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EPID:L-2023-LLA-0088, News Release-III-23-016: NRC to Conduct Open House to Discuss 2022 Performance of Clinton Nuclear Plant (Open) |
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MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release Project stage: Request ML24047A2562023-06-0707 June 2023 News Release-III-23-016: NRC to Conduct Open House to Discuss 2022 Performance of Clinton Nuclear Plant Project stage: Request ML23194A1662023-07-19019 July 2023 – Supplemental Information Needed for Acceptance of Requested Licensing Action Request for Partial Site Release Project stage: Acceptance Review ML23363A0302023-12-29029 December 2023 NRR E-mail Capture - Preliminary RAIs for Clinton Partial Site Release Project stage: RAI RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release Project stage: Request ML24158A0792024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Federal Register Notice Project stage: Meeting ML24158A0772024-07-0303 July 2024 Notice of Consideration of Approval of Partial Site Release, Public Meeting, and Request for Comments (EPID L-2023-LLA-0088) - Letter Project stage: Meeting PMNS20240922, Notice of Public Meeting2024-07-11011 July 2024 Notice of Public Meeting Project stage: Request ML24214A1402024-08-0505 August 2024 July 24, 2024, Summary of the Public Meeting Regarding Clinton Power Station, Unit 1, Partial Site Release Project stage: Meeting ML24211A2302024-09-11011 September 2024 – Request for Partial Site Release for Facility Operating License No. NPF-62 Project stage: Other 2024-02-08
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Category:Letter type:RS
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - 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-24-087, 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 2024-09-09
[Table view] Category:Report
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release NMP1L3469, Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits2022-06-30030 June 2022 Constellation Energy Company, LLC, Request for Use of Honeywell Mururoa V4F1 R Supplied Air Suits ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements RS-21-005, Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-01-20020 January 2021 Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-001, Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping2021-01-0404 January 2021 Revised Proposed Alternative to Utilize Code Cases N-878 and N-880 for Carbon Steel Piping ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting U-604712, Submittal of the Snubber Program Plan for the Fourth 10-Year Interval2020-06-24024 June 2020 Submittal of the Snubber Program Plan for the Fourth 10-Year Interval ML19228A0232019-08-15015 August 2019 Proposed Alternative to Utilize Code Case N-879 ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow RS-15-320, Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-0492015-12-14014 December 2015 Revised Final Integrated Plan Document - Mitigating Strategies NRC Order, EA-12-049 RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 RS-14-312, Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report2014-11-0303 November 2014 Supplemental Response to Request for Additional Information Regarding Fukushima Lessons Learned - Flood Hazard Reevaluation Report RS-14-277, Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 12014-09-24024 September 2014 Proposed Alternative to Utilize Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate Energy Class 2 or 3 Piping Section XI, Division 1 ML14164A2982014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 RS-14-112, Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA)2014-03-27027 March 2014 Reports Associated with Results of Post-Irradiation Examination (Pie) of Global Nuclear Fuel (Gnf) GE14i Isotope Test Assembly (ITA) ML13338A6562013-12-0909 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Clinton Power Station, Unit 1, TAC No.: MF0901 IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12340A3492012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-1432012-11-27027 November 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklists, C-1 Through C-143 RS-12-165, 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-142012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 ML12340A3482012-10-30030 October 2012 12Q0108.60-R-001, Rev. 0, Seismic Walkdown Checklist, C-286 Through F-14 2023-06-07
[Table view] Category:Miscellaneous
MONTHYEARRS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release ML22014A0052022-01-13013 January 2022 COVID-19 Related Request for Exemption from Part 26 Work Hours Requirements ML20303A1752020-10-23023 October 2020 Proposed Relief Request from Section XI Repair/Replacement Documentation for Bolting Replacement of Pressure Retaining Bolting ML18360A4852018-12-14014 December 2018 Attachment 17: Inconsistencies Between FLEX SE and Choice Letter Assumptions ML18360A4842018-12-14014 December 2018 Attachment 16: Graph of RPV Water Level ML18360A4832018-12-14014 December 2018 Attachment 15: FLEX and Cross-tie Training Material ML18360A4822018-12-14014 December 2018 Attachment 14: CPS Procedure 4200.01 C002, DC Load Shedding During a 580, Rev 5a ML18360A4812018-12-14014 December 2018 Attachment 13: Simulator Exercise Guide SE-JIT-42, Loss of AC, Loss of SDC and Lowering RPV Level, Rev 1 ML18360A4802018-12-14014 December 2018 Attachment 12: Time Validation - Performance of Division 3 DG to Division 2 Bus Cross-tie ML18360A4792018-12-14014 December 2018 Attachment 11: Procedures and Training Material on Maintaining RPV Pressure Low ML18360A4782018-12-14014 December 2018 Attachment 10: HEP Evaluation Related to Shutdown Cooling Isolation ML18360A4772018-12-14014 December 2018 Attachment 9: Procedures on Shutdown Cooling Isolation ML18360A4762018-12-14014 December 2018 Attachment 8: 2017 Training Material on Diesel Generator Air Start Flow Plow ML18360A4752018-12-14014 December 2018 Attachment 7: Time Validation - Performance of SBO and Starting of Division 2 Diesel Generator ML18360A4742018-12-14014 December 2018 Attachment 6: CPS Shift Manager Surveys Regarding ELAP Scenarios ML18360A4732018-12-14014 December 2018 Attachment 5: Senior Reactor Operator Surveys ML18360A4722018-12-14014 December 2018 Attachment 4: Training Material on Diesel Generator Malfunctions ML18360A4712018-12-14014 December 2018 Attachment 3: EC 626319, Battery Coping Time Evaluation to Support Inadvertent Isolation of Div. II Air Start Receiver Valves ML18360A4702018-12-14014 December 2018 Attachment 2: Response to NRC Questions and Documentation Requests ML18360A4692018-12-14014 December 2018 Attachment 1: Summary of Exelon Position RS-15-269, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2015-10-23023 October 2015 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors ML15062A1152014-12-22022 December 2014 International Atomic Energy Agency (Iaea), Operational Safety Review Team (Osart) Mission to Clinton Report - 11- 28 August 2014 ML14164A2982014-06-26026 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident IR 05000352/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000456/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML13008A2192013-01-31031 January 2013 U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000454/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000461/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000237/20132022013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000373/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000219/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000277/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000254/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000272/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee IR 05000289/20132012013-01-31031 January 2013 Exelon Generation Co., LLC, U.S. Nuclear Regulatory Commission (NRC) Office of Investigations (01) Investigation; Summary of 01 Report No. 3-2010-034; NRC Inspection Report Conference Letter - Licensee ML12178A2152012-08-0202 August 2012 Closeout of Bulletin 2011-01 Migrating Strategies. ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants RS-11-131, Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE142011-08-10010 August 2011 Plant Specific ECCS Evaluation Changes - 10 CFR 50.46 30-Day Report for Fuel Type GE14 ML1108712502011-03-24024 March 2011 BWR Vessel and Internals Inspection Summaries for Spring 2010 Outages RS-08-068, Additional Information Supporting the Request for License Amendment to Revise Local Power Range Monitor Calibration Frequency2008-05-16016 May 2008 Additional Information Supporting the Request for License Amendment to Revise Local Power Range Monitor Calibration Frequency U-603719, Annual Occupational Radiation Exposure Report for Clinton Power Station2005-03-21021 March 2005 Annual Occupational Radiation Exposure Report for Clinton Power Station ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement ML0309006042003-03-19019 March 2003 Additional Information Regarding Notice of Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC ML0303506252003-01-23023 January 2003 Request for NRC Written Consent to Proposed Amendments to Trust Agreement to Implement Assignment of Decommissioning Trust Funds for Amergen Energy Company, LLC RS-02-137, Power Uprate Ascension Test Report2002-08-0101 August 2002 Power Uprate Ascension Test Report 2023-06-07
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4300 Winfield Road Warrenville, IL 60555 630 657 2000 Office
RS-23-073 10 CFR 50.83
June 7, 2023
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461
Subject:
Request for Partial Site Release
Constellation Energy Generation, LLC (CEG) recently discovered that the required approval in accordance with 10 CFR 50.83, "Release of part of a power reactor facility or site for unrestricted use," was not obtained prior to the transfer of non-impacted land from the Clinton Power Station (CPS) site. Specifically, on September 17, 2003, a Quit Claim Deed was executed by AmerGen Energy Company, LLC to transfer 172.7 acres of land for the Clinton Lake Marina to DeWitt County, Illinois.
In accordance with 10 CFR 50.83(b), CEG requests approval to remove this portion of the site from the CPS Part 50 license (i.e., Facility Operating License No. NPF-62). The attachment provides the supporting information for this request in accordance with 10 CFR 50.83(b) for release of a non-impacted area. This includes a description of the property and evaluations of the effect of releasing this property. CEG's evaluation of the effect of releasing this property indicates that applicable regulatory requirements will continue to be met and no change is needed to the CPS Operating License or Technical Specifications.
CEG requests approval of this request by June 7, 2024.
There are no regulatory commitments contained in this letter. Should you have any questions concerning this letter, please contact Mr. Kenneth M. Nicely at (630) 657-2803.
Respectfully,
Patrick R. Simpson Sr. Manager Licensing Constellation Energy Generation, LLC
June 7, 2023 U.S. Nuclear Regulatory Commission Page 2
Attachment:
Supporting Information for Request for Partial Site Release
cc: NRC Regional Administrator, Region III NRC Senior Resident Inspector - Clinton Power Station Illinois Emergency Management Agency - Division of Nuclear Safety ATTACHMENT Supporting Information for Request for Partial Site Release
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Background===
Constellation Energy Generation, LLC (CEG) rec ently discovered that the required approval in accordance with 10 CFR 50.83, "Release of part of a power reactor facility or site for unrestricted use," was not obtained prior to the transfer of non-impacted land from the Clinton Power Station (CPS) site. Specifically, on September 17, 2003, a Quit Claim Deed was executed by AmerGen Energy Company, LLC to transfer 172.7 acres of land for the Clinton Lake Marina to DeWitt County, Illinois. This issue has been entered into CEG's Corrective Action Program.
This property has not been impacted by CPS operations and was evaluated for environmental concerns. No environmental concerns have been identified. This property has not been used for activities that could have radioactively contaminated the property.
In accordance with 10 CFR 50.83(b), CEG requests approval for the release of this non-impacted property from the jurisdiction of Fac ility Operating License No. NPF-62 for CPS.
Description of the Property
The Clinton Lake Marina was originally within the CPS site boundary, and this area was leased to an outside operator. The property consists of a 172.7-acre parcel, which includes a portion of the lake, the marina, marina support facilities, and surrounding wooded land. The property is on the far side of the Clinton Lake with respect to CPS and is located approximately 1.5 miles south of the CPS site, which is outside of the Exclusion Zone (i.e., 975 meters/0.6 miles) and within the Low Population Zone (i.e., 4018 meters/2.5 miles). The property was transferred to DeWitt County, Illinois for the Clinton Lake Marina in September 2003. Clinton Lake Marina services include boat rentals, limited food service, beverages, snacks, bait, propane tank exchange, slip rentals, and an on-site boat service department. It is known as the Barefoot Cove Marina at Clinton Lake.
The Clinton Lake Marina is not within the approximately 150 acres that comprise the Protected Area and Owner Controlled Area of the plant. It has no effect on the cooling function of the lake, which is designed to provide cooling water to the station and to remove the design heat load from the plant. Furthermore, transfer of the Clinton Lake Marina and functions of recreational use of the Clinton Lake Marina have no impact on structures, systems, or components within the Protected Area or the Owner Controlled Area.
Schedule for Property Release
This property was transferred to DeWitt County, Illinois on September 17, 2003. CEG recently discovered that the required approval in accordance with 10 CFR 50.83 was not obtained prior to the transfer of non-impacted land from the CPS site. Thus, there is no requested schedule of release.
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Results of 10 CFR 50.59 Evaluation
10 CFR 50.83(b) requires for non-impacted areas that the licensee submit the results of the evaluation performed in accordance with 10 CFR 50.59. Accordingly, CEG has performed a 10 CFR 50.59 review of the free release of this property.
The property transfer involves approximately 172.7 acres of the approximately 14,000 acres owned by CEG. This transfer does not involve property that is actively used for normal operations or that is needed for the site's Emergency Plan. The Updated Safety Analysis Report (USAR) describes the current land in a table of total acreage within the outer site boundary and has no other mention of the property.
The 10 CFR 50.59 review assessed the impact of the change in the site boundary on offsite dose calculations and effluent releases and concluded that the change:
- does not adversely affect any design function as described in the USAR,
- does not adversely affect how a design function as described in the USAR is performed or controlled,
- does not revise or replace an evaluation method used to establish design basis or safety analysis,
- does not involve a test or experiment not described in the USAR, and
- does not require a change to the Technical Specifications or Facility Operating License.
Therefore, this change in property ownership does not require prior NRC approval under the requirements of 10 CFR 50.59.
Historical Site Assessment
The 10 CFR 50.83 process includes a historical site assessment to identify potential or known sources of radioactive material or radioactive contamination that may have affected the property to be released.
The Annual Radiological Environmental Operating Report submitted to the NRC each year in accordance with Technical Specifications (TS) 5.6.2, "Annual Radiological Environmental Operating Report," includes summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program. It also includes environmental radiation measurements taken pursuant to the locations specified in the table and figures in the Offsite Dose Calculation Manual (ODCM), as well as summarized and tabulated results of these analyses and measurements in the format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979.
This information is used to calculate the offsite dose to the public. The radiation dose to the public in the vicinity of CPS is calculated by using the concentration of radioactive nuclides from
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each gaseous effluent release coupled with historical weather conditions. The dose from CPS gaseous radioactive effluents has been a small fraction of the limit for the maximum exposed member of the public.
Gaseous effluents from CPS are released to the environment via two gaseous effluent release points (i.e., the Common Station Heating, Ventilating, and Air Conditioning (HVAC) Stack and the Standby Gas Treatment System (SGTS) Stack. Each gaseous effluent release point is continuously monitored consisting of a surv eillance program of periodic sampling and analysis as specified in the ODCM.
CPS strictly controls effluents to ensure radioactivity released to the environment is maintained As Low As Reasonably Achievable (ALARA) and does not exceed federal release limit criteria.
Effluent controls include the operation of radiation monitoring systems within the plant as well as an offsite environmental analysis program.
The Radioactive Effluent Release Report submitt ed to the NRC each year in accordance with TS 5.6.3, "Radioactive Effluent Release Report," includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and process control program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I.
In addition to the TS requirements, a review of corrective action documents was completed for events that could have had a potential for releasing radioactive material to this property. The review identified no recorded events of any spills, leaks, or uncontrolled release of radioactive material on this land.
The annual Radioactive Effluent Release Reports are a detailed description of gaseous and liquid radioactive effluents released from CPS. These reports show that CPS continues to be operated well within federally required limits for offsite dose to the public.
In addition, the Radiological Environmental Monitoring Program (REMP) is conducted continuously for CPS in accordance with the ODCM. As reported in the annual Radiological Environmental Operating Reports, during each yearly reporting period, thousands of analyses are performed on thousands of samples. Assessments of the data gathered for the yearly reports and comparing the results with preoper ational data show there has been no adverse radiological impact on this property.
The findings of this review show the following:
- 1. The property has not been used for plant operations.
- 2. The property has not been used for storage of any radioactive material or waste.
- 3. There are no event records that any spills, leaks, or uncontrolled release of radioactive material have ever occurred on the property.
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- 4. The last liquid radioactive release from the plant was in 1992 in the circulating water discharge canal which is on the north side of Salt Fork. This property is located on the south side of Salt Fork and not in the groundwater gradient of the discharge canal.
- 5. No state or local agency has required additional groundwater monitoring or remedial actions on the property.
- 6. Three separate hydrogeologic studies have been conducted at CPS, in accordance with NEI 07-07, Review of Hydrogeologic Investigation Report (HIR), between 2006 and 2010. This property does not impact these studies.
- 7. The Radioactive Groundwater Protection Program (RGPP) conducts periodic monitoring of shallow groundwater. This program shows that shallow groundwater continues to flow predominantly towards the lake. This property is located on the south side of Salt Fork, whereas the plant is on the north side of Salt Fork; therefore, no contamination of this property through normal groundwater gradient flow can occur from plant discharges.
- 8. In assessing the data gathered for the REMP annual report and comparing each year's results with preoperational baseline data, it is concluded that the operation of CPS has had no adverse radiological impact on this property.
CPS continues to implement a radiation protection program commensurate with 10 CFR Part 20 and CPS TS 5.6.2 and 5.6.3. This property has no reasonable potential for residual radioactivity in excess of natural background or fallout levels; therefore, this property qualifies as a "non-impacted area" as defined in 10 CFR 50.2.
A historical cultural review was performed during the initial stages of planning and construction of the lake. The archaeological sites uncovered within CPS property boundaries are similar to other sites in Illinois and are not of major significance.
Evaluation of the Effect of Proposed Property Transfer
CEG has evaluated the effect of transferring the property in accordance with the criteria in 10 CFR 50.83(a)(1) to ensure that CPS will continue to comply with applicable statutory and regulatory requirements that may be affected by the release of the property. CEG has confirmed that the property transfer does not require a change to the Technical Specifications or Facility Operating License.
CEG's evaluation confirmed the following with respect to each of the areas listed in 10 CFR 50.83(a)(1)(i)-(vi):
(i) The dose to individual members of the public does not exceed the limits and standards of 10 CFR Part 20, Subpart D. CEG strictly controls effluents to ensure radioactivity released to the environment is maintained ALARA and does not exceed federal release limit criteria. Effluent controls include the operation of radiation monitoring systems within the plant as well as an offsite environmental analysis program. The release of this property does not change any controls used to comply with dose limits for individual
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members of the public. CEG has determined that this property was never used for any radiological purposes.
(ii) The impact on the effectiveness of emergency planning and physical security has been evaluated. No credit is taken for this property in either the Emergency Plan or the Security Plan. Therefore, the transfer of this property has no adverse effect on either plan.
(iii) Effluent releases remain within license conditions and, because the property is distant from the plant site and is not down-gradient of discharge structures, it does not have the potential to be affected by effluent releases. The plant programs to maintain effluent releases within license conditions remain in effect and the transfer of this property does not impact those programs. Therefore, the effluent releases from CPS will remain within license conditions.
(iv) The transfer of this land does not have any effect on the Environmental Monitoring Program or the Offsite Dose Calculation Manual, and neither requires revision as a result of this property transfer.
(v) The siting criteria of 10 CFR 100 continue to be met. The transfer of this property has been reviewed with respect to the siting criteria in 10 CFR 100 and it has no effect on meeting these criteria. In addition, the limits of 10 CFR 50.67, "Alternative source term,"
have been reviewed and the transfer has no effect on meeting these criteria.
(vi) Other statutory and regulatory requirements continue to be met. There are no changes to CPS' policies and procedures to ensure that statutory and regulatory requirements continue to be met as a result of this property transfer.
In summary, based on the considerations discuss ed above, this property transfer has no impact on CPS' continued compliance with applicable NRC regulatory standards.
Conclusion
CEG has evaluated the impact of releasing this property, and based on the reviews stated, the release of the property has been properly described as non-impacted. Accordingly, CEG requests NRC approval of the release of this property in accordance with 10 CFR 50.83(b).
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