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| issue date = 04/27/2011 | | issue date = 04/27/2011 | ||
| title = Acceptance Review Amendment Concerning Reactor Coolant System Leakage Instrumentation | | title = Acceptance Review Amendment Concerning Reactor Coolant System Leakage Instrumentation | ||
| author name = Brown E | | author name = Brown E | ||
| author affiliation = NRC/NRR/DORL/LPLIII-2 | | author affiliation = NRC/NRR/DORL/LPLIII-2 | ||
| addressee name = Pacilio M | | addressee name = Pacilio M | ||
| addressee affiliation = Exelon Nuclear | | addressee affiliation = Exelon Nuclear | ||
| docket = 05000237, 05000249 | | docket = 05000237, 05000249 | ||
| Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 27, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 LASALLE COUNTY STATION, UNITS 1 AND 2 -ACCEPTANCE REVIEW FOR AMENDMENT CONCERNING REACTOR COOLANT SYSTEM LEAKAGE INSTRUMENTION (TAC NOS. ME5978 AND ME5979}(RS-11-036) | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 27, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555 | ||
==SUBJECT:== | |||
LASALLE COUNTY STATION, UNITS 1 AND 2 -ACCEPTANCE REVIEW FOR AMENDMENT CONCERNING REACTOR COOLANT SYSTEM LEAKAGE INSTRUMENTION (TAC NOS. ME5978 AND ME5979}(RS-11-036) | |||
==Dear Mr. Pacilio:== | ==Dear Mr. Pacilio:== | ||
By letter dated April 4, 2011 (Agencywide Document Access Management System (ADAMS) Accession No. | |||
The proposed change will adopt the U.S. Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs), must fully describe the changes requested, and follow, as far as applicable, the form prescribed for original applications. | By letter dated April 4, 2011 (Agencywide Document Access Management System (ADAMS) | ||
Section 50.34 of 10 CFR addresses the content of technical information required. | Accession No. ML110960216), Exelon Generation Company, LLC submitted a license amendment for LaSalle County Station, Units 1 and 2. The proposed amendment would revise the Technical Specifications (TSs) to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status and establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable. The proposed change will adopt the U.S. Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." | ||
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs), must fully describe the changes requested, and follow, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations. | ||
The results of this review were previously communicated to Mr. Jeff Hansen by electronic mail on April 14, 2011. The purpose of this letter is to formally provide the final results of the NRC staffs acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | The results of this review were previously communicated to Mr. Jeff Hansen by electronic mail on April 14, 2011. The purpose of this letter is to formally provide the final results of the NRC staffs acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. | ||
M. Pacilio The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | |||
If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | M. Pacilio -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. If you have any questions regarding this matter, I may be reached at 301-415-2315. | ||
If you have any questions regarding this matter, I may be reached at 301-415-2315. | Sincerely, IRAJ Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv | ||
Sincerely, IRAJ Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv M. Pacilio -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. | |||
If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. | M. Pacilio -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. If you have any questions regarding this matter, I may be reached at 301-415-2315. | ||
If you have any questions regarding this matter, I may be reached at 301-415-2315. | Sincerely, IRA! | ||
Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv DISTRIBUTION: | Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv DISTRIBUTION: | ||
PUBLIC LPL3-2 RlF RidsNrrDorlLpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No.: | PUBLIC LPL3-2 RlF RidsNrrDorlLpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No.: ML111050459 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME EBrown SRohrer RCarlson DATE 4/19/11 4/19/11 4/27/11 OFFICIAL RECORD COpy}} | ||
Latest revision as of 00:54, 13 November 2019
| ML111050459 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/27/2011 |
| From: | Ellen Brown Plant Licensing Branch III |
| To: | Pacilio M Exelon Nuclear |
| Brown Eva, NRR/DORL, 415-2315 | |
| References | |
| TAC ME5978, TAC ME5979, RS-11-036 | |
| Download: ML111050459 (3) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 27, 2011 Mr. Michael J. Pacilio President and Chief Nuclear Officer Exelon Nuclear 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
LASALLE COUNTY STATION, UNITS 1 AND 2 -ACCEPTANCE REVIEW FOR AMENDMENT CONCERNING REACTOR COOLANT SYSTEM LEAKAGE INSTRUMENTION (TAC NOS. ME5978 AND ME5979}(RS-11-036)
Dear Mr. Pacilio:
By letter dated April 4, 2011 (Agencywide Document Access Management System (ADAMS)
Accession No. ML110960216), Exelon Generation Company, LLC submitted a license amendment for LaSalle County Station, Units 1 and 2. The proposed amendment would revise the Technical Specifications (TSs) to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status and establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable. The proposed change will adopt the U.S. Nuclear Regulatory Commission (NRC) approved Technical Specification Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation."
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the TSs), must fully describe the changes requested, and follow, as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.
The results of this review were previously communicated to Mr. Jeff Hansen by electronic mail on April 14, 2011. The purpose of this letter is to formally provide the final results of the NRC staffs acceptance review of this request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed change. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.
M. Pacilio -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. If you have any questions regarding this matter, I may be reached at 301-415-2315.
Sincerely, IRAJ Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor licenSing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv
M. Pacilio -2 The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the NRC staff to complete its technical review, you will be advised by separate correspondence. If you have any questions regarding this matter, I may be reached at 301-415-2315.
Sincerely, IRA!
Eva A. Brown, Senior Project Manager Plant Licensing Branch 111-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-237 and 50-249 cc: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL3-2 RlF RidsNrrDorlLpl3-2 Resource RidsNrrPMDresden Resource RidsNrrLASRohrer Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No.: ML111050459 NRR-106 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME EBrown SRohrer RCarlson DATE 4/19/11 4/19/11 4/27/11 OFFICIAL RECORD COpy