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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 April 4, 2006 RS-06-044 U. S . Nuclear Regulatory Commission ATTN : Document Control Desk Washington, DC 20555 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 License Amendment to Technical Specification 5 .6.5, "Core Operating Limits Report (COLR) ."
References:
(1) Letter from K. R. Jury (Exelon Generation Company, LLC) to USNRC, "Request for Amendment to Technical Specifications Section 5 .6.5, `Core Operating Limits Report (COLR)'", dated March 7, 2005 (2) Letter from S. P. Sands (USNRC) to C. M. Crane (Exelon Generation Company, LLC), LaSalle County Station, Units 1 and 2, "Issuance of Amendments Re: Technical Specifications Section 5 .6.5, `Core Operating Limits Report (COLR)'", dated February 1, 2006 Letter from H . N. Berkow (USNRC) to R. L. Gardner (Framatome), "Final Safety Evaluation for Framatome ANP Topical Report ANF-1358(P),
Revision 3, `The Loss of Feedwater Heating Transient in Boiling Water Reactors'", dated September 20, 2005 Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit,"
Exelon Generation Company, LLC, (EGC), hereby requests an 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 . The proposed changes will add one NRC-approved topical report reference to the list of analytical methods in TS 5.6.5, "Core Operating Report Limits (COLR)," and will delete seven obsolete references from the same TS section .
April 4, 2006 U.S . Nuclear Regulatory Commission Page 2 In Reference 1, EGC submitted a license amendment request (LAR) to add two NFIC-approved topical report references that provided: 1) a determination of fuel assembly critical power for previously loaded Global Nuclear Fuel (GNF) GE14 fuel, co-resident with reloaded Framatome ANP (FRA-ANP) ATRIUM-10 fuel; and 2) a new FRA-ANP EXEM BWR-2000 LOCA Methodology. The LAR was submitted in support of the re-introduction of ATRIUM-10 fuel in Unit 1atLSCS. The NRC approved this LAR in Reference 2. This submittal supports the continued irradiation of ATRIUM-10 in the LSCS reactors and the use of an NRC-approved analytical methodology for evaluating loss of feedwater heater (LOFWH) transients .
The added reference, Topical Report ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," will list a FRA-ANP method for evaluating the LOFWH transient. This topical report has been previously reviewed and approved by the NRC for use by licensees in Reference 3.
The seven deleted references describe previously approved Global Nuclear Fuel (GNF) and FRA-ANP methodologies for the analyses of ATRIUM-913 and GE9 fuel . Both of these fuel types have been or will be completely discharged from both LSCS reactors after the loading of ATRIUM-10 fuel during the LSCS Unit 2 refuel outage currently scheduled to begin in February 2007 (i .e., L2R1 1) .
This request is subdivided as follows :
Attachment 1 provides a description and evaluation of the proposed changes .
Attachment 2 provides a mark-up of TS pages with the proposed changes indicated.
Attachment 3 provides the typed TS pages with the proposed changes incorporated .
EGC requests approval of the proposed change by February 26, 2007 to support restart following I PR1 1 . Once approved, the amendment will be implemented within 30 days .
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.
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.
April 4, 2006 U.S. Nuclear Regulatory Commission Page 4 Should you have any questions or require additional information, please contact Mr. John L .
Schrage at (630) 657-2821 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 4th day of April 2006 .
Respectfully, Keith R. Jury I Director, Licensing and Regulatory Affairs : Evaluation of Proposed Changes : Mark-up of Proposed Technical Specifications Page Changes : Typed Pages for Technical Specifications Page Changes
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 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
- 12. Applicable Regulatory Requirements/Criteria 6.0 ENVIRONMENTAL EVALUATION
7.0 REFERENCES
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 1 .0 DESCRIPTION Pursuant to 10 CFR 50.90, 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 will add an NRC-approved topical report reference to the list of analytical methods in TS 5.6.5, "Core Operating Limits Report (COLR)," that may be used to determine core operating limits, and delete seven obsolete references from the same TS section .
The proposed changes will:
1 . add an NRC-approved Framatome Advanced Nuclear Power, Inc . (FRA-ANP) topical report reference for an updated methodology for evaluating loss of feedwater heating (LOFWH) transients ; and
- 2. delete seven references that were used in the analyses of ATRIUM-913 and GE9 fuel . These fuel types will no longer be irradiated in the LSCS reactors following the upcoming Unit 2 refueling outage, which is currently scheduled to begin February 2007 (i .e., 1_2131 1).
In Reference 1, EGC submitted a license amendment request (LAR) to add two NRC-approved topical report references that provided: 1) a determination of fuel assembly critical power for previously loaded Global Nuclear Fuel (GNF) GE14 fuel, co-resident with reloaded Framatome ANP (FRA-ANP) ATRIUM-10 fuel ; and 2) a new FRA-ANP EXEM BWR-2000 LOCH Methodology. The LAR was submitted in support of the re-introduction of ATRIUM-10 fuel in Unit 1 at LSCS. The NRC approved this LAR in Reference 2. The current submittal supports the continued irradiation of ATRIUM-10 in the LSCS reactors and the use of an NRC-approved analytical methodology for evaluating LOFWH transients .
ATRIUM-10 fuel is manufactured and licensed by FRA-ANP, a subsidiary of the AREVA group . This organization has previously been known as Siemens Power Corporation (SPC). Framatome ANP will analyze the LSCS Unit 2 Cycle 12 core reload .
2.0 PROPOSED CHANGE
S The added reference to TS 5.6.5 will list a FRA-ANP method for analyzing the LOFWH transient for various mixtures of Global Nuclear Fuels (GNF) and FRA-ANP fuel assemblies (i.e., ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors") . This topical report has been previously reviewed and approved by the NRC for use by licensees in Reference 3 .
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES The proposed changes will modify TS 5 .6.5 as follows:
1 . The current reference numbers 1, 2, 8, 12, 17, 18 and 21 are deleted.
2 . The remaining references are renumbered from 1 to 17.
3 . Topical Report ANF-1358(P)(A), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors," is added as a new Reference 18.
The marked-up and retyped TS pages are provided in Attachments 2 and 3.
3.0 BACKGROUND
The analytical methods currently listed in TS 5 .6.5 support the determination of core operating limits for both units by using the GNF or FRA-ANP methodology. LSCS Unit 1 currently uses a mixture of ATRIUM-10 and GE14 fuel in the core. The determination of GE14 and ATRIUM-10 fuel assembly critical power for the current operating cycle is determined with a FRA-ANP critical power correlation. Reference 2 provides the NRC approval for the use of the FRA-ANP critical power correlation for the GE14 fuel . Overall core operating limits for LSCS Unit 1 are determined using a FRA-ANP methodology, including a cycle-specific FRA-ANP evaluation of LOFWH transients .
LSCS Unit 2 currently uses a mixture of ATRIUM-9B, ATRIUM-10 and GE-14 fuel . The determination of fuel assembly critical power for the mixture of ATRIUM-913, ATRIUM-10 and GE14 fuel is determined with a GNF critical power correlation, and overall core operating limits are determined using GNF methodology.
EGC will continue to load FRA-ANP ATRIUM-10 fuel and completely discharge ATRIUM-913 during the upcoming Unit 2 Refueling Outage (L2R1 1) currently scheduled to begin February 2007. All GE9 fuel was completely discharged during a previous refueling outage. LSCS will use the most recent FRA-ANP methodologies to determine overall core operating limits for future core configurations, vice the current GNF methodology. This change will require the listing of an additional analytical methodology for evaluating LOFWH conditions with the FRA-ANP methodology. Thus, the proposed change will allow LSCS to use FRA-ANP's most recent LOFWH analytical method to determine core operating limits for LSCS Unit 1 and Unit 2.
4.0 TECHNICAL ANALYSIS
TS 5.6.5 requires that a COLR be established and that the analytical methods used to determine the core operating limits be those previously reviewed and approved by the NRC. The approved analytical methods are listed in TS 5.6.5.b. The analytical methods listed in this TS section support operation of certain types of fuel contained in the reactor Page 3 of 7
ATTACHMENT I EVALUATION OF PROPOSED CHANGES core, and list the analytical codes that are used to calculate operating parameters .
These analytical codes are utilized to predict core behavior under normal and accident conditions. The proposed addition of the FRA-ANP topical report will incorporate the analytical code necessary to use the most recent FRA-ANP methodologies to determine overall core operating limits for future core configurations .
The NRC, in Reference 3, approved topical report ANF-1358(P), Revision 3, "The Loss of Feedwater Heating Transient in Boiling Water Reactors ." This FRA-ANP topical report describes revisions made to the methodology for evaluation of LOFWH conditions. LSCS has determined that the use of the FRA-ANP topical report, described in Reference 3, and the LOFWH evaluation methodology contained in this report is appropriate for LSCS Units 1 and 2, and provides an equivalent level of protection as that currently provided.
The seven references that will be deleted from TS 5 .6.5 describe previously approved Global Nuclear Fuel (GNF) and FRA-ANP methodologies for the analyses of ATRIUM-9B and GE9 fuel . Both of these fuel types have been or will be completely discharged from both LSCS reactors after the loading of ATRIUM-10 fuel during the LSCS Unit 2 refuel outage currently scheduled to begin in February 2007 (i .e., L2R1 1) . Thus, these references are obsolete and unnecessary.
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration Pursuant to 10 CFR 50.90, Exelon Generation Company, LLC, (EGC), requests an amendment to Appendix A, Technical Specifications (TS), of Facility Operating License Nos. NPF-1 1 and NPF-18 for LaSalle County Station (LSCS), Units 1 and 2. The proposed amendment will add an NRC-approved topical report reference to the list of analytical methods in TS 5.6.5, "Core Operating Limits Report (COLR)," that may be used to determine core operating limits, and delete seven obsolete references from the same TS section .
According to 10 CFR 50.92(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:
1 . Involve a significant increase in the probability or consequences of an accident previously evaluated ; or
- 2. Create the possibility of anew or different kind of accident from any accident previously evaluated ; or
- 3. 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 Page 4 of 7
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 10 CFR 50.92 is provided below regarding the proposed license amendment.
1 . Does the change involve a significant increase in the probability or consequences of an accident previously evaluated?
TS 5.6.5 lists NRC-approved analytical methods used at LaSalle County Station (LSCS) to determine core operating limits . The proposed changes will add an NRC-approved topical report reference to the list of administratively controlled analytical methods in TS 5 .6.5, "Core Operating Limits Report (COLR)," that can be used to determine core operating limits, and delete seven obsolete references .
The addition of a Frarnatome ANP (FRA-ANP) methodology to determine overall core operating limits for future LSCS core configurations was approved by the NRC in Reference 2. LSCS Unit 2 will continue to load Framatome ANP ATRIUM-10 fuel during the Unit 2 Refueling Outage 11 currently scheduled for February 2007. The proposed change to TS Section 5.6.5 will add a FRA-ANP methodology as a reference to determine core operating limits for loss of feedwater heater (LOFWH) conditions. Thus, the proposed change will allow LSCS to use the most recent FRA-ANP methodology for analysis of LOFWH conditions .
The addition and deletion of approved analytical methods in TS Section 5.6 .5 has no effect on any accident initiator or precursor previously evaluated and does not change the manner in which the core is operated . The NRC-approved methods, ensure that the output accurately models predicted core behavior, have no effect on the type or amount of radiation released, and have no effect on predicted offsite doses in the event of an accident. Additionally the NRC-approved methods do not change any key core parameters that influence any accident consequences. Thus, the proposed changes do not have any effect on the probability of an accident previously evaluated.
The methodology conservatively establishes acceptable core operating limits such that the consequences of previously analyzed events are not significantly increased.
The proposed changes in the list of analytical methods do not affect the ability of LSCS to successfully respond to previously evaluated accidents and does not affect radiological assumptions used in the evaluations . Thus, the radiological consequences of any accident previously evaluated are not increased .
Therefore, the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES
- 2. Does the change create the possibility of a new or different kind of accident from any accident previously evaluated?
I The proposed changes to TS Section 5.6.5 do not affect the performance of any LSCS structure, system, or component credited with mitigating any accident previously evaluated . The NRC-approved analytical methodology for evaluating LOFWH transients will not affect the control parameters governing unit operation or the response of plant equipment to transient conditions. The proposed changes do not introduce any new modes of system operation or failure mechanisms .
Therefore, the proposed changes do not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the change involve a significant reduction in a margin of safety?
The proposed changes will add a reference to the list of analytical methods in TS 5 .6.5 that can be used to determine core operating limits and delete seven obsolete references . The proposed changes do not modify the safety limits or setpoints at which protective actions are initiated and do not change the requirements governing operation or availability of safety equipment assumed to operate to preserve the margin of safety . Therefore, the proposed changes provide an equivalent level of protection as that currently provided.
Therefore, the proposed changes do not involve a significant reduction in a margin of safety .
Based on the above information, EGC concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 Applicable Regulatory Requirements/Criteria TS 5.6.5 lists the NRC-approved analytical methods used at LSCS to determine core operating limits . The listed NRC-approved analytical methods provide the necessary administrative controls to ensure operation of the facility in a safe manner and thus are required for inclusion in the LSCS Technical Specifications in accordance with 10 CFR 50.36, "Technical specifications," paragraph (c)(5) . The deleted references describe analytical methodologies for fuel that will no longer be used at LSCS Units 1 and 2; as such, these references should be deleted from the TS.
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES 6.0 ENVIRONMENTAL EVALUATION EGC has evaluated this proposed 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 this proposed change meets the criteria for 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 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 processed as an amendment to the 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 surveillance requirement and the amendment meets the following specific criteria :
The amendment involves no significant hazards consideration .
As demonstrated in Section 5.1 above, "No Significant Hazards Consideration,"
the proposed change does not involve any significant hazards consideration.
(ii) There is no significant change in the types or significant increase in the amounts of any effluent that may be released offsite.
The proposed changes will add a reference to the list of administratively controlled analytical methods that can be used to determine core operating limits and delete seven obsolete references . The proposed change 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 offsite.
ATTACHMENT 1 EVALUATION OF PROPOSED CHANGES
7.0 REFERENCES
1 . Letter from K. R. Jury (EGC) to USNRC, "Request for Amendment to Technical Specifications Section 5.6.5, `Core Operating Limits Report (COLR)'", dated March 7, 2005
- 2. Letter from S. P. Sands (USNRC) to C. M . Crane (EGC), "LaSalle County Station, Units 1 and 2 - Issuance of Amendments Re: Technical Specifications Section 5.6.5, `Core Operating Limits Report (COLR)'", dated February 1, 2006
- 3. Letter from H. N. Berkow (USNRC) to R. L. Gardner (Framatome), "Final Safety Evaluation for Framatome ANP Topical Report ANF-1358(P), Revision 3, `The Loss of Feedwater Heating Transient in Boiling Water Reactors'"
dated September 20, 2005
ATTACHMENT 2 Mark-up of Proposed Technical Specifications Page Changes LaSalle Country Station, Units 1 and 2 REVISED TS PAGES 5 .6-3 5 .6-4
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .5 CORE OPERATING LIMITS REPORT (COLR) (continued)
- 4. The Rod Block Monitor Upscale Instrumentation Setpoint for the Rod Block Monitor-Upscale Function Allowable Value for Specification 3 .3 .2 .1 .
- b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents :
ANF-1125(P)(A), "ANFB Critical Power Correlation ."
Letter, Ashok C . Thadani (NRC) to R .A . Copeland (SPC),
"Acceptance for Referencing of ULTRAFLOWT" Spacer on 9x9-IX/X BWR Design," July 28, 1993 .
XN-NF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors ."
ANF-913(P)(A), "COTRANSA 2 : A Computer Program for Boiling Water Reactor Transient Analysis ."
6 ANF-CC-33(P)(A), "HUXY : A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option ."
XN-NF-80-19(P)(A), "Advanced Nuclear Fuel Methodology for Boiling Water Reactors ."
XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel ."
ANF-89-014(P)(A), "ANF Corporation Generic Mechanical Design for ANF Corporation 9x9-IX and 9x9-9X BWR Reload Fuel . "
EMF-CC-074( P) (A), Volume 4 - "BWR Stability Analysis :
Assessment of STAIF with input from MICROBURN-B2 ."
XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model ."
XN-NF-84-105(P)(A), "XCOBRA-T : A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis ."
(continued)
LaSalle I and 2 5 .6-3 Amendment No . 64113 ~-'
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 CORE OPERATING LIMITS REPORT (COLR) (continued) 12 . ANF-91-048(P)(A), "ANF Corporation Methodology for oiling Water Reactors EXEM BWR Evaluation Model ."
`y, ,1.22'. EMF-2209(P)(A), "SPCB Critical Power Correlation ."
/CJ. 14'. ANF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs ."
NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel ."
Icy, k~ NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods ."
EMF-1125(P)(A), "ANFB Critical Power Correlation Application for Co-Resident Fuel ."
ANF-1125(P)(A), "ANFB Critical Power Correlation Determination of ATRIUM-9B Additive Constant Uncertainties ."
1-T. EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model ."
EMF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors : Evaluation and Validation of CASMO-4/MICROBURN-B2 ."
NEDC-32981P(A), "GEXL96 Correlation for Atrium-9B Fuel ."
?.2 NEDC-33106P, "GEXL97 Correlation for Atrium-i0 Fuel .
lto, 2T EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel ."
1 -7, ,X' EMF-2361(P)(A), "EXEM BWR-2000 ECCS Evaluation Model .
The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i .e ., report number, title, revision, date, and any supplements) .
/AJ5 C72-1"" t (continued)
LaSalle I and 2 5 .6-4 dmert No . %4/~ 16
INSERT 1
- 18. ANF-1 358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors."
ATTACHMENT 3 Typed Pages Technical Specifications Page Changes LaSalle Country Station, Units 1 and 2 REVISED TS PAGES 5 .6-3 5 .6-4
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .5 CORE OPERATING LIMITS Kew nowu (continued)
The Rod Block Monitor Upscale Instrumentation Setpoint for the Rod Block Monitor-Upscale Function Allowable Value for Specification 3 .3 .2 .1 .
The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents :
I . XN-NF-524(P)(A), "ANF Critical Power Methodology for Boiling Water Reactors ."
- 2. ANF-913(P)(A), "COTRANSA 2 : A Computer Program for Boiling Water Reactor Transient Analysis ."
- 3. ANF-CC-33(P)(A), "HUXY : A Generalized Multirod Heatup Code with 10 CFR 50, Appendix K Heatup Option ."
XN-NF-80-19(P)(A), "Advanced Nuclear Fuel Methodology for Boiling Water Reactors ."
5, XN-NF-85-67(P)(A), "Generic Mechanical Design for Exxon Nuclear Jet Pump BWR Reload Fuel ."
EMF-CC-074(P)(A), Volume 4 - "BWR Stability Analysis :
Assessment of STAY with input from MICROBURN-B2 ."
XN-NF-81-58(P)(A), "RODEX2 Fuel Rod Thermal-Mechanical Response Evaluation Model ."
- 8. XN-NF-84-105(P)(A), "XCOBRA-T : A Computer Code for BWR Transient Thermal-Hydraulic Core Analysis ."
- 9. EMF-2209(P)(A), "SPCB Critical Power Correlation ."
10 . IMF-89-98(P)(A), "Generic Mechanical Design Criteria for BWR Fuel Designs ."
11 . NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel ."
12 . NFSR-0091, "Benchmark of CASMO/MICROBURN BWR Nuclear Design Methods ."
(continued)
LaSalle 1 and 2 5 .6-3 Amendment No . /
Reporting Requirements 5 .6 5 .6 Reporting Requirements 5 .6 .5 CORE OPERATING - LIMITS REPORT unjur (continued) 13 EMF-85-74(P)(A), "RODEX2A (BWR) Fuel Rod Thermal-Mechanical Evaluation Model ."
14 MF-2158(P)(A), "Siemens Power Corporation Methodology for Boiling Water Reactors : Evaluation and Validation of CASMO-4/MICROBURN-B2 ."
15 NEDC-33106P, - GEXL97 Correlation for Atrium-10 Fuel,"
16 EMF-2245(P)(A), "Application of Siemens Power Corporation's Critical Power Correlations to Co-Resident Fuel ."
17 MF-2361(P)(A), - EXEM BWR-2000 ECCS Evaluation Model .
18 ANF-1358(P)(A), "The Loss of Feedwater Heating Transient in Boiling Water Reactors ."
The COLR will contain the complete identification for each of the TS referenced topical reports used to prepare the COLR (i .e ., report number, title, revision, date, and any supplements) .
(continued)
LaSalle 1 and 2 5 .6-4 Amendment No . /