ML17191B439
| ML17191B439 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 09/13/1999 |
| From: | Rossbach L NRC (Affiliation Not Assigned) |
| To: | Kingsley O COMMONWEALTH EDISON CO. |
| References | |
| GL-92-01, TAC-MA1186, TAC-MA1187, NUDOCS 9909160079 | |
| Download: ML17191B439 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION Mr. Oliver D. Kingsley, President Nuclear Generation Group Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, IL 60515 WASHINGTON, D.C. 20555-0001 September 13, 1999
SUBJECT:
RESPONSE TO THE REQUESTS FOR ADDITIONAL INFORMATION TO GENERIC LETTER 92-01, REVISION 1, SUPPLEMENT 1 - DRESDEN NUCLEAR POWER STATION, UNITS 2 AND 3 (TAC NOS. MA1186 AND MA1187)
Dear Mr. Kingsley:
On May 19, 1995, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter 92-01, Revision 1, Supplement 1 (GL), "Reactor Vessel Structural Integrity," to holders of nuclear operating licenses. In issuing the GL the staff requested addressees 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 Part 50 of Title 10 of the Code of Federal Regulations (Appendices G and H to 10 CFR Part 50).
On August 17, 1995, you submitted your*initial response to the GL and provided the requested information relative the structural integrity assessment for Dresden Nuclear Power Station, Units 2 and 3. The staff evaluated your response to the GL and provided its conclusion relative to your response on April 24, 1997. However, since the time of the staffs 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&I) boiling water reactor 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 April 30, 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 Dresden station. 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
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- 0. Kingsley 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 Dresden on July 30, 1998. As a result of the staff's review of your responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the 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 October 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 Nos. MA1186 and MA1187. The staff appreciates your efforts in regard to this matter.
Docket Nos. 50-237 and 50-249 cc: See next page Sincerely, Lawrence W. Rossbach, Project Manager, Section 2 Project Directorate Ill Dlvlslo11 of Llcemsl11g Prujet:l Ma11C:1yl::!1111:111t" Office of Nuclear Reactor Regulation
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- 0. Kingsley Commonwealth Edison Company cc:
Commonwealth Edison Company Site Vice President - Dresden 6500 N. Dresden Road Morris, Illinois 60450-9765 Commonwealth Edison Company Dresden Station Manager 6500 N. Dresden Road Morris, Illinois 60450-9765 U.S. Nuclear Regulatory Commission Dresden Resident Inspectors Office 6500 N. Dresden Road Morris, Illinois 60450-9766 Regional Administrator U.S. NRC, Region Ill 801 Warrenville Road Lisle, Illinois 60532-4351 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Chairman Grundy County Board Administration Building 1320 Union Street Morris, Illinois 60450 Document Control Desk-Licensing Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, Illinois 60515 Commonwealth Edison Company Reg. Assurance Manager - Dresden 6500 N. Dresden Road Morris, Illinois 60450-9765 Mr. David Helwig Senior Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515 Dresden Nuclear Power Station Units 2 and 3 Mr. Gene H. Stanley PWR Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515 Mr. Christopher Crane BWR Vice President Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 900 Downers Grove, Illinois 60515 Mr. R. M. Krich Vice President - Regulatory Services Commonwealth Edison Company Executive Towers West Ill 1400 Opus Place, Suite 500 Downers Grove, Illinois 60515 Ms. Pamela B. Stroebel Senior Vice President and General Counsel Commonwealth Edison Company P.O. Box 767 Chk:a90, llllr1ult:; 80090-0707
- 0. Kingsley September 13, 1999 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 staffs RAI for Dresden on July 30, 1998. As a result of the staffs review of your responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the 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 NRG 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 October 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 staffs efforts in regard to TAC Nos. MA 1186 and MA 1187. The staff appreciates your efforts in regard to this matter.
Docket Nos. 50-237 and 50-249 cc: See next page Distribution:
Docket File PDlll r/f ACRS, TE26 A. Lee, 07D4 PUBLIC OGG, 015818 M. Ring, Riii Sincerely, Original signed by:
Lawrence W. Rossbach, Project Manager, Section 2 Project Directorate Ill nivi:::;inn of Licensing Project ManaQement Office of Nuclear Reactor Regulation DOCUMENT NAME: G:\\PDlll-2\\dresden\\MPAa1186.wpd To receive a copy of this document, indic tei the box: "C" 7--.Copy without enclosur
" = Copy with enclosures "N" = No copy OFFICE NAME DATE
'\\.
- 0. Kingsley September 13, 1999 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 staffs RAI for Dresden on July 30, 1998. As a result of the staffs review of your responses to GL 92-01, Revision 1; GL 92-01, Revision 1, Supplement 1; and the 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 October 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 staffs efforts in regard to TAC Nos. MA 1186 and MA 1187. The staff appreciates your efforts in regard to this matter.
Docket Nos. 50-237 and 50-249 cc: See next page Distribution:
Docket File PDlll r/f ACRS, TE26 A. Lee, 07D4 PUBLIC OGC, 015818 M. Ring, Riii Sincerely, Original signed by:
Lawrence W. Rossbach, Project Manager, Section 2 Project Directorate Ill Division of Licensing Project Management Office of Nuclear Reactor Regulation DOCUMENT NAME: G:\\PDlll-2\\dresden\\MPAa1186.wpd
" = Copy with enclosures "N" = No copy OFFICE NAME DATE