| | Start date | Site | Title | System |
|---|
| 2CAN092501, Request to Revise Typographical Errors in Technical Specifications | 4 September 2025 | Arkansas Nuclear | Request to Revise Typographical Errors in Technical Specifications | Reactor Coolant System
Shutdown Cooling
Containment Spray |
| ML25230A081 | 2 September 2025 | Vogtle | Units 3 and 4 — Issuance of Amendment to Revise Technical Specification 3.3.15 and 3.3.16 | Steam Generator
Reactor Coolant System
Feedwater
Residual Heat Removal
Automatic Depressurization System |
| 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 |
| ML25224A250 | 12 August 2025 | Vogtle | NRR E-mail Capture - for Your Action - RAIs - Vogtle 4 - Emergency License Amendment Request (LAR) Regarding Core Makeup Tanks (L-2025-LLA-0127) | Reactor Coolant System |
| NL-25-0318, Response to NRC Requests Regarding Emergency License Amendment Request One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating | 12 August 2025 | Vogtle | Response to NRC Requests Regarding Emergency License Amendment Request One-Time Change to Technical Specification 3.5.2, Core Makeup Tanks (Cmts) - Operating | Reactor Coolant 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 |
| 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 |
| ML25224A200 | 7 August 2025 | Technical Specifications Task Force | Meeting Handouts - TSTF-605, RCS WIC, Presubmittal Description | Steam Generator
Reactor Coolant System
Feedwater
Emergency Diesel Generator
Reactor Pressure Vessel
Residual Heat Removal
Decay Heat Removal |
| 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 |
| RS-25-098, Supplement to the Request for Additional Information Related to License Amendment Requests to Adopt TSTF-505, TSTF-591, and 10 CFR 50.69 | 2 June 2025 | Dresden | Supplement to the Request for Additional Information Related to License Amendment Requests to Adopt TSTF-505, TSTF-591, and 10 CFR 50.69 | Emergency Diesel Generator
Control Room Envelope |
| 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 |
| ML25085A435 | 22 May 2025 | 05200050 | SDAA - FSER Chapter 9 - Auxiliary Systems | Secondary containment
HVAC
Residual Heat Removal
Fuel Pool Cooling and Cleanup
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 |
| 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 |
| ENS 57689 | 4 May 2025 17:30:00 | Callaway | Both Trains of Emergency Core Cooling System Inoperable | Emergency Core Cooling System
Containment Spray |
| 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 |
| 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 |
| RS-25-078, Response to the Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Inormed Completion Times TSTF-505, Revision 2, Provide Risk-. | 23 April 2025 | Dresden | Response to the Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt Risk Inormed Completion Times TSTF-505, Revision 2, Provide Risk-. | |
| LR-N25-0038, License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 3 | 21 April 2025 | Hope Creek | License Amendment Request (LAR) - Hope Creek Technical Specification Conversion to NUREG-1433, Revision 5, Supplement 3 | Feedwater
High Pressure Coolant Injection
Reactor Core Isolation Cooling
Reactor Pressure Vessel
Core Spray
Main Steam Line |
| ML25097A184 | 16 April 2025 | Vogtle | Supplement to the Regulatory Audit Plan in Support of the Review of the LAR to Increase Flexibility in Mode Restraints and the LAR for Shutdown Actions Mode Change Restrictions | Reactor Coolant System
Service water
Residual Heat Removal
Automatic Depressurization System
Emergency Core Cooling System
Decay Heat Removal |
| 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 |
| 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 |
| ENS 57633 | 28 March 2025 08:06:00 | Palo Verde | High Pressure Safety Injection Pump Inoperable | Control Rod |
| 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 |
| ML25058A198 | 14 March 2025 | | Summary of March 10 2024 NRC Public Meeting with PWROG Executive Committee | Reactor Coolant System |
| RS-25-016, License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T | 14 March 2025 | Byron
Braidwood | License Amendment Request to Adopt TSTF-286, TSTF-471, TSTF-571-T | Steam Generator
Reactor Coolant System
Residual Heat Removal
Decay Heat Removal
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 |
| IR 05000461/2024004 | 6 February 2025 | Clinton | Integrated Inspection Report 05000461/2024004 | Service water
Reactor Core Isolation Cooling
Main Turbine
Core Spray
Residual Heat Removal
Reactor Water Cleanup
Standby Gas Treatment System
Control Rod |
| NL-24-0325, License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic | 24 January 2025 | Vogtle | License Amendment Request: Move Surveillance Requirements from Technical Specifications (TS) 3.3.15 and 3.3.16 Engineered Safety Feature Actuation System (ESFAS) Actuation Logic | Steam Generator
Reactor Coolant System
Feedwater
Residual Heat Removal
Automatic Depressurization System
Main Steam Safety Valve
Decay Heat Removal
Main Steam Line
Control Rod |
| NL-24-0417, License Amendment Request: Shutdown Actions Mode Change Restrictions | 23 January 2025 | Vogtle | License Amendment Request: Shutdown Actions Mode Change Restrictions | Steam Generator
Reactor Coolant System
Feedwater
Residual Heat Removal
Automatic Depressurization System
Decay Heat Removal
Control Rod |
| 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 |
| ML24346A310 | 11 December 2024 | 05200050 | LLC - Response to SDAA Audit Question Number A-19.1-52 | Reactor Pressure Vessel
Emergency Core Cooling System |
| ML24339B304 | 4 December 2024 | Grand Gulf
Arkansas Nuclear
River Bend
Waterford | Application to Revise Technical Specifications to Use Online Monitoring Methodology | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Reactor Protection System
Auxiliary Feedwater
Primary containment
Main Turbine
Shutdown Cooling
Safety Parameter Display System
Reactor Pressure Vessel
Residual Heat Removal
Shield Building
Intermediate Range Monitor
Remote shutdown
Emergency Core Cooling System
Main Steam Line
Control Rod
Main Steam
Containment Spray |
| ML24325A440 | 26 November 2024 | Vogtle | Summary of November 19, 2024, Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a Proposed License Amendment Request for Modes 5 & 6 for Vogtle Electric Generating Plant, Units 3 & 4 | Reactor Coolant System
Decay Heat Removal
Control Room Envelope |
| ML24326A107 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.5.3-3 | Reactor Coolant System
Emergency Core Cooling System
Decay Heat Removal |
| ML24326A097 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.6.3-1 | Emergency Core Cooling System
Decay Heat Removal |
| ML24326A093 | 21 November 2024 | 05200050 | LLC Submittal of the NRCs Request for Docketing of Resolved Audit Responses | Reactor Coolant System
Emergency Core Cooling System |
| ML24326A135 | 21 November 2024 | 05200050 | Response to NuScale Technical Report Audit Question Number: A-16.3.6.3-2 | Steam Generator
Reactor Coolant System
Feedwater
Main Steam Isolation Valve
Reactor Pressure Vessel
Emergency Core Cooling System
Decay Heat Removal
Main Steam |
| CNL-24-021, Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) | 12 November 2024 | Watts Bar
Sequoyah | Application to Revise Technical Specification Limiting Condition of Operation 3.5.2, ECCS – Operating, Note 1 to Include Residual Heat Removal Pump Flow Paths (SQN-TS-23-04 and WBN-TS-23-020) | Steam Generator
Reactor Coolant System
Reactor Pressure Vessel
Residual Heat Removal
Emergency Core Cooling System
Control Rod
Containment Spray |
| ML24317A223 | 12 November 2024 | Vogtle | Slides - SNC Presentation - Pre-Submittal Meeting on November 19, 2024 - Proposed Vogtle 3 and 4 Modes 5 and 6 LAR | Decay Heat Removal
Control Rod |
| IR 05000321/2024003 | 30 October 2024 | Hatch | Edwin I Hatch, Units 1 and 2 - Integrated Inspection Report 05000321/2024003 and 05000366/2024003 | Service water
High Pressure Coolant Injection
Emergency Diesel Generator
Reactor Core Isolation Cooling
Main Turbine
HVAC
Core Spray
Residual Heat Removal
Standby Gas Treatment System
Standby Liquid Control
Circulating Water System
Residual Heat Removal Service Water
Main Steam Line
Main Condenser
Control Rod |
| ML24269A008 | 24 October 2024 | 05200050 | Audit Status - the Staff Review of the NuScale Power, LLC Standard Design Approval (SDA) Application - NuScale US460 | Reactor Coolant System
Feedwater
Main Steam Isolation Valve
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML24276A133 | 17 October 2024 | FitzPatrick | Issuance of Amendment No. 357 Revise Technical Specifications to Adopt TSTF-529, Clarify Use and Application Rules, Revision-4, and Administrative Changes | Secondary containment
High Pressure Coolant Injection
Reactor Core Isolation Cooling
Primary containment
Reactor Pressure Vessel
Residual Heat Removal
Automatic Depressurization System
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Low Pressure Coolant Injection |
| ML24269A063 | 25 September 2024 | Davis Besse | Enclosure E: Davis-Besse Nuclear Power Station, Unit 1, Technical Requirements Manual, Revision 24 | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Service water
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Reactor Pressure Vessel
Shield Building
Intermediate Range Monitor
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Rod
Main Steam
Containment Spray |
| 05000461/LER-2023-002-01, Reactor Core Isolation Cooling Inoperable Prior to Mode Change | 24 September 2024 | Clinton | Reactor Core Isolation Cooling Inoperable Prior to Mode Change | Reactor Core Isolation Cooling
High Pressure Core Spray |
| ML24158A069 | 19 August 2024 | 05200050 | SDAA Chapter 9, Auxiliary Systems, SE with No Open Items | Steam Generator
Reactor Coolant System
Feedwater
Secondary containment
Service water
Emergency Diesel Generator
HVAC
Reactor Pressure Vessel
Residual Heat Removal
Fuel Pool Cooling and Cleanup
Standby Liquid Control
Remote shutdown
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Control Room Envelope
Control Rod
Main Steam |
| 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 |
| 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 |
| ML24215A208 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.1.9-3 | |
| ML24215A172 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.4.3-1 | Reactor Coolant System |
| ML24215A178 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16-10 | Steam Generator
Reactor Coolant System
Feedwater
Main Steam Isolation Valve
Emergency Core Cooling System
Decay Heat Removal
Control Rod
Main Steam |
| ML24215A207 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.1.9-2 | |
| ML24215A001 | 2 August 2024 | 05200050 | LLC, Submittal of the NRCs Request for Docketing of Resolved Audit Responses | Steam Generator
Reactor Coolant System
Feedwater
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML24215A189 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.5.3-1 | Reactor Coolant System
Shutdown Cooling
Emergency Core Cooling System
Decay Heat Removal |
| 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 |
| ML24215A206 | 2 August 2024 | 05200050 | LLC, Response to SDAA Audit Question Number A-16.3.1.9-1 | |
| ML24176A120 | 29 July 2024 | Grand Gulf | Issuance of Amendment 234 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b | Service water
Reactor Protection System
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
High Pressure Core Spray
Residual Heat Removal
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Safety Relief Valve
Control Room Envelope
Containment Spray
Low Pressure Coolant Injection |
| ML24138A200 | 24 May 2024 | 05200050 | Audit Status May 2024 - the Staff Review of the Nuscale Power, LLC Standard Design Approval Application - NuScale US460 | Steam Generator
Reactor Coolant System
Feedwater
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| ML24142A438 | 20 May 2024 | Hope Creek | Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 10 | 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 |
| ML24081A007 | 16 May 2024 | River Bend | Issuance of Amendment No. 213 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times – RITSTF Initiative 4b | Service water
Reactor Protection System
Reactor Core Isolation Cooling
Primary containment
Shutdown Cooling
High Pressure Core Spray
Residual Heat Removal
Automatic Depressurization System
Standby Liquid Control
Emergency Core Cooling System
Main Steam Line
Safety Relief Valve
Control Room Envelope
Control Rod |