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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 25, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LIMERICK GENERATING STATION, UNITS 1 AND 2 - | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 25, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS. | ||
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS. ME3306 AND ME3307) | ME3306 AND ME3307) | ||
==Dear Mr. Pacilio:== | ==Dear Mr. Pacilio:== | ||
By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. | By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. | ||
The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. | The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." | ||
Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | Please contact me at 301-415-2833, if you have any questions. | ||
The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." Please contact me at 301-415-2833, if you have any questions. | Sincerely, | ||
Sincerely, Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 | ~,~-.: | ||
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 | |||
==Enclosure:== | ==Enclosure:== | ||
As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 RELIEF REQUEST 13R-14 NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS DOCKET NOS. 50-352 AND 50-353 By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. | As stated cc w/encl: Distribution via Listserv | ||
The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. Please expand the synopsis of what inspections have already been performed on the components for which this alternative is requested to include all indications that were found and how these indications were dispositioned. If no indications were found during any inspections, please state so. Please confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) used in Enclosure 2 to 13R-14, "Plant Specific Applicability," are correct and applicable to both LGS Units 1 and 2. The staff notes that some of these values would be expected to be unit, or nozzle-specific. | |||
June 25,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LIMERICK GENERATING STATION, UNITS 1 AND 2 - | REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 RELIEF REQUEST 13R-14 NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS DOCKET NOS. 50-352 AND 50-353 By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. | ||
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS. ME3306 AND ME3307) | : 1. Please expand the synopsis of what inspections have already been performed on the components for which this alternative is requested to include all indications that were found and how these indications were dispositioned. If no indications were found during any inspections, please state so. | ||
: 2. Please confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.) | |||
used in Enclosure 2 to 13R-14, "Plant Specific Applicability," are correct and applicable to both LGS Units 1 and 2. The staff notes that some of these values would be expected to be unit, or nozzle-specific. | |||
June 25,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | |||
==SUBJECT:== | |||
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS. | |||
ME3306 AND ME3307) | |||
==Dear Mr. Pacilio:== | ==Dear Mr. Pacilio:== | ||
By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." Please contact me at 301-415-2833, if you have any questions. | |||
Sincerely, /raJ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 | By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. | ||
The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information." | |||
Please contact me at 301-415-2833, if you have any questions. | |||
Sincerely, | |||
/raJ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353 | |||
==Enclosure:== | ==Enclosure:== | ||
As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | ||
PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDciCvib Resource DWidrevitz, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number: ML101540503 | PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDciCvib Resource DWidrevitz, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number: ML101540503 | ||
* concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CVIB/BC | * concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CVIB/BC LPL1-2/BC NAME PBamford ABaxter MMitchell* HChernoff DATE 06/16/2010 06/23/2010 05/19/2010 06/25/2010 OFFICIAL RECORD COpy}} | ||
HChernoff DATE 06/16/2010 06/23/2010 05/19/2010 06/25/2010 OFFICIAL RECORD COpy}} | |||
Latest revision as of 17:31, 13 November 2019
| ML101540503 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/25/2010 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Pacilio M Exelon Nuclear |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME3306, TAC ME3307 | |
| Download: ML101540503 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 25, 2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 SUB~IECT: LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS.
ME3306 AND ME3307)
Dear Mr. Pacilio:
By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements.
The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information."
Please contact me at 301-415-2833, if you have any questions.
Sincerely,
~,~-.:
Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 RELIEF REQUEST 13R-14 NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS DOCKET NOS. 50-352 AND 50-353 By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements. The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
- 1. Please expand the synopsis of what inspections have already been performed on the components for which this alternative is requested to include all indications that were found and how these indications were dispositioned. If no indications were found during any inspections, please state so.
- 2. Please confirm that the single set of values (e.g., nozzle radii, nozzle thicknesses, etc.)
used in Enclosure 2 to 13R-14, "Plant Specific Applicability," are correct and applicable to both LGS Units 1 and 2. The staff notes that some of these values would be expected to be unit, or nozzle-specific.
June 25,2010 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUEST 13R-14, NOZZLE-TO-VESSEL WELD AND INNER RADII EXAMINATIONS (TAC NOS.
ME3306 AND ME3307)
Dear Mr. Pacilio:
By letter dated February 1, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100330138), Exelon Generation Company, LLC submitted a relief request for Limerick Generating Station (LGS), Units 1 and 2. The request proposes an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Table IWB-2500-1, concerning nozzle-to-vessel weld and nozzle inner radii examination requirements.
The Nuclear Regulatory Commission staff has been reviewing the response and has determined that additional information is needed to complete its review. The specific questions are found in the enclosed request for additional information (RAI). The questions were sent via electronic transmission on June 3, 2010, to Mr. Thomas Loomis, of your staff. The draft questions were sent to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. The draft questions were discussed in a teleconference with your staff on June 16, 2010. It was agreed that a response to this RAI would be submitted by July 30, 2010. If a response is not received by that date, the request will be subject to denial, pursuant to Title 10 of the Code of Federal Regulations, Section 2.108, "Denial of application for failure to supply information."
Please contact me at 301-415-2833, if you have any questions.
Sincerely,
/raJ Peter Bamford, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-352 and 50-353
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDciCvib Resource DWidrevitz, NRR RidsRgn1 MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number: ML101540503
- concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CVIB/BC LPL1-2/BC NAME PBamford ABaxter MMitchell* HChernoff DATE 06/16/2010 06/23/2010 05/19/2010 06/25/2010 OFFICIAL RECORD COpy