manager-Fort Cainoun Station Omaha Public Power District Fort Calhoun Station FC-1-1 Plant Post Office Box 399.
. Hwy. 75 - North of Fort Calhoun 4
Fort Calhoun, Nebraska 68023 l
Mr. Mark T. Frans i
Manager-Nuclear Licensing L
Omaha Public Power District Fort Calhoun Station FC-2-4 Adm.
Post Office Box 399 Hwy. 75 - North of Fort Calhoun Fort Calhoun, Nebraska 68023-0399 l
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