| | Start date | Site | Title | System |
|---|
| ML25268A301 | 25 September 2025 | Browns Ferry | Core Operating Limits Report for Unit 1 Cycle 16 Operation, Revision 1; Unit 2 Cycle 24 Operation, Revision 1; and Unit 3 Cycle 22 Operation, Revision 1 | Feedwater
Reactor Protection System
Safety Relief Valve
Moisture Separator Reheater
Control Rod |
| 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 |
| 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 |
| L-PI-25-026, Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements | 3 September 2025 | Prairie Island | Application to Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements | Steam Generator
Reactor Coolant System
Control Rod |
| NLS2025035, Application to Revise Technical Specifications to Adopt TSTF-576, Revise Safety/Relief Valve Requirements | 23 August 2025 | Cooper | Application to Revise Technical Specifications to Adopt TSTF-576, Revise Safety/Relief Valve Requirements | Reactor Coolant System
Secondary containment
Service water
Reactor Protection System
Main Steam Isolation Valve
Primary containment
Shutdown Cooling
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Residual Heat Removal Service Water
Emergency Core Cooling System
Main Steam Line
Safety Relief Valve
Control Rod
Main Steam
Containment Spray
Main Turbine Bypass System |
| 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 |
| ML25212A186 | 21 August 2025 | | Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 2, 2025 | Residual Heat Removal
Standby Liquid Control
Main Steam Line |
| ML25104A095 | 5 August 2025 | Hope Creek | Issuance of Amendment No. 239 Revise Technical Specification Actions for Reactor Coolant System Safety/Relief Valves | Reactor Coolant System
Feedwater
Reactor Protection System
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Reactor Pressure Vessel
Core Spray
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System
Main Steam Line
Safety Relief Valve
Control Rod
Main Steam |
| ML25162A001 | 30 June 2025 | | Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: July 8, 2025 | Containment Spray |
| NMP1L3612, Constellation Energy Generation, LLC - Relief Request for Alternative to Examination Category B-G-1, Item B6.20, Reactor Vessel Closure Stud Examinations | 16 June 2025 | Calvert Cliffs
Peach Bottom
Nine Mile Point
Byron
Braidwood
Limerick
FitzPatrick
LaSalle | Constellation Energy Generation, LLC - Relief Request for Alternative to Examination Category B-G-1, Item B6.20, Reactor Vessel Closure Stud Examinations | Reactor Coolant System
Reactor Pressure Vessel
Main Steam Line |
| WBL-25-032, Unit 2 - Revised Pressure and Temperature Limits Reports (PTLR) | 10 June 2025 | Watts Bar | Unit 2 - Revised Pressure and Temperature Limits Reports (PTLR) | Reactor Coolant System
Reactor Pressure Vessel |
| NL-25-0205, Units 3 and 4 License Amendment Request: Move Surveillance Requirements from Technical Specifications 3.3.15 and 3.3.16, Engineered Safety Feature Actuation System (ESFAS) Actuation Logic - Response to RAI | 10 June 2025 | Vogtle | Units 3 and 4 License Amendment Request: Move Surveillance Requirements from Technical Specifications 3.3.15 and 3.3.16, Engineered Safety Feature Actuation System (ESFAS) Actuation Logic - Response to RAI | Reactor Coolant System
Residual Heat Removal |
| ML25111A239 | 9 June 2025 | Prairie Island | Issuance of Amendment Nos. 247 and 235 Revise the TS Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumptions | Steam Generator
Reactor Coolant System
Reactor Protection System
Main Steam |
| WBL-25-026, Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual | 5 June 2025 | Watts Bar | Periodic Submission for Changes Made to the Technical Specification Bases and Technical Requirements Manual | Steam Generator
Reactor Coolant System
Feedwater
Main Steam Isolation Valve
Auxiliary Feedwater
Auxiliary Building Gas Treatment System
Residual Heat Removal
Control Room Emergency Ventilation
Shield Building
Main Steam Safety Valve
Remote shutdown
Emergency Gas Treatment System
Emergency Core Cooling System
Decay Heat Removal
Control Rod
Containment Spray
Control Room Emergency Air Temperature Control System |
| ML25150A321 | 30 May 2025 | Limerick | Nuclear Radiological Emergency Plan Document Revision | Reactor Coolant System
Feedwater
Secondary containment
Service water
Primary Containment Isolation System
Primary containment
Shutdown Cooling
Reactor Pressure Vessel
Residual Heat Removal
Fuel Pool Cooling and Cleanup
Remote shutdown
Spray Pond
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Safety Relief Valve
Control Rod |
| ML25093A254 | 27 May 2025 | Browns Ferry | Issuance of Amendment Nos. 335, 358, and 318 Revision 3 to Revise Safety/Relief Valve Requirements | Reactor Coolant System
Automatic Depressurization System |
| 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 |
| ML25085A429 | 22 May 2025 | 05200050 | SDAA - FSER Chapter 5 - Reactor Coolant System and Connecting Systems | Steam Generator
Reactor Coolant System
Feedwater
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| IR 05000259/2025001 | 9 May 2025 | Browns Ferry | Integrated Inspection Report 05000259/2025001 05000260/2025001 and 05000296/2025001 | Reactor Coolant System
Feedwater
High Pressure Coolant Injection
Emergency Diesel Generator
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Main Turbine
Shutdown Cooling
Reactor Recirculation Pump
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Reactor Water Cleanup
Control Room Emergency Ventilation
Standby Liquid Control
Emergency Equipment Cooling Water
Residual Heat Removal Service Water
Steam Jet Air Ejector
Decay Heat Removal
Safety Relief Valve
Control Rod
Main Steam
Low Pressure Coolant Injection |
| 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 |
| ML25071A389 | 9 April 2025 | Cook | Issuance of Amendment Nos. 365 and 346 Regarding Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors | Reactor Coolant System
Reactor Protection System
Decay Heat Removal |
| ML25041A271 | 14 March 2025 | Catawba | Issuance of Amendment Nos. 320 and 316 to Revise Technical Specification 3.4.3, Reactor Coolant System Pressure and Temperature Limits | Reactor Coolant System
Reactor Pressure Vessel
Residual Heat Removal |
| 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 |
| ML25042A041 | 10 February 2025 | Browns Ferry | NRR E-mail Capture - Request for Additional Information - TVA LAR to Revise Browns Ferry Technical Specification 3.4.3 by Adopting TSTF-576 | |
| IR 05000259/2024004 | 31 January 2025 | Browns Ferry | Integrated Inspection Report 05000259/2024004 and 05000260/2024004 and 05000296/2024004 | Secondary containment
High Pressure Coolant Injection
Emergency Diesel Generator
Reactor Core Isolation Cooling
Reactor Recirculation Pump
Reactor Pressure Vessel
Reactor Water Cleanup
Standby Liquid Control
Residual Heat Removal Service Water
Safety Relief Valve
Control Rod
Main Steam |
| ML24332A008 | 29 January 2025 | | PTLR SER in Support of NuScale SDAA Section 5.3 | Reactor Coolant System
Reactor Pressure Vessel
Emergency Core Cooling System |
| ML24330A280 | 29 January 2025 | | SDAA Chapter 5, Reactor Coolant System and Connecting Systems, Advance SE with No Open Items (Non-proprietary) | Steam Generator
Reactor Coolant System
Feedwater
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML25010A069 | 17 January 2025 | Browns Ferry | NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, License Amendment Request to Adopt TSTF-576 Re Safety/Relief Valve Requirements | |
| IR 05000282/2024001 | 13 January 2025 | Prairie Island | Reissued Integrated Inspection Report 05000282/2024001 & 05000306/2024001 | Steam Generator
Reactor Coolant System
Feedwater
Service water
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Residual Heat Removal
Shield Building
Main Steam |
| 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 |
| CP-202400472, Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules | 16 December 2024 | Comanche Peak | Application to Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules | Reactor Coolant System |
| 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 |
| 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 |
| ML24326A095 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16-13 | Reactor Coolant System |
| ML24313A063 | 14 November 2024 | Vogtle | Integrated Inspection Report and Assessment Follow-Up Letter 05200025/2024003 and 05200026/2024003 | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Turbine
Residual Heat Removal
Automatic Depressurization System |
| IR 05000333/2024003 | 12 November 2024 | FitzPatrick | Integrated Inspection Report 05000333/2024003 | Feedwater
Service water
High Pressure Coolant Injection
Emergency Diesel Generator
Shutdown Cooling
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Control Room Emergency Ventilation
Residual Heat Removal Service Water
Decay Heat Removal
Safety Relief Valve
Rod Worth Minimizer
Main Condenser
Control Rod
Main Steam
Extraction steam |
| CNL-24-014, License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) | 4 November 2024 | Watts Bar
Sequoyah | License Amendment Request to Revise the Sequoyah Nuclear Plant, Units 1 and 2 and Watts Bar Nuclear Plant, Units 1 and 2 Technical Specifications to Use Online Monitoring Methodology (SQN-TS-24-02 and WBN-TS-23-22) | Steam Generator
Reactor Coolant System
Feedwater
Primary containment
Remote shutdown
Emergency Core Cooling System |
| IR 05000259/2024003 | 4 November 2024 | Browns Ferry | Integrated Inspection Report 05000259/2024003 and 05000260/2024003 and 05000296/2024003 | Reactor Coolant System
Feedwater
High Pressure Coolant Injection
Reactor Protection System
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
Reactor Recirculation Pump
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Standby Gas Treatment System
Standby Liquid Control
Residual Heat Removal Service Water
Decay Heat Removal
Safety Relief Valve
Main Condenser
Control Rod
Main Steam |
| ENS 57326 | 17 September 2024 05:27:00 | Vogtle | Automatic Reactor Trip and Manual Safeguards Actuation | Reactor Coolant System
Reactor Protection System
Shutdown Cooling
Residual Heat Removal |
| ML24249A145 | 11 September 2024 | Technical Specifications Task Force | Final Traveler SE of TSTF 576, Revision 3, Revise Safety/Relief Valve Requirements | Reactor Coolant System
Reactor Protection System
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System |
| 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 |
| ML24228A091 | 27 August 2024 | | Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: September 3, 2024 | Steam Generator
Reactor Coolant System
Main Steam Isolation Valve
Residual Heat Removal
Remote shutdown
Main Steam Line
Containment Spray |
| ML24183A108 | 8 August 2024 | Quad Cities | – Issuance of Amendment Nos. 302 and 298 Adoption of Tstf-505, Provide Risk Informed Extended Completion Times – RITSTF Initiative 4b | Reactor Coolant System
Feedwater
Secondary containment
Service water
High Pressure Coolant Injection
Reactor Protection System
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Main Turbine
Shutdown Cooling
Reactor Pressure Vessel
Core Spray
Residual Heat Removal
Reactor Water Cleanup
Control Room Emergency Ventilation
Automatic Depressurization System
Standby Liquid Control
Intermediate Range Monitor
Residual Heat Removal Service Water
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Rod
Main Steam
Low Pressure Coolant Injection |
| ML24215A132 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-5.PTLR-9 | Reactor Coolant System
Feedwater
Main Steam |
| 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 |
| ML24053A102 | 1 August 2024 | Technical Specifications Task Force | Draft Traveler Safety Evaluation of TSTF-576, Revise Safety/Relief Valve Requirements | Reactor Coolant System
Reactor Protection System
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System |
| ML24183A016 | 25 July 2024 | Cook | Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report | Reactor Coolant System
Reactor Pressure Vessel |
| ML24197A093 | 17 July 2024 | Vogtle | MD 8.3 - 24-004 Vogtle, Unit 3 - 7-8-2024 - Reactor Trip and Safeguards Actuation Resulting from a Loss of Feedwater Event EN 57215 | Steam Generator
Reactor Coolant System
Feedwater
Primary containment
Residual Heat Removal |
| ML24192A349 | 10 July 2024 | Catawba | Acceptance of Requested Licensing Action License Amendment Application to Revise Technical Specification 3.4.3, RCS Pressure and Temperature Limits | |
| RA-23-0245, License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits | 18 June 2024 | Catawba | License Amendment Request Proposing to Revise Technical Specification 3.4.3, RCS Pressure and Temperature (P/T) Limits | |
| L-PI-24-014, License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption | 3 June 2024 | Prairie Island | License Amendment Request to Revise the Technical Specification Definition of Reactor Trip System (RTS) Response Time and Apply Response Time Testing to RTS Trip Functions with Time Delay Assumption | Steam Generator
Reactor Coolant System |
| ML24135A177 | 15 May 2024 | Prairie Island | Integrated Inspection Report 05000282/2024001 and 05000306/2024001 | Steam Generator
Reactor Coolant System
Feedwater
Service water
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Shield Building
Main Steam |
| IR 05000324/2024001 | 9 May 2024 | Brunswick | Integrated Inspection Report 05000324/2024001 and 05000325/2024001 | Feedwater
Service water
Emergency Diesel Generator
Main Steam Isolation Valve
Reactor Core Isolation Cooling
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Reactor Water Cleanup
Automatic Depressurization System
Residual Heat Removal Service Water
Decay Heat Removal
Main Steam Line
Safety Relief Valve
Control Rod |
| ML24191A337 | 6 May 2024 | Callaway | Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter B 3.4, Reactor Coolant System | Steam Generator
Reactor Coolant System
Feedwater
Service water
Shutdown Cooling
Residual Heat Removal
Main Steam Safety Valve
Decay Heat Removal
Main Steam Line
Control Rod |
| ML24191A211 | 6 May 2024 | Callaway | Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter 19, License Renewal Supplement | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Service water
Emergency Diesel Generator
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Circulating Water System
Main Steam Line
Control Rod |
| ML24191A330 | 6 May 2024 | Callaway | Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter B 3.0, Safety Limits (Sls) | Reactor Coolant System |
| ML24191A323 | 6 May 2024 | Callaway | Final Safety Analysis Report Rev. OL-27 and Technical Specification Bases Rev. 25, Chapter 3.4, Reactor Coolant System | Steam Generator
Reactor Coolant System
Service water
Emergency Diesel Generator
Shutdown Cooling
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal |
| ML24149A283 | 6 May 2024 | Callaway | Final Safety Analysis Report Revision OL-27 and Technical Specification Bases Revision 25, Chapter 19, License Renewal Supplement | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Service water
Emergency Diesel Generator
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Circulating Water System
Main Steam Line
Control Rod |