| Start date | Site | Title | System |
---|
IR 05000277/2024002 | 4 September 2024 | Peach Bottom | Reissued Integrated Inspection Report 05000277/2024002 and 05000278/2024002 | Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Core Spray Residual Heat Removal Standby Liquid Control Reactor Building Closed Loop Cooling Main Steam Line Safety Relief Valve Main Condenser Control Rod Main Steam |
ML24227A549 | 14 August 2024 | Peach Bottom | Integrated Inspection Report 05000277/2024002 and 05000278/2024002 | Reactor Coolant System Feedwater Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Core Spray Residual Heat Removal Standby Liquid Control Reactor Building Closed Loop Cooling Main Steam Line Main Condenser Control Rod Main Steam |
L-2024-122, Core Operating Limits Report | 12 August 2024 | Turkey Point | Core Operating Limits Report | Reactor Coolant System Control Rod |
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 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 |
ML24197A240 | 24 July 2024 | | Monthly (28-day) Federal Register Notice - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations - Publication Date: August 6, 2024 | Reactor Coolant System Emergency Diesel Generator Primary containment Reactor Pressure Vessel |
ML24179A129 | 24 June 2024 | Oconee Mcguire Catawba Harris Brunswick Robinson McGuire | Acceptance Review for LAR to Revise TS to Adopt TSTF-234-A, Revision 1 | |
NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information | 14 June 2024 | Farley | RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information | Reactor Coolant System Core Spray Residual Heat Removal Control Room Emergency Filtration System |
ML24151A009 | 11 June 2024 | 07201015 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 1 - Appendix a & B | |
ML24151A010 | 11 June 2024 | 07201015 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 2 - Appendix a & B | |
ML24151A025 | 11 June 2024 | 07201015 | Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate - Appendix a & B | |
RA-23-0028, Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable | 23 May 2024 | Catawba Harris Robinson | Application to Revise Technical Specifications to Adopt TSTF-234-A, Revision 1, Add Action for More than One (D)Rpi Inoperable | Reactor Coolant System Control Rod |
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 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 |
ML24135A091 | 9 May 2024 | Turkey Point | Periodic Update to the Updated Final Safety Analysis Report, Chapter 14, Appendices a Through G | Steam Generator Reactor Coolant System Control Rod Containment Spray |
L-2024-073, Cycle 34 Core Operating Limits Report | 1 May 2024 | Turkey Point | Cycle 34 Core Operating Limits Report | Reactor Coolant System Control Rod |
NL-24-0026, Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint | 19 April 2024 | Hatch | Application to Revise Technical Specifications Surveillance Requirements to Increase Safety/Relief Valves Setpoint | Reactor Coolant System Feedwater High Pressure Coolant Injection Main Steam Isolation Valve Reactor Core Isolation Cooling Reactor Pressure Vessel Residual Heat Removal Standby Liquid Control Emergency Core Cooling System Main Steam Line Safety Relief Valve Control Rod |
L-24-018, Submittal of Core Operating Limits Report, Cycle 24, Revision 0 | 16 April 2024 | Davis Besse | Submittal of Core Operating Limits Report, Cycle 24, Revision 0 | Reactor Protection System Control Rod |
IR 05000259/2023004 | 6 February 2024 | Browns Ferry | Integrated Inspection Report 05000259/2023004; 05000260/2023004 and 05000296/2023004 | High Pressure Coolant Injection Emergency Diesel Generator Reactor Core Isolation Cooling Core Spray Residual Heat Removal Standby Liquid Control Residual Heat Removal Service Water Control Room Envelope Control Rod |
IR 05000263/2023004 | 31 January 2024 | Monticello | Integrated Inspection Report 05000263/2023004 | Reactor Coolant System Feedwater High Pressure Coolant Injection Shutdown Cooling HVAC Core Spray Residual Heat Removal Standby Gas Treatment System Stator Water Cooling Standby Liquid Control Main Steam Line Main Condenser Control Rod Main Steam Low Pressure Coolant Injection |
GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation | 5 December 2023 | Columbia | Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation | Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Reactor Water Cleanup Standby Liquid Control Main Steam Line |
WBL-23-055, of the Unit 2 Cycle 6 Core Operating Limits Report | 22 November 2023 | Watts Bar | of the Unit 2 Cycle 6 Core Operating Limits Report | Control Rod |
L-2023-078, License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles | 15 November 2023 | Turkey Point | License Amendment Request 278, Incorporate Advanced Fuel Products, Extend Surveillance Intervals and 10 CFR 50.46 Exemption Request to Facilitate Transition to 24-Month Fuel Cycles | Steam Generator Reactor Coolant System Feedwater High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Auxiliary Feedwater Reactor Core Isolation Cooling Primary containment Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Control Room Emergency Ventilation Main Steam Safety Valve Emergency Core Cooling System Main Steam Line Main Condenser Control Rod Main Steam Containment Spray |
ML23304A387 | 31 October 2023 | 05200050 | LLC Revision 1 to Standard Design Approval Application, Part 4, US460 Generic Technical Specifications, Vol. 1 | 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 |
ML23304A388 | 31 October 2023 | 05200050 | LLC Revision 1 to Standard Design Approval Application, Part 4, US460 Generic Technical Specifications, Vol. 2 | Steam Generator Reactor Coolant System Feedwater Main Steam Isolation Valve Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Main Steam |
ML23283A279 | 10 October 2023 | Sequoyah | Revisions to the Sequoyah Nuclear Plant Units 1 and 2 Technical Requirements Manual | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Diesel Generator Auxiliary Feedwater HVAC Reactor Pressure Vessel Residual Heat Removal Control Rod |
NRC-23-0063, Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1 | 9 October 2023 | Fermi | Inservice Testing Program for Pumps and Valves - Part 12: IST Program Pump Basis Revision 1 | Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Shutdown Cooling HVAC Reactor Pressure Vessel Core Spray Residual Heat Removal Fuel Pool Cooling and Cleanup Automatic Depressurization System Standby Liquid Control Emergency Equipment Cooling Water Residual Heat Removal Service Water Low Pressure Cooling Injection Emergency Core Cooling System Decay Heat Removal Main Condenser Control Rod Containment Spray Low Pressure Coolant Injection |
ML23283A034 | 9 October 2023 | Fermi | Inservice Testing Program for Pumps and Valves - Part 11: IST Program Valve Basis Revision 1 | Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Primary containment Main Turbine Shutdown Cooling Reactor Recirculation Pump Reactor Pressure Vessel Core Spray Residual Heat Removal Automatic Depressurization System Standby Liquid Control Emergency Equipment Cooling Water Residual Heat Removal Service Water Emergency Core Cooling System Main Steam Line Safety Relief Valve Main Condenser Control Rod Main Steam Containment Spray Low Pressure Coolant Injection |
ML23275A111 | 2 October 2023 | Saint Lucie | Improved Technical Specifications (ITS) Revision 2 Submittal Volumes 1 Through 16 | Steam Generator Reactor Coolant System Feedwater Secondary containment Reactor Protection System Auxiliary Feedwater Shutdown Cooling Reactor Pressure Vessel Residual Heat Removal Shield Building Remote shutdown Emergency Core Cooling System Decay Heat Removal Main Steam Line Control Rod Containment Spray |
ML23275A110 | 2 October 2023 | Saint Lucie | License Amendment Request Revision 2 for the Technical Specifications Conversion to NUREG-1432, Revision 5 | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Primary containment Shutdown Cooling Reactor Pressure Vessel Control Room Emergency Ventilation Shield Building Main Steam Safety Valve Remote shutdown Emergency Core Cooling System Decay Heat Removal Control Room Envelope Control Rod Containment Spray |
ML23275A119 | 2 October 2023 | Saint Lucie | Improved Technical Specifications Conversion, Section 3.4, Reactor Coolant System, Revision 2 - Volume 9 | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Auxiliary Feedwater Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Steam Bypass Control System Main Steam Safety Valve Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser |
ML23275A116 | 2 October 2023 | Saint Lucie | Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 - Volume 6 | Steam Generator Reactor Coolant System Reactor Protection System Shutdown Cooling Reactor Pressure Vessel Emergency Core Cooling System Main Steam Line Control Rod Main Steam |
ML23264A041 | 27 September 2023 | Watts Bar | NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides | |
ML23263A260 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 6 - Appendix a & B | |
ML23255A253 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate - Appendix a | |
ML23255A251 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 7 - Appendix a & B | |
ML23255A250 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 6 - Appendix a & B | |
ML23255A249 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 5 - Appendix a & B | |
ML23255A248 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 4 - Appendix a & B | |
ML23255A247 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 3 - Appendix a & B | |
ML23255A252 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 8 - Appendix a & B | |
ML23255A245 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 1 - Appendix a | |
ML23255A246 | 12 September 2023 | 07201025 | Conditions for Cask Use and Technical Specifications, Renewed Amendment 2 - Appendix a & B | |
ML23199A294 | 9 August 2023 | Palo Verde | Issuance of Amendment Nos. 221, 221, and 221, to Revise Technical Specifications to Adopt TSTF-107, Separate Control Rods That Are Untrippable Versus Inoperable | Control Rod |
IR 05000440/2023002 | 2 August 2023 | Perry | Integrated Inspection Report 05000440/2023002 | Reactor Coolant System Feedwater Service water Reactor Protection System Main Steam Isolation Valve Primary containment Emergency Response Data System Reactor Recirculation Pump Residual Heat Removal Standby Liquid Control Main Steam Line Safety Relief Valve Control Rod Main Steam |
ML23206A053 | 25 July 2023 | Hatch | 2A, Exam Draft Items (Hatch 2021-301) | Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Recirculation Pump Safety Parameter Display System HVAC Reactor Pressure Vessel Core Spray Reactor Building Ventilation Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Stator Water Cooling Automatic Depressurization System Standby Liquid Control Circulating Water System Intermediate Range Monitor Remote shutdown Emergency Core Cooling System Main Steam Line Safety Relief Valve Rod Worth Minimizer Main Condenser Control Rod Main Steam Containment Spray |
ML22297A283 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 2 | |
ML22297A289 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 8 | |
ML22297A288 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 7 | |
ML22297A287 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 6 | |
ML22297A286 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 5 | |
ML22297A285 | 14 July 2023 | 07201025 | Preliminary Appendix A- Conditions for Cask Use and Technical Specifications, Renewed Amendment 4 | |
ML22297A284 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 3 | |
ML22297A282 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Amendment 1 | |
ML22297A281 | 14 July 2023 | 07201025 | Preliminary Appendix a - Conditions for Cask Use and Technical Specifications, Renewed Initial Certificate | |
RS-23-059, 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 | 8 June 2023 | Quad Cities | 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 | Reactor Coolant System Feedwater Service water High Pressure Coolant Injection Reactor Protection System Emergency Diesel Generator Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling HVAC Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Standby Gas Treatment System Control Room Emergency Ventilation Automatic Depressurization System Standby Liquid Control Circulating Water System Intermediate Range Monitor Residual Heat Removal Service Water Emergency Core Cooling System Decay Heat Removal Main Steam Line Main Condenser Control Rod Main Steam Low Pressure Coolant Injection Main Turbine Bypass System |
GNRO-2023/00014, 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 | 6 June 2023 | Grand Gulf | 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 | Reactor Coolant System Feedwater Service water Reactor Protection System Emergency Diesel Generator Main Steam Isolation Valve Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Reactor Pressure Vessel High Pressure Core Spray Core Spray Residual Heat Removal Reactor Water Cleanup Automatic Depressurization System Standby Liquid Control Intermediate Range Monitor Emergency Core Cooling System Decay Heat Removal Main Steam Line Safety Relief Valve Control Room Envelope Control Rod Main Steam Containment Spray Low Pressure Coolant Injection Main Turbine Bypass System |
ML23214A242 | 25 May 2023 | Monticello | Breakout Questions - Aging Management Audit - Monticello Unit 1 - Subsequent License Renewal Application | Reactor Coolant System Feedwater Secondary containment Service water High Pressure Coolant Injection Emergency Diesel Generator Primary containment Main Turbine Reactor Pressure Vessel Core Spray Residual Heat Removal Reactor Water Cleanup Fuel Pool Cooling and Cleanup Standby Liquid Control Main Condenser Control Rod Main Steam Extraction steam |
L-2023-063, Enclosure 2, Volume 1: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Application of Selection Criteria to Technical Specifications, Revision 2, Volume 1 | 24 May 2023 | Turkey Point | Enclosure 2, Volume 1: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Application of Selection Criteria to Technical Specifications, Revision 2, Volume 1 | Steam Generator Reactor Coolant System Feedwater Emergency Diesel Generator Auxiliary Feedwater Residual Heat Removal Control Room Emergency Ventilation Standby Liquid Control Control Rod Main Steam Containment Spray |
ML23151A444 | 24 May 2023 | Turkey Point | Enclosure 2, Volume 6: Turkey Point Nuclear Plant, Units 3 and 4, Improved Technical Specifications Conversion, Section 3.1, Reactivity Control Systems, Revision 2 | Steam Generator Reactor Coolant System Feedwater Reactor Protection System Emergency Core Cooling System Main Steam Line Control Rod Main Steam |
ML23061A012 | 9 May 2023 | Surry | Issuance of Amendment Nos. 312 and 312, Regarding Technical Specifications Task Force (TSTF) Traveler 547, Revision 1 | Reactor Coolant System Control Rod Main Steam |
ML23073A290 | 2 May 2023 | Browns Ferry | Issuance of Amendment Nos. 328, 351, and 311 Adoption of TSTF-505, Revision 2, for Risk-Informed Completion Times and TSTF-439, Revision 2, to Eliminate Second Completion Times | Feedwater High Pressure Coolant Injection Reactor Protection System Reactor Core Isolation Cooling Primary containment Main Turbine Shutdown Cooling Residual Heat Removal Control Room Emergency Ventilation Automatic Depressurization System Standby Liquid Control Emergency Equipment Cooling Water Emergency Core Cooling System Main Steam Line Control Rod Low Pressure Coolant Injection |