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EPID:L-2020-LLA-0215, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (Withdrawn, Closed) EPID:L-2020-LLA-0217, TSTF-448 (Withdrawn, Closed) EPID:L-2020-LLA-0240, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (Withdrawn, Closed) |
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MONTHYEARRS-20-108, Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 32020-09-0202 September 2020 Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3 Project stage: Request RS-20-124, Request for Exemption from Certain Record Retention Requirements2020-09-30030 September 2020 Request for Exemption from Certain Record Retention Requirements Project stage: Request ML20304A1472020-10-29029 October 2020 License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Request RS-20-132, License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition2020-10-29029 October 2020 License Amendment Request, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Request ML20322A4432020-10-30030 October 2020 NRR E-mail Capture - Dresden Nuclear Power Station, Units 1, 2 and 3, and Byron Station, Units 1 and 2 - Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements Project stage: Acceptance Review ML20317A3132020-10-30030 October 2020 Acceptance of Requested Licensing Action, Proposed Partial Exemption from Record Retention Requirements Project stage: Acceptance Review ML20307A4452020-11-0202 November 2020 Attachment 3 - Proposed Revision to Site Emergency Plan Project stage: Request ML20307A4552020-11-0202 November 2020 Attachment 3 - Proposed Revision to Site Emergency Plan, Exhibit B, Radiological Emergency Plan Annex for Dresden Station (Procedure EP-AA-1004) Project stage: Request ML20307A4342020-11-0202 November 2020 License Amendment Request - Proposed Changes to Emergency Plan for Post-Shutdown and Permanently Defueled Condition Project stage: Request RS-20-131, Part II: Planning Standards and Criteria2020-11-0202 November 2020 Part II: Planning Standards and Criteria Project stage: Request ML20324A6172020-11-17017 November 2020 Acceptance Review License Amendment Request - Proposed Changes to Dresden Emergency Plan Project stage: Acceptance Review ML20343A1372020-12-0707 December 2020 Acceptance Review Dresden, Units 2 and 3, LAR for Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Acceptance Review ML21036A1102021-02-0404 February 2021 NRR E-mail Capture - Draft RAIs for Byron Station, Unit Nos. 1 and 2, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Draft RAI RS-21-018, Request for Rescission of NRC Orders EA-12-049, EA-12-051, and EA-13-1092021-02-23023 February 2021 Request for Rescission of NRC Orders EA-12-049, EA-12-051, and EA-13-109 Project stage: Request ML21063A3202021-03-0202 March 2021 RAIs for Dresden, Units 2 and 3, Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition (EPID L-2020-LLA-0239) (E-mail) Project stage: RAI RS-21-024, Response to Request for Additional Information (RAI) Regarding Byron Station, Units 1 and 2, 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 (RAI) Regarding Byron Station, Units 1 and 2, License Amendment Request - Proposed Defueled Technical Specifications and Revised License Conditions for Permanently Defueled Condition Project stage: Response to RAI RS-21-021, License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition2021-03-17017 March 2021 License Amendment Request - Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently Defueled Condition Project stage: Request ML21076A4382021-03-17017 March 2021 Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50, Appendix E Project stage: Request ML21081A0972021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events (EPID L-2021-JLD-0004) (E-mail) Project stage: Acceptance Review ML21081A0792021-03-19019 March 2021 Acceptance Review for Byron Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Acceptance Review ML21078A2182021-03-19019 March 2021 Acceptance Review for Dresden Order EA-13-109, Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions Project stage: Acceptance Review ML21081A0222021-03-19019 March 2021 Acceptance Review for Dresden Order EA-12-051, Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation Project stage: Acceptance Review ML21081A0722021-03-19019 March 2021 Acceptance Review for Dresden Order EA-12-049, Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events (EPID L-2021-JLD-0000) (E-mail) Project stage: Acceptance Review ML21105A0002021-04-12012 April 2021 Acceptance Review (LAR)-Dresden Nuclear Power Station, Units 1, 2, and 3, Proposed Changes to the Dresden Nuclear Power Station Emergency Plan and Emergency Action Level Scheme for the Permanently De-fueled Condition Project stage: Acceptance Review 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 Project stage: Acceptance Review RS-21-060, Post-Shutdown Decommissioning Activities Report2021-07-28028 July 2021 Post-Shutdown Decommissioning Activities Report Project stage: Request RS-21-059, Post-Shutdown Decommissioning Activities Report2021-07-28028 July 2021 Post-Shutdown Decommissioning Activities Report Project stage: Request RS-21-068, Response to Request for Additional Information 2 Regarding License Amendment Request - Proposed Defueled Tech Specs and Revised License Conditions for Permanently Defueled Condition2021-07-29029 July 2021 Response to Request for Additional Information 2 Regarding License Amendment Request - Proposed Defueled Tech Specs and Revised License Conditions for Permanently Defueled Condition Project stage: Response to RAI ML21244A4012021-08-10010 August 2021 (Final) Request for Information (RAI) Dresden, Units 1, 2, 3, and ISFSI Request for Exemptions from Portions of 10 CFR 50.47 and 10 CFR 50 Appendix E Project stage: RAI ML21263A0492021-09-28028 September 2021 Withdrawal of Licensing Actions Associated with Permanent Shut Down and Decommissioning and Related FRNs Project stage: Request ML21263A0552021-09-28028 September 2021 ISFSI Withdrawal of Licensing Actions Associated with the Scheduled Permanent Shut Down and Decommissioning of the Units (Letter) Project stage: Withdrawal ML21260A1392021-09-28028 September 2021 ISFSI Withdrawal of Licensing Actions Associated with the Scheduled Permanent Shut Down and Decommissioning of Units (EPIDs L-2020-LLA-0215,L-2020-LLE-0156,L-2020-LLA-0238,L-2020-LLA-0240,L-2021-JLD-0004,L-2021-JLD-0005,L-2021-LRO-0041 Project stage: Withdrawal ML21260A1352021-09-28028 September 2021 ISFSI Withdrawal of Licensing Actions Associated with the Scheduled Permanent Shut Down and Decommissioning of Units Project stage: Request 2021-02-04
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Category:Letter type:RS
MONTHYEARRS-24-088, Relief Requests Associated with the Fifth Inservice Inspection Interval2024-09-13013 September 2024 Relief Requests Associated with the Fifth Inservice Inspection Interval RS-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-24-064, Nuclear Radiological Emergency Plan Document Revisions2024-06-28028 June 2024 Nuclear Radiological Emergency Plan Document Revisions RS-24-066, Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller2024-06-25025 June 2024 Inservice Testing Interval Extension for Essential Service Water Valves Due to Required Use of Containment Chiller 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-24-044, License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed2024-05-28028 May 2024 License Amendment to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 and 10 CFR 50 Appendix K. Attachments 1 to 11 Enclosed RS-24-043, Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications2024-05-24024 May 2024 Application to Remove Power Distribution Monitoring System (Pdms) Details from Technical Specifications 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-24-026, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR)2024-04-25025 April 2024 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 5.6.5, Core Operating Limits Report (COLR) RS-24-034, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-04-10010 April 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-24-024, Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2024-03-22022 March 2024 Response to Request for Additional Information Regarding Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 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-23-117, 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-23-114, Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds2023-11-0101 November 2023 Proposed Alternative for Examination of Pressurizer Circumferential and Longitudinal Shell-to-Head Welds and Nozzle-to-Vessel Welds 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-23-100, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-10-13013 October 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-108, Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles2023-10-11011 October 2023 Proposed Alternative for Examinations of Examination Categories B-B, B-D, and C-A Steam Generator Pressure Retaining Welds and Full Penetration Welded Nozzles RS-23-105, Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections2023-10-10010 October 2023 Proposed Alternative for Examinations of Examination Category C-B Steam Generator Nozzle-to-Shell Welds and Nozzle Inside Radius Sections RS-23-093, License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel.2023-09-29029 September 2023 License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel. RS-23-094, Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 752023-09-29029 September 2023 Relief Request I4R-24, Alternative for Post-Peening Reexamination Frequency for Reactor Pressure Vessel Head Penetration Nozzle Number 75 RS-23-091, Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals2023-09-26026 September 2023 Relief Request I4R-25, Alternative Requirements for Reactor Pressure Vessel Inservice Inspection Intervals 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-23-083, Withdrawal - Proposed Alternatives Related to the Steam Generators2023-06-27027 June 2023 Withdrawal - Proposed Alternatives Related to the Steam Generators 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-23-078, 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-23-075, Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process2023-06-0707 June 2023 Application for Technical Specification Improvement to Extend the Completion Time for Condition B of Technical Specification 3.5.1, Accumulators, Using the Consolidated Line Item Improvement Process 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-23-056, Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 102023-04-20020 April 2023 Response to Request for Additional Information to Braidwood Station, Unit 1, and Byron Station, Unit 1, for Steam Generator License Renewal Response to Commitment 10 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-23-055, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2023-04-10010 April 2023 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors 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-23-038, Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly2023-02-27027 February 2023 Response to Request for Additional Information for the Byron Proposal to Reinsert an Accident Tolerant Fuel Lead Test Assembly RS-23-040, Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators2023-02-21021 February 2023 Constellation Energy Generation, LLC, Supplemental Information - Proposed Alternatives Related to the Steam Generators 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 2024-09-13
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4300 Winfield Road Exelon Generation Warrenville, IL 60555 630 657 2000 Office RS-21-018 EA-12-049 EA-12-051 EA-13-109 February 23, 2021 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455 Dresden Nuclear Power Station , Units 2 and 3 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-237 and 50-249
Subject:
Request for Rescission of NRC Orders EA-12-049, EA-12-051, and EA-13-109 References : 1) Order EA-12-049, "Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis-External Events," dated March 12, 2012 (ML12054A735)
- 2) Order EA-12-051 , "Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation," dated March 12, 2012(ML12056A044)
- 3) Order EA-13-109, "Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions," dated June 6, 2013(ML13143A321)
- 4) Letter from L. Lund (U .S. Nuclear Regulatory Commission (NRC)) to B. C.
Hanson (Exelon Generation Company, LLC (EGC)), "Byron Station, Units 1 and 2 - Documentation of Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-lchi Accident,"
dated May 1, 2018 (ML18094A754)
- 5) Letter from R. J Bernardo (NRC) to B. C. Hanson (EGC), "Dresden Nuclear Power Station, Units 2 and 3 - Documentation of Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-lchi Accident," dated November 17, 2020 (ML20300A235)
- 6) Letter from J. Bradley Fewell (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Certification of Permanent Cessation of
U.S . Nuclear Regulatory Commission February 23, 2021 Page 2 Power Operations for Byron Station, Units 1 and 2," dated September 2, 2020 (NRC Accession No . ML20246G613)
- 7) Letter from J. Bradley Fewell (Exelon Generation Company, LLC) to U.S.
Nuclear Regulatory Commission, "Certification of Permanent Cessation of Power Operations for Dresden Nuclear Power Station, Units 2 and 3," dated September 2, 2020 (NRC Accession No. ML20246G627)
The NRC issued Orders EA-12-049 (Reference 1), EA-12-051 (Reference 2) to all power reactor licensees, and EA-13-109 (Reference 3) to boiling water reactor (BWR) power reactor licensees with Mark I and II containments in response to the lessons learned from the Fukushima Dai-lchi Accident. Subsequently, through the rulemaking process, the NRC promulgated a new regulation , 10 CFR 50.155, "Mitigation of Beyond Design-Basis Events," to make the requirements of Refences 1 and 2 generically applicable. 10 CFR 50.155 became effective on September 9, 2019, with either a two- or three-year implementation period depending upon which Orders a licensee had previously received. 10 CFR 50.155 also has provisions to withdraw References 1 and 2 on September 9, 2022, which is the latest date a licensee can implement the requirements of 10 CFR 50.155. Byron Station, Units 1 and 2 (Byron) is obligated to comply with References 1 and 2. Dresden Nuclear Power Station, Units 2 and 3 (Dresden) is obligated to comply with References 1, 2, and 3. Byron and Dresden are in full compliance with References 1, 2, and 3 as documented in References 4 and 5, respectively. Byron and Dresden have completed all actions required to implement 10 CFR 50.155 as of December 31 , 2020.
Section IV of the Orders (References 1, 2, and 3) stipulates that the NRC's Director of the Office of Nuclear Reactor Regulation may, in writing, relax or rescind any of the conditions of the Orders upon demonstration by the licensee of good cause. The following paragraphs provide EGC's demonstration of good cause.
EGC requests the NRC to rescind Orders EA-12-049 (Reference 1) and EA-12-051 (Reference 2) for Byron and Dresden in that they are duplicative of 10 CFR 50.155.
EGC has notified the NRC in accordance with 10 CFR 50.82(a)(1 )(i) of the planned permanent shutdowns of Byron and Dresden in References 6 and 7, respectively. Byron is planned to be permanently shutdown no later than the end of September 2021 and Dresden is planned to be permanently shutdown no later than the end of November 2021 . Following shutdown, each unit's reactor vessel is intended to be permanently defueled.
The applicability of the requirements contained in 10 CFR 50.155 changes depending upon plant decommissioning status. For example, once the certifications described in 10 CFR 50.82(a)(1) have been submitted, licensees need only comply with the mitigation strategies, training , and documentation of changes associated with spent fuel pool cooling; equipment needed to maintain or restore core cooling and containment are no longer required .
In the case of Byron and Dresden, maintaining compliance with References 1 and 2 when equivalent requirements of 10 CFR 50.155 are not applicable creates unnecessary regulatory burden following the certification of the permanent removal of fuel from the reactor vessels in accordance with 10 CFR 50 .82(a)(1 )(ii). The permanent removal of fuel from the reactor
U.S . Nuclear Regulatory Commission February 23, 2021 Page 3 vessels is expected to occur well in advance of September 9, 2022, when the subject Orders would automatically be withdrawn . EGC requests References 1 and 2 be rescinded for Byron and Dresden effective once the NRC is notified in accordance with 10 CFR 50.82(a)(1 )(ii) that fuel has been permanently removed from the reactor vessels . Following rescission of References 1 and 2, EGC will continue to be required to comply with 10 CFR 50.155. As such, for Byron and Dresden, References 1 and 2 can be rescinded as they are no longer needed to ensure adequate protection of public health and safety.
In addition, EGC requests the NRC to rescind Order EA-13-109 (Reference 3) for Dresden effective once the NRC is notified in accordance with 10 CFR 50.82(a)(1 )(ii) that fuel has been permanently removed from the reactor vessels. Once the reactor vessel in each unit has been permanently defueled, no source of energy will exist within the containment to require the availability of the equipment mandated by Reference 3. Maintaining compliance with Reference 3 would be an unnecessary regulatory burden in that circumstance. As such, Reference 3 can be rescinded as it is no longer needed for Dresden to ensure adequate protection of public health and safety.
Exelon requests rescission of the subject NRC Orders for Byron and Dresden by August 27, 2021, in order to support future decommissioning efforts and preparations for and the timely transition of Byron and Dresden to a permanently shutdown and defueled condition.
Exelon requests that the rescission of these orders become effective following submittal of the certifications required by 10 CFR 50.82(a)(1) that Byron , Units 1 and 2, and Dresden , Units 2 and 3, have been permanently shutdown and defueled.
There are no regulatory commitments contained within this submittal. Should you have any questions concerning this submittal, please contact Mitchel Mathews at (630) 657-2819.
Respectfully, Patrick R. Simpson Sr. Manager - Licensing Exelon Generation Company, LLC cc: NRC Director - Office of Nuclear Reactor Regulation NRC Regional Administrator- NRC Region Ill NRC Project Manager, NRR - Dresden, Units 2 and 3 NRC Senior Resident Inspector - Dresden NRC Project Manager, NRR - Byron NRC Senior Resident Inspector - Byron Director, NRC Division of Fuel Management, NMSS Illinois Emergency Management Agency - Division of Nuclear Safety