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{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 June 10, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LIMERICK GENERATING STATION, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2009 Mr. Charles G. Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | ||
ME0742 THROUGH ME0751) | |||
==SUBJECT:== | |||
LIMERICK GENERATING STATION, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. ME0742 THROUGH ME0751) | |||
==Dear Mr. Pardee:== | ==Dear Mr. Pardee:== | ||
By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 1O-year inservice testing interval at Limerick Generating Station, Units 1 and 2. The U.S. Nuclear RegUlatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. | By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 1O-year inservice testing interval at Limerick Generating Station, Units 1 and 2. | ||
Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. | The U.S. Nuclear RegUlatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. These questions were discussed with your staff in a teleconference on June 4,2009, and it was agreed that you would provide responses by July 17,2009. | ||
These questions were discussed with your staff in a teleconference on June 4,2009, and it was agreed that you would provide responses by July 17,2009. Please contact me at 301-415-2833 if you have any questions. | Please contact me at 301-415-2833 if you have any questions. | ||
Sincerely, Peter J. 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 | Sincerely, | ||
£-/iL~'fP Peter J. 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 UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL REGARDING RELIEF REQUESTS ASSOCIATED WITH THIRD INSERVICE TESTING LIMERICK GENERATING STATION, UNITS 1 AND DOCKET NOS. 50-352 AND By letter dated February 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. | As stated cc w/encl: Distribution via Listserv | ||
ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third Inservice Testing (1ST) interval for Limerick Generating Station (LGS), Units 1 and 2. The applicable code for the third interval 1ST program is the American Society of Mechanical Engineers (ASME) [Operation and Maintenance] OM Code, 2004 edition. The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. Request for Relief 11-PRR-1 Rev. 1: A replacement for Code Case OMN-9, Code Case OMN-16, is included in the OMB-2006 addenda, with applicability specified that includes the proposed third 1ST interval code of record, (ASME OM Code, 2004 edition). This code case has been approved for use by the OM Committee with a new expiration date of June 1, 2009, and provides more date references and requirements. Please explain why Code Case OMN-9 was requested to be used instead of Code Case OMN-16, or provide a revised request that references Code Case OMN-16. Request for Relief GVRR-5 Rev. 3: Please discuss why the requirements of ISTC 5221(c) can not be implemented and why relief is not required from the requirements of ISTC 5221(c). Please discuss why the requirements of ISTC 5222 can not be utilized for testing of the identified check valves. | |||
Request for Relief 47-VRR-2 Rev. 0: Please provide a discussion of why relief is required from the identified ASME OM Code requirements for each component identified. The relief request states that reverse flow verification of 47-1(2)-38 is demonstrated by normal control rod motion. Please clarify how scram insertion time testing demonstrates the valve close function required by the ASME OM Code. | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 By letter dated February 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third Inservice Testing (1ST) interval for Limerick Generating Station (LGS), Units 1 and 2. The applicable code for the third interval 1ST program is the American Society of Mechanical Engineers (ASME) [Operation and Maintenance] OM Code, 2004 edition. | ||
Enclosure | The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review. | ||
- | Request for Relief 11-PRR-1 Rev. 1: | ||
Please address how the requirements of ISTC 3100 and ISTC 3310 will be met. | : 1. A replacement for Code Case OMN-9, Code Case OMN-16, is included in the OMB-2006 addenda, with applicability specified that includes the proposed third 1ST interval code of record, (ASME OM Code, 2004 edition). This code case has been approved for use by the OM Committee with a new expiration date of June 1, 2009, and provides more up-to date references and requirements. Please explain why Code Case OMN-9 was requested to be used instead of Code Case OMN-16, or provide a revised request that references Code Case OMN-16. | ||
June 10, 2009 Mr. Charles G. | Request for Relief GVRR-5 Rev. 3: | ||
Pardee President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LIMERICK GENERATING STATION, UNITS 1 AND 2 - | : 1. Please discuss why the requirements of ISTC 5221(c) can not be implemented and why relief is not required from the requirements of ISTC 5221(c). | ||
REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. ME0742 THROUGH ME0751) | : 2. Please discuss why the requirements of ISTC 5222 can not be utilized for testing of the identified check valves. | ||
Request for Relief 47-VRR-2 Rev. 0: | |||
: 1. Please provide a discussion of why relief is required from the identified ASME OM Code requirements for each component identified. | |||
: 2. The relief request states that reverse flow verification of 47-1 (2)-38 is demonstrated by normal control rod motion. Please clarify how scram insertion time testing demonstrates the valve close function required by the ASME OM Code. | |||
Enclosure | |||
-2 | |||
: 3. The relief request states that testing is performed with reactor coolant system pressure greater than or equal to 950 [pounds per square inch gauge] psig. Please address how the requirements of ISTC 3100 and ISTC 3310 will be met. | |||
June 10, 2009 Mr. Charles G. Pardee 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 REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. ME0742 THROUGH ME0751) | |||
==Dear Mr. Pardee:== | ==Dear Mr. Pardee:== | ||
By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 10-year inservice testing interval at Limerick Generating Station, Units 1 and 2. The U.S. Nuclear Regulatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. | |||
Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. | By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 10-year inservice testing interval at Limerick Generating Station, Units 1 and 2. | ||
These questions were discussed with your staff in a teleconference on June 4, 2009, and it was agreed that you would provide responses by July 17, 2009. | The U.S. Nuclear Regulatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. These questions were discussed with your staff in a teleconference on June 4, 2009, and it was agreed that you would provide responses by July 17, 2009. | ||
Please contact me at 301-415-2833 if you have any questions. | Please contact me at 301-415-2833 if you have any questions. | ||
Sincerely, /raJ Peter J. 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 | Sincerely, | ||
/raJ Peter J. 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: | As stated cc w/encl: Distribution via Listserv DISTRIBUTION: | ||
Distribution via Listserv DISTRIBUTION: | PUBLIC RidsNrrPMPBamford Resource RidsNrrLAABaxter Resource LPL1-2 RtF RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl1-2 Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource MOrenak, NRR WPoertner, NRR Accession Number' ML091480003 *concurrence via memo OFFICE LPL 1-2/PM LPL 1-2/LA CPTB/BC LPL 1-2/BC NAME PBamford ABaxter JMcHale* HChernoff DATE 6/4/09 6/10109 05/13/2009 6110109 Official Record Copy}} | ||
PUBLIC RidsNrrPMPBamford Resource RidsNrrLAABaxter Resource LPL1-2 RtF RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl1-2 Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource MOrenak, NRR WPoertner, NRR Accession Number' ML091480003 | |||
*concurrence via memo OFFICE | |||
Latest revision as of 06:21, 14 November 2019
| ML091480003 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 06/10/2009 |
| From: | Peter Bamford Plant Licensing Branch 1 |
| To: | Pardee C Exelon Generation Co, Exelon Nuclear |
| Bamford, Peter J., NRR/DORL 415-2833 | |
| References | |
| TAC ME0742, TAC ME0743, TAC ME0744, TAC ME0745, TAC ME0746, TAC ME0747, TAC ME0748, TAC ME0749, TAC ME0750, TAC ME0751 | |
| Download: ML091480003 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 June 10, 2009 Mr. Charles G. Pardee 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 REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. ME0742 THROUGH ME0751)
Dear Mr. Pardee:
By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 1O-year inservice testing interval at Limerick Generating Station, Units 1 and 2.
The U.S. Nuclear RegUlatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. These questions were discussed with your staff in a teleconference on June 4,2009, and it was agreed that you would provide responses by July 17,2009.
Please contact me at 301-415-2833 if you have any questions.
Sincerely,
£-/iL~'fP Peter J. 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
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 REQUEST FOR ADDITIONAL INFORMATION REGARDING RELIEF REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL LIMERICK GENERATING STATION, UNITS 1 AND 2 DOCKET NOS. 50-352 AND 50-353 By letter dated February 18, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third Inservice Testing (1ST) interval for Limerick Generating Station (LGS), Units 1 and 2. The applicable code for the third interval 1ST program is the American Society of Mechanical Engineers (ASME) [Operation and Maintenance] OM Code, 2004 edition.
The Nuclear Regulatory Commission (NRC) staff has been reviewing the submittal and has determined that additional information is needed to complete its review.
Request for Relief 11-PRR-1 Rev. 1:
- 1. A replacement for Code Case OMN-9, Code Case OMN-16, is included in the OMB-2006 addenda, with applicability specified that includes the proposed third 1ST interval code of record, (ASME OM Code, 2004 edition). This code case has been approved for use by the OM Committee with a new expiration date of June 1, 2009, and provides more up-to date references and requirements. Please explain why Code Case OMN-9 was requested to be used instead of Code Case OMN-16, or provide a revised request that references Code Case OMN-16.
Request for Relief GVRR-5 Rev. 3:
- 1. Please discuss why the requirements of ISTC 5221(c) can not be implemented and why relief is not required from the requirements of ISTC 5221(c).
- 2. Please discuss why the requirements of ISTC 5222 can not be utilized for testing of the identified check valves.
Request for Relief 47-VRR-2 Rev. 0:
- 1. Please provide a discussion of why relief is required from the identified ASME OM Code requirements for each component identified.
- 2. The relief request states that reverse flow verification of 47-1 (2)-38 is demonstrated by normal control rod motion. Please clarify how scram insertion time testing demonstrates the valve close function required by the ASME OM Code.
Enclosure
-2
- 3. The relief request states that testing is performed with reactor coolant system pressure greater than or equal to 950 [pounds per square inch gauge] psig. Please address how the requirements of ISTC 3100 and ISTC 3310 will be met.
June 10, 2009 Mr. Charles G. Pardee 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 REQUESTS ASSOCIATED WITH THE THIRD INSERVICE TESTING INTERVAL (TAC NOS. ME0742 THROUGH ME0751)
Dear Mr. Pardee:
By letter dated February 18, 2009 (Agencywide Documents Access and Management System Accession No. ML090500720), Exelon Generation Company, LLC, submitted a set of relief requests associated with the third 10-year inservice testing interval at Limerick Generating Station, Units 1 and 2.
The U.S. Nuclear Regulatory Commission has determined that a response to the enclosed Request for Additional Information (RAI) is necessary in order for the staff to complete its review. The questions in the enclosure were sent to Mr. Thomas Loomis of your staff via electronic transmission, in draft form, on May 26, 2009. The draft RAI was sent to ensure that the questions were understandable, the regulatory basis was clear and to determine if the information was previously docketed. These questions were discussed with your staff in a teleconference on June 4, 2009, and it was agreed that you would provide responses by July 17, 2009.
Please contact me at 301-415-2833 if you have any questions.
Sincerely,
/raJ Peter J. 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 RidsNrrPMPBamford Resource RidsNrrLAABaxter Resource LPL1-2 RtF RidsRgn1 MailCenter Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsNrrDorlLpl1-2 Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource MOrenak, NRR WPoertner, NRR Accession Number' ML091480003 *concurrence via memo OFFICE LPL 1-2/PM LPL 1-2/LA CPTB/BC LPL 1-2/BC NAME PBamford ABaxter JMcHale* HChernoff DATE 6/4/09 6/10109 05/13/2009 6110109 Official Record Copy