| | Start date | Site | Title | System |
|---|
| L-25-189, Submittal of Post Accident Monitor Report | 8 October 2025 | Beaver Valley | Submittal of Post Accident Monitor Report | Main Steam |
| ML25232A194 | 10 September 2025 | Vogtle | Issuance of Amendment Nos. 208 and 206 to Revise Technical Specification Table 3.3.8-1, Engineered Safeguards Actuation System Instrumentation | Steam Generator
Reactor Coolant System
Reactor Protection System
Residual Heat Removal
Control Rod |
| ML25153A008 | 21 August 2025 | Byron
Braidwood | Units, 1 and 2 - Issuance of Amendments to Revise Technical Specifications to Use Framatome Gaia Fuel (EPID L-2024-LLA-0072) (NON-PROPRIETARY) | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Steam Isolation Valve
Auxiliary Feedwater
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Control Room Emergency Ventilation
Emergency Core Cooling System
Main Steam Line
Control Rod
Containment Spray |
| RA-25-0014, License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding | 18 August 2025 | Mcguire
Catawba
McGuire | License Amendment Request to Adopt the Full Spectrum Loss of Coolant Accident Methodology and Axiom Fuel Cladding Topical Reports and Associated 10 CFR 50.46 Exemption Request for Use of Axiom Fuel Cladding | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Emergency Diesel Generator
Auxiliary Feedwater
Residual Heat Removal
Main Steam Safety Valve
Emergency Core Cooling System
Main Steam Line
Control Rod
Containment Spray |
| IR 05000255/2025301 | 29 July 2025 | Palisades | NRC Initial License Examination Report 05000255/2025301 | Steam Generator
Feedwater
Main Steam Isolation Valve
Main Steam Line
Main Steam |
| L-24-267, Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program | 10 July 2025 | Beaver Valley
Davis Besse
Perry
Comanche Peak | Vistra Operations Company LLC (Vistra Opco) Application to Revise Technical Specifications to Implement an Online Monitoring Program | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Reactor Protection System
Main Steam Isolation Valve
Auxiliary Feedwater
Reactor Core Isolation Cooling
Primary containment
Residual Heat Removal
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Main Condenser
Control Rod
Main Steam
Containment Spray |
| ML25092A126 | 9 July 2025 | University of Texas at Austin | Examination Report Letter No. 50-602/OL-25-01, University of Texas - Austin | HVAC
Emergency Core Cooling System
Control Rod |
| NL-25-0231, License Amendment Request Proposing Removal of RCS Subcooling Margin Monitor from Technical Specifications List of Post Accident Monitoring Instrumentation | 29 June 2025 | Farley | License Amendment Request Proposing Removal of RCS Subcooling Margin Monitor from Technical Specifications List of Post Accident Monitoring Instrumentation | Steam Generator
Reactor Coolant System
Auxiliary Feedwater
Emergency Core Cooling System |
| LR-N25-0054, Core Operating Limits Report - Cycle 31 | 25 June 2025 | Salem | Core Operating Limits Report - Cycle 31 | Reactor Coolant System
Control Rod |
| ML25175A182 | 24 June 2025 | Farley | NRR E-mail Capture - Regarding the Farley Pre-submittal Meeting on RCS Subcooling Margin Monitor | Reactor Coolant System |
| ML25169A074 | 23 June 2025 | Farley | Pre-submittal Meeting Slides - Farley Units 1 and 2 - Removal of RCS Subcooling Margin Monitor from TS List of Post Accident Monitoring Instrumentation | Reactor Coolant System |
| L-2025-105, Correction to Special Report - Post Accident Monitoring (PAM) Instrumentation | 28 May 2025 | Turkey Point | Correction to Special Report - Post Accident Monitoring (PAM) Instrumentation | |
| ML25094A166 | 22 May 2025 | 05200050 | SDAA - FSER Chapter 15 - Transient and Accident Analyses | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Steam Isolation Valve
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML25085A422 | 22 May 2025 | 05200050 | SDAA - FSER Chapter 16 - Technical Specifications | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Primary containment
Shutdown Cooling
HVAC
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Room Envelope
Control Rod
Main Steam
Containment Spray |
| L-2025-099, Special Report - Post Accident Monitoring (PAM) Instrumentation | 12 May 2025 | Turkey Point | Special Report - Post Accident Monitoring (PAM) Instrumentation | |
| ML25106A307 | 7 May 2025 | Prairie Island | Issuance of Amendment Nos. 24x and 23x Revise the Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program | Steam Generator |
| ML25091A289 | 9 April 2025 | Saint Lucie | Regulatory Audit Plan in Support of License Amendment Request for Licensing Basis Changes in Support of St. Lucie Unit 2 Transition to 24-Month Fuel Cycles | Feedwater
Main Steam Isolation Valve
Auxiliary Feedwater
Control Room Emergency Ventilation
Shield Building
Remote shutdown
Emergency Core Cooling System
Containment Spray |
| ML25099A279 | 9 April 2025 | 05200050 | LLC - Part 4, US460 Generic Technical Specifications, Revision 2, Volume 1 - Specifications | Steam Generator
Reactor Coolant System
Feedwater
Main Steam Isolation Valve
Reactor Pressure Vessel
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Rod
Main Steam |
| ML25029A125 | 26 March 2025 | 05200050 | US460 SDAA Chapter 15 SER | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Steam Isolation Valve
HVAC
Reactor Pressure Vessel
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Control Room Envelope
Control Rod
Main Steam |
| ML25079A225 | 20 March 2025 | Millstone | License Amendment Request to Revise Technical Specifications Related to Control Building Isolation, Accident Monitoring Instrumentation Accumulator and Refueling Water Storage Tank Boron Concentration | Steam Generator
Reactor Coolant System
Secondary containment
Emergency Diesel Generator
Auxiliary Feedwater
Primary containment
Control Room Emergency Ventilation
Shield Building
Emergency Gas Treatment System
Emergency Core Cooling System
Main Steam Line
Control Room Envelope
Control Rod
Main Steam |
| ML25059A411 | 28 February 2025 | 05200050 | LLC Submittal of US460 Standard Design Approval Technical Specifications Development, TR-101310, Revision 1 | Steam Generator
Reactor Coolant System
Feedwater
Reactor Pressure Vessel
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| PNP 2025-002, License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis | 5 February 2025 | Palisades | License Amendment Request to Include Leak Before Break Methodology for Primary Coolant System Hot and Cold Leg Piping in Palisades Licensing Basis | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Auxiliary Feedwater
Shutdown Cooling
Reactor Pressure Vessel
Main Steam Line
Main Condenser
Control Rod
Main Steam |
| ML25016A209 | 23 January 2025 | Point Beach | Issuance of Amendment Nos. 277 and 279 Regarding Adoption of TSTF-577, Revised Frequencies for Steam Generator Tube Inspections | Steam Generator |
| ML25021A061 | 16 January 2025 | Summer | Special Report 2025-001 for Virgil Summer Nuclear Station, Unit 1, Inoperable Loose-Part Monitoring System Channel | |
| ML24305A241 | 7 January 2025 | | SDAA Chapter 16 Technical Specifications SE with No Open Items | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Primary containment
Shutdown Cooling
HVAC
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Room Envelope
Control Rod
Main Steam
Containment Spray |
| ML25002A202 | 6 January 2025 | | Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: January 21, 2025 | Reactor Coolant System
Service water
Primary containment
Shutdown Cooling
Residual Heat Removal
Standby Liquid Control
Residual Heat Removal Service Water |
| ML24297A130 | 18 December 2024 | Cook | Issuance of Amendment Nos. 364 and 345 Regarding Change to the Technical Specification Requirement for Neutron Flux Instrumentation | Steam Generator
Reactor Coolant System
Reactor Protection System
Auxiliary Feedwater
Primary containment
Residual Heat Removal
Emergency Core Cooling System
Main Steam Line
Control Rod |
| L-2024-199, Special Report - Post Accident Monitoring Instrumentation | 10 December 2024 | Turkey Point | Special Report - Post Accident Monitoring Instrumentation | |
| ML24326A111 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.3.1-9 | Control Rod |
| ML24326A126 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.3-2 | Reactor Coolant System
Reactor Pressure Vessel
Emergency Core Cooling System
Control Rod
Main Steam |
| ML24326A109 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.3.1-7 | Emergency Core Cooling System
Decay Heat Removal |
| NL-24-0217, License Amendment Request: Source Range Neutron Flux Doubling Function Applicability | 1 November 2024 | Vogtle | License Amendment Request: Source Range Neutron Flux Doubling Function Applicability | Steam Generator
Reactor Coolant System
Residual Heat Removal
Control Rod |
| ML24151A384 | 31 October 2024 | Limerick | – Issuance of Amendment Nos. 264 and 226 Support to Digital Modernization Project Installation (EPID L-2023-LLA-0025) and Exemption from the Requirements of 10 CFR 50.62 | Secondary containment
High Pressure Coolant Injection
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Primary containment
Reactor Recirculation Pump
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Reactor Water Cleanup
Standby Gas Treatment System
Standby Liquid Control
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Safety Relief Valve
Control Rod
Main Steam
Low Pressure Coolant Injection |
| ML24261B949 | 24 October 2024 | Diablo Canyon | Issuance of Amendment Nos. 246 and 248 Revision to Technical Specification 5.6.6, Reactor Coolant System (RCS) Pressure and Temperature Limits Report (PTLR) | Reactor Coolant System
Reactor Pressure Vessel |
| L-PI-24-044, Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program | 21 October 2024 | Prairie Island | Application to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program | Steam Generator |
| LR-N24-0068, Core Operating Limits Report - Cycle 28 | 21 October 2024 | Salem | Core Operating Limits Report - Cycle 28 | Reactor Coolant System
Control Rod |
| ML24290A105 | 7 October 2024 | Summer | Core Operating Limits Report VCSNS Unit 1 Cycle 29, Revision 0 | Reactor Coolant System
Feedwater
Control Rod |
| ML24250A195 | 29 August 2024 | Vogtle | VTS-5.6.5 Updated 8-29-24 | Steam Generator
Reactor Coolant System
Emergency Diesel Generator
Emergency Core Cooling System |
| AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request | 15 August 2024 | Cook | Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request | Steam Generator
Reactor Coolant System
Reactor Protection System
Auxiliary Feedwater
Reactor Pressure Vessel
Emergency Core Cooling System
Control Rod |
| ML24059A425 | 14 August 2024 | Harris | Issuance of Amendment No. 202 Regarding Alignment of Certain Technical Specifications with Improved Standard Technical Specifications | Steam Generator
Feedwater
Auxiliary Feedwater
Primary containment
Remote shutdown
Control Rod |
| ML24215A344 | 6 August 2024 | | 2024 NEI RP Forum - NRC Presentation (ML24215A344) | Secondary containment
Primary containment
HVAC |
| ML24215A175 | 2 August 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number A-16-5 | Steam Generator
Reactor Coolant System
Feedwater
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML24215A179 | 2 August 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number A-16-6 | Steam Generator
Reactor Coolant System
Feedwater
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML24215A193 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.3.1-5 | Steam Generator
Reactor Coolant System
Feedwater
Reactor Pressure Vessel
Emergency Core Cooling System
Decay Heat Removal
Main Steam |
| ML24214A002 | 1 August 2024 | Vogtle | Final SRO Written Exam Vogtle Units 3 and 4 2024-301 Combined (Redacted for Public Release) | Steam Generator
Reactor Coolant System
Feedwater
Service water
Main Turbine
Shutdown Cooling
Residual Heat Removal
Main Steam Line
Main Condenser
Control Rod
Main Steam
Extraction steam |
| IR 05000250/2024002 | 1 August 2024 | Turkey Point | Integrated Inspection Report 05000250/2024002 and 05000251/2024002 | Steam Generator
Reactor Coolant System
Emergency Diesel Generator
Auxiliary Feedwater
Qualified Safety Parameter Display System
Safety Relief Valve
Main Steam
Containment Spray |
| L-2024-113, License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections | 24 July 2024 | Point Beach | License Amendment Request 294, Application to Revise Technical Specifications to Adopt TSTF- 577, Revised Frequencies for Steam Generator Tube Inspections | Steam Generator |
| L-24-164, BV-2, Post Accident Monitor Report | 27 June 2024 | Beaver Valley | BV-2, Post Accident Monitor Report | |
| AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring | 13 June 2024 | Cook | Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring | Intermediate Range Monitor |
| 05000445/LER-2024-002, (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions | 3 June 2024 | Comanche Peak | (Cpnpp), Unit 1, Condition Prohibited by Technical Specifications Due to Inoperable Remote Shutdown System Functions | Emergency Diesel Generator
Remote shutdown
Control Rod |
| ML24141A267 | 23 May 2024 | 07201026 | 13 Renewed CoC No. 1026, Amendment No. 2, Appendix C - Fuelsolutions W74 Canister Technical Specifications | |
| ML24141A258 | 23 May 2024 | 07201026 | 04 Renewed CoC No. 1026, Amendment No. 0, Appendix B - Fuelsolutions W21 Canister Technical Specifications | Control Rod |
| ML24141A275 | 23 May 2024 | 07201026 | 21 Renewed CoC No. 1026, Amendment No. 4, Appendix C - Fuelsolutions W74 Canister Technical Specifications | |
| ML24141A271 | 23 May 2024 | 07201026 | 17 Renewed CoC No. 1026, Amendment No. 3, Appendix C - Fuelsolutions W74 Canister Technical Specifications | |
| ML24141A263 | 23 May 2024 | 07201026 | 09 Renewed CoC No. 1026, Amendment No. 1, Appendix C - Fuelsolutions W74 Canister Technical Specifications | |
| ML24141A262 | 23 May 2024 | 07201026 | 08 Renewed CoC No. 1026, Amendment No. 1, Appendix B - Fuelsolutions W21 Canister Technical Specifications | Control Rod |
| ML24141A274 | 23 May 2024 | 07201026 | 20 Renewed CoC No. 1026, Amendment No. 4, Appendix B - Fuelsolutions W21 Canister Technical Specifications | Control Rod |
| ML24141A276 | 23 May 2024 | 07201026 | 22 Final Safety Evaluation Report for Renewed CoC No. 1026, Amendments No. 0-4 | |
| ML24141A270 | 23 May 2024 | 07201026 | 16 Renewed CoC No. 1026, Amendment No. 3, Appendix B - Fuelsolutions W21 Canister Technical Specifications | Control Rod |
| W3F1-2024-0011, Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program | 8 May 2024 | Waterford | Licensee Amendment Request to Modify Surveillance Requirements in Support of Surveillance Frequency Control Program | Steam Generator
Reactor Coolant System
Feedwater
Primary containment |