ML101890664: Difference between revisions

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| issue date = 07/14/2010
| issue date = 07/14/2010
| title = Request for Additional Information Regarding Relief Request I3R-13, Pressure Testing of Primary Containment Instrument Gas Piping
| title = Request for Additional Information Regarding Relief Request I3R-13, Pressure Testing of Primary Containment Instrument Gas Piping
| author name = Bamford P J
| author name = Bamford P
| author affiliation = NRC/NRR/DORL/LPLI-2
| author affiliation = NRC/NRR/DORL/LPLI-2
| addressee name = Pacilio M J
| addressee name = Pacilio M
| addressee affiliation = Exelon Nuclear
| addressee affiliation = Exelon Nuclear
| docket = 05000352, 05000353
| docket = 05000352, 05000353
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==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==
By letter dated January 22,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.
By letter dated January 22,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.
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 July 6, 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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6, 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. 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  
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 July 6, 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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6, 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. 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-13 PRESSURE TESTING OF PRIMARY CONTAINMENT INSTRUMENT GAS PIPING DOCKET NOS. 50-352 AND 50-353 By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 100261546), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request for Limerick Generating Station, 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 IWD-2500-1, as referenced by paragraph IWD-5210, concerning a system leakage test with a VT-2 visual examination.
As stated cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION LIMERICK GENERATING STATION, UNITS 1 AND 2 RELIEF REQUEST 13R-13 PRESSURE TESTING OF PRIMARY CONTAINMENT INSTRUMENT GAS PIPING DOCKET NOS. 50-352 AND 50-353 By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request for Limerick Generating Station, 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 IWD-2500-1, as referenced by paragraph IWD-5210, concerning a system leakage test with a VT-2 visual examination.
The proposed alternative would apply to the Primary Containment Instrument Gas (PCIG) piping, as specified in the submittal. The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. For the proposed alternative pressure decay test, what would be an acceptable rate of pressure loss above which the licensee would initiate leak detection and perform necessary corrective action to repair/replace any leakage in the piping? What is the operating pressure for the PCIG piping to which the piping is required to be pressurized during system leakage test?
The proposed alternative would apply to the Primary Containment Instrument Gas (PCIG) piping, as specified in the submittal. The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. For the proposed alternative pressure decay test, what would be an acceptable rate of pressure loss above which the licensee would initiate leak detection and perform necessary corrective action to repair/replace any leakage in the piping? What is the operating pressure for the PCIG piping to which the piping is required to be pressurized during system leakage test?
Enclosure July 14, 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 -
Enclosure July 14, 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 -
Line 32: Line 32:


==Dear Mr. Pacilio:==
==Dear Mr. Pacilio:==
By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.
By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.
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 July 6, 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 July 6, 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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6,2010. 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.
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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6,2010. 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.
Line 40: Line 40:
As stated cc w/encl:
As stated cc w/encl:
Distribution via Listserv DISTRIBUTION:
Distribution via Listserv DISTRIBUTION:
PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDciCvib Resource PPatnaik, NRR RidsRgn1MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number' ML 101890664
PUBLIC RidsOgcRp Resource LPLI-2 R/F RidsAcrsAcnw_MailCTR Resource RidsNrrDciCvib Resource PPatnaik, NRR RidsRgn1MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number' ML101890664
* concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CSGB/BC LPL1-2/BC NAME PBamford ABaxter (SUttle for) RTaylor* HChernoff DATE 07/08/2010 07/12/2010 07/06/2010 07/14/2010 OFFICIAL RECORD COPY}}
* concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CSGB/BC LPL1-2/BC NAME PBamford ABaxter (SUttle for) RTaylor* HChernoff DATE 07/08/2010 07/12/2010 07/06/2010 07/14/2010 OFFICIAL RECORD COPY}}

Revision as of 06:53, 11 July 2019

Request for Additional Information Regarding Relief Request I3R-13, Pressure Testing of Primary Containment Instrument Gas Piping
ML101890664
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 07/14/2010
From: Peter Bamford
Plant Licensing Branch 1
To: Pacilio M
Exelon Nuclear
Bamford, Peter J., NRR/DORL 415-2833
References
TAC ME3141, TAC ME3142
Download: ML101890664 (3)
v • d • e


Text

UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 J u 1 y 14, 201 0 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 REGARDING RELIEF REQUEST 13R-13, PRESSURE TESTING OF PRIMARY CONTAINMENT INSTRUMENT GAS PIPING (TAC NOS. ME3141 AND ME3142)

Dear Mr. Pacilio:

By letter dated January 22,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.

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 July 6, 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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6, 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. 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-13 PRESSURE TESTING OF PRIMARY CONTAINMENT INSTRUMENT GAS PIPING DOCKET NOS. 50-352 AND 50-353 By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), Exelon Generation Company, LLC (Exelon, the licensee) submitted a relief request for Limerick Generating Station, 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 IWD-2500-1, as referenced by paragraph IWD-5210, concerning a system leakage test with a VT-2 visual examination.

The proposed alternative would apply to the Primary Containment Instrument Gas (PCIG) piping, as specified in the submittal. The Nuclear Regulatory Commission staff has been reviewing the submittal and has determined that additional information is needed to complete its review. For the proposed alternative pressure decay test, what would be an acceptable rate of pressure loss above which the licensee would initiate leak detection and perform necessary corrective action to repair/replace any leakage in the piping? What is the operating pressure for the PCIG piping to which the piping is required to be pressurized during system leakage test?

Enclosure July 14, 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 REGARDING RELIEF REQUEST 13R-13, PRESSURE TESTING OF PRIMARY CONTAINMENT INSTRUMENT GAS PIPING (TAC NOS. ME3141 AND ME3142)

Dear Mr. Pacilio:

By letter dated January 22, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML100261546), 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," concerning a system leakage test with a VT-2 visual examination for the Primary Containment Instrument Gas (PCIG) piping.

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 July 6, 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. In a teleconference with Mr. Loomis on July 8, 2010, it was agreed that a response to this RAI would be submitted by August 6,2010. 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, Ira! 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 PPatnaik, NRR RidsRgn1MailCenter Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl1-2 Resouce RidsNrrPMLimerick Resource RidsNrrLAABaxter Resource ADAMS Accession Number' ML101890664

  • concurrence via email OFFICE LPLI-2/PM LPLI-2/LA CSGB/BC LPL1-2/BC NAME PBamford ABaxter (SUttle for) RTaylor* HChernoff DATE 07/08/2010 07/12/2010 07/06/2010 07/14/2010 OFFICIAL RECORD COPY
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