| | Start date | Site | Title | System |
|---|
| ML25260A487 | 17 September 2025 | Technical Specifications Task Force
99902042 | Correction to TSTF-585, Revision 5, Revise LCO 3.0.3 to Require Managing Risk | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Main Steam Isolation Valve
Auxiliary Feedwater
High Pressure Core Spray
Residual Heat Removal
Circulating Water System
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line |
| ML25247A004 | 17 September 2025 | Vogtle | SNC Slides - Pre-Submittal Meeting - Vogtle 3 and 4 - TSTF-505, 50.69, and TSTF-425 LARs | Reactor Protection System
Automatic Depressurization System
Main Steam Safety Valve
Control Room Envelope |
| ML25259A122 | 16 September 2025 | | Olpf September 2025 Update | Steam Generator
Reactor Coolant System
Feedwater
Safety Parameter Display System
Reactor Pressure Vessel
Control Rod |
| TSTF-25-06, TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5 | 10 September 2025 | Technical Specifications Task Force
99902042 | TSTF Response to NRC Request for Additional Information on TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk and Transmittal of Revision 5 | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Main Steam Isolation Valve
Auxiliary Feedwater
High Pressure Core Spray
Residual Heat Removal
Circulating Water System
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line |
| RA-25-0217, Core Operating Limits Report (COLR) for Unit 2 Cycle 28 Reload Core | 4 September 2025 | Catawba | Core Operating Limits Report (COLR) for Unit 2 Cycle 28 Reload Core | Steam Generator
Reactor Coolant System |
| ML25240B609 | 28 August 2025 | Texas A&M University | Texas A&M Engineering Experiment Station - License Amendment Request for Facility Operating License No. R-23 (Docket No. 50-59) - Revision to TS 3.5 to Remove the Reactor Console, Control Rod Drives, and Associated Electronics from Storage | Reactor Protection System
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 |
| ML25225A229 | 15 August 2025 | Vogtle | Issuance of Emergency Amendment No. 202 to Revise Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating (Emergency Circumstances) | Steam Generator
Reactor Coolant System
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System
Control Rod |
| ML25226A079 | 14 August 2025 | Millstone | Response to Request for Additional Information Regarding Proposed Amendment to Revise Specifications Related to Control Building Isolation, Accident Monitoring Instrumentation, Accumulator and Refueling Water. | Secondary containment |
| NL-25-0317, Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating | 11 August 2025 | Vogtle | Emergency License Amendment Request: One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating | Steam Generator
Reactor Coolant System
Feedwater
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System |
| IR 05000298/2025002 | 11 August 2025 | Cooper | Integrated Inspection Report 050002982025002 | Reactor Coolant System
Feedwater
Secondary containment
Service water
Reactor Protection System
Emergency Diesel Generator
Reactor Core Isolation Cooling
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Residual Heat Removal Service Water
Emergency Core Cooling System
Main Condenser
Control Rod
Containment Spray |
| IR 05000335/2025002 | 6 August 2025 | Saint Lucie
07200061 | Integrated Inspection Report 05000335/2025002, 05000389/2025002, 07200061/2024001 and 07200061/2025001 | Reactor Coolant System
Emergency Diesel Generator
Auxiliary Feedwater
Emergency Core Cooling System
Control Rod |
| ML25216A236 | 4 August 2025 | | RIPE Workshop - Sessions 3 Updated with Grip | Decay Heat Removal |
| ML25147A107 | 22 July 2025 | Vogtle | Issuance of Amendments to Remove Completed Combined License (COL) Conditions | Steam Generator
Residual Heat Removal
Shield Building
Automatic Depressurization System |
| ML25197A608 | 15 July 2025 | Millstone | Request for Additional Information LAR to Revise Selected TSs - Control Building Isolation; Accident Monitoring; Accumulators, RWST; & Secondary Containment SRs | Secondary containment |
| 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 |
| LR-N25-0058, License Amendment Request (LAR) - Hope Creek Technical Specification Coversion to NUREG-1433, Revision 5, Supplement 4 | 24 June 2025 | Hope Creek | License Amendment Request (LAR) - Hope Creek Technical Specification Coversion to NUREG-1433, Revision 5, Supplement 4 | Reactor Coolant System
High Pressure Coolant Injection
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
Core Spray
Residual Heat Removal
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System
Decay Heat Removal
Low Pressure Coolant Injection |
| ML25126A076 | 30 May 2025 | Palo Verde | Issuance of Amendment Nos. 225, 225 and 225, Regarding Revision Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands and Use Gothic Code | Reactor Coolant System
Shutdown Cooling
Emergency Core Cooling System
Decay Heat Removal
Containment Spray |
| 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 |
| RA-25-0136, Transmittal of Core Operating Limits Report (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 34 (Revision 0) | 15 May 2025 | Oconee | Transmittal of Core Operating Limits Report (COLR) for Oconee Nuclear Station (ONS) Unit 1 Cycle 34 (Revision 0) | Steam Generator
Control Rod |
| ML25119A052 | 15 May 2025 | Palo Verde | Regulatory Audit Summary Report in Support of License Amendment Request to Revise TSs 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands and to Use Gothic Code | |
| ML25134A164 | 14 May 2025 | Hope Creek | Enclosure 2, Volume 10: Hope Creek Generating Station - Improved Technical Specifications Conversion ITS Section 3.5 Emergency Core Cooling Systems (Eccs), RPV Water Inventory Control, and Reactor Core Isolation Cooling (RCIC) System | Reactor Coolant System
Feedwater
Secondary containment
Service water
High Pressure Coolant Injection
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Main Turbine
Shutdown Cooling
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Automatic Depressurization System
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Safety Relief Valve
Control rod blade
Control Rod
Containment Spray
Low Pressure Coolant Injection |
| ML25129A077 | 13 May 2025 | Grand Gulf | Integrated Inspection Report 05000416.2025001 | Reactor Coolant System
Service water
Reactor Core Isolation Cooling
Primary containment
High Pressure Core Spray
Core Spray
Residual Heat Removal
Emergency Core Cooling System
Main Steam Line
Main Condenser
Control Rod |
| IR 05000263/2025001 | 12 May 2025 | Monticello | Integrated Inspection Report 05000263/2025001 | Feedwater
Secondary containment
High Pressure Coolant Injection
Emergency Diesel Generator
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
Core Spray
Residual Heat Removal
Control Rod
Low Pressure Coolant Injection |
| IR 05000254/2025001 | 8 May 2025 | Quad Cities | Integrated Inspection Report 05000254/2025001 and 05000265/2025001 | Reactor Coolant System
Feedwater
Service water
High Pressure Coolant Injection
Emergency Diesel Generator
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Core Spray
Residual Heat Removal
Standby Gas Treatment System
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System
Safety Relief Valve
Control Rod
Low Pressure Coolant Injection |
| ML25086A180 | 2 May 2025 | Fermi | – Amendment 231 to Adopt TSTF-505, TSTF-439, TSTF-591 | Reactor Coolant System
Feedwater
Service water
High Pressure Coolant Injection
Reactor Protection System
Reactor Core Isolation Cooling
Primary containment
Main Turbine
Shutdown Cooling
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Automatic Depressurization System
Standby Liquid Control
Emergency Equipment Cooling Water
Residual Heat Removal Service Water
Steam Jet Air Ejector
Emergency Core Cooling System
Main Steam Line
Safety Relief Valve
Moisture Separator Reheater
Control Rod
Main Turbine Bypass System |
| RS-25-089, Additional Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 | 1 May 2025 | Byron
Braidwood | Additional Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 | Steam Generator
Reactor Coolant System
Main Steam Line |
| ML25107A192 | 30 April 2025 | | Accident Sequence Precursor Program 2024 Annual Report | Steam Generator
Reactor Coolant System
Feedwater
Service water
Emergency Diesel Generator
Auxiliary Feedwater
Reactor Core Isolation Cooling
Main Transformer
Core Spray
Residual Heat Removal
Residual Heat Removal Service Water
Emergency Core Cooling System |
| RA-25-0114, (Mns), Unit 1 - Cycle 31, Revision 0, Core Operating Limits Report (COLR) | 23 April 2025 | McGuire | (Mns), Unit 1 - Cycle 31, Revision 0, Core Operating Limits Report (COLR) | Steam Generator
Reactor Coolant System |
| CNL-25-057, Response to Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1 | 22 April 2025 | Watts Bar
Sequoyah | Response to Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1 | Residual Heat Removal
Emergency Core Cooling System |
| RS-25-088, Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 | 21 April 2025 | Byron
Braidwood | Response to Request for Additional Information Related to License Amendment to Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2 to Transition to Framatome Gaia Fuel and Exemptions to 10 CFR 50.46 | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Reactor Pressure Vessel
Residual Heat Removal
Main Steam Safety Valve
Emergency Core Cooling System
Main Steam Line
Control Rod
Containment Spray |
| CNL-25-041, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line. | 10 April 2025 | Browns Ferry | License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-423-A, Revision 1, Technical Specifications End States, NEDC-32988-A, Using the Consolidated Line. | Secondary containment
Service water
High Pressure Coolant Injection
Reactor Protection System
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
Residual Heat Removal
Automatic Depressurization System
Emergency Equipment Cooling Water
Residual Heat Removal Service Water
Emergency Core Cooling System
Decay Heat Removal
Main Condenser
Control Rod
Low Pressure Coolant Injection |
| 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 |
| ML25090A018 | 28 March 2025 | Palo Verde | Supplement to License Amendment Request to Revise the Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code | Emergency Core Cooling System |
| RA-25-0086, Cycle 30, Revision 1, Core Operating Limits Report (COLR) | 27 March 2025 | McGuire | Cycle 30, Revision 1, Core Operating Limits Report (COLR) | Steam Generator
Reactor Coolant System |
| ML25091A046 | 27 March 2025 | | FOIA-2025-000406 Released Set 1 | Steam Generator
Feedwater
Secondary containment
Service water
High Pressure Coolant Injection
Reactor Protection System
Emergency Diesel Generator
Auxiliary Feedwater
Reactor Core Isolation Cooling
Primary containment
Main Turbine
Reactor Pressure Vessel
Core Spray
Control Room Emergency Ventilation
Standby Liquid Control
Emergency Core Cooling System
Main Steam Line
Safety Relief Valve
Control rod blade
Main Condenser
Control Rod
Low Pressure Coolant Injection |
| 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 |
| ML25084A368 | 25 March 2025 | 05200050 | LLC, Submittal of Presentation Material Entitled ACRS Subcommittee Meeting (Open Session) Chapters 1, 4, and 15, PM-180495, Revision 0 | Steam Generator
Reactor Coolant System
Feedwater
Reactor Pressure Vessel
Emergency Core Cooling System
Main Steam Line
Control Rod |
| ML25085A273 | 25 March 2025 | Watts Bar
Sequoyah | Request for Confirmation of Information - TVA LAR to Revised Sequoyah Nuclear Plant, Units 1 and 2, and Watts Bar Nuclear Plant, Units 1 and 2, TS LCO 3.5.2, Note 1 | Residual Heat Removal
Emergency Core Cooling System |
| 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 |
| NRC-25-0015, 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, TSTF-439, Revision 2 | 19 March 2025 | Fermi | 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, TSTF-439, Revision 2 | Reactor Core Isolation Cooling
Automatic Depressurization System |
| CNL-25-039, Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-576 | 10 March 2025 | Browns Ferry | Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-576 | Reactor Coolant System
Main Steam Isolation Valve
Main Turbine
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System
Main Steam Line
Control Rod |
| ML25066A098 | 7 March 2025 | Technical Specifications Task Force
99902042 | Transmittal of TSTF-585, Revision 4, Revise LCO 3.0.3 to Require Managing Risk | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Main Steam Isolation Valve
Auxiliary Feedwater
High Pressure Core Spray
Residual Heat Removal
Circulating Water System
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line |
| ML25063A238 | 4 March 2025 | | Olpf March 2025 | Steam Generator
Reactor Coolant System
Feedwater
Safety Parameter Display System
Reactor Pressure Vessel
Control Rod |
| 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 |
| 05000298/LER-2024-003-01, High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications | 20 February 2025 | Cooper | High Pressure Coolant Injection Steam Leak Causes Condition That Could Have Prevented Fulfillment of a Safety Function and a Condition Prohibited by Technical Specifications | High Pressure Coolant Injection
Core Spray
Emergency Core Cooling System
Main Condenser
Low Pressure Coolant Injection |
| ML24169A116 | 6 February 2025 | Armed Forces Radiobiology Research Institute | Examination Report Letter No. 50-170/OL-25-01, Armed Forces Radiobiology Research Institute | Reactor Protection System
Control Rod |
| ML25016A345 | 21 January 2025 | Palo Verde | Audit Plan for License Amendment Request to Revise Technical Specifications 3.5.1 and 3.5.2 Safety Injection Tank Pressure Bands, and to Use GOTHIC Code | |
| 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 |
| ML24358A228 | 26 December 2024 | Technical Specifications Task Force | Final Traveler SE of TSTF-597, Revision 0, Eliminate LCO 3.0.3 Mode 2 Requirement | Primary containment
Control Rod |
| ML24350A006 | 15 December 2024 | 05000128 | Submission of Technical Specification Required Report for Event Notification 56489, Operation in Violation of a Technical Specification; License No. R-83, Docket No: 50-128 | Control Rod |
| ML24268A198 | 9 December 2024 | Technical Specifications Task Force | Draft Traveler SE of TSTF-597, Rev 0, Eliminate LCO 3.0.3 Mode 2 Requirement | Primary containment
Control Rod |
| CNL-24-049, Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements | 9 December 2024 | Browns Ferry | Brows Ferry Nuclear Plant, Units 1, 2 and 3 - License Amendment Request for Adoption of TSTF-576 to Revise Safety/Relief Valve Requirements | Reactor Coolant System
Main Steam Isolation Valve
Main Turbine
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System
Main Steam Line
Control Rod |