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Category:Letter type:RS
MONTHYEARRS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation 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-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release 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-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release 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-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release 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-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air 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-23-003, 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-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing 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-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications 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-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station 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-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan 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-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock 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-22-027, 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-22-023, 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-22-019, 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-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values 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-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-070, Proposed Alternative to Utilize Code Case N-8932021-06-30030 June 2021 Proposed Alternative to Utilize Code Case N-893 RS-21-069, Third Inservice Inspection Interval Relief Request I3R-182021-06-28028 June 2021 Third Inservice Inspection Interval Relief Request I3R-18 RS-21-054, Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations2021-04-29029 April 2021 Response to NRC Regulatory Issue Summary 2021-01, Preparation and Scheduling of Operator Licensing Examinations 2024-09-09
[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 ML24045A0262024-02-14014 February 2024 License Renewal Application RS-24-012, Application for Renewed Operating License - Appendix E, Applicants Environmental Report2023-11-30030 November 2023 Application for Renewed Operating License - Appendix E, Applicants Environmental Report RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation 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-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing 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-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock 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 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 ML21188A0202021-08-11011 August 2021 Issuance of Amendment No. 239 One-Time Extension of Containment Type a Integrated Leakage Rate Test Frequency RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications 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-21-014, License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency2021-02-24024 February 2021 License Amendment Request for One-Time Extension of the Containment Type a Integrated Leakage Rate Test Frequency 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-20-053, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2020-04-30030 April 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 RS-19-054, Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-06-18018 June 2019 Application to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control 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-18-116, Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 12018-09-28028 September 2018 Application to Revise Technical Specifications to Adopt TSTF-476, Improved BPWS Control Rod Insertion Process (NEDO-33091), Revision 1 RS-18-105, License Amendment Request to Recapture Low-Power Testing Time2018-09-17017 September 2018 License Amendment Request to Recapture Low-Power Testing Time 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-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) ML18053A1822018-01-31031 January 2018 Enclosure 3 - Clinton Power Station, Unit 1 - Evaluation of Proposed Changes 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 ML18053A1702018-01-31031 January 2018 Attachment 3A - Clinton Power Station, Unit 1 - Marked-up Emergency Plan EP-AA-1000 Pages ML18053A1712018-01-31031 January 2018 Attachment 3B - Clinton Power Station, Unit 1 - Clean Emergency Plan EP-AA-1000 Pages RS-18-005, License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation2018-01-0909 January 2018 License Amendment Request to Incorporate Revised Alternative Source Term Dose Calculation 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-17-076, License Amendment Request to Revise Spent Fuel Pool Level2017-07-18018 July 2017 License Amendment Request to Revise Spent Fuel Pool Level RS-17-017, License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations2017-05-0404 May 2017 License Amendment Request to Clarify RHR Subsystem Operability Requirements During Decay Heat Removal Operations 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-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-228, Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-211, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 12016-11-0404 November 2016 License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition - Supplement 1 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-16-143, License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition2016-08-11011 August 2016 License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition ML16229A2792016-08-11011 August 2016 Attachments 1 - 7: Clinton - License Amendment Request - Proposed Changes to the Emergency Plan for Permanently Defueled Condition 2024-04-12
[Table view] Category:Technical Specifications
MONTHYEARML24157A3242024-07-11011 July 2024 Issuance of Amendment No. 254 Revision of Reactor Water Cleanup Isolation Valve Timing 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-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air ML22095A2702022-05-12012 May 2022 Issuance of Amendment Nos. 227, 227, 229, 229, and 245, Respectively, Regarding Adoption of TSTF 273, Safety Function Determination Program Clarifications 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 RS-22-048, 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls)2022-03-31031 March 2022 2 to Updated Safety Analysis Report, B 2.0 Safety Limits (Sls) ML22111A2142022-03-31031 March 2022 2 to Updated Safety Analysis Report, Chapter 16, Technical Specifications 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 ML21193A1302021-07-14014 July 2021 Correction to Amendment No. 238 Issued June 28, 2021, Technical Specifications Task Force Traveler TSTF-505, Revision 2, Provide Risk Informed Extended Completion Times - RITSTF Initiative 4B ML21033A5302021-04-0101 April 2021 Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems 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 ML18303A3132019-01-0303 January 2019 Issuance of Amendment 221 Regarding Revised Alternative Source Term Dose Calculation 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-16-228, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-16-228, Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2016-11-17017 November 2016 Clinton Power Station License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition ML16111A1042016-05-11011 May 2016 Issuance of Amendments to Revise the Reactor Steam Dome Pressure in Technical Specification 2.1.1, Reactor Core SLs (CAC Nos. MF6640-MF6644) ML15251A5842015-12-18018 December 2015 Issuance of Amendment Concerning Revision to Integrated Leak Test Intervals (TAC No. MF5291)(RS-14-308) ML15280A2582015-10-22022 October 2015 Issuance of Amendment Related to One-Time Extension of Completion Time for Shutdown Service Water (TAC No. MF6705)(RS-15-264) RS-15-260, Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time2015-09-30030 September 2015 Response to Request for Additional Information Regarding License Amendment Request for a One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time RS-15-246, Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time2015-09-10010 September 2015 Exigent License Amendment Request for One-Time Extension of the Shutdown Service Water Division 2 Subsystem Completion Time ML15141A0582015-07-28028 July 2015 Issuance of Amendments Regarding Emergency Action Level Schemes (TAC Nos. MF4232-MF4251) RS-15-121, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2015-04-21021 April 2015 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. ML14323A5222015-04-0808 April 2015 Issuance of Amendments Regarding the Emergency Plan Definition of Annual Training RS-14-308, License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment.2014-11-17017 November 2014 License Amendment Request to Revise Technical Specification 5.5.2, Primary Coolant Sources Outside Containment. ML14085A5322014-07-21021 July 2014 Issuance of Amendments Adoption of TSTF-522 Ventilation System Surveillance Requirements 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 ML1122319432011-10-0404 October 2011 Issuance of License Amendment No. Request for Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Values to Licensee Control RS-11-117, License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating.2011-08-15015 August 2011 License Amendment Request to Modify Technical Specifications Section 3.8.1, AC Sources - Operating. RS-11-073, License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies.2011-06-13013 June 2011 License Amendment Request to Modify Technical Specifications Section 3.1.2, Reactivity Anomalies. ML1109702192011-05-0606 May 2011 Correction to Issuance of License Amendments Regarding Risk-informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a License-controlled Program RS-10-050, License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing2010-10-28028 October 2010 License Amendment Request to Remove Operating Mode Restrictions for Performing Division 3 AC Sources Surveillance Testing RS-10-148, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control2010-10-0808 October 2010 License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control RS-10-131, License Amendment Request to Revise Technical Specifications Limiting Condition for Operation 3.7.6, Main Turbine Bypass System2010-09-23023 September 2010 License Amendment Request to Revise Technical Specifications Limiting Condition for Operation 3.7.6, Main Turbine Bypass System RS-10-039, License Amendment Request to Administratively Revise Technical Specifications2010-06-0404 June 2010 License Amendment Request to Administratively Revise Technical Specifications RS-10-093, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B2010-05-21021 May 2010 Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Revision 3, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML1002000052010-01-15015 January 2010 License Amendment, Modify CPS License Condition 2.B.(6) and Create New License Conditions 1.J, 2.B.(7) and 2.C.(25) as Part of a Pilot Program to Irradiate Cobalt (Co)-59 Target to Produce Co-60 RS-09-074, License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies2009-06-26026 June 2009 License Amendment Request to Modify Clinton Power Station Facility Operating License in Support of the Use of Isotope Test Assemblies ML0907108682009-04-0202 April 2009 Licensed Amendment, Adopted TSTF-2, Relocate the 10-year Sediment Cleaning of the Fuel Oil Storage Tank to Licensee Control ML0829400102008-10-30030 October 2008 Issuance of Amendment Technical Specification Change as Part of Implementation of TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil ML0826103082008-09-12012 September 2008 Tech Spec Pages for Amendment 181 License Amendment to Increase the Interval Between Local Power Range Monitor 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 ML0819601482008-06-30030 June 2008 Tech Spec Page for Amendment 179 Regarding TS Changes Related to Surveillance Frequency for Scram Discharge Volume Water Level Float Switch 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. 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 ML0731003892007-10-31031 October 2007 Technical Specifications, Changes Resulting from the Incorporation of TSTF-448, Control Room Habitability. RS-07-133, Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process2007-09-27027 September 2007 Application for Technical Specification Change TSTF-374, Revision to TS 5.5.9 for Diesel Fuel Oil Using Consolidated Line Item Improvement Process RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators2007-07-19019 July 2007 Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators 2024-07-11
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RS-05-032 10 CFR 50 .90 March 25, 2005 U . S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Clinton Power Station, Unit 1 Facility Operating License No . NPF-62 NRC Docket No. 50-461 Subject : Request for Technical Specification Change to Revise Secondary Containment Bypass Leakage Surveillance Requirement
References:
(1) Letter from Michael J . Pacilio (AmerGen Energy Company, LLC) to U . S. NRC, "Request for License Amendment Related to Application of Alternative Source Term," dated April 3, 2003 (2) Letter from Keith R. Jury (Exelon Generation Company, LLC) to U . S . NRC, "Additional Information Supporting the Request for License Amendment Related to Application of the Alternative Source Term," dated December 23, 2003 Letter from Patrick R. Simpson (Exelon Generation Company, LLC) to U. S . NRC, "Request for Exemption from 10 CFR 50 Appendix J in Support of Request for License Amendment Related to Application of the Alternative Source Term," dated July 1, 2004 Pursuant to 10 CFR 50.90, "Application for amendment of license or construction permit," AmerGen Energy Company, LLC (AmerGen) hereby requests an amendment to Appendix A, Technical Specifications (TS), of Facility Operating License No. NPF-62 for Clinton Power Station (CPS), Unit 1 . The proposed change revises TS Surveillance Requirement (SR) 3.6.1 .3.8 to add a note excluding leakage through primary containment penetrations 1 MC-1 01 and 1 MC-1 02 from the secondary containment bypass leakage total specified in the SR.
In Reference 1, AmerGen requested a change to the TS to support application of an alternative source term (AST) methodology in accordance with 10 CFR 50.67, "Accident source term," with the exception that Technical Information Document (TID) 14844, "Calculation of Distance Factors for Power and Test Reactor Sites," will continue to be
March 25, 2005 U. S . Nuclear Regulatory Commission Page 2 used as the radiation dose basis for equipment qualification. AmerGen had indicated in Reference 1 that the dose consequences from leakage through the primary containment purge lines had been analyzed based on an assumed leakage through those lines.
Since there are separate TS limits on these leak paths, and since dose consequences were evaluated separately, the leakage through the primary containment purge lines no longer needed to be considered in determining compliance with the primary containment leakage limit (La) or with the secondary containment bypass leakage limit (0.08*La) .
In response to a request for additional information (Reference 2), it was determined that this constituted an exception to the requirements of 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," and therefore AmerGen submitted an exemption request in Reference 3. Subsequent to submittal of Reference 3, the NRC indicated that an Appendix J exemption request would not be an acceptable approach for resolution of this issue. Therefore, AmerGen has decided to submit an amendment request to revise the secondary containment bypass leakage SR.
Revising the secondary containment bypass leakage SR will allow CPS to utilize the flexibility provided by the assumptions used in the AST analysis (i.e., the increased leakage through the primary containment purge lines and the separate dose analysis for this leakage) and still remain in compliance with the requirements of 10 CFR 50, Appendix J (i .e., no need for an exemption to Appendix J). Therefore, this proposed change acknowledges the separate dose analysis performed for the primary containment purge lines as provided in Reference 1 while ensuring the secondary containment bypass leakage rate is measured and verified against the required limit as specified in the Primary Containment Leakage Rate Testing Program . Based on the related issues between the AST analyses and this proposed amendment request, approval of this proposed change is contingent on the approval of the CPS application of the AST in Reference 1 .
In light of the above, AmerGen formally requests that the proposed 10 CFR 50, Appendix J exemption request provided in Reference 3 be withdrawn . to this letter provides the evaluation of the proposed change to TS SR 3.6.1 .3.8 for the revision to the secondary containment bypass leakage rate testing .
Attachments 2 and 3 provide a copy the of the marked up and typed TS page, respectively . contains copies of marked up TS Bases pages provided for information only .
AmerGen is requesting approval of this change by December 31, 2005 with implementation within 60 days of issuance of the amendment. Approval by this date will allow sufficient time to revise the Primary Containment Leakage Rate Testing Program prior to the start of the next refueling outage in February 2006.
There are no regulatory commitments contained in this letter .
This proposed change has been reviewed by the CPS Plant Operations Review Committee and approved by the Nuclear Safety Review Board in accordance with the requirements of the Quality Assurance Program .
March 25, 2005 U . S. Nuclear Regulatory Commission Page 3 AmerGen is notifying the State of Illinois of this application for amendment by transmitting a copy of this letter and its attachments to the designated State Official.
Should you have any questions related to this information, please contact Mr. Timothy A. Byam at (630) 657-2804 .
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 25th day of March 2005.
Keith R. Jury Director - Licensing and Regulatory Affairs AmerGen Energy Company, LLC Attachments:
- 1. Evaluation of Proposed Changes
- 2. Markup of Proposed Technical Specification Page I Retyped Technical Specification Page
- 4. Markup of Proposed Technical Specification Bases Page cc: Regional Administrator- NRC Region III NRC Senior Resident Inspector - Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
ATTACHMENT I Evaluation of Proposed Changes Page I of 7
Subject:
Request bar Technical Specification Change to Revise Secondary Containment Bypass Leakage Surveillance Requirement 1 .0 DESCRIPTION
2.0 PROPOSED CHANGE
S 10 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
6.0 ENVIRONMENTAL CONSIDERATION
7.0 REFERENCES
ATTACHMENT 1 Evaluation of Proposed Changes Page 2 of 7 1 .0 DESCRIPTION This is a request from AmerGen Energy Company, LLC (AmerGen) to amend Appendix A, Technical Specifications (TS), of Facility Operating License No. NPF-62 for Clinton Power Station (CPS) . The proposed change revises TS Surveillance Requirement (SR) 3.6 .1 .3.8 to add a note excluding leakage through primary containment penetrations 1 MC-1 01 and 1 MC-1 02 from the secondary containment bypass leakage total specified in the SR.
As described in Reference 1, AmerGen has performed a dose consequences analysis for leakage through the primary containment purge lines. The analysis assumed a leak rate of <0 .02 L,, for each penetration. Since a separate dose analysis had been performed far the primary containment purge lines, Reference 1 states that these penetrations no longer need to be considered in determining compliance with the secondary containment bypass leakage or the primary containment leakage rate limits .
Further evaluation determined that compliance with the requirements of 10 CFR 50, Appendix J, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors ; requires consideration of these penetrations in the secondary containment bypass leakage and primary containment leakage rates . Therefore, it was determined that this change be proposed.
Implementation of this proposed change will provide operational flexibility by allowing CPS to utilize the additional margin to the regulatory dose limits provided by the implementation of alternative source terms (AST).
2.0 PROPOSED CHANGE
S The proposed change revises the Note to TS SR 3.6.1 .3.8 to read as follows.
1 . Leakage through penetrations 1 MC-1 01 and 1 MC-1 02 is excluded .
- 2. Only required to be met in MODES 1, 2, and 3 ."
In addition, the TS Bases will be revised to document the basis for the proposed Note .
The Bases changes will be implemented in accordance with the CPS TS Bases Control Program defined in TS 5.5.11 .
3.0 BACKGROUND
According to 10 CFR 50, Appendix J, the purpose of the leak test requirements is to ensure the following.
(a) Leakage through the primary reactor containment or systems and components penetrating the containment does not exceed allowable leakage rates specified in the TS.
(b) Integrity of the containment structure is maintained during its service life.
ATTACHMENT I Evaluation of Proposed Changes Page 3 of 7 In accordance with 10 CFR 50, Appendix J, Option B, paragraph 111 .13, performance of Type B and Type C containment leakage tests (i .e., local leak rate tests) are required .
The Type B pneumatic tests detect and measure local leakage rates across pressure retaining, leakage-limiting boundaries while Type C pneumatic tests measure containment isolation valve leakage rates . These tests are required to be performed prior to initial criticality and periodically thereafter at intervals based on the safety significance and historical performance of each boundary and isolation valve. The intent of these tests is to ensure the integrity of the overall containment system as a barrier to fission product release to reduce the risk from reactor accidents. 10 CFR 50, Appendix J goes on to require that the tests must demonstrate that the sum of the leakage rates at accident pressure of Type 13 test, and pathway leakage rates from Type C tests, is less than the performance criterion (i .e., maximum allowable primary containment leakage rate, L a ) with margin, as specified in the TS .
The CPS primary containment purge lines (i .e., penetrations 1 MC-1 01 and 1 IVIC-1 02) are currently subject to leakage rate testing under TS SR 3.6.1 .3.5. As stated in the Bases for SR 3.6.1 .3.5, the current leakage rate acceptance criterion is X0.01 L a for each penetration. Historically, the leakage performance of penetrations 1 IVIC-1 01 and 1 IVIC-1 02 has been very good . There have been no failures to meet the required leakage limits for several cycles of operation.
However, as part of the AST analysis, the dose consequences from the leakage through the primary containment purge lines have been evaluated based on a leak rate of 0.02 L a for each penetration . The AST analysis, summarized in Reference 1, demonstrated that the consequences due to a loss of coolant accident (LOCA), including the assumed separate primary containment purge line leak rate and secondary containment bypass leakage, are within regulatory limits and are therefore acceptable . As a result, Reference 1 proposes a revised acceptance criterion of :!5;0.02 L a as identified in the Bases for SR 3.6.1 .3.5 . Referenc e 1 goes on to state that since a separate dose analysis has been performed for the primary containment purge lines, these penetrations no longer need to be considered in determining compliance with the secondary containment bypass leakage path SR 3.6.1 .3 .8 Wit of <0 .08 La . However, rather than take an exemption to the requirements of 10 CFR 50, Appendix J, AmerGen is requesting a change to the note for SR 3.6.1 .3.8 to take credit for the additional leakage assumed in the AST analysis .
4.0 TECHNICAL ANALYSIS
As discussed above, the dose consequences from leakage through the primary containment purge lines have been evaluated as part of the AST analysis . The analysis was based on a leak rate of 0.02 L a far each purge penetration. The AST analysis demonstrated that the consequences due to a LOCA, including the assumed separate primary containment purge line leak rate and secondary containment bypass leakage, are within regulatory limits and are therefore acceptable .
ATTACHMENT 1 Evaluation of Proposed Changes Page 4 of 7 The proposed change to SR 3.6.1 .3 .8 does not change the requirement to perform the ILRT per TS 5.5.13, "Primary Containment Leakage Rate Testing Program." The leakage through the primary containment purge lines will continue to be included in the containment leakage measured during the ILRT . The proposed change does not revise the acceptance criterion for the ILRT . CPS will also continue to test and evaluate the leakage through of the primary containment purge lines (i.e., penetrations 1 IVIC-1 01 and 1 IVIC-1 02) by implementation of TS SR 3.6.1 .3.5 . The results of the Type C testing on 1 IVIC-1 01 and 1 MC-1 02 will be evaluated against the specified 0.02 L, acceptance criterion assumed in the AST analysis . All remaining secondary containment bypass leakage will be evaluated against the 0.08 L, acceptance criterion specified in SR 3 .6.1 .3 .8. The proposed change does not revise the TS requirement to perform leakage rate testing on the primary containment purge valves with resilient seals. The containment purge penetrations will continue to be leak tested in accordance with a separate TS SR and will be evaluated against specified acceptance criteria based on analysis .
The proposed change to TS SIR 3.6.1 .3 .8 accounts for the revised LOCA analysis taking credit for the AST. The proposed change is based on the increase in the amount of leakage through the containment purge lines assumed in the AST LOCA analysis while also acknowledging the assumed secondary containment bypass leakage. Since the calculated doses remain within the regulatory limits for implementation of AST, then the proposed change is also acceptable .
5 .0 REGULATORY ANALYSIS 5.1 No Significant Hazards Consideration AmerGen Energy Company (AmerGen), LLC is requesting a revision to the Facility Operating License No. NPF-62 for Clinton Power Station (CPS), Unit 1 .
The proposed change revises the Note to Technical Specification (TS)
Surveillance Requirement (SR) 3.6.1 .3.8 to exclude the leakage through the primary containment purge penetrations from the secondary containment bypass leakage based on the assumptions used in the alternative source term (AST)
LOCA analysis . Specifically, the AST LOCA analysis assumed an increased leakage through the primary containment purge lines .
AmerGen has evaluated whether or not a significant hazards consideration is involved with the proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below.
1 . Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment adds a note excluding the leakage through the primary containment purge lines from the secondary containment bypass
ATTACHMENT I Evaluation of Proposed Changes Page 5 of 7 leakage based on separate analysis of these paths using the assumptions in the alternative source term (AST) revision to the loss of coolant accident (LOCA) analyst.
The proposed change does not require modification to the facility . The proposed change in secondary containment bypass leakage does not affect the operation of any facility equipment, the interface between facility systems, or the reliability of any equipment . In addition, secondary containment bypass leakage does not constitute an initiator of any previously evaluated accidents. Therefore, the proposed amendment does not involve a significant increase in the probability of an accident previously evaluated .
The radiological consequences of the COCA analysis using the primary containment purge line leakage as separate from the secondary containment bypass leakage, has been evaluated as part of the application of AST assumptions . The results conclude that the radiological consequences remain within applicable regulatory limits .
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Z Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not affect the design, functional performance or operation of the facility . No new equipment is being introduced and installed equipment is not being operated in a new or different manner. Similarly, the proposed change does not affect the design or operation of any structures, systems or components involved in the mitigation of any accidents, nor does it affect the design or operation of any component in the facility such that new equipment failure modes are created . There are no setpoints at which protective or mitigative actions are initiated that are affected by this proposed action . No change is being made to procedures relied upon to respond to an off-normal event.
As such the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Does the proposed amendment involve a significant reduction in a margin of safety?
Response : No.
Margins of safety are established in the design of components, the configuration of components to meet certain performance parameters, and in the establishment of setpoints to initiate alarms or actions. The proposed change
ATTACHMENT 1 Evaluation of Proposed Changes Page 6 of 7 adds a note excluding the leakage through the primary containment purge lines from the secondary containment bypass leakage based on separate analysis of these paths using the assumptions in the AST revision to the LOCA analysis .
There is no change in the design of the affected systems, no alteration of the setpoints at which alarms or actions are initiated, and no change in plant configuration from original design .
The margin of safety is considered to be that provided by meeting the applicable regulatory limits . The AST analysis indicates that the doses following a LOCA remain within the regulatory limits, and therefore, there is not a significant reduction in a margin of safety. The AST analysis confirms the change continues to ensure that the doses at the exclusion area and low population zone boundaries, as well as the control room, are within the corresponding regulatory limits .
Therefore, operation of CPS in accordance with the proposed change will not involve a significant reduction in a margin of safety .
Conclusion Based on the above, AmerGen concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92, "Issuance of amendment," paragraph (c), and, accordingly, a finding of no significant hazards consideration is justified.
5.2 Applicable Regulatory Requirements/Criteria The proposed change has been evaluated to determine whether applicable regulations and requirements continue to be met. AmerGen has determined that not the proposed change does require any exemptions or relief from regulatory requirements, other than the Technical Specifications, and does not affect conformance with any General Design Criteria (GDC) differently than described in the CPS Updated Safety Analysis Report (USAR). The proposed change ensures the leakage rate of the secondary containment bypass leakage paths is consistent with the accident analyses as described in the USAR .
CPS continues to be in compliance with the requirements of 10 CFR 50, Appendix J. Primary containment leakage testing will continue to be performed as required and the results will be evaluated to demonstrate that containment leakage does not exceed allowable leakage rates and that the integrity of the containment structure is maintained .
The original AST analysis utilized the assumptions and guidance provided by Regulatory Guide (RG) 1 .183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ." No exceptions to the RG 1 .183 were taken for the LOCA analyses . The LOCA analysis assumption for leakage through the primary containment purge lines that provide the basis for the proposed change is consistent with the RG 1 .183 guidance.
ATTACHMENT I Evaluation of Proposed Changes Page 7 of 7 The dose consequences due to a LOCA assuming a 0.02 L,, leakage through each primary containment purge line complies with the requirements of 10 CFR 50.67, "Accident source term," and the guidance of RG 1 .183 .
In conclusion, based on the considerations described above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the NRC regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public .
This proposed change is based on the analyses completed in support of the CPS proposed application of an AST methodology. As described above, the AST analysis assumed a certain leakage through the primary containment purge lines and included a separate dose analysis for these penetrations . Therefore, review and approval of this proposed change is contingent on the approval of the CPS AST amendment request submitted in Reference 1 .
6.0 ENVIRONMENTAL CONSIDERATION
A review has determined that the proposed amendment would change a requirement with respect to installation or use a facility component located within the restricted area, as defined in 10 CFR 20, "Standards for Protection Against Radiation," or would change an inspection or surveillance requirement. However, the proposed amendment does not significant involve (i) a hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51 .22, "Criterion for categorical exclusion; identification of licensing and regulatory actions eligible for categorical exclusion or otherwise not requiring environmental review," paragraph (c)(9) . Therefore, pursuant to 10 CFR 51 .22, paragraph (b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
1 . Letter from Michael J . Pacilio (AmerGen Energy Company, LLC) to U. S.
NRC, "Request for License Amendment Related to Application of Alternative Source Term," dated April 3, 2003
ATTACHMENT 2 Markup of Proposed Technical Specification Page CLINTON POWER STATION, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-62 Request for Technical Specification Change to Revise Secondary Containment Bypass Leakage Surveillance Requirement REVISED TECHNICAL SPECIFICATION PAGE 3.6-19
PCIVS 3 .6-1 .3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3 .6 .1-3 .8 __________________NOTE-_________________
Dnly required to be met in MODES 1, 2, and 3 .
Verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths is 5 0-08 L a when pressurized to Primary Containment i Pa-Leakage Rate Testing Program SR 3 .6 .1 .3 .9 __________________NOTE-_________________
only required to be met in MODES 1, 2, and 3 .
Verify total leakage rate through all In accordance four main steam lines is § 112 scfh when with the tested at 1 Pa- Primary Containment Leakage Rate Testing Program SR 3 .6 .1 .3-10 __________________NOTE-_________________
Only required to be met in MODES 1, 2, and 3 .
Verify combined leakage rate through In accordance hydrostatically tested lines that with the penetrated the primary containment is Primary within limits . Containment Leakage Rate Testing Program CLINTON 3-6-19 Amendment No . 145
ATTACHMENT 3 Retyped Technical Specification Page CLINTON POWER STATION, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-62 Request for Technical Specification Change to Revise Secondary Containment Bypass Leakage Surveillance Requirement REVISED TECHNICAL SPECIFICATION PAGE 3.6-19
PCIVS 3 .6 .1 .3 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE FREQUENCY SR 3 .6 .1 .3 .8 __________________NOTE-_________________
1 . Leakage through penetrations 1MC-101 and 1MC-102 is excluded .
2 . Only required to be met in MODES 1, 2, and 3 .
verify the combined leakage rate for all In accordance secondary containment bypass leakage with the paths is ! 0 .08 L a when pressurized to Pr!
Containment 1 P- Leakage Rate Testing Program SR 3 .6 .1 .3 .9 __________________NOTE-_________________
only required to be met in MODES 1, 2, and 3 .
Verify total leakage rate through all In accordance four main steam line is 1 112 scfh when with the Primary tested at ~! Containment Leakage Rate Testing Program SR 3 .6 .1 .3 .10 __________________NOTE-_________________
only required to be met in MODES 1, 2, and 3 .
Verify combined leakage rate through accordance hydrostatically tested lines that h the penetrated the primary containment is merry within limits . Containment Leakage Rate Testing Program (continued)
CLINTON 3 .6-19 Amendment No .
ATTACHMENT 4 Markup of Proposed Technical Specification Bases Page CLINTON POWER STATION, UNIT 1 FACILITY OPERATING LICENSE NO. NPF-62 Request for Technical Specification Change to Revise Secondary Containment Bypass Leakage Surveillance Requirement REVISED TECHNICAL SPECIFICATION BASES PAGE (For Information Only)
B 3.6-27
PCIVS B 3 .6 .1 .3 BASES SURVEILLANCE SR - 3 .6 .1 .3 .8 (continued)
REQUIREMENTS leakage through the isolation device . If both isolation valves in the penetration are closed, the actual leakage rate is the lesser leakage rate of the two valves . This method of quantifying maximum pathway leakage is only to be used for this SR .
The Frequency is consistent with the Primary Containment Leakage Rate Testing Program . This SR simply imposes additional acceptance criteria . Secondary containment bypass leakage is considered part of La, to this SR which states that these valves are only required to meet this leakage limit in MODES 1, 2 and 3 . In the other conditions, the Reactor Coolant System is not pressurized and specific primary containment leakage limits are not required .
With regard to leakage rate values obtained pursuant to this SR, as read from plant indication instrumentation, the specified limit is considered to be a nominal value and therefore does not require compensation for instrument indication uncertainties (Ref . 9) .
SR 3 .6 .1 .3 .9 The analyses in References 1, 2, and 3 are based on leakage that is less than the specified leakage rate . Leakage through all four main steamlines must be 5 112 scfh when tested at Pa (9 .0 psig) . The MSIV leakage rate must be verified to be in accordance with the assumptions of References 1, 2, and 3 . A Note is added to this SR which states that these valves are only required to meet this leakage limit in MODES 1, 2, and 3 . In the other conditions, the Reactor Coolant System is not pressurized and primary containment leakage limits are not required .
The Frequency is required by the Primary Containment Leakage Rate Testing Program .
(continued)
CLINTON B 3 .6-27 Revision No . 7- 2
Bases Insert #1 (page B 3.6-27) :
Note 1 states that primary containment purge penetrations 1 MC-1 01 and 1 MC-1 02 are excluded from this SR verifying the secondary containment bypass leakage. The leakage through these penetrations is measured by SR 3.6.1 .3.5 and the consequences associated with this leakage are evaluated separately as part of the LOCA analysis .
Therefore, the leakage through the primary containment purge penetrations is excluded from the total secondary containment bypass leakage as verified in this SR. A second Note is provided