ML20210K522
| ML20210K522 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/04/1999 |
| From: | Wetzel B NRC (Affiliation Not Assigned) |
| To: | Sellman M WISCONSIN ELECTRIC POWER CO. |
| References | |
| GL-92-01, TAC-MA0564, TAC-MA0565, NUDOCS 9908060153 | |
| Download: ML20210K522 (5) | |
Text
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i UNITED STATES y
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NUCLEAR REGULATORY COMMISSION t,
WASHINGTON, D.C. 2006H001 August 4, 1999 l
Mr. Michael B. Sellman Senior Vice President and Chief Nuclear Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, WI 53201
SUBJECT:
POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 - RESPONSE TO THE REQUESTS FOR INFORMATION IN GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NOS. MA0564 AND MA0565 )
Dear Mr. Sellman:
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 stsff 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) 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 10 CFR Part 50).
On August 16,1995, you submitted your initial response to GL 92-01, Rev.1, Supp.1, and provided the requested information relative to the structural integrity assessments for Point Beach Nuclear Plant 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 August 19,1996. 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, i
Revision 1 for CE-fabricated RPV welds, and BAW-2325, Revision 1 for B&W-fabricated RPV O
welds. As a result of the efforts by'CE and B&W, the riaff determined that additional information was necessary relative tb the structural integrity assessments for your plants.
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On September 28,1998, you provided your final response to the staff regarding your assessment of the information in the topical reports noted above. 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 additional information in your September 28,1998 letter, the staff has revised the information in the OG0022 ER8 I8MA M888$66 S MF[$B @M P
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M. Sellman Reactor Vessel integrity Database (RVID) and is releasing it as RVID Version 2. It should be noted, however, that potential discrepancies related to the fluences assigned for the surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1 report were discovered during the staffs review of R.E. Ginna. The fluence values recorded for these data points (which you utilized in your evaluation of the Point Beach Unit i vessel) and the assessment of the Point Beach Unit 1 weld in the RVID use what the staff believes to be the most accurate and up-to-date information. While this updated information resulted in a not increase in the RTers value for the Point Beach Unit 1 weld manufactured from weld wire heat 61782, it remains a nonlimiting material.
The new RVID database diskettes are posted on the World Wide Web at a location that 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 pressure-temperature (P-T) limits, pressurized thermal shock (PTS), or upper-shelf energy should reference the most current information.
This closes the staffs efforts in regard to TAC Nos. MA0564 and MA0565. The staff appreciates your efforts in regard to this matter.
Sincerely, u h.
Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate lil Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page J
5 Mr. Michael B. Sellman Point Beach Nuclear Plant Wisconsin Electric Power Company Units 1 and 2 cc:
Mr. John H. O'Neill, Jr.
Ms. Sarah Jenkins Shaw, Pittman, Potts & Trowbridge Electric Division 2300 N Street, NW Public Service Commission of Wisconsin Washington, DC 20037-1128 P.O. Box 7854 Madison, Wisconsin 53707-7854 Mr. Richard R. Grigg President and Chief Operating Officer Wisconsin Electric Power Company 231 West Michigan Street Milwaukee, Wisconsin 53201 Mr. Mark E. Reddemann i
Site Vice President Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Mr. Ken Duveneck Town Chairman Town of Two Creeks 13017 State Highway 42 Mishicot, Wisconsin 54228 Chairman Public Service Commission of Wisconsin P.O. Box 7854 Madison, Wisconsin 53707-7854 Regional Administrator, Region lll U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Resident inspector's Office U.S. Nuclear Regulatory Commission 6612 Nuclecr Road Two Rivers, Wisconsin 54241 October 1994 u
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-p M. Sellmarr
-2' August 4, 1999 Reactor Vessel integrity Database (RVID) and is releasing it as RVID Version 2. It should be
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noted, however, that potential discrepancies related to the fluences assigned for the surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1 report were discovered during the staff's review of R.E. Ginna. The fluence values' recorded for these data points (which you utilized in your evaluation of the Point Beach Unit 1 vessel) and the assessment of the Point Beach Unit 1 weld in the RVID use what the staff believes to be the most accurate and up-to-date information. While this updated information resulted in a net increase in the RTp1, value for the Point Beach Unit 1 weld manufactured from weld wire heat 61782, it remains a nonlimiting material.
' The new RVID database diskettes are posted on the World Wide Web at a location that 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 pressure-temperature (P-T) limits, pressurized thermal shock (PTS), or upper-shelf energy should reference the most current information.
This closes the staff's efforts in regard to TAC Nos. MA0564 and MA0565. The staff appreciates your efforts in regard to this matter.
Sincerely, Original signed by.
Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Reg,ulation Docket Nos. 50-266 and 50-301
. cc: See next page DISTRIBUTION Docket File PUBLIC
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7/ 7 /99 M 7/ 8 /99 W // /96 '
OFFICIAL FgCORD COPY
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M. Cellman August 4, 1999 Reactor Vessel Integrity Database (RVID) and is releasing it as RVID Version 2. It should be noted, however, that potential discrepancies related to the fluences assigned for the surveillance capsule data (weld wire heat 61782) in the BAW-2325, Revision 1 report were discovered during the staff's review of R.E. Ginna. The fluence values recorded for these data j
points (which you utilized in your evaluation of the Point Beach Unit 1 vessel) and the assessment of the Point Beach Unit 1 weld in the RVID use what the staff believes to be the most accurate and up-to-date information. While this updated information resulted in a net increase in the RTns value for the Point Beach Unit 1 weld manufactured from weld wire heat 61782, it remains a nonlimiting material.
The new RVID database diskettes are posted on the World Wide Web at a locction that is i
linked to the NRC home page (http /www.nrc. gov /NRR/RVID/index.html). We recommend
/
l that you review this information. If the staff does not receive comments by September 1,1999, l
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 pressure-temperature (P-T) limits, pressurized thermal shock (PTS), or upper-shelf energy should reference the most current information.
This closes the staff's ef* orts in regard to TAC Nos. MA0564 and MA0565. The staff appreciates your efforts in regard to this matter.
Sincerely, Original signed by:
l Beth A. Wetzel, Senior Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management l
Office of Nuclear Reactor Regulation Docket Nos. 50-266 and 50-301 cc: See next page DISTRIBUTION Docket File l
PUBLIC OGC ACRS GGrant, Rlli CCraig/CThomas ADLee, EMCB MMitchell, EMCB DOCUMENT NAME: G':\\PDill-1\\PTBEACH\\Ltra0564.wp OFFICE PM:LPD3d 1L LA:LPD4 E /
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,NAME BWetzel C CJamersorriX KV6cfirnan d'LCCraig "Wff DATE 7/ 7 /99 7/ 1 /99 N' 7/ 8 /99 9/ // /9f '
OFFICIAL $ORD COPY
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