Letter Sequence Request |
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TAC:ME5978, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation (Approved, Closed) |
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MONTHYEARRS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. Project stage: Request ML1110504592011-04-27027 April 2011 Acceptance Review Amendment Concerning Reactor Coolant System Leakage Instrumentation Project stage: Acceptance Review RS-11-123, Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs..2011-08-15015 August 2011 Supplemental Information Related to License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for Rcs.. Project stage: Supplement ML1205901862012-03-0101 March 2012 Correction to Issuance of Amendments Regarding Technical Specifications Task Force (TSTF) Traveler TSTF-475, Revision 3, Revise Boiling Water Reactors Operability Project stage: Approval 2011-04-04
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Category:Letter type:RS
MONTHYEARRS-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-23-120, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-103, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023 Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor RS-23-084, Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-07-24024 July 2023 Response to Request for Additional Information Regarding the Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-037, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2023-02-22022 February 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-22-085, Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis2023-01-12012 January 2023 Application to Revise Design Basis to Allow Use of Plastic Section Properties in Lower Downcomer Braces Analysis RS-23-006, Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023 Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-035, Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0404 March 2022 Supplemental Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-033, Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0303 March 2022 Response to Request for Additional Information Regarding Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-032, Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs2022-03-0202 March 2022 Relief Request I4R-13 Relief from Code Examinations for 1B33-F060A and 1B33-F060B Repairs RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-018, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station2022-02-22022 February 2022 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for LaSalle County Station RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021 Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5 RS-21-109, Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 20212021-10-14014 October 2021 Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 2021 RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-085, Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016)2021-08-17017 August 2021 Response to Request for Additional Information Regarding License Amendment Request to Incorporate Licensing Topical Report NEDE-33885PA, Revision 1, GNF CRDA Application Methodology (EPID-L-2021-LLA-0016) RS-21-064, License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter2021-06-30030 June 2021 License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-055, Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended.2021-05-10010 May 2021 Response to Third Round Request for Additional Information (Rals) for LaSalle License Amendment Request to Adopt Risk Informed Completion Times TSTF- 505, Revision 2, Provide Risk-Informed Extended. RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations RS-21-050, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-16016 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) RS-21-045, Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165)2021-04-0707 April 2021 Response to Request for Additional Information (RAI) Regarding Request for License Amendment Regarding Ultimate Heat Sink (EPID-L-2020-LLA-0165) 2024-06-28
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML23073A2182023-03-22022 March 2023 Issuance of Amendment No. 258 to Renewed Facility Operating Licenses Exigent Amendment to Revise Design Basis Related to Seismic Requirements RS-23-048, Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements2023-03-0707 March 2023 Exigent Amendment Request to Revise Design Basis Related to Seismic Requirements RS-23-006, Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report2023-01-10010 January 2023 Supplemental Information Regarding License Amendment Request Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report ML22332A4492022-11-10010 November 2022 License Amendment Request - Relocation of Pressure and Temperature Limit Curves to the Pressure and Temperature Limits Report RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements ML21277A1932021-11-16016 November 2021 Enclosure 2, Draft Conforming License Amendments RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021 Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5 JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position RS-21-064, License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter2021-06-30030 June 2021 License Amendment Request Re New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies - Cover Letter RS-21-039, Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments2021-03-25025 March 2021 Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments ML21057A2732021-02-25025 February 2021 Application for Order Approving License Transfers and Proposed Conforming License Amendments RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink2020-07-17017 July 2020 Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink RS-20-031, License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process2020-04-30030 April 2020 License Amendment Request - Application to Adopt Technical Specification Task Force (TSTF) Traveler TSTF-568, Revision 2, Revise Applicability of BWR/4 TS 3.6.2 .5 and TS 3.6 .3.2, Using the Consolidated Line Item Improvement Process RS-20-011, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2020-01-31031 January 2020 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b RS-19-044, License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions2019-08-28028 August 2019 License Amendment Request - Deletion of Facility Operating License Conditions Related to Decommissioning Trust Provisions RS-19-069, License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3)2019-08-23023 August 2019 License Amendment Request Supporting Emergency Plan Emergency Action Level Change (EAL RAL3) JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-040, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-06-25025 June 2019 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML19036A5862019-03-21021 March 2019 Issuance of Amendments to Revise the Emergency Response Organization Staffing Requirements RS-19-003, Application to Adopt TSTF-564, Safety Limit Mcpr.2019-02-0101 February 2019 Application to Adopt TSTF-564, Safety Limit Mcpr. RS-18-130, Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2018-11-0101 November 2018 Application to Revise Technical Specifications to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-18-032, Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers2018-04-25025 April 2018 Application to Adopt TSTF-372, Addition of LCO 3.0.8, Inoperability of Snubbers RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator2018-04-19019 April 2018 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator RS-17-161, Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR)2018-03-0101 March 2018 Fleet License Amendment Request to Relocate Technical Specification Unit/Facility/Plant Staff Qualification ANSI N18.1-1971 and ANSl/ANS-3.1-1978 Requirements to the Exelon Quality Assurance Topical Report (QATR) RS-18-023, License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs)2018-02-27027 February 2018 License Amendment Request to Revise the Technical Specifications (TS) Surveillance Requirement (SR) 3.4.4.1 to Revise the Lower Setpoint Tolerances for Safety/Relief Valves (S/Rvs) RS-18-021, Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 Exelon Generation Co, LLC - License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements RS-18-021, License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements2018-01-31031 January 2018 License Amendment Request for Approval of Changes to Emergency Plan EP-AA-1000 Staffing Requirements ML18053A1752018-01-31031 January 2018 Attachment 5A - LaSalle Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1762018-01-31031 January 2018 Attachment 5B - LaSalle Clean Emergency Plan EP-AA-1000 Pages ML18053A1842018-01-31031 January 2018 Enclosure 5 - LaSalle - Evaluation of Proposed Changes RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-01-24024 January 2018 License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-17-127, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-12-13013 December 2017 Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. RS-17-137, Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements2017-11-0808 November 2017 Application to Revise Technical Specifications to Adopt TSTF-551, Revise Secondary Containment Surveillance Requirements RS-17-049, Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process2017-03-28028 March 2017 Application to Revise Technical Specifications to Adopt TSTF-529 Clarify Use and Application Rules, Revision 4, Using the Consolidated Line Item Improvement Process RS-16-225, Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review2016-11-0808 November 2016 Revised Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods and Request for Exigent Review RS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16280A4022016-10-0606 October 2016 License Amendment Request - Supplement Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-198, Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods2016-09-30030 September 2016 Request for License Amendment Regarding High Burnup Atrium-10 Partial Length Fuel Rods ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. ML16036A3482016-02-0505 February 2016 Maintenance of Draft Supplemental Environmental Impact Statement at the Seneca Public Library in Regards to the Review of the LaSalle County Station License Renewal Application (TAC Nos. MF5567 and MF5568) RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings RS-15-305, Corrections to the License Renewal Application Dated December 9, 20142015-12-0202 December 2015 Corrections to the License Renewal Application Dated December 9, 2014 RS-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2015-11-19019 November 2015 Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. RS-15-193, Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application2015-08-0606 August 2015 Responds to NRC Requests for Additional Information, Set 5, Dated July 7, 2015 Related to the License Renewal Application RS-15-221, Revisions to License Renewal Application, Applicant'S Environmental Report - Operating License Renewal Stage2015-07-31031 July 2015 Revisions to License Renewal Application, Applicant'S Environmental Report - Operating License Renewal Stage 2023-05-25
[Table view] Category:Technical Specification
MONTHYEARRS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling ML22332A4512022-11-10010 November 2022 Attachment 3 - Markup of Technical Specification Bases Pages (for Information Only) RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML22111A2572022-04-13013 April 2022 Technical Specification Bases RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-087, Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink2020-07-17017 July 2020 Request for a License Amendment to LaSalle County Station, Units 1 and 2, Technical Specification 3.7.3, Ultimate Heat Sink JAFP-20-0049, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2020-06-22022 June 2020 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-20-029, Technical Specification Bases2020-04-13013 April 2020 Technical Specification Bases RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-19-039, Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls2019-06-26026 June 2019 Fleet License Amendment Request - Common Language for Technical Specification High Radiation Area Administrative Controls RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator2018-04-19019 April 2018 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator RS-18-044, Revised Technical Specification Bases2018-04-11011 April 2018 Revised Technical Specification Bases RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-01-24024 January 2018 License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System RS-16-191, License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies2016-10-26026 October 2016 License Amendment Request to Revise Technical Specifications 5.5.13, Primary Containment Leakage Rate Testing Program, for Permanent Extension of Type a and Type C Leak Rate Test Frequencies ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-080, Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases2016-04-11011 April 2016 Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases RS-15-002, License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating2015-01-12012 January 2015 License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating RS-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.2014-12-22022 December 2014 License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of. RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process RS-12-184, Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 152012-10-11011 October 2012 Request to Revise Technical Specification 2.1.1.2 for Minimum Critical Power Ratio Safety Limit - Cycle 15 RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-02-22022 February 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. ML1003213072010-01-27027 January 2010 Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-10-001, LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-08-132, LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 LaSalle County Station, Units 1 and 2 - Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 RS-08-132, Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 52008-10-23023 October 2008 Transmittal Letter of Additional Information Regarding Request for License Amendment Regarding Application of Alternative Source Term. Attachments 1 - 5 ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses RA-08-047, Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item I2008-06-0909 June 2008 Application for Technical Specification Change Regarding Revision of Control Rod Notch Surveillance Test Frequency, Clarification of SRM Insert Control Rod Action and Clarification of a Frequency Example Using the Consolidation Line Item Im RS-08-045, Technical Specification Bases2008-04-14014 April 2008 Technical Specification Bases RS-07-165, License Amendment Request Regarding Spent Fuel Storage Pool Criticality2007-12-13013 December 2007 License Amendment Request Regarding Spent Fuel Storage Pool Criticality RS-07-069, Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink2007-06-29029 June 2007 Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process RS-07-034, Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection2007-04-0606 April 2007 Additional Information Supporting the License Amendment Request Associated with Revised Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection RS-06-181, Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report2006-12-15015 December 2006 Byron, Dresden, LaSalle, Peach Bottom, and Quad Cities Nuclear Plants, Request for Technical Specification Change to Provide Consistency with EGC Quality Assurance Topical Report RS-06-154, Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program.2006-11-17017 November 2006 Request for Amendment to Technical Specifications Section 5.5.7, Inservice Testing Program. RS-06-089, Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power2006-08-16016 August 2006 Additional Information Supporting the License Amendment Request Associated with Direct Current Electrical Power ML0504902692005-02-0404 February 2005 Request for Change to Technical Specifications Traversing In-core Probe (TIP) System ML0434900702004-12-10010 December 2004 Tech Spec Pages for License Amendments 170 & 156, Pressure-Temperature Limits RS-04-125, Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program2004-11-29029 November 2004 Exelon/Amergen Request for Amendment to Technical Specifications Administrative Controls to Incorporate Requirement for Control Room Envelope Integrity Program RS-04-067, Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process2004-04-30030 April 2004 Amergen, Request for Amendment to Technical Specifications Regarding Mode Change Limitations Using the Consolidated Line Item Improvement Process RS-03-079, Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing2003-05-19019 May 2003 Request for Amendment to Technical Specifications, Surveillance Requirement 3.7.7.1 for Turbine Bypass Valve Testing RS-03-031, Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.82003-04-18018 April 2003 Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.8 RS-03-040, Request for Amendment to Technical Specifications Section 5.7, High Radiation Area.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Section 5.7, High Radiation Area. RS-03-029, Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation.2003-03-31031 March 2003 Request for Amendment to Technical Specifications Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation. ML0234505702002-11-27027 November 2002 Request for Technical Specifications Change to Eliminate Requirements for Post Accident Sampling System Using the Consolidated Line Item Improvement Process RS-02-164, Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program.2002-10-24024 October 2002 Request for Amendment to Technical Specification 5.5.13, Primary Containment Leakage Rate Testing Program. RS-02-110, Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation.2002-07-0808 July 2002 Request for Amendment to Technical Specifications Table 3.3.8.1-1, Loss of Power Instrumentation. RS-02-076, Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-122002-05-31031 May 2002 Request for Amendment to Technical Specifications, Excess Flow Check Valve Testing Surveillance Requirement 3.6.1.3.8 & Relief Request RV-12 2023-05-25
[Table view] Category:Bases Change
MONTHYEARML22332A4512022-11-10010 November 2022 Attachment 3 - Markup of Technical Specification Bases Pages (for Information Only) RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration ML22111A2572022-04-13013 April 2022 Technical Specification Bases RS-20-115, Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2020-11-18018 November 2020 Application to Revise Technical Specifications to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements RS-20-029, Technical Specification Bases2020-04-13013 April 2020 Technical Specification Bases RS-20-009, Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2020-01-31031 January 2020 Application to Revise LaSalle County Station Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b JAFP-19-0067, Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability2019-06-27027 June 2019 Application to Adopt TSTF-427, Revision 2, Allowance for Non Technical Specification Barrier Degradation on Supported System Operability RS-18-028, License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator2018-04-19019 April 2018 License Amendment Request to Remove Operating Mode Restrictions for Performing Surveillance Testing of the Division 3 Battery and High Pressure Core Spray Diesel Generator RS-18-044, Revised Technical Specification Bases2018-04-11011 April 2018 Revised Technical Specification Bases RS-18-009, License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System2018-01-24024 January 2018 License Amendment Request for Temporary Extensions to Technical Specifications Supporting Maintenance on Portions of the Core Standby Cooling System ML16209A2182016-07-26026 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Lnservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing. RS-16-080, Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases2016-04-11011 April 2016 Updated Final Safety Analysis Report (Ufsar), Revision 22, Technical Specification Bases RS-15-002, License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating2015-01-12012 January 2015 License Amendment Request to Revise Technical Specifications Sections 3.5.1, ECCS - Operating RS-14-322, License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of.2014-12-22022 December 2014 License Amendment Request for Addition of New LCO 3.10.8 for Reactor Vessel Hydrostatic and Leak Testing Requirements and for Adoption of TSTF-484, Revision 0, Use Of. RS-14-192, Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process2014-07-14014 July 2014 Application to Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Revision 2, Using the Consolidated Line Item Improvement Process RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-02-22022 February 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. ML1003213072010-01-27027 January 2010 Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-10-001, LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 3 - Markup of Proposed Technical Specifications Bases and Technical Requirements Manual Pages RS-08-045, Technical Specification Bases2008-04-14014 April 2008 Technical Specification Bases RS-07-069, Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink2007-06-29029 June 2007 Request for a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink RS-07-020, Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process2007-04-12012 April 2007 Exelon/Amergen Application to Revise Technical Specifications Regarding Control Room Envelope Habitability in Accordance with TSTF-448, Revision 3, Using the Consolidated Line Item Improvement Process ML0504902692005-02-0404 February 2005 Request for Change to Technical Specifications Traversing In-core Probe (TIP) System RS-03-031, Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.82003-04-18018 April 2003 Request for Amendment to Technical Specifications Surveillance Requirement 3.6.1.3.8 2022-04-13
[Table view] Category:Technical Specifications
MONTHYEARRS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs ML22332A4502022-11-10010 November 2022 Attachment 2 - Markup of Technical Specification Pages ML22090A0862022-04-29029 April 2022 Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V ML21347A0382022-01-13013 January 2022 Issuance of Amendments to Revise Reactor Coolant Leakage Requirements JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position ML21158A2282021-07-13013 July 2021 Issuance of Amendments to Renewed Facility Operating Licenses a License Amendment to Technical Specification 3.7.3, Ultimate Heat Sink ML21265A5362021-06-30030 June 2021 Attachment 2: LaSalle County Station Units 1 & 2 - Proposed Technical Specifications Markups ML21082A4222021-05-27027 May 2021 Issuance of Amendment Nos. 249 and 235 to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems ML21013A0052021-02-0404 February 2021 Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2 RS-20-136, Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018)2020-10-29029 October 2020 Response to Request for Additional Information Re License Amendment Requests for Amendments to Renewed Facility OL to Adopt 10CFR50.69 & to Adopt TSTF-505, Rev. 2 (EPID L-2020-LLA-0017 and EPID-L-2020-LLA-0018) RS-20-016, County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems2020-04-13013 April 2020 County, Nine Mile Point, Peach Bottom Atomic and Quad Cities - Application to Revise Technical Specifications to Adopt TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Systems RS-18-020, Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement2018-06-15015 June 2018 Application to Revise Technical Specifications to Modify the APRM Channel Adjustment Surveillance Requirement RS-17-127, Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-12-13013 December 2017 Submittal of Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. ML17257A3042017-10-30030 October 2017 Non-Proprietary - Issuance of Amendments Request to Revise Suppression Pool Swell Design Analysis and the Facility Licensing Basis ML16259A0592016-10-19019 October 2016 License Appendix a and B RS-16-035, County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings2016-02-0303 February 2016 County, and Quad Cities - Request for License Amendment to Address Secondary Containment Access Openings ML15324A4392015-12-17017 December 2015 Issuance of Amendments (CAC Nos. MF5471-MF5476) RS-15-279, Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2015-11-19019 November 2015 Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. ML15202A5782015-11-19019 November 2015 Issuance of Amendment to Revise the Ultimate Heat Sink Temperature Limits ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training ML14353A0832015-01-29029 January 2015 Issuance of Amendments Revising Peak Calculated Primary Containment Internal Pressure ML14220A5172014-11-25025 November 2014 Issuance of Amendment Revising Pressure and Temperature Limits ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements RS-13-092, License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure2013-09-0505 September 2013 License Amendment Request to Revise Peak Calculated Primary Containment Internal Pressure RS-13-137, Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process2013-09-0303 September 2013 Application to Revise Technical Specifications to Adopt TSTF-522, Revise Ventilation System Surveillance Requirements to Operate for 10 Hours Per Month, Using the Consolidated Line Item Improvement Process RS-11-149, Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit2011-10-12012 October 2011 Request for Technical Specification Change for Minimum Critical Power Ratio Safety Limit RS-11-036, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.2011-04-0404 April 2011 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation. RS-11-014, Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks2011-01-28028 January 2011 Additional Information Supporting License Amendment Request Regarding the Use of Neutron Absorbing Inserts in Unit 2 Spent Fuel Pool Storage Racks ML1018303612010-09-16016 September 2010 License Amendment, Measurement Uncertainty Recapture Power Uprate RS-10-080, License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limit Curves2010-04-19019 April 2010 License Amendment Request Regarding Reactor Coolant System Pressure and Temperature Limit Curves RS-10-015, Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System.2010-02-22022 February 2010 Request for Amendment to Technical Specification 3.1.7, Standby Liquid Control (SLC) System. RS-10-001, LaSalle, Units 1 and 2, Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages2010-01-27027 January 2010 LaSalle, Units 1 and 2, Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages ML1003213062010-01-27027 January 2010 Attachment 2 - Markup of Proposed Operating License and Technical Specifications Pages ML0927202312009-10-0202 October 2009 Correction Letter for License Amendment Nos. 195 and 182, Revise Local Power Range Monitor Calibration Frequency ML0924504042009-09-0303 September 2009 Correction Letter for License Amendment Nos. 193 and 180 Obsolete License Conditions and Revise Technical Specifications RS-09-110, Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications2009-08-11011 August 2009 Additional Information Supporting Request for License Amendment to Delete Obsolete License Conditions and Revise Technical Specifications RS-09-020, Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating.2009-03-26026 March 2009 Request for a License Amendment to Technical Specification 3.5.1, Emergency Core Cooling Systems (ECCS) Operating. ML0823907072008-08-21021 August 2008 Revised T.S. Pages Oyster Creek Nuclear Generating Station and Peach Bottom Atomic Power Station, Unit 3-Correction to Facility Operating Licenses ML0821301362008-07-25025 July 2008 Braidwood/Byron/Clinton/Dresden/Lasalle/Oyster Creek/Peach Bottom/Quad Cities/Three Mile Island - Tech Spec Pages for Amds to Change TS Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators RS-08-091, Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency2008-07-25025 July 2008 Request for a License Amendment to Revise Local Power Range Monitor Calibration Frequency RA-08-024, Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours.2008-04-21021 April 2008 Amergen, Energy LLC, License Amendment Request to Remove References to NRC Generic Letter 82-12, Nuclear Power Plant Staff Working Hours. ML0807303512008-03-10010 March 2008 Tech. Spec. Pages, Issuance of Amendments Revise TS 3.7.5 RS-08-012, Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications2008-02-28028 February 2008 Amergen Company, Request for Amendment to Administrative Controls Section of Technical Specifications ML0733310942007-11-19019 November 2007 Tech Specs for Amendments to Provide Consistency with Quality Assurance Topical Report ML0731003892007-10-31031 October 2007 Technical Specifications, Changes Resulting from the Incorporation of TSTF-448, Control Room Habitability. ML0728907472007-10-12012 October 2007 Technical Specifications, Revise Technical Specifications, Section 5.5.7, Inservice Testing Program. ML0727603342007-09-27027 September 2007 Technical Specifications, Issuance of Amendments Required Action End States Consistent with Technical Specification Task Force TSTF-423 2023-08-30
[Table view] |
Text
n Nuclear RS-11-036 April 4, 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 LaSalle County Station, Units 1 and 2 Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373 and 50-374 10 CFR 50.90
Subject:
License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation" In accordance with 10 CFR 50.90, "Application for amendment of license, construction permit, or early site permit," Exelon Generation Company, LLC (EGC) is submitting a request for an amendment to the Technical Specifications (TS) of Facility Operating License Nos. NPF-11 and NPF-18 for LaSalle County Station, Units 1 and 2 (LSCS). The proposed amendment would revise the TS to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status; establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable; and make TS Bases changes which reflect the proposed changes and more accurately reflect the contents of the facility design basis related to operability of the RCS leakage detection instrumentation.
These changes are consistent with NRC-approved Revision 3 to TSTF Improved Standard Technical Specification (STS) Change Traveler TSTF-514, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." The availability of this TS improvement was announced in the Federal Register on December 17, 2010, (75 FR 79048) as part of the consolidated line item improvement process (CUIP).
- Attachment 1 provides an evaluation of the proposed changes.
- Attachment 2 provides the markup pages of existing TS to show the proposed changes.
- Attachment 3 provides the markup pages of the existing TS Bases to show the proposed changes.
- Attachment 4 provides revised (clean) TS pages. EGC requests approval of the proposed license amendment by April 4, 2012, with the amendment being implemented within 60 days.
U. S. Nuclear Regulatory Commission April 4, 2011 Page 2 In accordance with 10 CFR 50.91(a)(1), "Notice for Public Comment," the analysis about the issue of no significant hazards consideration using the standards in 10 CFR 50.92 is being provided to the NRC. The proposed amendment has been reviewed by the LSCS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the EGC Quality Assurance Program. EGC is notifying the State of Illinois of this application for a change to the TS by sending a copy of this letter and its attachments to the designated State Official in accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b). There are no regulatory commitments contained within this letter. Should you have any questions concerning this letter, please contact Mitchel Mathews at (630) 657-2819.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of April 2011. Attachment 1: Attachment 2: Attachment 3: Attachment 4: Evaluation of Proposed Changes Markup pages of existing TS to show the proposed changes. Markup pages of existing TS Bases to show the proposed changes. Clean TS Pages cc: Illinois Emergency Management Agency -Division of Nuclear Safety ATTACHMENT 1 Evaluation of Proposed Changes
Subject:
License Amendment Request for Adoption of TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation"
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
S
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination 5.2 Applicable Regulatory ReqUirements/Criteria 6.0 ENVIRONMENTAL CONSIDERATION
7.0 REFERENCES
Page 1 of 7
1.0 DESCRIPTION
ATTACHMENT 1 Evaluation of Proposed Changes The proposed amendment would revise the Technical Specifications (TS) to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status; establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable and make conforming TS Bases changes. These changes are consistent with NRC-approved Revision 3 to Technical Specification Task Force (TSTF) Standard Technical Specification (STS) Change Traveler TSTF-514, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." The availability of this TS improvement was announced in the Federal Register on December 17,2010 (75 FR 79048) as part of the consolidated line item improvement process (CUIP).
2.0 PROPOSED CHANGE
S The proposed changes revise and add a new Condition D to TS 3.4.7, "RCS Leakage Detection Instrumentation," and revise the associated bases. New Condition D is applicable when the drywell atmospheric gaseous radiation monitor is the only operable TS-required instrument monitoring RCS leakage, i.e., TS-required particulate, sump, and drywell air cooler condensate flow monitors are inoperable.
New Condition D Required Actions require monitoring RCS leakage by obtaining and analyzing grab samples of the drywell atmosphere every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; monitoring RCS leakage using administrative means every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />; and taking action to restore monitoring capability using another monitor within 7 days. Additionally, the TS Bases, which summarize the reasons for the specifications, are revised to clarify the specified safety function for each required instrument in Limiting Condition for Operation (LCO) Bases, delete discussion from the TS Bases that could be construed to alter the meaning of TS operability requirements, and reflect the changes made to TS 3.4.7. Exelon Generation Company, LLC (EGC) is not proposing variations or deviations from the TS changes described in TSTF-514, Revision 3, or the NRC staffs model safety evaluation (SE) published in the Federal Register on December 17, 2010 (75 FR 79048) as part of the CUIP Notice of Availability.
3.0 BACKGROUND
NRC Information Notice (IN) 2005-24, "Nonconservatism in Leakage Detection Sensitivity," dated August 3,2005, informed addressees that the reactor coolant activity assumptions for primary containment atmospheric gaseous radioactivity monitors may be non-conservative.
This means the monitors may not be able to detect a one gallon per minute leak within one hour. Some licensees, in response to IN 2005-24, have taken action to remove the gaseous radioactivity monitor from the TS list of required monitors.
However, industry experience has shown that the primary containment atmospheric gaseous radiation monitor is often the first monitor to indicate an increase in RCS leak rate. As a result, the TSTF and the NRC staff met on April 29, 2008, and April 14, 2009, to develop an alternative approach to address the issue identified in IN 2005-24. The agreed upon solution is to retain the primary containment atmospheric gaseous radiation monitor in the LCO list of required equipment, revise the Page 2 of 6 ATTACHMENT 1 Evaluation of Proposed Changes specified safety function of the gas monitor to specify the required instrument sensitivity level, to revise the Actions requiring additional monitoring, and provide less time before a plant shutdown is required when the primary containment atmospheric gaseous radiation monitor is the only operable monitor. 4.0 TECHNICAL ANALYSIS EGC has reviewed TSTF-514, Revision 3, and the model SE published on December 17, 2010, (75 FR 79048) as part of the CLlIP Notice of Availability.
EGC has concluded that the technical bases presented in TSTF Traveler-514, Revision 3, and the model SE prepared by the NRC staff are applicable to LaSalle County Station, Units 1 and 2 (LSCS). General Design Criterion (GDC) 30, "Quality of Reactor Coolant Pressure Boundary," of Appendix A to 10 CFR Part 50, "General Design Criteria for Nuclear Power Plants," requires that means be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage. An evaluation against the GDC 30 is provided in Section 3.1.2.4.1 of the LSCS UFSAR. As discussed in Appendix B of the LSCS UFSAR, LSCS is committed to NRC Regulatory Guide (RG) 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," Revision O. NRC RG 1.45 describes methods acceptable to the NRC to assure that leakage detection and collection systems provide maximum practical identification of leaks within the reactor coolant pressure boundary.
The LSCS RCS leakage detection systems are consistent with the recommendations of NRC RG 1.45, Revision O. The administrative means of monitoring include diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions.
As described in Section 5.2.5.2 of the LSCS Updated Final Safety Analysis Report (UFSAR), "Leak Detection Devices Within Primary Containment," EGC utilizes the following diverse methods to detect unidentified leakage at LSCS: drywell floor drain sump measurement, drywell equipment drain sump, drywell cooler drain flow, drywell pressure, drywell temperature, drywell air sampling, reactor vessel head closure seal annulus pressure, reactor water recirculation pump seal flow rate, safety/relief valve discharge piping temperature, and valve packing leakage. There are diverse alternative methods for determining that RCS leakage has not increased, from which appropriate indicators may be selected based on plant conditions.
EGC will utilize the following method or methods considering the current plant conditions and historical or expected sources of unidentified leakage: drywell floor drain sump measurement, drywell equipment drain sump, drywell cooler drain flow, drywell pressure, drywell temperature, drywell air sampling, reactor vessel head closure seal annulus pressure, reactor water recirculation pump seal flow rate, safety/relief valve discharge piping temperature, valve packing leakage, component cooling water system outlet temperatures, component cooling water system makeup, reactor recirculation system pump seal pressure and temperature, reactor recirculation system pump motor cooler temperatures, drywell cooling fan outlet temperatures, reactor building chiller amperage, and control rod drive system flange temperatures.
Actions to verify that these indications have not increased since the required monitors became inoperable and Page 3 of 6 ATTACHMENT 1 Evaluation of Proposed Changes the analysis of drywell atmospheric grab samples are sufficient to alert the operating staff to an unexpected increase in RCS leakage. 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination Exelon Generation Company, LLC (EGC) has evaluated the proposed changes to the TS using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration.
An analysis of the issue of no significant hazards consideration is presented below: Description of Amendment Request: The proposed amendment would revise TS 3.4.7, "RCS Leakage Detection Instrumentation," Conditions and Required Actions and the licensing basis for the drywell atmospheric gaseous radiation monitor, as well as make associated TS Bases changes for TS 3.4.7. Basis for proposed no significant hazards consideration determination:
As required by 10 CFR 50.91(a), the EGC analysis of the issue of no significant hazards consideration using the standards in 10 CFR 50.92 is presented below: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response:
No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only required operable Reactor Coolant System (RCS) leakage detection instrumentation monitor is the drywell atmospheric gaseous radiation monitor. The monitoring of RCS leakage is not a precursor to any accident previously evaluated.
The monitoring of RCS leakage is not used to mitigate the consequences of any accident previously evaluated.
Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response:
No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only required operable RCS leakage detection instrumentation monitor is the drywell atmospheric gaseous radiation monitor. The proposed change does not involve a physical alteration of the plant (Le., no new or different type of equipment will be installed) or a change in the methods governing normal plant operation.
Therefore, it is concluded that Page 4 of 6 ATTACHMENT 1 Evaluation of Proposed Changes the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety? Response:
No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only required operable RCS leakage detection instrumentation monitor is the drywell atmospheric gaseous radiation monitor. Reducing the amount of time the plant is allowed to operate with only the drywell atmospheric gaseous radiation monitor operable increases the margin of safety by increasing the likelihood that an increase in RCS leakage will be detected before it potentially results in gross failure. Therefore, it is concluded that the proposed change does not involve a significant reduction in a margin of safety. Based upon the above analysis, EGC concludes that the requested change does not involve a significant hazards consideration, as set forth in 10 CFR 50.92(c), "Issuance of Amendment." 5.2 Applicable Regulatory Requirements/Criteria A description of the proposed TS change and its relationship to applicable regulatory requirements were published in the Federal Register Notice of Availability on December 17, 2010 (75 FR 79048). EGC has reviewed the NRC staffs model SE referenced in the CUIP Notice of Availability and concluded that the regulatory evaluation section is applicable to LSCS. General Design Criterion (GDC) 30, "Quality of Reactor Coolant Pressure Boundary," of Appendix A to 10 CFR Part 50, "General DeSign Criteria for Nuclear Power Plants," requires that means be provided for detecting and, to the extent practical, identifying the location of the source of reactor coolant leakage. An evaluation against the GDC 30 is provided in Section 3.1.2.4.1 of the LSCS UFSAR. As discussed in Appendix B of the LSCS UFSAR, LSCS is committed to NRC Regulatory Guide 1.45, "Reactor Coolant Pressure Boundary Leakage Detection Systems," Revision O. NRC Regulatory Guide (RG) 1.45 describes methods acceptable to the NRC to assure that leakage detection and collection systems provide maximum practical identification of leaks within the reactor coolant pressure boundary.
The LSCS RCS leakage detection systems are consistent with the recommendations of NRC RG 1.45, Revision O. Page 5 of 6 ATTACHMENT 1 Evaluation of Proposed Changes 6.0 ENVIRONMENTAL CONSIDERATION The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, and would change an inspection or surveillance requirement.
However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
7.0 REFERENCES
7.1 TSTF-514 "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation," Revision 3 7.2 U.S. Nuclear Regulatory Commission Model Safety Evaluation on the "Technical Specification Task Force (TSTF) Change TSTF-514, "Revised BWR Operability Requirements and Actions for RCS Leakage Instrumentation," dated December 7,2010 Page 6 of 6 ATTACHMENT 2 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Markup Pages of Existing Technical Specifications to Show the Proposed Changes MARKUP OF EXISTING REVISED TS PAGES 3.4.7-2 New Condition D
ACTIONS CONDITION C. Drywell air cooler condensate flow rate monitoring system inoperable.
RCS Leakage Detection Instrumentation 3.4.7 REQUI RED ACTION ------------
NOT E -------------
Not applicable when the required drywell atmospheric monitoring system is inoperable.
C.1 Perform SR 3.4.7.1. COMPLETION TIME Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> .g. Requi red drywell .g.1 Restore required drywell atmospheric monitoring system to OPERABLE status. 30 days atmospheric monitoring system inoperable.
Drywell ai r cool er condensate flow rate monitoring system inoperable. Required Action and associated Completion Time of Condition A, ot met. All required leakage detection systems inoperable.
LaSalle 1 and 2 .g.2 1 Restore drywell air cooler condensate flow rate monitoring system to OPERABLE status. Be in MODE 3. Be in MODE 4. Enter LCO 3.0.3. 30 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Immediately 3.4.7-2 Amendment No. 171/157 New Condition D
ATTACHMENT 3 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Markup Pages of Existing Technical Specifications Bases to Show the Proposed Change MARKUP OF EXISTING TS BASES PAGES B 3.4.7-1 B 3.4.7-2 B 3.4.7-3 B 3.4.7-4 B 3.4.7-5 B 3.4.7-7 RCS Leakage Detection Instrumentation B 3.4.7 B 3.4 REACTOR COOLANT SYSTEM (RCS) B 3.4.7 RCS Leakage Detection Instrumentation BASES BACKGROUND LaSalle 1 and 2 GDC 30 of 10 CFR 50, Appendix A (Ref. 1), requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide (Ref. 2) describes acceptable methods for selecting leakage detection systems. Limits on LEAKAGE from the reactor coolant pressure boundary (RCPB) are required so that appropriate action can be taken before the integrity of the RCPB is impaired (Ref. 2). Leakage detection systems for the RCS are provided to alert the operators when leakage rates above normal background levels are detected and also to supply quantitative measurement of rates. The Bases for LCO 3.4.5, "RCS Operational LEAKAGE," iscuss the limits on RCS LEAKAGE rates. Systems for separating the LEAKAGE of an identified source from an unidentified source are necessary to provide prompt and quantitative information to the operators to permit them to take immediate corrective action. LEAKAGE from the RCPB inside the drywell is detected by at least one of three independently monitored variables, such as drywell air cooler condensate flow rate, sump flow rate, and drywell gaseous and particulate radioactivity levels. The primary means of quantifying LEAKAGE in the drywell is the drywell floor drain sump flow monitoring system. The drywell floor drain sump flow monitoring system monitors the LEAKAGE collected in the floor drain sump. This unidentified LEAKAGE consists of LEAKAGE from control rod drives, valve flanges or packings, floor drains, the closed cooling water subsystems, and drywell air cooling unit condensate drains, and any LEAKAGE not collected in the drywell equipment drain sump. The drywell floor drain sump has a weir level transmitter that supplies floor drain sump fill-up rate flow indication in the main control room. The drywell floor drain sump flow monitoring system contains an additional method of measuring drywell floor drain sump flow through the use of a magnetic flow meter. The flow meter is installed on the piping that runs parallel to the sump pump piping. When in use, the magnetic flow meter measures a (continued)
B 3.4.7-1 Revision BASES BACKGROUND (continued)
APPLICABLE SAFETY ANALYSES LaSalle 1 and 2 RCS Leakage Detection Instrumentation B 3.4.7 continuous flow in the line and will display a flow rate in the control room. The floor drain sump has level switches that start and stop the sump pumps when required.
The sump pump which is selected Lead starts on a high level in the sump. The other pump starts, and a control room alarm is annunciated, if the sump level reaches the high-high level. The pumps stop when low level is reached in the sump. A timer starts each time the first sump pump starts. A second timer starts when the pump is stopped. If the pump takes longer than a given time to pump down the sump, or if the pump starts too soon after the previous pumpdown, an alarm is sounded in the control room indicating a higher than normal sump fill-up rate. A flow monitor in the discharge line of the drywell floor drain sump pumps provides flow input to a flow totalizer, which is indicated in the control room. The magnetic flow meter indication also provides an input to the flow totalizer.
The totalizer inputs can be swapped using hand switches located in the Auxiliary Electric Equipment Room and the Reactor Building.
Both monitors cannot be used simultaneously.
The flow totalizer can be used to quantify the amount of inputs. The drywell air monitoring systems continuously monitor the drywell atmosphere for airborne particulate and gaseous radioactivity.
A sudden increase of radioactivity, which may be attributed to RCPB steam or reactor water LEAKAGE, is annunciated in the control room. The drywell atmosphere particulate and gaseous radioactivity monitoring systems are not capable of quantifying leakage rates, but are sensitive enough to indicate increased LEAKAGE rates of 1 gpm within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. Larger changes in LEAKAGE rates are detected in proportionally shorter times (Ref. 3). Condensate from the drywell coolers is routed to the drywell floor drain sump and is monitored by a flow transmitter that provides indication and alarms in the control room. This drywell air cooler condensate flow rate monitoring system serves as an added indicator, but not quantifier, of RCS unidentified LEAKAGE. A threat of significant compromise to the RCPB exists if the barrier contains a crack that is large enough to propagate (continued)
B 3.4.7-2 Revision BASES APPLICABLE SAFETY ANALYSES (continued)
LCD APPLICABI LITY ACTIONS LaSalle 1 and 2 RCS Leakage Detection Instrumentation B 3.4.7 rapidly. LEAKAGE rate limits are set low enough to detect the LEAKAGE emitted from a single crack in the RCPB (Refs. 4 an i). Each of the leakage detection systeffis inside the drywell is designed with the capability of detecting LEAKAGE less than the established LEAKAGE rate liffiits and providing appropriate alarffi of excess LEAKAGE in the control rOOffi. A control room alarm allows the operators to evaluate the significance of the indicated LEAKAGE and, if necessary, shut down the reactor for further investigation and corrective action. The allowed LEAKAGE rates are well the rates predicted for critical crack sizes (Ref. *-K 5 Therefore, these actions provide adequate response before a significant break in the RCPB can occur. RCS leakage detection instrumentation satisfies Criterion 1 of 10 CFR 50.36(c)(2)(ii).
The drywell floor drain SUffiP flow ffionitoring systeffi is required to quantify the unidentified LEAKAGE froffi the RCS. Thus, for the systeffi to be considered OPERABLE, the floor drain SUffiP fillup rate ffionitor or the ffiagnetic flow ffieter portion of the systeffi ffiUSt be OPERABLE.
The other ffionitoring systeffis provide early alarffis to the operators so closer exaffiination of other detection systeffis will be ffiade to deterffiine the extent of any corrective action that ffiay be required.
With the leakage detection systeffis inoperable, ffionitoring for LEAKAGE in the RCPB is degraded.
In MODES 1, 2, and 3, leakage detection systems are required to be OPERABLE to support LCD 3.4.5. This Applicability is consistent with that for LCD 3.4.5. With the drywell floor drain sump flow monitoring system inoperable, no other form of sampling can provide the equivalent information to quantify leakage. However, the drywell atmospheric activity monitor and the drywell air cooler condensate flow rate monitor will provide indications of changes in leakage. (continued)
B 3.4.7-3 Revision 22 BASES ACTIONS (continued)
LaSalle 1 and 2 RCS Leakage Detection Instrumentation B 3.4.7 With the drywell floor drain sump flow monitoring system inoperable, but with RCS unidentified and total LEAKAGE being determined every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (SR 3.4.5.1), operation may continue for 30 days. The 30 day Completion Time of Required Action A.l is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.
With both gaseous and particulate drywell atmospheric monitoring channels inoperable (i .e., the required drywell atmospheric monitoring system), grab samples of the drywell atmosphere shall be taken and analyzed to provide periodic leakage information.
Provided a sample is obtained and analyzed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may continue operation since at least one other form of drywell leakage detection (i .e., air cooler condensate flow rate monitor) is available.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. With the required drywell air cooler condensate flow rate monitoring system inoperable, SR 3.4.7.1 is performed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to provide periodic information of activity in the drywell at a more frequent interval than the routine Frequency of SR 3.4.7.1. The 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE and recognizes that other forms of leakage detection are available.
However, this Required Action is modified by a Note that allows this action to be not applicable if the required drywell atmospheric monitoring system is inoperable.
Consistent with SR 3.0.1, Surveillances are not required to be performed on inoperable equipment.
Gd With both the gaseous and particulate drywell atmospheric monitor channels and the drywell air cooler condensate flow rate monitor inoperable, the only means of detecting LEAKAGE is the drywell floor drain sump flow monitor. This (continued)
B 3.4.7-4 Revision ft
BASES ACTIONS SURVEILLANCE REQUIREMENTS LaSalle 1 and 2 RCS Leakage Detection Instrumentation B 3.4.7 If any Required Action of Condition A, B, C, *r-D met within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions in an orderly manner and without challenging plant systems. With all required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LCO 3.0.3 is required.
The Surveillances are modified by a Note to indicate that when a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, provided the other required instrumentation (the drywell sump flow monitoring system, drywell atmospheric monitori ng channel, or the drywell ai r cool er condensate flow monitoring system, as applicable) is OPERABLE.
Upon (continued)
B 3.4.7-5 Revision .f-9.
BASES SURVEI LLANCE REQUIREMENTS REFERENCES LaSalle 1 and 2 RCS Leakage Detection Instrumentation B 3.4.7 SR 3.4.7.3 (continued) drywell. The Frequency of 24 months is a typical refueling cycle and considers channel reliability.
Operating experience has proven this Frequency is acceptable.
- 1. 10 CFR 50, Appendix A, GDC 30. 2. Regulatory Guide 1.45 3. 4-:-GEAP-5620, "Failure Behavior in ASTM A106B Pipes Containing Axial Through-Wall Flaws," April 1968. NUREG-75/067, "Investigation and Evaluation of Cracking in Austenitic Stainless Steel Piping of Boiling Water Reactor Plants," October 1975. UFSAR, Section 5.2.5.5.2.
1 6 UFSAR S t' 52511 I ..rEL.-----, . , ec Ion . . . . .
B 3.4.7-7 Revision G-
TS Bases Insert No.1 This LCO requires instruments of diverse monitoring principles to be OPERABLE to provide confidence that small amounts of unidentified LEAKAGE are detected in time to allow actions to place the plant in a safe condition, when RCS LEAKAGE indicates possible RCPB degradation.
The LCO requires three instruments to be OPERABLE.
The drywell floor drain sump monitoring system is required to quantify the unidentified LEAKAGE rate from the RCS. Thus, for the system to be considered OPERABLE, either the flow monitoring or the sump level monitoring portion of the system must be OPERABLE and capable of determining the leakage rate. The identification of an increase in unidentified LEAKAGE will be delayed by the time required for the unidentified LEAKAGE to travel to the drywell floor drain sump and it may take longer than one hour to detect a 1 gpm increase in unidentified LEAKAGE, depending on the origin and magnitude of the LEAKAGE. This sensitivity is acceptable for containment sump monitor OPERABILITY.
The reactor coolant contains radioactivity that, when released to the primary containment, can be detected by the gaseous or particulate primary containment atmospheric radioactivity monitor. Only one of the two detectors is required to be OPERABLE.
Radioactivity detection systems are included for monitoring both particulate and gaseous activities because of their sensitivities and rapid responses to RCS LEAKAGE, but have recognized limitations.
Reactor coolant radioactivity levels will be low during initial reactor startup and for a few weeks thereafter, until activated corrosion products have been formed and fission products appear from fuel element cladding contamination or cladding defects. If there are few fuel element cladding defects and low levels of activation products, it may not be possible for the gaseous or particulate primary containment atmospheric radioactivity monitors to detect a 1 gpm increase within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> during normal operation.
However, the gaseous or particulate containment primary atmospheric radioactivity monitor is OPERABLE when it is capable of detecting a 1 gpm increase in unidentified LEAKAGE within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> given an RCS activity equivalent to that assumed in the design calculations for the monitors (Reference 6). An increase in humidity of the drywell atmosphere could indicate the release of water vapor to the drywell. Drywell air cooler condensate flow rate is instrumented to detect when there is an increase above the normal value by 1 gpm. The time required to detect a 1 gpm increase above the normal value varies based on environmental and system conditions and may take longer than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This sensitivity is acceptable for drywell air cooler condensate flow rate monitor OPERABILITY.
The LCO is satisfied when monitors of diverse measurement means are available.
Thus, the drywell floor drain sump monitoring system, in combination with a gaseous or particulate primary containment atmospheric radioactivity monitor and a drywell containment air cooler condensate flow rate monitoring system, provides an acceptable minimum.
TS Bases Insert No.2 0.1. 0.2.
0.3.1. and 0.3.2 With the drywell floor drain sump monitoring system and the drywell air cooler condensate flow rate monitoring system inoperable, the only means of detecting LEAKAGE is the primary containment atmospheric gaseous radiation monitor. A Note clarifies this applicability of the Condition.
The primary containment atmospheric gaseous radiation monitor typically cannot detect a 1 gpm leak within one hour when RCS activity is low. In addition, this configuration does not provide the required diverse means of leakage detection.
Indirect methods of monitoring RCS leakage must be implemented.
Grab samples of the primary containment atmosphere must be taken and analyzed and monitoring of RCS leakage by administrative means must be performed every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to provide alternate periodic information.
Administrative means of monitoring RCS leakage include monitoring and trending parameters that may indicate an increase in RCS leakage. There are diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions.
It is not necessary to utilize all of these methods, but a method or methods should be selected considering the current plant conditions and historical or expected sources of unidentified leakage. The administrative methods are drywell floor drain sump measurement, drywel/ equipment drain sump, drywell cooler drain flow, drywell pressure, drywell temperature, drywell air sampling, reactor vessel head closure seal annulus pressure, reactor water recirculation pump seal flow rate, safety/relief valve discharge piping temperature, valve packing leakage, component cooling water system outlet temperatures, component cooling water system makeup, reactor recirculation system pump seal pressure and temperature, reactor recirculation system pump motor cooler temperatures, drywell cooling fan outlet temperatures, reactor building chiller amperage, and control rod drive system flange temperatures.
These indications, coupled with the atmospheric grab samples, are sufficient to alert the operating staff to an unexpected increase in unidentified LEAKAGE. The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval is sufficient to detect increasing RCS leakage. The Required Action provides 7 days to restore another RCS leakage monitor to OPERABLE status to regain the intended leakage detection diversity.
The 7 day Completion Time ensures that the plant will not be operated in a degraded configuration for a lengthy time period.
ATTACHMENT 4 LASALLE COUNTY STATION UNITS 1 AND 2 Docket Nos. 50-373 and 50-374 License Nos. NPF-11 and NPF-18 Revised Technical Specifications (Clean) Pages REVISED TS PAGES 3.4.7-2 3.4.7-3 3.4.7-4 ACTIONS CONDITION C. Drywell air cooler condensate flow rate monitoring system inoperable. ----------NOTE-----------Only applicable when the primary containment atmospheric gaseous radiation monitor is the only OPERABLE monitor. D. Drywell floor drain sump monitoring system inoperable Drywell air cooler condensate flow rate monitoring system inoperable.
LaSalle 1 and 2 RCS Leakage Detection Instrumentation 3.4.7 REQU I RED ACTI ON ------------
NOTE -----------
--Not applicable when the required drywell atmospheric monitoring system is inoperable.
C.1 Perform SR 3.4.7.1. 0.1 Analyze grab samples of the primary containment atmosphere.
AND 0.2 Monitor RCS LEAKAGE by administrative means. AND 0.3.1 Restore drywell floor drain sump monitoring system to OPERABLE status. OR 0.3.2 Restore drywell air cooler condensate flow rate monitoring system to OPERABLE status. COMPLETION TIME Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 7 days 7 days (continued) 3.4.7-2 Amendment No.
ACTIONS CONDITION E. Required drywell E.1 atmospheric monitoring system inoperable.
Drywell air cooler condensate flow rate monitoring system inoperable.
E.2 F. Required Action and F.1 associated Completion Time of Condition A, AND B, C, 0, or E not met. G. All required leakage detection systems inoperable.
LaSalle 1 and 2 F.2 G.1 RCS Leakage Detection Instrumentation 3.4.7 REQUIRED ACTION Restore required drywell atmospheri c monitoring system to OPERABLE status. Restore drywell air cooler condensate flow rate monitoring system to OPERABLE status. Be in MODE 3. Be in MODE 4. Enter LCO 3.0.3. COMPLETION TIME 30 days 30 days 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Immediately 3.4.7-3 Amendment No.
RCS Leakage Detection Instrumentation 3.4.7 SURVEILLANCE REQUIREMENTS -------------------------------------
NOT E -------------------------------------
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the other required leakage detection instrumentation is OPERABLE.
SR 3.4.7.1 SR 3.4.7.2 SR 3.4.7.3 LaSalle 1 and 2 SURVEI LLANCE Perform CHANNEL CHECK of required drywell atmospheric monitoring system. Perform CHANNEL FUNCTIONAL TEST of required leakage detection instrumentation.
Perform CHANNEL CALIBRATION of required leakage detection instrumentation.
FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program 3.4.7-4 Amendment No.