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Category:Exemption from NRC Requirements
MONTHYEARML24065A4822024-04-0101 April 2024 Attachment - Exemption Dresden ML24078A3772024-03-15015 March 2024 Email to the State of Illinois Requesting Review of the Dresden Exemption Request Environmental Assessment RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 ML24044A0732024-02-28028 February 2024 Federal Register Notice - Issuance of Multiple Exemptions Regarding 10 CFR Part 73 - January 2024 ML23354A2812024-01-0404 January 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0031 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) ML23328A0092023-11-22022 November 2023 Supplement - Dresden Security Rule Exemption Request ISFSI Docket No. Reference (EPID L-2023-LLE-0031) (Email) RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML21305A0192022-03-16016 March 2022 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(b) Related to Submission of Subsequent License Renewal Application (EPID L-2021-LLE-0048) (FRN) ML21305A0162022-03-15015 March 2022 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(b) Related to Submission of Subsequent License Renewal Application (EPID L-2021-LLE-0048) (Letter) ML21305A0182022-03-15015 March 2022 Exemption from the Requirements of 10 CFR Part 2, Section 2.109(b) Related to Submission of Subsequent License Renewal Application (EPID L-2021-LLE-0048) (Exemption) RS-21-114, Request for Exemption from 10 CFR 2.109(b)2021-10-28028 October 2021 Request for Exemption from 10 CFR 2.109(b) ML21204A1242021-08-23023 August 2021 Exemption Related to the Approval Authority for Suspension of Security Measures in an Emergency or During Severe Weather ML21103A0082021-04-12012 April 2021 Acceptance Review (Exemption Request): Dresden Nuclear Power Station, Units 1, 2, and 3-Request for Exemption from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E ML21076A4382021-03-17017 March 2021 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E ML21076A4392021-03-17017 March 2021 Attachment 1 - Requests for Exemptions from Portions of 10 CFR 50.47(b), 10 CFR 50.47(c)(2) and 10 CFR 50, Appendix E ML20322A3032020-12-14014 December 2020 Exemption from Annual Force-On-Force Exercise Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel, Subsection VI.C.3(I)(1) (EPID L-2020-LLE-0203 (COVID-19)) NMP1L3362, Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency2020-11-13013 November 2020 Request for an Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding 2020 Annual Force-on-Force (FOF) Exercises Due to COVID- 19 Public Health Emergency ML20271A0002020-10-13013 October 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for September 2020 ML20248H5652020-10-0505 October 2020 Letter, Exemption from the Requirements of Title 10 of the Code of Federal Regulations Part 50, Appendix J ML20248H5662020-10-0505 October 2020 Exemption from the Requirements of Title 10 of the Code of Federal Regulations Part 50, Appendix J RS-20-124, Request for Exemption from Certain Record Retention Requirements2020-09-30030 September 2020 Request for Exemption from Certain Record Retention Requirements RS-20-113, Request for Exemption from Specific Provisions in 10 CFR 73.55(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather2020-09-28028 September 2020 Request for Exemption from Specific Provisions in 10 CFR 73.55(p)(1)(i) and (p)(1)(ii) Related to the Suspension of Security Measures in an Emergency or During Severe Weather ML20259A4922020-09-28028 September 2020 Exemption from Select Requirements of 10 CFR Part 26 (EPID L-2020-LLE-0143 (COVID-19)) ML20243A0002020-09-23023 September 2020 FRN - Notice of Issuance of Multiple Exemptions Regarding Various Parts of 10 CFR Due to COVID-19 Impacts for August 2020 ML20259A1162020-09-14014 September 2020 Incoming Request-Dresden-Exelon Generation Co., LLC ML20216A2602020-08-27027 August 2020 Exemption Request from Certain Requirements of 10 CFR Part 73, Appendix B, General Criteria for Security Personnel (COVID-19) ML0614302462006-06-27027 June 2006 TMI and Zion - Exemption from the Requirements of 10 CFR 50.54(a)(3) Re Submittal of Changes to Quality Assurance Topical Report ML0233805992002-11-25025 November 2002 Exemption Request from the Requirements of 10 CFR 50.36(c)(1) ML0223502112002-10-0202 October 2002 Exemption from the Requirements of 10 CFR 50.719(e)(4) ML0218603302002-07-12012 July 2002 Exemption, Reschedule Requalification Examination 2024-04-01
[Table view] Category:Letter type:RS
MONTHYEARRS-24-073, Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information2024-07-31031 July 2024 Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations – Additional Information Supporting Request to Withhold Security-Related Information RS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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-24-056, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors2024-05-28028 May 2024 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report 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-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 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-24-016, Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations2024-03-14014 March 2024 Request for Alternative Schedule to Complete Decommissioning Beyond 60 Years of Permanent Cessation of Operations RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-24-017, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS2024-02-23023 February 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station – Holtec MPC-68MCBS RS-23-121, Sixth Ten-Year Interval Inservice Testing Program2023-11-30030 November 2023 Sixth Ten-Year Interval Inservice Testing Program RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-107, Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2023-11-0808 November 2023 Relief Request I5R-22, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval RS-23-102, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-16016 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-071, Application to Adopt TSTF-564, Safety Limit MCPR2023-08-30030 August 2023 Application to Adopt TSTF-564, Safety Limit MCPR RS-23-078, Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2023-06-16016 June 2023 Supplement to License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-070, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-05-16016 May 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel RS-23-057, Supplement to License Amendment Request Regarding Transition to GNF3 Fuel2023-04-17017 April 2023 Supplement to License Amendment Request Regarding Transition to GNF3 Fuel 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-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H 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-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request 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-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-116, Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval2022-11-0101 November 2022 Submittal of Relief Requests Associated with the Sixth Inservice Testing Interval RS-22-115, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2022-10-19019 October 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-22-066, License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times2022-08-25025 August 2022 License Amendment Request to Revise Technical Specification 3.1.4, Control Rod Scram Times 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-22-065, License Amendment Request Regarding Transition to GNF3 Fuel2022-08-18018 August 2022 License Amendment Request Regarding Transition to GNF3 Fuel RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval RS-22-099, Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-102022-07-19019 July 2022 Submittal of Upcoming Sixth Inservice Inspection Interval Relief Requests I6R-09 and I6R-10 RS-22-082, Defueled Safety Analysis Report Update, Revision 112022-06-22022 June 2022 Defueled Safety Analysis Report Update, Revision 11 RS-22-080, Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals2022-06-0909 June 2022 Withdrawal and Proposed Alternative I6R-08 Associated with Code Case N-921 for Sixth Inservice Inspection Intervals RS-22-064, License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.12022-06-0808 June 2022 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies with Proposed Change to Technical Specifications Section 4.3.1 RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellation'S Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-046, Relief Requests Associated with the Sixth Inservice Inspection Interval2022-03-25025 March 2022 Relief Requests Associated with the Sixth Inservice Inspection Interval RS-22-042, Report on Status of Decommissioning Funding for Shutdown Reactors2022-03-23023 March 2022 Report on Status of Decommissioning Funding for Shutdown Reactors 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 2024-07-31
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARRS-24-063, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-06-14014 June 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-021, Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-222024-04-0202 April 2024 Response to Request for Additional Information for 10 CFR 50.55a Request No. I5R-22 RS-24-022, Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.2142024-03-0808 March 2024 Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to Support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 RS-23-119, Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information2023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information RS-23-041, Response to Request for Additional Information for Alternative Request RV-23H2023-03-14014 March 2023 Response to Request for Additional Information for Alternative Request RV-23H RS-23-004, Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request2023-01-23023 January 2023 Response to Request for Additional Information Regarding Transition to GNF3 Fuel License Amendment Request RS-22-117, Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies2022-11-0303 November 2022 Response to Request for Additional Information License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies RS-22-101, Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval2022-08-10010 August 2022 Response to Request for Additional Information Related to Relief Request I6R-01 Associated with the Sixth Inservice Inspection Interval 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 NMP1L3447, Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2022-02-0202 February 2022 Constellation Energy Generation, LLC - Response to Request for Additional Information - Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0087, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-09-16016 September 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments 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 JAFP-21-0044, Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments2021-06-11011 June 2021 Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments JAFP-21-0032, Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-04-20020 April 2021 Response to Request for Additional Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting RS-21-036, Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2021-03-16016 March 2021 Response to Request for Additional Information Re Dresden License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition RS-21-029, Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition2021-03-15015 March 2021 Response to RAI Re License Amendment Request - Proposed Changes to Byron & Dresden Stations Emergency Plan for Post-Shutdown and Permanently Defueled Condition RS-20-112, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-5682020-09-0303 September 2020 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-568 RS-20-038, Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance2020-05-0606 May 2020 Response to Request for Additional Information for the License Amendment Request to Change Technical Specifications to Increase Allowable MSIV Leakage Rates and Revise Secondary Containment Surveillance RS-19-112, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control2019-12-0505 December 2019 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Following Adoption of TSTF-542, Reactor Pressure Vessel Water Inventory Control RS-19-101, Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From...2019-10-30030 October 2019 Seismic Probabilistic Risk Assessment Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights From... JAFP-19-0057, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-06-0404 June 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 NMP1L3279, Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants2019-05-0101 May 2019 Response to Request for Additional Information - Proposed Alternatives to Utilize Code Cases N-878 and N-880 for Plants JAFP-19-0006, Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-8802019-01-0808 January 2019 Response to Request for Additional Information - Proposed Alternative to Utilize Code Cases N-878 and N-880 RS-18-143, Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements2018-11-29029 November 2018 Supplemental Information Supporting License Amendment Requests for Approval of Changes to Emergency Plan Staffing Requirements RS-18-097, Response to Request for Additional Information and Supplemental Information-License Amendment.2018-07-27027 July 2018 Response to Request for Additional Information and Supplemental Information-License Amendment. RS-18-061, Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis)2018-05-0202 May 2018 Response to Request for Additional Information Regarding Decommissioning Funding Plans for Independent Spent Fuel Storage Installations (Isfsis) RS-18-022, Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program.2018-02-14014 February 2018 Response to NRC Request for Additional Information for Request for License Amendment to Revise Technical Specification 5.5.12, Primary Containment Leakage Rate Testing Program. RS-17-088, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Integrated Assessment Submittal2017-09-0808 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Integrated Assessment Submittal RS-17-086, Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control.2017-07-13013 July 2017 Supplement to Application to Revise Technical Specifications to Adopt TSTF-542, Reactor Pressure Vessel Water Inventory Control. RS-17-044, Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2017-03-13013 March 2017 Response to Request for Additional Information Regarding Proposed Alternative for the Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography RS-16-244, Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings2016-12-12012 December 2016 Additional Information Regarding Request for License Amendment to Address Secondary Containment Access Openings RS-16-124, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2016-08-31031 August 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident RS-16-166, Supplemental Information Related to Inservice Inspection Interval Relief Request I5R-082016-08-22022 August 2016 Supplemental Information Related to Inservice Inspection Interval Relief Request I5R-08 RS-16-159, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings2016-07-28028 July 2016 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment to Address Secondary Containment Access Openings RA-16-049, Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure2016-05-26026 May 2016 Response to Request for Additional Information Regarding Requests to Withhold Emergency Preparedness Documents from Public Disclosure RS-16-105, Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel2016-04-26026 April 2016 Supplemental Information in Support of Request for License Amendment Regarding Transition to Areva Fuel RS-16-077, Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls.2016-04-14014 April 2016 Response to Request for Additional Information Regarding Request for License Amendment to Reduce the Reactor Steam Dome Pressure Specified in the Technical Specification 2.1.1, Reactor Core Sls. RS-16-018, Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel2016-01-28028 January 2016 Response to Request for Additional Information Regarding Request for License Amendment Regarding Transition to Areva Fuel RS-15-258, County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment Request Adding Technical Specification for Inservice Leak and Hydrostatic Testing Operation2015-09-29029 September 2015 County, and Quad Cities - Response to Request for Additional Information Regarding License Amendment Request Adding Technical Specification for Inservice Leak and Hydrostatic Testing Operation RS-15-185, County - Supplemental Information Regarding Seismic Hazard Risk Evaluation and Seismic Hazard Prioritization Results - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near.2015-07-22022 July 2015 County - Supplemental Information Regarding Seismic Hazard Risk Evaluation and Seismic Hazard Prioritization Results - Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near. IR 05000249/19780121978-09-0101 September 1978 Letter Regarding Supplemental Response to Ie Inspection Report 05000249/1978012 - Dresden Unit 3 ML17252B1311978-09-0101 September 1978 Letter Regarding Supplemental Response to IE Inspection Report 05000249/1978012 - Dresden Unit 3 ML17252B1381976-11-0808 November 1976 Letter Regarding Response to the Item Noted Under Enforcement Action in Inspection Report 05000249/1976020 - Dresden Unit 3 ML17252B1451976-06-28028 June 1976 Letter Regarding 06/14/1976 Letter Concerning Actions Taken in Response to Request for Commitments in Areas of Concern - Dresden Unit 3 and IE Inspection Report 05000249/1976007 ML17252B1571975-10-16016 October 1975 Letter Referring to 09/19/1975 Letter Informing of Steps Taken to Correct Items of Noncompliance Brought to Attention in 08/29/1975 Letter - Dresden Units 2 and 3 ML17252B0491974-01-0707 January 1974 Answers to AEC Questions on Quality Assurance for Operations - Dresden Unit 3 ML17238A7511973-08-31031 August 1973 Quad-Cities Stations Units 1 and 2 - 10 CFR 50, Appendix J ML17238A7351972-04-26026 April 1972 Additional Information to Final Report of Safety Valve Operation Following a Feedwater Transient - Dresden Unit 3 ML17238A7491972-02-22022 February 1972 Hydrogen Control Equipment - Dresden Units 2 and 3 ML17238A7151971-09-13013 September 1971 Performance of the Dresden Units 2 and 3 Emergency Core Cooling Systems 2024-06-14
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Subject:
Response to Request for Additional Information by the Office of Nuclear Material Safeguards and Safety to support Review of a Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 For Dresden Nuclear Power Station -
Holtec MPC-68MCBS
References:
- 1. Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 For Dresden Nuclear Power Station - Holtec MPC-68MCBS (ML24054A031)
- 2. Electronic mail message from Yen-Ju Chen (NRC) to Christian Williams (Constellation Energy Generation, LLC)
RE: Request for Additional Information for Dresden Exemption Request dated March 1, 2024 (ML24067A124)
By letter dated February 23, 2024 (Reference 1), Constellation Energy Generation, LLC requested an exemption from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10 CFR 72.212(b)(11), and 10 CFR 72.214 for the Dresden Independent Spent Fuel Storage Installation.
By email dated March 1, 2024 (Reference 2), the NRC communicated a request for additional information necessary to complete the review of the referenced request.
The attachment to this letter provides the request for additional information as well as the CEG response.
There are no regulatory commitments contained in this submittal.
Response to Request for Additional Information Dresden Nuclear Power Station 10 CFR Part 72 Exemption Request March 8, 2024 Page 2 of 2
If you have any questions or require additional information, please contact Christian Williams at (267) 533-5 724.
Respectfully,
David T. Gudger Sr. Manager, Licensing Constellation Energy Generation, LLC
Attachment:
Response to Request for Additional Information Needed for Constellation Request for Specific Exemption From Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Dresden Nuclear Power Station
cc: w/ Attachment Regional Administrator - NRC Region III Resident/Senior Resident Inspector - Dresden Nuclear Power Station NRC Project Manager - Dresden Nuclear Power Station Illinois Emergency Management Agency - Division of Nuclear Safety
Attachment
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 AND 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION (ML24054A031)
RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
By letter dated February 23, 2024 (Reference 1), Constellation Energy Generation, LLC (CEG) requested an exemption from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3),
10 CFR 72.212(b)(5)(i), 10 CFR 72.212(b)(11), and 10 CFR 72.214 for the Dresden Independent Spent Fuel Storage Installation (ISFSI).
The exemption would allow Dresden to conti nue to store loaded Holtec 68M M ulti-Purpose Canisters with a Continuous Basket Shim (MPC-68MCBS) and load MPC -68MCBS canisters during future campaigns.
By email dated March 1, 2024 (Reference 2), the NRC communicated a request for additional information necessary to complete the review of the referenced exemption request.
The requested information as well as the CEG responses are provided in this attachment.
From Reference 2:
[T]he staff is requesting additional information to complete the review of Dresdens exemption request dated February 23, 2024 (ML24054A031). Please provide the following information by the end of business day today, March 1, 2024, in order to support your requested need date of April 18, 2024.
In response to the requested date of March 1, 2024, CEG informed the NRC that a response would be provided no later than March 8, 2024.
RAI 1: For future loading, provide the procedures for handling the dry cask storage system (i.e.,
loading, handling, and transit) that demonstrate that the system is either handled with a single failure proof device such that a drop is considered non-credible or administrative controls are in place to protect the lift height, which include an acceptable analysis that the MPC confinement boundary is maintained. GLs can refer to specific FSAR section and describe how it applies to site specific situations.
In the exemption request, under the technical justification for structural and confinement, Dresden stated that the structural assessment considered the handling operations for the dry cask storage system. Provide the handling procedures to support the justification in the exemption request.
CEG Response to RAI 1:
The following is t aken from the Dresden 72.212 Evaluation Report, Revision 15
Section 1.1 Conditions of the CoC
[]
Section 1.1.4 Condition 5 - Heavy Loads Requirements
Page 1 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
Condition 5 of CoC 1014 requires cask lifts to be performed in accordance with existing plant heavy load requirements and procedures.
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Section 9.1.4.3.2 of the DNPS Units 2 & 3 UFSAR (Reference 6) specifies administrative controls applicable to handling heavy loads including spent fuel casks in the DNPS Units 2 and 3 Reactor Building. These administrative controls are implemented through procedures DOS 0800-06, "Unit 2/3 Reactor Building Crane Operations in Restricted Mode Test", DFP 0800-20, "Operation of 2/3 Reactor Building 125/9 ton Crane" and DMP 5800-18, "Load Handling of Heavy Loads and Lifting Devices" (References 15, 16 and 17, respectively).
Section 9.1.4.3.2 of the DNPS UFSAR describes the single-failure-proof design of the reactor building overhead crane. The reactor building overhead crane is licensed as single-failure-proof for loads up to 110 tons. Since the crane is single failure proof and the HI-TRAC/MPC lifting yokes and devices (References 69 and 70) comply with ANSI N14.6 (Reference 62), the requirements for the components used for heavy load lifting inside the Reactor Building in accordance with NUREG 0612 (Reference 71) have been met.
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Section 1.2 CoC 1014 Appendix A - Technical Specifications Compliance
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Section 1.2.3.2 Section 5.5 Cask Transport Evaluation Program
Section 5.5 establishes requirements for the site transportation of a loaded HI-STORM 100 overpack or HI-TRAC 100 transfer cask.
A loaded HI-TRAC is not required to be transported outside structures governed by 10 CFR 50 for West ISFSI operations. Therefore, Section 5.5 does not apply to HI-TRAC activities in this 72.212 Evaluation Report.
Transportation of a loaded HI-STORM 100 overpack into and out of the Reactor Building is provided by a low-profile transporter with Hilman Roller System that provides support from underneath in compliance with Section 5.5.
Transportation of a loaded HI-STORM 1 00 overpack between the Reactor Building and the ISFSI is accomplished by a VCT [Vertical Cask Transporter]. The VCT is a lifting device designed in accordance with ANSI N14.6 (Reference 62) and has redundant drop protection features (Reference 33). Accordingly, use of the VCT complies with Section 5.5.a.3 and the overpack may be lifted to any height necessary during transport operations.
The applicable procedures governing the activities discussed in Section 1.2.3.2 are listed below.
Page 2 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
- DFP 0800-64 TRANSPORTER OPERATIONS
- DFP 0800-65 SPENT FUEL CASK SITE TRANSPORTATION
- DFP 0800-68 HI -TRAC PREPARATION
- DFP 0800-69 HI -TRAC MOVEMENT WITHIN UNIT 2/3 REACTOR BUILDING
- DFP 0800-70 HI -TRAC LOADING OPERATIONS
- DFP 0800-82 HI -TRAC/MPC UNLOA DING OPERATIONS IN THE UNIT 2/3 REACTOR BUILDING
RAI 2: Demonstrate that radiation release during a postulated accident is within the regulatory limits.
The analyses in Holtecs Final Safety Analysis Report (FSAR) for accident conditions demonstrate the consequences of accidents challenging the integrity of the confinement barrier and shielding design features should not exceed limits established in 10 CFR 72.106. The analyses in the FSAR also demonstrate that offsite doses during normal operations and anticipated occurrences should not exceed the limits of 10 CFR 72.104.
In the exemption request, under environmental consideration, Dresden states that the confinement boundary maintains its structural integrity during accident conditions. Demonstrate that the site-specific dose calculations for the postulated release would be within the regulatory limits, e.g., information/calculations from the 72.212 report.
CEG Response to RAI 2:
In a memorandum, SAFETY DETERMINATION OF A POTENTIAL STRUCTURAL FAILURE OF THE FUEL BASKET DURING ACCIDENT CONDITIONS FOR THE HI-STORM 100 AND HI-STORM FLOOD/WIND DRY CASK STORAGE SYSTEMS dated January 31, 2024 (Reference 3 of the subject exemption request), ( ML24018A085), the NRC documented the following conclusion:
A non-mechanistic tip-over accident condition is considered a hypothetical accident scenario and may affect the HI-STORM FW overpack by resulting in limited and localized damage to the outer shell and radial concrete shield. As the damage is localized and the vast majority of the shielding material remains intact, the effect on the dose at the site boundary is negligible.
Therefore, the site boundary doses for the loaded HI-STO RM FW overpack for accident conditions are equivalent to the normal condition doses, which meet the Title 10 of the Code of Federal Regulations (10 CFR) Section 72.106 radiation dose limits.
Dresdens Radiation Shielding Analysis demonstrating compliance with 10 CFR 72.104 is documented in Section 3.1 of the Dresden 72.212 Evaluation Report Revision 15 (Reference 4 of the subject exemption request). The results of the shielding analysis are provided in Section 3.1.3
Page 3 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
Regarding compliance with 10 CFR 72.106, Section 11.2.3.3 of the HI -STORM 100 Final Safety Analysis Report, Revision 11.1 (Reference 5 of the subject exemption request) demonstrates that there are no accidents which would significantly affect shielding effectiveness of the HI-STORM 100 system and that the requirements of 10 CFR 72.106 are easily met by the HI-STORM 100 system for the postulated tip-over event.
The minimum distance from the West ISFSI to the Site boundary is, as documented in Section 3.1.3 of the Dresden 72.212 Evaluation Report, Revision 15, approximately 650 meters and the distance to the restricted area boundary is approximately 150 meters both of which are greater than the 100 -meter minimum distance specified in 10 CFR 72.106.
Based on the above and the NRCs conclusion that damage is localized and the vast majority of the shielding material remains intact, compliance with 10 CFR 72.104 and 10 CFR 72.106 is not impacted by a non-mechanistic tip-over event resulting in basket failure. Therefore, compliance is not impacted by approving the subject exemption request.
RAI 3: Demonstrate that this exemption is otherwise in [the] public interest. Provide site-s pecific information on why this exemption is needed right now and why it is in the public interest to grant this exemption.
CEG Response to RAI 3:
From Reference 1:
C) Otherwise in the Public Interest
It is in the publics interest to grant an exemption, since dry storage places the fuel in an inherently safe, passive system, and the exemption would permit the continued storage of already loaded canisters before full compliance. This exemption would also allow upcoming loading campaigns to proceed on time to move fuel into the dry storage condition and maintain the ability to offload fuel from the reactor, thus allowing continued safe reactor operation.
The following Dresden-specific information is being provided to demonstrate that this exemption is otherwise in the publics interest.
Maintain Full Core Discharge Capabilities :
The most significant impact of not being able to use CBS type canisters in upcoming campaigns relates to the ability to effectively manage the margin to full core discharge capability (FCDC) in the Dresden Unit 3 (DRE-3) and Dresden Unit 2 (DRE -2) Spent Fuel Pools (SFP).
The following margin discussion is based on anticipated loading schedules, which are not controlled documents, and should be considered estimates or targets.
Page 4 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
Currently, DRE-3 has a FCDC margin of 54 open cells in the SFP. Loading 3 MPC -68M and 1 MPC-68MCBS in the 2024 Spent Fuel Loading Campaign (SFLC) will increase this margin to 326 open cells. The upcoming 2024 refueling outage (D3R28) will decrease the FCDC margin to 78 open cells due to a planned discharge of 248 fuel bundles. If DRE -3 removes the 1 MPC -
68MCBS canister from 2024 SFLC scope, the FCDC margin will drop to only 10 open cells.
Since DRE-3 doesnt have a SFLC scheduled in 2025, the FCDC margin will remain at 10 until the 2026 SFLC. Having a FCDC margin of only 10 open cells for over a year of DRE -3 operation is an unnecessary risk to spent fuel pool (SFP) inventory and SFP operations. Also, in order to maintain a positive FCDC margin through the D RE-3 2026 refueling outage, the site will need to load 4 MPC-68MCBS canisters during the 2026 SFLC. The Spent Fuel Management Strategy for DRE-3 currently shows only 3 MPC -68MCBS in scope for the 2026 SFLC.
Currently DRE-2 has a FCDC margin of 67 open cells in the SFP. Loading 4 MPC-68MCBS in the 2025 Spent Fuel Loading Campaign (SFLC) will increase this margin to 339 open cells. The 2025 refueling outage (D2R29) will decrease the FCDC margin to 119 open cells due to a planned discharge of 220 fuel bundles. If DRE-2 cant load any MPC -68MCBS canisters in 2025 the margin to FCDC will go negative (margin of -153). FCDC margin will remain negative until the 2027 SFLC. Having a negative margin for over a year of DRE -2 operation is an unnecessary risk to spent fuel pool (SFP) inventory and SFP operations. Also, in order to recover a positive FCDC margin through the DRE-2 2027 refueling outage, the site will need to load 6 MPC -
68MCBS canisters during the 2027 SFLC. The Spent Fuel Management Strategy for DRE -2 currently shows only 4 MPC-68MCBS in scope for the 2027 SFLC.
Having low margins to FCDC makes it difficult to stage the complete reload batch of fuel in the SFP in preparation for outages. This presents a potential reactivity management risk to fuel handling operations during pre-and post-outage.
Decay Heat Removal Requirements:
Each spent fuel bundle contributes to the decay heat removal demand on the spent fuel pool cooling systems. The estimated decay heat from the spent fuel that is scheduled to be moved to dry storage is 1 to 2% per cask. Additionally, removing spent fuel bundles from the fuel pool allows for dispersion of the remaining heat load.
Accident Consequences and Probability:
Design Bases Accidents associated with the fuel pool include a loss of fuel pool cooling event and a fuel handling accident (FHA). T he consequence of a loss of fuel pool cooling is made worse due to the 1 to 2% additional decay heat load contributing to increasing fuel pool temperatures as well as the additional spent fuel experiencing the loss of cooling.
The consequence of an FHA is not impacted however the likelihood of an FHA is increased based on additional fuel moves required to manage fuel pool loading with extra bundles in to pool.
Page 5 of 6 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NEEDED FOR CONSTELLATION REQUEST FOR SPECIFIC EXEMPTION FROM CERTAIN REQUIREMENTS OF 10 CFR 72.212 and 10 CFR 72.214 FOR DRESDEN NUCLEAR POWER STATION
Margin to Capacity:
Once s pent fuel pool capacity is reached, the ability to refuel to the operating reactor is limited thus taking away a highly reliable clean energy source.
Logistical Considerations and Cascading Impact:
Cask Loading campaigns are budgeted, planned, and scheduled years in advance of the actual performance. Campaigns are scheduled based on the availability of the specialized work force and equipment that is shared throughout the CEG fleet. These specialty resour ces support multiple competing priorities i ncluding refueling outages, loading campaigns, fuel pool cleanouts, fuel inspections, fuel handling equipment upgrades and maintenance, fuel sipping, new fuel receipt, and crane maintenance and upgrades. Eachof these activities limit the available windows to complete cask loading campaigns and delays in any one of these activities has an obvious cascading impact on all other scheduled specialized activities.
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Conclusion:==
Maintaining adequate FCDC margin ensures operational flexibility necessary for sustained safe and efficient operation of the operating nuclear facility.
Additionally, based on the logistic and financial impact on CEG as discussed above when compared to the minimal safety benefit discussed in the NRC safety memo, delaying the use of the MPC-68MCBS c anisters does not provide a measurable public benefit.
In contrast, approval of the referenced exemption request supports the continued safe, efficient, and cost-effective operation of the Dresden Nuclear Power Station.
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