Letter Sequence Request |
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EPID:L-2021-LLA-0124, Order (Granting Motion to Extend Hearing Requests Deadline) (Approved, Closed) |
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MONTHYEARML21144A1252021-05-24024 May 2021 Order (Granting Motion to Extend Hearing Requests Deadline) Project stage: Request ML21168A3282021-06-17017 June 2021 Motion to Enter Second Amended Protective Order Project stage: Request ML21181A3762021-06-30030 June 2021 Combined Motion of Exelon to File Its Answers to the Edf and Epstein-TMIA Hearing Requests on Illinois New Hearing Request Deadline and Motion of Elpc to Move Exelon Deadline to Answer Elpc Hearing Request to July 30 2021 Project stage: Request ML21183A1692021-06-30030 June 2021 License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications Sections 4.3.1 and 5.6.5 Project stage: Request ML21210A0942021-07-29029 July 2021 NRR E-mail Capture - La Salle, 1 & 2 - Acceptance of Licensing Action License Amendment Request New Fuel Storage Vault and Spent Fuel Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124) Project stage: Acceptance Review PMNS20211084, a Closed Meeting with Exelon Generation Company, LLC Regarding Proprietary Information in the Request for the Amendments to Renewed Facility Operating Licenses for LaSalle County Station, Units 1 and 22021-08-31031 August 2021 a Closed Meeting with Exelon Generation Company, LLC Regarding Proprietary Information in the Request for the Amendments to Renewed Facility Operating Licenses for LaSalle County Station, Units 1 and 2 Project stage: Meeting RS-21-109, Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 20212021-10-14014 October 2021 Request to Withhold Meeting Materials for the Non-Public Meeting Held on September 2, 2021 Project stage: Request ML21181A0582021-10-15015 October 2021 Summary of Public Closed Meeting with Exelon Generation Company, LLC Regarding Proprietary Information Marking in the LAR Associated with Transition to New Fuel at Lasalle County Station, Units 1 and 2 Project stage: Meeting RS-21-115, Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.52021-11-0404 November 2021 Supplemental Information for License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Specifications 4.3.1 and 5.6.5 Project stage: Supplement 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 Project stage: Request ML22025A2272022-02-17017 February 2022 Request for Withholding Information from Public Disclosure License Amendment Request Related to New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Project stage: Withholding Request Acceptance ML22126A0392022-05-0606 May 2022 NRR E-mail Capture - Lasalle 1 and 2 Draft (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to TS Sections 4.3.1 and 5.6.5 Project stage: Draft RAI ML22138A4112022-05-18018 May 2022 NRR E-mail Capture - Lasalle 1 and 2 - (RAI) License Amendment Request Regarding New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Changes to TS Sections 4.3.1 and 5.6.5 (EPID-L-2021-LLA-0124) Project stage: RAI RS-22-083, Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical2022-06-17017 June 2022 Response to Request for Additional Information Related to the License Amendment Request to Change New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies, with Proposed Changes to Technical Project stage: Response to RAI ML22181B0902022-07-0505 July 2022 Request for Withholding Information from Public Disclosure Project stage: Withholding Request Acceptance ML22214A0042022-08-0202 August 2022 Audit Plan to Support the Review of Amendments to Revise Criticality Safety Analysis Methodologies (Epids L-2022-LLA-0085, L-2021-LLA-0124, and L-2021-LLA-0159) Project stage: Other ML22234A1692022-08-22022 August 2022 R. E. Ginna Nuclear Power Plant, Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) Project stage: Request ML22264A0842022-09-20020 September 2022 R. E. Ginna Nuclear Power Plant - Clarification Letter to the Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) Project stage: Request RA22-041, Unit 2 Cycle 19 Core Operating Limits Report Revision2022-10-0505 October 2022 Unit 2 Cycle 19 Core Operating Limits Report Revision Project stage: Request RS-22-109, Response to Request for Additional Information License Amendments Related to Fuel Storage2022-10-12012 October 2022 Response to Request for Additional Information License Amendments Related to Fuel Storage Project stage: Response to RAI ML22300A2532022-11-0303 November 2022 Regulatory Audit Report to Support the Review of Amendments to Revise Criticality Safety Analysis Methodologies (Epids L-2022-LLA-0085, L-2021-LLA-0124, and L-2021-LLA-0159) Project stage: Approval ML22362A0382022-12-28028 December 2022 R. E. Ginna Nuclear Power Plant - Letter to Withdraw Application to Revise Technical Specifications 5.6.5, Core Operating Limits Report (COLR) Project stage: Request ML22341A2222022-12-28028 December 2022 Issuance of Amendment Nos. 257 and 243 to Renewed Facility Operating Licenses New Fuel Storage Vault and Spent Fuel Storage Pool Criticality Methodologies and Changes to Core Operating Limits Report Project stage: Approval ML23031A2992023-02-0707 February 2023 R. E. Ginna Nuclear Power Plant - Withdrawal of an Amendment Request Project stage: Withdrawal 2022-11-03
[Table View] |
Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLCML22032A333 |
Person / Time |
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Site: |
Calvert Cliffs, Dresden, Peach Bottom, Salem, Nine Mile Point, Byron, Three Mile Island, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, 07200078, 07200077 |
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Issue date: |
02/01/2022 |
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From: |
Reddick D Constellation Energy Generation |
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To: |
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation |
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References |
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JAFP-22-014, NMPL13446, RS-22-015, TMI-22-003 |
Download: ML22032A333 (4) |
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Similar Documents at Calvert Cliffs, Dresden, Peach Bottom, Salem, Nine Mile Point, Byron, Three Mile Island, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle, 07200078, 07200077 |
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Category:Letter type:RS
MONTHYEARRS-24-104, Nuclear Radiological Emergency Plan Document Revision2024-11-0101 November 2024 Nuclear Radiological Emergency Plan Document Revision RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality2024-10-23023 October 2024 Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality RS-24-097, Notice of Intent to Pursue Subsequent License Renewal for Three Mile Island Nuclear Station, Unit 12024-10-23023 October 2024 Notice of Intent to Pursue Subsequent License Renewal for Three Mile Island Nuclear Station, Unit 1 RS-24-103, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-10-21021 October 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-102, Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-5912024-10-21021 October 2024 Supplement to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, and TSTF-591 RS-24-080, Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in .2024-10-16016 October 2024 Request to Replace Formerly Submitted Documents Available in the Agency Documents Access and Management System (ADAMS) with Documents Redacted in . RS-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-24-095, Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals2024-10-10010 October 2024 Relief Request I4R-19 and I4R-26, Associated with the Fourth and Fifth Inservice Inspection Intervals RS-24-092, Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-09-25025 September 2024 Revised Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-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-24-090, Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-09-12012 September 2024 Response to Request for Additional Information - Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-087, 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-24-078, Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing Interval2024-08-20020 August 2024 Alternative Request RV-08, Revision 1, Associated with Safety Relief Valve Testing 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-24-070, Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions2024-07-12012 July 2024 Independent Spent Fuel Storage Installation, Nine Mile Point, Units 1 and 2, Quad Cities, Units 1 and 2, R. E. Ginna - Nuclear Radiological Emergency Plan Document Revisions 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-24-053, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed2024-06-0606 June 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed RS-24-058, Regarding Subsequent License Renewal Environmental Review2024-06-0505 June 2024 Regarding Subsequent License Renewal Environmental Review RS-24-057, License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink2024-06-0404 June 2024 License Amendment to Technical Specification 3.7.9, Ultimate Heat Sink 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-24-052, 2023 Annual Radiological Environmental Operating Report2024-05-15015 May 2024 2023 Annual Radiological Environmental Operating Report RS-24-042, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-05-10010 May 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion 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-24-049, Updated Notice of Intent to Pursue Subsequent License Renewal Applications2024-05-0909 May 2024 Updated Notice of Intent to Pursue Subsequent License Renewal Applications RS-24-046, 10 CFR 50.46 Annual Report2024-05-0606 May 2024 10 CFR 50.46 Annual Report RS-24-038, Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds2024-05-0202 May 2024 Relief Request Concerning Extension of Permanent Relief from Ultrasonic Examination of Reactor Pressure Vessel Circumferential Shell Welds RS-24-047, 2023 Annual Radioactive Effluent Release Report2024-05-0101 May 2024 2023 Annual Radioactive Effluent Release 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-24-032, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion2024-04-0505 April 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion 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-24-019, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF2024-03-19019 March 2024 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Completion Times TSTF RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS 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-24-015, Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval2024-02-29029 February 2024 Submittal of RP-01 Relief Request Associated with the Sixth Inservice Testing Interval 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-24-014, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors2024-02-22022 February 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-24-013, Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators2024-02-13013 February 2024 Response to Request for Additional Information Regarding Proposed Alternative to Distribution Requirements of ASME Code Table IWC-2411-1 for the Steam Generators RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release 2024-09-09 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Byron]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Ginna]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:FitzPatrick]] OR [[:LaSalle]] OR [[:07200078]] OR [[:07200077]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Peach Bottom]] OR [[:Salem]] OR [[:Nine Mile Point]] OR [[:Byron]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Limerick]] OR [[:Ginna]] OR [[:Clinton]] OR [[:Quad Cities]] OR [[:FitzPatrick]] OR [[:LaSalle]] OR [[:07200078]] OR [[:07200077]] </code>. |
Text
RS-22-015 JAFP-22-014 NMPL13446 TMI-22-003 February 1, 2022 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Braidwood Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456, STN 50-457, and 72-73 Byron Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454, STN 50-455, and 72-68 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Nuclear Power Plant, Units 1 and 2 Independent Spent Fuel Storage Installation Materials License No. SNM-2505 NRC Docket No. 72-08 and 72-78 Clinton Power Station, Unit 1 Facility Operating License No. NPF-62 NRC Docket No. 50-461 and 72-1046 Dresden Nuclear Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-2 Renewed Facility Operating License Nos. DPR-19 and DPR-25 NRC Docket Nos. 50-10, 50-237, 50-249, and 72-37 James A. FitzPatrick Nuclear Power Plant Renewed Facility Operating License No. DPR-59 NRC Docket Nos. 50-333 and 72-12 LaSalle County Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-11 and NPF-18 NRC Docket Nos. 50-373, 50-374, and 72-70 Limerick Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. NPF-39 and NPF-85 NRC Docket Nos. 50-352, 50-353, and 72-65
U.S. Nuclear Regulatory Commission Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon February 1, 2022 Page 2 Nine Mile Point Nuclear Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-63 and NPF-69 NRC Docket Nos. 50-220, 50-410, and 72-1036 Peach Bottom Atomic Power Station, Units 1, 2 and 3 Facility Operating License No. DPR-12 Subsequent Renewed Facility Operating License Nos. DPR-44 and DPR-56 NRC Docket Nos. 50-171, 50-277, 50-278, and 72-29 Quad Cities Nuclear Power Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-29 and DPR-30 NRC Docket Nos. 50-254, 50-265, and 72-53 R.E. Ginna Nuclear Power Plant Renewed Facility Operating License No. DPR-18 NRC Docket Nos. 50-244 and 72-67 Salem Generating Station, Units 1 and 2 Renewed Facility Operating License Nos. DPR-70 and DPR-75 NRC Docket Nos. 50-272, 50-311, and 72-48 Three Mile Island Nuclear Station, Unit 1 Renewed Facility License No. DPR-50 NRC Docket No. 50-289 and 72-77
References:
- 1) Letter from Blake A. Purnell, U.S. Nuclear Regulatory Commission, to David P. Rhoades, Exelon Generation Company, LLC - "Order Approving Transfer of Licenses and Draft Conforming License Amendments (EPID L-2021-LLM-0000)," dated November 16, 2021 (ML21277A248)
- 2) Letter from Darani M. Reddick, Exelon Generation Company, LLC, to U.S.
Nuclear Regulatory Commission - Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments, dated January 24, 2022 (ML22024A490)
Subject:
Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC In the Reference 1 letter, the U.S. Nuclear Regulatory Commission (NRC) issued an Order approving the indirect transfer of the facility operating licenses and other cited supporting licenses for the plants noted above in support of the requested Exelon Generation Company, LLC (Exelon) Spin Transaction. The Reference 2 letter provided information regarding the final legal entity names and other related information associated with the Spin Transaction.
This letter provides notice that the Spin Transaction has been consummated. Exelon Generation Company, LLC changed its name to Constellation Energy Generation, LLC and the indirect transfer of the cited licenses was completed today, February 1, 2022. As noted in the
U.S. Nuclear Regulatory Commission Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon February 1, 2022 Page 3 Reference 2 letter, the respective licenses related to Zion Nuclear Power Station will not be included in conjunction with the Spin Transaction and will be transferred separately.
Prior to the indirect license transfers, Exelon made docketed submittals to the NRC that requested specific licensing actions, such as license amendment requests, relief requests, exemption requests, etc. This letter requests that the NRC continue to process all pending licensing actions on the schedules previously requested by Exelon.
There are no regulatory commitments contained in this correspondence.
If you have any questions, please contact David P. Helker at 610-765-5525.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 1st day of February 2022.
Respectfully, Reddick, Digitally signed by Reddick, Darani M.
DN: cn=Reddick, Darani M.
Darani M. Date: 2022.02.01 11:55:37
-05'00' Darani M. Reddick Director, Licensing Constellation Energy Generation, LLC cc: Regional Administrator - NRC Region I Regional Administrator - NRC Region III Director, Office of Nuclear Reactor Regulation Director, Office of Nuclear Material Safety and Safeguards NRC Senior Resident Inspector - Braidwood Station NRC Senior Resident Inspector - Byron Station NRC Senior Resident Inspector - Calvert Cliffs Nuclear Power Plant NRC Senior Resident Inspector - Clinton Power Station NRC Senior Resident Inspector - Dresden Nuclear Power Station NRC Senior Resident Inspector - James A. FitzPatrick Nuclear Power Plant NRC Senior Resident Inspector - LaSalle County Station NRC Senior Resident Inspector - Limerick Generating Station NRC Senior Resident Inspector - Nine Mile Point Nuclear Station NRC Senior Resident Inspector - Peach Bottom Atomic Power Station NRC Senior Resident Inspector - Quad Cities Nuclear Power Station NRC Senior Resident Inspector - R. E. Ginna Nuclear Power Plant NRC Senior Resident Inspector - Salem Generating Station NRC Project Manager, NMSS - Three Mile Island Nuclear Station NRC Project Manager, NRR - Constellation Generation Fleet Illinois Emergency Management Agency - Division of Nuclear Safety Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources W. DeHaas - Pennsylvania Bureau of Radiation Protection
U.S. Nuclear Regulatory Commission Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon February 1, 2022 Page 4 cc: continued S. Seaman - State of Maryland P. Mulligan - New Jersey Bureau of Nuclear Engineering A. L. Peterson, NYSERDA B. Frymire, NYSPSC