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Category:Letter type:RS
MONTHYEARRS-24-092, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS2024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS RS-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-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-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 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-21-064, 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 2024-09-19
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML24103A2042024-04-12012 April 2024 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-591-A, Revise Risk Informed Completion Time (RICT) Program Revision 0 and Revise 10 CFR 50.69 License Condition 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 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-20-009, 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-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-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) 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 ML18053A1752018-01-31031 January 2018 Attachment 5A - LaSalle Marked-up Emergency Plan EP-AA-1000 Pages 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 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 2024-04-12
[Table view] Category:Technical Specifications
MONTHYEARML24018A0682024-02-0909 February 2024 Issuance of Amendment Nos. 262 and 247 Revised Design Bases of Lower Downcomer Braces 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 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. 2024-02-09
[Table view] |
Text
10 CFR 50.90 RS-06-003 March 16, 2006 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-1 1 and NPF-1 8 NRC Docket Nos. 50-373 and 50-374
Subject:
Request for a License Amendment to Revise Allowable Values for Reactor Core Isolation Cooling Temperature Based Leak Detection.
In accordance with 10 CFR 50.90, "Application for amendment of license or construe permit," Exelon Generation Company, LLC (EGC) requests the following amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-1 I and NPF-18 for LaSalle County Station (LSCS) Units 1 and 2. Specifically, the proposed changes will modify TS 3.3.6.1, "Primary Containment Isolation Instrumentation," Table 3.3.6.1-1 to revise the Allowable Values for Reactor Core Isolation Cooling (RCIC) temperature based leak detection.
The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current reactor coolant leak detection analytical limit.
The attached amendment request is subdivided as shown below.
Attachment 1 provides a description of the proposed change .
Attachment 2 includes the marked-up TS page with the proposed change indicated .
Attachment 3 includes the associated typed TS page with the proposed change incorporated .
EGC requests approval of the proposed change by January 30, 2007, with the amendment being implemented within 60 days of issuance .
The proposed changes have 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.
March 16, 2006 U . S. Nuclear Regulatory Commission Page 2 In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," EGC is notifying the State of Illinois of this application for changes to the TS by transmitting a copy of this letter and its attachments to the designated State Official .
Should you have any questions concerning this letter, please contact Ms . Alison Mackellar at (630) 657-2817 .
I declare under penalty of perjury that the foregoing is true and correct . Executed on the 16th day of March 2006.
Keith R . Jury Director, Licensing and Regulatory Affairs : Evaluation of Proposed Change : Mark-up of Proposed Technical Specifications Page Change : Typed Page for Technical Specification Change
ATTACHMENT 1 Evaluation of Proposed Change INDEX 1 .0 DESCRIPTION
2.0 PROPOSED CHANGE
S
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria 6.0 ENVIRONMENTAL EVALUATION
7.0 REFERENCES
Page 1 of 10
ATTACHMENT 1 Evaluation of Proposed Change 1 .0 DESCRIPTION In accordance with 10 CFR 50 .90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests the following amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-1 1 and NPF-1 8 for LaSalle County Station (LSCS) Units 1 and 2. Specifically, the proposed changes I modify TS 3361 . . ., "Primary Containment Isolation Instrumentation," Table 3.3.6.1-1 ; to e the Allowable Values for Reactor Core Isolation Cooling (RCIC) system temperature based leak detection.
The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current leak detection analytical limit. The temperature limits correspond to a 25 gpm leak as determined by LSCS calculations . The proposed changes will revise TS Table 3.3.6.1-1 Allowable Values for the following four RCIC system isolation functions.
Item 3.e. RCIC Equipment Room Temperature - High Item 3.f. RCIC Equipment Room Differential Temperature - High Item 3.g. RCIC Steam Line Tunnel Temperature - High Item 3 .h . RCIC Steam Line Tunnel Differential Temperature - High We request approval of the proposed license amendment by January 30, 2007. Once approved, the amendment will be implemented within 60 days .
2.0 PROPOSED CHANGE
S The proposed change will revise TS Table 3.3.6.1-1 Allowable Values for the leak based instrument functions associated with RCIC Isolation .
The current Allowable Values for these functions are :
291 .OOF for RCIC Equipment Room Temperature - High 189 .OOF for RCIC Equipment Room Differential Temperature - High 277.OOF for the RCIC Steam Line Tunnel Temperature - High 155.OOF for the RCIC Steam Line Tunnel Differential Temperature - High The proposed change revises the Allowable Values to the following:
297.OOF for RCIC Equipment Room Temperature - High 188.OOF for RCIC Equipment Room Differential Temperature - High
!5 267.OOF for the RCIC Steam Line Tunnel Temperature - High
<_ 163.OOF for the RCIC Steam Line Tunnel Differential Temperature - High 3 .0 BACKGROUND The RCIC system is considered a safe shutdown system rather than an emergency core cooling system. It is designed to automatically perform its function during a total loss of AC power.
RCIC instrumentation and controls are designed to meet the requirements of control systems and standards as stated in the LSCS Updated Final Safety Analysis Report (UFSAR). The RCIC leak detection isolation functions are not credited in any UFSAR transient or accident Page 2 of 10
ATTACHMENT 1 Evaluation of Proposed Change analysis, since the bounding analyses are performed for large breaks such as reactor recirculation line or main steam line breaks .
The RCIC system automatically initiates to ensure adequate core cooling in the event that the reactor is isolated from the main condenser during power operation with a loss of main feedwater flow. The RCIC system is designed to add water inventory to the reactor vessel thus assuring continuity of core cooling. Reactor vessel water level is maintained or supplemented by the RCIC system during the following conditions:
- a. reactor vessel isolated and maintained in the hot standby condition;
- b. reactor vessel isolated coincident with a loss of normal coolant flow from the reactor feedwater system; or
- c. plant shutdown where of a loss of normal feedwater system is experienced before the reactor is depressurized to where the reactor shutdown cooling mode of the residual heat removal system can be placed in operation.
The RCIC system provides relatively cool water to the reactor vessel either from the Cycled Condensate Storage Tank or from the suppression pool and uses steam from the reactor to drive the RCIC turbine driven pump . The water supply to the reactor vessel and the steam supply to the turbine both assist in decay heat removal from the core. The water is injected into the vessel through the head spray nozzle of the reactor.
The RCIC temperature leak detection system at LSCS uses area ambient or differential temperature increases to detect small primary coolant boundary leaks in the Main Steam Line Tunnel and in various rooms of the RCIC system and the Reactor Water Cleanup (RWCU) system .
Inputs to the RCIC system isolation function are listed in Table 3.3.6.1-1, "Primary Containment Isolation Instrumentation," and include the following:
RCIC Equipment Room Temperature - High RCIC Equipment Room Differential Temperature - High RCIC Steam Line Tunnel Temperature - High RCIC Steam Line Tunnel Differential Temperature - High These functions are inputs to the logic that initiates an isolation of the Group 8 (i .e., RCIC steam line) isolation valves at a leak rate equivalent to 25 gpm in the RCIC steam pipe . This isolation function is independent of the RCIC steam line flow rate, RCIC steam line pressure, or Drywell pressure isolation functions .
While responding to a LSCS Corrective Action Program action item, the existing reactor coolant leak detection calculation {1-001324, Revision 5A) and the RCIC leak detection setpoint calculation (NED-I-EIC-0213, Revision 1 G) were reviewed in May 2005. During this review it was determined that the RCIC leak detection setpoint calculation used design inputs from Revision 0 of the reactor coolant leak detection calculation, dated October 17, 1997, rather than the current Revision 5A dated March 2003. The Allowable Values in LSCS TS Table 3 .3.6 .1-1 are derived from the RCIC leak detection setpoint calculation, and were therefore no longer supported by the current calculation, (i.e., the Allowable Values were not prepared using design Page 3 of 10
ATTACHMENT 1 Evaluation of Proposed Change inputs from the current (i.e., Revision 5A) reactor coolant leak detection calculation) . It should be noted that Revision 5 of the reactor coolant leak detection calculation, dated December, 1998, first modified the affected RCIC Allowable Values in LSCS Table 3 .3 .6 .1-1 ; however, the need for a TS revision was not identified at that time .
All the affected instruments are currently meeting the setpoint requirement in their respective LSCS instrument surveillance procedure . A review of completed surveillances for the last three years for the RCIC Equipment Room and the RCIC Steam Line Tunnel instrumentation was performed. The as-found data for all TS RCIC system isolation instrumentation indicate that the existing Allowable Values were never challenged .
An extent of condition review was performed on all instrument setpoint calculations listed in the LSCS Technical Requirements Manual Appendix D to ensure that the outdated calculation concern was limited to the RCIC leak detection system. All calculation based Allowable Values were reviewed and the setpoint calculations were found to be consistent with the current analytical limits .
NRC Administrative Letter 98-10, "Disposition i ng of Technical Specifications that are insufficient to assure Plant Safety," addresses the NRC's expectations regarding correction of facility TS when they are found to contain nonconservative values . In the case of a deficient TS, these expectations include the evaluation of compensatory measures, such as administrative controls implemented in accordance with 10 CFR 50.59, "Changes, tests, and experiments," and prompt actions to correct the TS.
Substantial margin remains between the current field setting of the RCIC system leak detection instrumentation setpoints and the calculated values for both the Limiting Trip Setpoints and the TS Allowable Values . In addition, the operational history of the equipment indicates that normal instrument variability does not result in a challenge to the Allowable Value . Based on this information, no compensatory measures were found necessary beyond this request for a correction to the subject TS Allowable Values .
The proposed changes will revise TS Table 3 .3.6.1-1 Allowable Values for four RCIC system isolation functions as noted below.
Increase the Allowable Value for Function 3.e., "RCIC Equipment Room Temperature - High," from <_ 291 .0- F to < 297.0°F Decrease the Allowable Value for Function 3.f., "RCIC Equipment Room Differential Temperature - High," from <_ 189.0°F to <_ 188.0°F 0 Decrease the Allowable Value for Function 3 .g ., "RCIC Steam Line Tunnel Temperature - High," from < 277 .0°F to 5 267.0°F Increase the Allowable Value for Function 3.h., "RCIC Steam Line Tunnel Differential Temperature - High," from <_ 155.0°F to <_ 163.0°F The proposed revision to the Allowable Values does not change any of the RCIC system leak detection isolation setpoints.
Page 4 of 10
ATTACHMENT 1 Evaluation of Proposed Change
4.0 TECHNICAL ANALYSIS
The leak detection system at LSCS uses area ambient or differential temperature increases to detect small primary coolant boundary leaks in the Main Steam Line Tunnel and in various rooms of the RCIC System and the RWCU System.
The current LSCS TS Allowable Values for the RCIC temperature based leak detection were based on analytical limits determined in calculations that identified the plant areas with reactor coolant piping outside of containment that required area ambient and differential temperature monitoring leak detection and determined the theoretical area heat rise for various design pipe leak rates . The current Allowable Values contained in TS Table 3.3.6.1-1 are based on calculations that used design inputs from Revision 0 of the reactor coolant leak detection calculation .
The proposed change is based on revised analytical limits for a leak rate equivalent to 25 gpm determined by the most current revisions to the heat rise calculations based on the existing reactor coolant leak detection calculation (L-001324, Revision 5A). Setpoint calculations have been performed to determine the nominal trip setpoints and Allowable Values for the instrumentation associated with the leak detection function based on the revised analytical limits determined by the latest heat rise calculations .
There is no change to the methodology or instrument error values approved for use in Amendments 147 and 133 to the LSCS TS issued on March 30, 2001 . These amendments converted the previous TS for LSCS to Improved Technical Specifications (ITS) based on NUREG 1433, "Standard Technical Specifications, General Electric Plants BWR/4," Revision 1, dated April 1995, as documented in Reference 5 . The Safety Evaluation for these amendments documents LSCS identification of the Nuclear Engineering Standard NES-EIC-20 .04, Revision 1, "Analysis of Instrument Channel Setpoint Error and Instrument Loop Accuracy ."
In recent industry communications the NRC has identified a concern with the use of Allowable Values as limits used in TS to satisfy the requirements of 10 CFR 50.36, "Technical Specifications ." Limiting safety system settings (LSSS) for nuclear reactors are settings for automatic protective devices related to those variables having significant safety functions .
Where a LSSS is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded . The RCIC leak detection/isolation function is not protecting a safety limit and therefore does not meet the definition of a LSSS .
As required by GL 91-04, "Changes in Technical Specification Surveillance Intervals to Accommodate a 24-Month Fuel Cycle," continuing evaluation processes are in place to evaluate drift data for instruments evaluated drift in the 24-month fuel cycle extension request so that any variation in the assumed values of will be identified and incorporated in the LSSS calculations . The RCIC system isolation functions are not considered to be LSSS, however, these parameters are also required to meet setpoint standards in accordance with NES-EIC-20 .04, as documented in Reference 5 . To address concerns of verification of functionality, RCIC system isolation instrumentation as-left values are verified within the required tolerance after the completion of all TS calibration surveillances.
Page 5 of 10
ATTACHMENT 1 Evaluation of Proposed Change
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration In accordance with 10 CFR 50.90, "Application for amendment of license or construction permit," Exelon Generation Company, LLC (EGC) requests the following amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-1 1 and Units NPF-18 for LaSalle County Station (LSCS) 1 and 2. Specifically, the proposed changes will modify TS 3.3 .6.1, "Primary Containment Isolation Instrumentation," Table 3 .3 .6.1-1 ; to revise the Allowable Values for Reactor Core Isolation Cooling (RCIC) system temperature based leak detection.
The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current reactor coolant leak detection calculation analytical limit. The temperature limits correspond to a 25 gpm leak as determined by LSCS calculations . The proposed changes will revise TS Table 3.3.6.1-1 Allowable Values for the following four RCIC system isolation functions.
Item 3.e . RCIC Equipment Room Temperature - High Item 3.f. RCIC Equipment Room Differential Temperature - High Item 3.g. RCIC Steam Line Tunnel Temperature - High Item 3.h. RCIC Steam Line Tunnel Differential Temperature - High According to 10 CFR 50.92, "Issuance of amendment," paragraph (c), a proposed amendment to an operating license involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not:
Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated ; or Involve a significant reduction in a margin of safety .
In support of this determination, an evaluation of each of the three criteria set forth in 10 CFR 50.92 is provided below regarding the proposed license amendment.
The proposed TS change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current reactor coolant leak detection calculation analytical limit . The proposed changes will revise TS Table 3.3.6.1-1 Allowable Values for the following four RCIC system isolation functions as noted below.
Increase the Allowable Value for Function 3.e ., "RCIC Equipment Room Temperature - High," from ~ 291 .011F to <_ 297.OOF Page 6 of 10
ATTACHMENT 1 Evaluation of Proposed Change Decrease the Allowable Value for Function V., "RCIC Equipment Room Differential Temperature - High," from < 189.4°F to <_ 188.4°F Decrease the Allowable Value for Function 3.g., "RCIC Steam Line Tunnel Temperature - High," from <277 .OOF to <_ 267.0"F Increase the Allowable Value for Function 3.h., "FICIC Steam Line Tunnel Differential Temperature - High, "from <_ 155.4°F to <_ 163.4°F The function of the instrumentation listed on TS Table 3.3.6.1-1, in combination with other accident mitigation features, 4 to limit fission product release during and following postulated Design Bast Accidents to within allowable limits . The Allowable Values specified in TS Table 3.3.6.1-1 provide assurance that the instrumentation will perform as designed.
The Allowable Values for RCIC system isolation are not a precursor to any accident previously evaluated. Accidents are assumed to be initiated by equipment failure . The proposed change does not alter the initiation conditions or operational parameters for the system . There is no increase in the failure probability of the system . As such, the probability of occurrence for a previously evaluated accident is not increased.
The Allowable Values specified in Table 3.3.6.1-1 provide assurance that the RCIC system will perform as designed. The proposed revision to the Allowable Values does not change any of the RCIC system leak detection isolation actuation setpoints .
Thus, the radiological consequences of any accident previously evaluated are not increased .
Based on the above information, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated .
The proposed TS change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change does not affect the control parameters governing unit operation or the response of plant equipment to transient conditions. The proposed change does not change or introduce any new equipment, modes of system operation or failure mechanisms .
The proposed change is based on revised reactor coolant leak detection calculation analytical limits determined by the most current revision to the heat rise calculation .
Setpoint calculations have been performed to determine the nominal trip setpoints and Allowable Values for the instrumentation associated with the leak detection function based on the revised analytical limits determined by the heat rise calculations . The proposed revision to the Allowable Values does not change any of the RCIC system leak detection isolation actuation setpoints.
Based on the above information, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Page 7 of 14
ATTACHMENT 1 Evaluation of Proposed Change The proposed TS change does not involve a significant reduction in a margin of safety.
The proposed change will revise TS Table 3.3.6.1-1 Allowable Values for the instrument functions associated with RCIC Isolation .
The current Allowable Values for these functions are:
291 .OOF for RCIC Equipment Room Temperature - High 189.011 F for RCIC Equipment Room Differential Temperature - High 277.OOF for the RCIC Steam Line Tunnel Temperature - High 155.OOF for the RCIC Steam Line Tunnel Differential Temperature - High The proposed change revises the Allowable Values to the following:
!5; 297.01F for RCIC Equipment Room Temperature - High 188.OOF for RCIC Equipment Room Differential Temperature - High 267.OOF for the RCIC Steam Line Tunnel Temperature - High 163.0017 for the RCIC Steam Line Tunnel Differential Temperature - High The proposed change is a result of revising the setpoint calculation for the subject temperature instruments based on the current analytical limit. The proposed changes will revise TS Table 3 .3.6.1-1 Allowable Values for the subject four RCIC system isolation functions and will provide assurance that the RCIC system will perform as designed . The proposed revision to the Allowable Values does not change any of the RCIC system leak detection isolation actuation setpoints.
Margin of safety is established by the design and qualification of plant equipment, the operation of the plant within analyzed limits, and the point at which protective or mitigative actions are being initiated. The proposed change does not alter these considerations . The proposed allowable values will still ensure that the results of the accident analysis remain valid.
Based on this information, the proposed change does not involve a significant reduction in a margin of safety .
Based on the above evaluation, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c) .
5.2 Applicable Regulatory Requirements/Criteria 10 CFR 50.36(c)(1) requires that the plant Technical Specifications will include items in the following categories ; safety limits, limiting safety system settings, and limiting control settings .
Limiting safety system settings (LSSS) for nuclear reactors are settings for automatic protective devices related to those variables having significant safety functions . Where a LSSS is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded . The RCIC leak detection/isolation function is not protecting a safety limit and therefore does not meet the definition of a LSSS .
Page 8 of 10
ATTACHMENT 1 Evaluation of Proposed Change 10 CFR 50, Appendix A, General Design Criteria (GDC) 54 requires that piping systems penetrating primary containment be provided with leak detection, isolation and containment capabilities having redundancy, reliability and performance capabilities which reflect the importance to safety of isolating systems. The RCIC High Energy Line Break leak detection/isolation equipment monitors temperature and initiates a RCIC system isolation when area ambient temperature reaches a preset limit.
TS Table 3.3.6.1-1 lists primary containment isolation instrumentation that are required to function, in combination with other accident mitigation features, to limit fission product release during and following postulated Design Basis Accidents to within limi Impact on Previous Submittals/Precedent The NRC is currently reviewing a similar change for the Oyster Creek Generating Station, which was submitted on February 2, 2005, (i .e., Reference 1).
6.0 ENVIRONMENTAL EVALUATION EGC has evaluated this proposed operating license amendment consistent with the criteria for identification of licensing and regulatory actions requiring environmental assessment in accordance with 10 CFR 51 .21, "Criteria for and identification of licensing and regulatory actions requiring environmental assessments ." EGC has determined that these proposed changes meet the criteria for a categorical exclusion set forth in paragraph (c)(9) of 10 CFR 51 .22, "Criterion for categorical exclusion ; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," and as such, has determined that no irreversible consequences exist in accordance with paragraph (b) of 10 CFR 50.92, "Issuance of amendment." This determination is based on the fact that this change is being proposed as an amendment to a license issued pursuant to 10 CFR 50, "Domestic Licensing of Production and Utilization Facilities," which changes a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or which changes an inspection or a surveillance requirement, and the amendment meets the following specific criteria :
The amendment involves no significant hazards consideration.
As demonstrated in Section 5 .1, "No Significant Hazards Consideration," the proposed significant changes do not involve any hazards consideration.
(111) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
The proposed change to allowable values associated with the RCIC system isolation function does not result in an increase in power level, does not increase the production nor alter the flow path or method of disposal of radioactive waste or byproducts ; thus, there will be no change in the amounts of radiological effluents released offsite.
Based on the above evaluation, the proposed change will not result in a significant change in the types or significant increase in the amounts of any effluent released offske .
Page 9 of 10
ATTACHMENT 1 Evaluation of Proposed Change There is no significant increase in individual or cumulative occupational radiat exposure.
The proposed change to allowable values associated with the RCIC system isolation function will not result in any changes to the previously analyzed configuration of the facility. There will be no change in the level of controls or methodology used for the processing of radioactive effluents or handling of solid radioactive waste, nor will the proposal result in any change in the normal radiation levels in the plant; therefore, there will be no increase in individual or cumulative occupational radiation exposure resulting from this change.
7.0 REFERENCES
from 1 . Letter CC. N. Swenson, (Exelon Generation Company, LLC), to NRC, "Technical Specification Change Request No. 280 - Reactor Water Clean-Up High Energy Line Break Detection and Isolation," dated February 2, 2005 2 . "Ambient and Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection," L-001324, Revision 5A
- 3. "Ambient and Differential Temperature Design Basis Calculations for Reactor Coolant Leak Detection," L-001324, Revision 0
- 4. "FICIC Equipment Area/Pipe Tunnel High Ambient and Differential Temperature Outboard and Inboard Error Analysis," NED-I-EIC-0213, Revision 1 G
- 5. Letter from NRC to 0. D. Kingsley, (Exelon Generation Company, LLC), "Issuance of Amendments," dated March 30, 2001 Page 1 0 of 10
ATTACHMENT 2 Markup of Proposed Technical Specifications Page Change LASALLE COUNTY STATION REVISED TS PAGE 3.3 .6.1-7
Primary Containment Isolation Instrumentation 3 .3 .6 .1 Table 3 .3 .6 .1-1 (page 2 of 4)
Primary Containment Isolation instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SU~ VE E ALLOWABLE FUNCTION CONDITio" SYSTEM ACTION C .1 RANHW40 ALUE (continued)
- e. 1,2,3 SP 3 .3 .6 .1 .1 a 37 .0 inches SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 Reactor SR 3 .3 .6 .1 .1 ? 11 .0 inches Level-Low, Level 3 SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 Manual Initiation 1 .2,3 1 G SR 3 .3 .6 .1 .5 NA
- 3. Reactor Core Isolatio Cooling (RCIC) System Isolation RCIC Steam Line lao 1 F A 3 .3 .6 .1 .2 5 176 .4 inches Flow-High SR 3,3 .6 .1 .3 water 0 3 .3 .6 .1 .5 RCIC Steam Line 1 F SR 3 .3 .6 .1 .2 > 2 .6 seconds and Flow-Timer SR 3 .3 .6 .1 .4 <_ 5 .5 seconds 2 3 .3 .6 .1 .5 RCIC Steam Supply 1,2,3 2 F SR 3 .3 .6 .1 .2 ? 58 .2 prig Pressure-Low SR 3,3 .6-4 5 13~1 .5 RCIC Turbine Exhaust 1,2,3 2 F SR 3 .3 .6 .1 .2 :5 300 inches water Diaphragm Pressure-High 5 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5
.2, Ct -7 . 0 , F RCIC Equipment Room 1,2,3 1 F SR 3 .3 .6 .1-7emperature-High 5 3 .3 .6 .1 .2 SR 3,3 .6 .1-4 SR 3 .3 .6 .1 .5 I 99 .0 0 F RCIC Equipment Rcom 1,2,3 1 F SR 3 .3 .6 .1 .1 s; Differential 5 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 F
RAC Steam Line Tunnel 1,2,3 1 F SR h3J .1-1 S Temperature-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 j b 3 . 0'*F Steam Line Tunnel 1,2,3 SR 3 .3 .6 .1 .1 I 4SV*+-
rential A 3,3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .4 5 hhvi .5 Drywell Pressure-High 1,2,3 2 F SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 (continued)
LaSalle 1 and 2 3 .3 .6 .1-7 Amendment No .
ATTACHMENT 3 Typed Page for Technical Specification Change LASALLE COUNTY STATION REVISED TS PAGE 3.3.6.1-7
Primary Containment Isolation Instrumentation 3 .3 .6 .1 Tab :
Prirr=rv Ccnta aticn I-, _ .
ICABLE .,"S
_S DR RE UIRED _,
E rt- P R REC SURVEIL . ;E ALLOWABLE
-DNS i S EM ACi ,I C .1 REQU - ' S VALUE Isolation Reactor Vesse idaYer 1,2,3 2 a SR 3 .3 .6 .1 .1 ? -137 .3 inches Level-Low Low Low, SR 3 .3 .6 .1 .2 Level 1 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 Reactor 1,0 ' 3 SR 3 .3 .6 .1 .1 o 11 .0 inches Level-Low, Level SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 Manual Initiation 1,2,3 1 G SR 3 .3 .6 .1 .5 Reactor Core Isolation Cooing (RCIC) System isolation RCIC Steam Line 1,2,3 1 F SR 3 .3 .6 .1 .2 _ 176 .0 inches Flow-Nigh SR 3 .3 .6 .1 .3 water SR 3 .3 .6 .1 .5
- b. RCIC Steam Line 1,2,3 1 F SR 3 .3 .6 .1 .2 >_ 2 .6 seconds and Flow-Timer SR 3 .3 .6 .1 .4 <_ 5 .5 seconds SR 3 .3 .6 .1 .5 RCIC Steam Supply 1,2,3 2 F SR 3 .3 .6 .1 .2 z 58 .2 psig Pressure-Low SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 RCIC Turbine Exhaust 1,2,3 2 F SR 3 .3 .6 .1 .2 s 300 inches water Diaphragm Pressure-High SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 e . RCIC Equipment Room 1,2,3 1 F SR 3 .3 .6 .1 .1 _ 297 .0°F Temperature-High SR 3 .3 .6 .1 .2 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 RCIC Equipment Room 1,2,3 1 F SR 3 .3 .6 .1 .1 <_ 188 .0°F Differentia SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .4 OR 3 .3 .6 .1 .5 Steam Line Tunnel 1 ,2,3 SR 3 .3 .6 .1 .1 5 267 .0'F tore-Hi OR 3 .3 .6 .1 .2 OR 3 .3 .6 .1 .4 OR 3 .3 .6 .1 .5 RCIC Steam Line Tunnel 1,2,3 1 F SR 3 .3 .6 .1 .1 _ 163 .0°F Differential SR 3 .3 .6 .1 .2 Temperature-High SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 Drywe'1 Pressure-H=gh 1,2,3 2 F SR 3 .3 .6 .1 .2 < 1 .77 SR 3 .3 .6 .1 .4 SR 3 .3 .6 .1 .5 (continued)
LaSalle 1 and 2 3 .3 .6 .1-7 Amendment No . 1