Letter Sequence Response to RAI |
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Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming AmendmentsML21259A040 |
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, Zion, FitzPatrick, LaSalle |
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Issue date: |
09/16/2021 |
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From: |
David Helker Exelon Generation Co |
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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-21-0087, NMP1L3426, RS-21-098, TMI-21-028 |
Download: ML21259A040 (9) |
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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, Zion, FitzPatrick, LaSalle |
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Category:Letter type:JAFP
MONTHYEARJAFP-23-0065, License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications2023-12-14014 December 2023 License Amendment Request to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision 4, and Administrative Changes to the Technical Specifications JAFP-23-0069, Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements2023-12-0707 December 2023 Supplemental Response to Part 73 Exemption Request Withdrawal of Request for Exemption from 10 CFR 73, Subpart B, Preemption Authority Requirements JAFP-23-0057, and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023 and Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation JAFP-23-0064, Emergency Plan Document Revision2023-11-15015 November 2023 Emergency Plan Document Revision JAFP-23-0063, Registration of Spent Fuel Cask Use2023-11-13013 November 2023 Registration of Spent Fuel Cask Use JAFP-23-0059, Registration of Spent Fuel Cask Use2023-10-24024 October 2023 Registration of Spent Fuel Cask Use JAFP-23-0048, Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-31031 August 2023 Supplemental Information for License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0050, Physical Security Plan, Revision 242023-08-31031 August 2023 Physical Security Plan, Revision 24 JAFP-23-0047, Correction to the 2022 Annual Radioactive Effluent Release Report2023-08-30030 August 2023 Correction to the 2022 Annual Radioactive Effluent Release Report JAFP-23-0040, License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis2023-08-0303 August 2023 License Amendment Request to Update the Technical Specification Bases to Change the Fuel Handling Accident Analysis JAFP-23-0043, 10 CFR 50.46 Annual Report2023-07-31031 July 2023 10 CFR 50.46 Annual Report JAFP-23-0038, License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance2023-07-28028 July 2023 License Amendment Request to Modify Technical Specification Surveillance Requirement (SR) 3.4.3.1 Safety Relief Valves (S/Rvs) Setpoint Lower Tolerance JAFP-23-0033, License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation2023-06-28028 June 2023 License Amendment Request - Technical Specifications (TS) Section 3.3.1.2, Source Range Monitors (SRM) Instrumentation JAFP-23-0025, 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 2022 Annual Radiological Environmental Operating Report JAFP-23-0023, 2022 Annual Radioactive Effluent Release Report2023-04-27027 April 2023 2022 Annual Radioactive Effluent Release Report JAFP-23-0010, 2022 REIRS Transmittal of NRC Form 52023-03-20020 March 2023 2022 REIRS Transmittal of NRC Form 5 JAFP-23-0008, Supplement to Inservice Inspection Summary Report Cycle 252023-02-22022 February 2023 Supplement to Inservice Inspection Summary Report Cycle 25 JAFP-22-0053, Inservice Inspection Summary Report Cycle 252022-12-20020 December 2022 Inservice Inspection Summary Report Cycle 25 JAFP-22-0046, Core Operating Limits Report Cycle 262022-10-17017 October 2022 Core Operating Limits Report Cycle 26 JAFP-22-0040, 10 CFR 50.46 Annual Report2022-07-29029 July 2022 10 CFR 50.46 Annual Report JAFP-22-0033, Core Operating Limits Report Mid-Cycle 252022-06-23023 June 2022 Core Operating Limits Report Mid-Cycle 25 JAFP-22-0032, Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b..2022-06-16016 June 2022 Response to Request for Additional Information for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b.. JAFP-22-0030, Oswego County and New York State Participation in the Emergency Plan2022-05-13013 May 2022 Oswego County and New York State Participation in the Emergency Plan JAFP-22-0029, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report JAFP-22-0028, 2021 Annual Radioactive Effluent Release Report2022-04-27027 April 2022 2021 Annual Radioactive Effluent Release Report JAFP-22-0026, 2021 REIRS Transmittal of NRC Form 52022-04-0707 April 2022 2021 REIRS Transmittal of NRC Form 5 JAFP-22-2020, Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Info2022-03-0404 March 2022 Supplemental Information No. 1 for James A. FitzPatrick Nuclear Power Plant to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b. and 10CFR 50.69, Risk-Informed JAFP-22-0017, Amendments to Indemnity Agreements2022-02-15015 February 2022 Amendments to Indemnity Agreements JAFP-22-0007, Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102022-01-31031 January 2022 Summary of Changes to Exelon Generation Company, LLC, Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 JAFP-22-0010, Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments2022-01-24024 January 2022 Supplemental Information in Response to Order Consenting to License Transfers and Approval of Draft Conforming License Amendments JAFP-22-0008, Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary2022-01-14014 January 2022 Response to Request for Supplemental Information by the Office of Nuclear Reactor Regulation to Support Review of a License Amendment Request to Eliminate Selected Response Time Testing for Reactor Protection System and Primary JAFP-21-0093, Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation2021-10-18018 October 2021 Propose Change to Eliminate Selected Response Time Testing for Reactor Protection System and Primary Containment Isolation Instrumentation JAFP-21-0089, Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2021-09-27027 September 2021 Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position 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 JAFP-21-0083, Notification of Readiness for NRC 95001 Inspection2021-09-0909 September 2021 Notification of Readiness for NRC 95001 Inspection JAFP-21-0081, Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements2021-09-0303 September 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-582, Revision 0, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements JAFP-21-0075, Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs2021-08-12012 August 2021 Proposed Relief Request Associated with Reactor Pressure Vessel Water Level Instrumentation Partial Penetration Nozzle Repairs JAFP-21-0073, Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance.2021-08-0909 August 2021 Response to Request for Additional Information Regarding Application to Revise the James A. FitzPatrick Nuclear Power Plant Limiting Condition for Operation (LCO) 3.5.1, ECCS - Operating Surveillance. JAFP-21-0070, 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 4b2021-07-30030 July 2021 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 JAFP-21-0069, Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors2021-07-30030 July 2021 Application to Adopt 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors JAFP-21-0071, 10 CFR 50.46 Annual Report2021-07-29029 July 2021 10 CFR 50.46 Annual Report JAFP-21-0064, Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting2021-07-0707 July 2021 Supplemental Information - Proposed Alternative Concerning ASME Section XI Repair/Replacement Documentation for Replacement of Pressure Retaining Bolting JAFP-21-0053, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-14014 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0051, Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request - One Time Extension to TS 3.5.1 Condition a, TS 3.6.1.9 Condition a, and TS 3.6.4.1 Condition a Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0052, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-13013 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement JAFP-21-0050, Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement2021-06-12012 June 2021 Emergency License Amendment Request, One Time Extension of Condition a to TS 3.5.1, TS 3.6.1.9, and TS 3.6.4.1 Completion Time to Support Residual Heat Removal (RHR) Pump Motor Replacement 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-21-0042, Reply to a Notice of Violation; EA-20-1382021-06-0303 June 2021 Reply to a Notice of Violation; EA-20-138 JAFP-21-0041, Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing2021-05-17017 May 2021 Supplement to Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing JAFP-21-0040, 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 SRs2021-05-14014 May 2021 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 2023-08-31 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 [[:Zion]] OR [[:FitzPatrick]] OR [[:LaSalle]] </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 [[:Zion]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>. Category:Response to Request for Additional Information (RAI)
MONTHYEARML24031A6612024-01-31031 January 2024 International, Rsi Responses on HI-STORM Umax Revisions to Amendments 0, 1, and 2 NL-24-0014, Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical.2024-01-30030 January 2024 Revised Response to Request for Additional Information Regarding License Amendment Request to Relax the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs in Technical. ML24026A1962024-01-26026 January 2024 GEH - Response to NRC Request for Additional Information ML24025A1362024-01-25025 January 2024 Louisiana Energy Services, LLC - Response to Request for Supplemental Information Regarding LAR 23-07 NLS2024006, Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-022024-01-25025 January 2024 Response to Nuclear Regulatory Commission'S Request for Additional Information for Relief Request RC3-02 ML24025A0952024-01-24024 January 2024 Clarifications Related to the NRC Staff'S EA for Crystal River NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML24012A2452024-01-12012 January 2024 Response to Request for Additional Information to Proposed Method to Manage Environmentally Assisted Fatigue for the Pressurizer Surge Line NRC-24-0002, Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.122024-01-12012 January 2024 Clarification for Request for Additional Information Responses for License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, Surveillance Requirement SR 3.8.1.12 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 ML24011A1702024-01-11011 January 2024 Washington State University, Revised Responses to Request for Additional Information in Reference to LAR 2023-1: License Amendment Request - Section 5 of the Technical Specifications and Bases ML24011A1712024-01-11011 January 2024 Washington State University, Technical Specifications and Bases, Amendment 22 CNL-23-071, Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-472024-01-11011 January 2024 Response to Request for Additional Information Regarding Browns Ferry Nuclear Plant, Units 1, 2, and 3, Inservice Inspection and Augmented Program Interval Revised Request for Alternative 0-ISI-47 PLA-8096, Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval2024-01-0404 January 2024 Response to Request for Additional Information Regarding Proposed Relief Request for the Fifth 10-Year Inservice Test Program Interval RS-24-001, Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval2024-01-0303 January 2024 Response to Request for Additional Information Regarding Relief Request I5R-26, Inservice Inspection Program Relief Request Regarding Examination Coverage for the Fifth Inservice Inspection Interval ML24004A0402024-01-0303 January 2024 Response to NRCs November 8, 2023, Request for Additional Information - Related to Independent Spent Fuel Storage Installation L-PI-23-034, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System,2024-01-0202 January 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.7.8, Cooling Water (Cl) System, ML23361A0992023-12-27027 December 2023 LLC, Response to NRC Request for Additional Information (RAI 10083) on the NuScale Standard Design Approval Application ML23361A0942023-12-21021 December 2023 Response to Request for Additional Information Regarding Proposed License Amendment Request to Revise Technical Specifications for Reactor Core Safety Limits, Fuel Assemblies and Core Operating Limits Report . L-PI-23-035, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report2023-12-20020 December 2023 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications Section 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report ML23354A2882023-12-20020 December 2023 TRISO-X, LLC, Response to Request for Additional Information Part 2-1 for the TRISO-X Environmental Report and License Application ML23354A2112023-12-20020 December 2023 Response to Request for Additional Information for the TMI-2 Post-Shutdown Decommissioning Activities Report, Rev. 5 L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 ML23349A0472023-12-15015 December 2023 GEH Response to NRC Request for Additional Information RS-23-128, Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days2023-12-15015 December 2023 Response to Request for Additional Information for the Emergency License Amendment Request Increase Technical Specifications Completion Time in TS 3.8.1.B.4 from 7 Days to 30 Days ML23349A2082023-12-15015 December 2023 TRISO-X, LLC, Response to Request for Additional Information Set 6 (Structural, Material Control and Accounting, and Fire Safety) for the TRISO-X License Application ML23348A3732023-12-14014 December 2023 Acu Msrr - Environmental Review Requests for Confirmatory Information - Closure Confirmation for CA- 2, 5 and 6 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) ML23345A2112023-12-11011 December 2023 NAC International, Inc., Submittal of Replacement Pages for Supplemental Responses to the Nrc'S Request for Additional Information to Nac'S for the NAC OPTIMUS-L Transportation Package and Safety Analysis Report, Revision 1 ML23346A0972023-12-11011 December 2023 License Amendment Request to Revise the Emergency Plan Relocation of the Technical Support Center - Response to NRC Request for Additional Information ML23343A0022023-12-0909 December 2023 Response to Request for Additional Information Set 5 (Chemical Safety and Radiation Protection) for the TRISO-X License Application ML23346A2622023-12-0808 December 2023 Cimarron Environmental Response Trust, Response to October 2, 2023, Request for Additional Information L-PI-23-033, Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 32023-12-0505 December 2023 Supplement to License Amendment Request to Revise Technical Specification 3.8.1, Surveillance Requirement 3.8.1.2, Note 3 ML23338A3062023-12-0404 December 2023 Attachment 1: HI-STORM 100 Amendment 18 RAI Responses (non-proprietary) ML23334A1952023-11-30030 November 2023 Response to Request for Additional Information in Reference to LAR 2023-1: License Amendment Request Section 5 of the Technical Specifications and Bases for the Washington State University Modified Triga Reactor and Facility License R-76, P L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports L-2023-155, Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-06542023-11-28028 November 2023 Supplement to Response to Request for Additional Information, Revised NextEra Common Emergency Plan, and Revised Site-Specific Emergency Plan Annexes Regarding License Amendment Request for Common Emergency Plan Consistent with NUREG-0654, L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-2023-162, Response to 50.69 2nd Round of Rals2023-11-21021 November 2023 Response to 50.69 2nd Round of Rals ML23321A2472023-11-17017 November 2023 Attachment 1: Holtec International - Summary of Additional Clarifications/Changes Submitted for Review ML23321A2192023-11-17017 November 2023 International, NRC Clarification Questions from EA-23-044 Holtec Pec Presentation ML23297A261 (Edited Excerpt from the Pec Transcript ML23307A107) NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 ML23319A2032023-11-15015 November 2023 Cimarron Environmental Response Trust - Response to November 1, 2023, Request for Additional Information Related to Nuclear Criticality Safety CCN:23-09, 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 ML23317A1032023-11-10010 November 2023 Supplemental Information Letter for Part 73 Exemption Request - Responses to Request for Confirmatory Information 2024-01-04 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 [[:Zion]] OR [[:FitzPatrick]] OR [[:LaSalle]] </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 [[:Zion]] OR [[:FitzPatrick]] OR [[:LaSalle]] </code>. |
Text
200 Exelon Way Kennett Square, PA 19348 www.exeloncorp.com 10 CFR 50.80 10 CFR 50.90 10 CFR 72.50 RS-21-098 JAFP-21-0087 NMP1L3426 TMI-21-028 September 16, 2021 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 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 Response to Request for Additional Information Approval of License Transfers and Conforming Amendments September 16, 2021 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 Zion Nuclear Power Station, Units 1 and 2 Facility Operating License Nos. DPR-39 and DPR-48 NRC Docket Nos. 50-295, 50-304, and 72-1037
References:
- 1) Letter from J. Bradley Fewell, Exelon Generation Company, LLC to U.S.
Nuclear Regulatory Commission - "Application for Order Approving License Transfers and Proposed Conforming License Amendments," dated February 25, 2021 (ML21057A273)
- 2) Letter from David P. Helker, Exelon Generation Company, LLC to U.S.
Nuclear Regulatory Commission - "Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments," dated March 25, 2021 (ML21084A165)
- 3) Electronic Mail Message from Blake Purnell, U.S. Nuclear Regulatory Commission, to David P. Helker, Exelon Generation Company, LLC -
"Request for Additional Information, Exelon Generation Company, LLC, Approval of Transfer of Licenses and Conforming Amendments," dated May 24, 2021 (ML21144A213)
- 4) Letter from David P. Helker, Exelon Generation Company, LLC to U.S.
Nuclear Regulatory Commission - "Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments," dated June 11, 2021 (ML21162A292)
U.S. Nuclear Regulatory Commission Response to Request for Additional Information Approval of License Transfers and Conforming Amendments September 16, 2021 Page 3
- 5) Electronic Mail Message from Blake Purnell, U.S. Nuclear Regulatory Commission, to J. Bradley Fewell, Exelon Generation Company, LLC -
"Request for Additional Information, Exelon Generation Company, LLC, Approval of Transfer of Licenses and Conforming Amendments," dated September 10, 2021 (ML21256A190)
Subject:
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments By letter dated February 25, 2021 (Reference 1), and in accordance with Section 184 of the Atomic Energy Act of 1954, as amended (the "Act"), 10 CFR 50.80, 10 CFR 50.90, and 10 CFR 72.50, Exelon Generation Company, LLC ("Exelon Generation"), on behalf of itself and Exelon Corporation, Exelon FitzPatrick, LLC ("Exelon FitzPatrick, LLC"), Nine Mile Point Nuclear Station, LLC ("NMP LLC"), R.E. Ginna Nuclear Power Plant, LLC ("Ginna LLC"), and Calvert Cliffs Nuclear Power Plant, LLC ("Calvert LLC") (collectively, "Applicants"), requested certain written consents related to a proposed transaction in which Exelon Corporation will transfer its 100% ownership of Exelon Generation to a newly-created subsidiary that will then be spun-off to Exelon Corporation shareholders, becoming Exelon Generations new ultimate parent company, so that neither the new ultimate parent company nor Exelon Generation nor its subsidiaries will be affiliated with Exelon Corporation ("Spin Transaction").
On March 25, 2021 (Reference 2), Exelon Generation submitted a supplemental response in support of the Reference 1 submittal. By electronic mail message dated May 24, 2021 (Reference 3), the U.S Nuclear Regulatory Commission (NRC) notified Exelon Generation that additional information was needed to complete its review of the Reference 1 submittal as supplemented (Reference 2). On June 11, 2021 (Reference 4), Exelon Generation responded to the Reference 3 RAI. More recently, in an electronic mail message dated September 10, 2021 (Reference 5), the NRC requested that Exelon Generation provide additional clarifying information in support of the review of the license transfer application as supplemented. to this letter provides the response to the request for additional information (RAI) question contained in Reference 5.
Exelon Generation has reviewed the information supporting a finding of no significant hazards consideration, and the environmental consideration, that were previously provided to the NRC in Reference 1, Reference 2, and Reference 4 letters. Exelon Generation has concluded that the information provided in this response to the Reference 5 RAI does not affect the bases for concluding that the proposed license amendments do not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92. In addition, Exelon Generation has concluded that the information in this response does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendments.
U.S. Nuclear Regulatory Commission Response to Request for Additional Information Approval of License Transfers and Conforming Amendments September 16, 2021 Page 4 In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," subsection (b), Exelon Generation is notifying the Commonwealth of Pennsylvania and the States of Illinois, Maryland, New Jersey, and New York of the updates to its application for license amendments by transmitting a copy of this letter and attachment to the designated State Officials.
There are no regulatory commitments contained in this submittal.
Please contact David P. Helker (Exelon Generation) at 610-765-5525 if you have any questions or require any additional information regarding this response to the NRC's RAI.
I declare under penalty of perjury that the foregoing is true and correct. Executed on the 16th day of September 2021.
Respectfully, David P. Helker Sr. Manager, Licensing Exelon Generation Company, LLC
Attachment:
Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments cc: (w/ Attachment)
Regional Administrator - NRC Region I Regional Administrator - NRC Region III 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, NMSS - Zion Nuclear Power Station NRC Project Manager, NRR - Exelon Generation Fleet Illinois Emergency Management Agency - Division of Nuclear Safety Director, Bureau of Radiation Protection - Pennsylvania Department of Environmental Resources
U.S. Nuclear Regulatory Commission Response to Request for Additional Information Approval of License Transfers and Conforming Amendments September 16, 2021 Page 5 cc: continued (w/ Attachment)
W. DeHaas - Pennsylvania Bureau of Radiation Protection S. Seaman - State of Maryland P. Mulligan - New Jersey Bureau of Nuclear Engineering A. L. Peterson, NYSERDA B. Frymire, NYSPSC
ATTACHMENT Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments
Attachment Response to Request for Additional Information Request for Approval of Transfer of Licenses and Conforming Amendments Page 1 of 3 ATTACHMENT Response to Request for Additional Information Request for Approval of Transfer of Licenses and Conforming Amendments By letter dated February 25, 2021 (Reference 1), as supplemented on March 25, 2021 (Reference 2), Exelon Generation Company, LLC (Exelon Generation), requested U.S. Nuclear Regulatory Commission (NRC) consent to the indirect transfer of control of the licenses to support a proposed transaction in which Exelon Corporation will transfer its 100 percent ownership of Exelon Generation to a newly-created subsidiary (referred to as HoldCo in the application) that will then be spun off to Exelon Corporation shareholders, becoming Exelon Generations new ultimate parent company.
By electronic mail message dated May 24, 2021 (Reference 3), the NRC notified Exelon Generation that additional information was needed to complete its review of the Reference 1 submittal as supplemented in the Reference 2 letter. On June 11, 2021 (Reference 4), Exelon Generation responded to the Reference 3 request for additional information (RAI).
The NRC continues to review the application, as supplemented, and determined that additional clarifying information is needed to complete its review. In an electronic mail message dated September 10, 2021 (Reference 5), the NRC issued the following question. The question is reiterated below followed by Exelon Generation's response.
Request for Additional Information 1 Section III.D of the application states that the Constellation Energy Nuclear Group, LLC (CENG)
Board will be dissolved and the Operating Agreement with CENG will be terminated as part of the spin transaction. The application states that SpinCo would hold decision making authority over safety, security, and reliability at Calvert Cliffs, NMP, and Ginna following the spin transaction. In addition, CENG will be removed from the upstream ownership chain of Calvert LLC.
Section VI.B of the application states, in part, that SpinCo will maintain separate support agreements for the benefit of Calvert LLC, NMP LLC, and Ginna LLC. The Applicants state that these new support agreements will replace the existing financial support terms referenced in the licenses for these facilities. The proposed SpinCo support agreements do not appear to involve CENG. As part of the application, the Applicants request the NRCs consent to terminate the existing Exelon Corporation Support Agreement, Exelon Corporation Guarantee, and CENG cash pool arrangement and associated Master Demand Notes for Calvert Cliffs, NMP, and Ginna and instead implement the updated SpinCo support agreements.
The application requested amendments to the Calvert Cliffs, Units 1 and 2; NMP, Units 1 and 2; and Ginna licenses to "delete the license conditions referencing the CENG Board, Fourth Amended and Restated Operating Agreement, Support Agreements, Parent Guarantees, and cash pool agreements associated with prior license transfers and replace them with revised license conditions referencing the updated SpinCo Support Agreement, as detailed in the Application."
Attachment Response to Request for Additional Information Request for Approval of Transfer of Licenses and Conforming Amendments Page 2 of 3 The proposed markup of the licenses for Calvert Cliffs, Units 1 and 2; NMP, Units 1 and 2; and Ginna includes conforming changes to the current license conditions for the Exelon Corporation Support Agreement to reflect the proposed SpinCo Support Agreement. However, the markup indicates that the reference to CENG should be retained. For example, the proposed markup for the additional condition of page 9 of Appendix C to the Calvert Cliffs, Unit 1, license states, in part (emphasis added):
Calvert Cliffs Nuclear Power, LLC, or CENG shall not take any action to cause
[SPINCO], or its successors and assigns, to void, cancel, or materially modify the
[SPINCO] Support Agreement or cause it to fail to perform, or impair its performance under the [SPINCO] Support Agreement, without the prior written consent of the NRC.
The retention of the reference to CENG in these conditions does not appear to be consistent with the elimination of the operating and financial agreements with CENG.
Request Confirm that references to CENG should be removed from the proposed Calvert Cliffs, Units 1 and 2; NMP, Units 1 and 2; and Ginna license conditions related to the SpinCo Support Agreements. Otherwise, identify any agreements with CENG that could allow CENG to void, cancel, or materially modify the SpinCo Support Agreements or cause it to fail to perform, or impair its performance under the SpinCo Support Agreements.
Response
Exelon Generation hereby confirms that references to CENG should be removed from the proposed Calvert Cliffs, Units 1 and 2; NMP, Units 1 and 2; and Ginna license conditions related to the SpinCo Support Agreements.
References:
- 1. Letter from J. Bradley Fewell, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission - "Application for Order Approving License Transfers and Proposed Conforming License Amendments," dated February 25, 2021 (ML21057A273)
- 2. Letter from David P. Helker, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission - "Supplemental Information Regarding Application for Order Approving Transfers and Proposed Conforming License Amendments," dated March 25, 2021 (ML21084A165)
- 3. Electronic Mail Message from Blake Purnell, U.S. Nuclear Regulatory Commission, to David P. Helker, Exelon Generation Company, LLC - "Request for Additional Information, Exelon Generation Company, LLC, Approval of Transfer of Licenses and Conforming Amendments," dated May 24, 2021 (ML21144A213)
Attachment Response to Request for Additional Information Request for Approval of Transfer of Licenses and Conforming Amendments Page 3 of 3
- 4. Letter from David P. Helker, Exelon Generation Company, LLC to U.S. Nuclear Regulatory Commission - "Response to Request for Additional Information Regarding Request for Approval of Transfer of Licenses and Conforming Amendments," dated June 11, 2021 (ML21162A292)
- 5. Electronic Mail Message from Blake Purnell, U.S. Nuclear Regulatory Commission, to J.
Bradley Fewell, Exelon Generation Company, LLC - "Request for Additional Information, Exelon Generation Company, LLC, Approval of Transfer of Licenses and Conforming Amendments," dated September 10, 2021 (ML21256A190)