| | Start date | Site | Title | Topic |
|---|
| ML26037A091 | 26 February 2026 | Ginna | R. E. Ginna Nuclear Power Plant - Issuance of Amendment No. 161 to Adopt TSTF-51, Revision 2 | Unanalyzed Condition
Shutdown Margin
Surveillance Frequency Control Program
Recently irradiated fuel
Fire Protection Program |
| L-2026-032, Annual Radioactive Effluent Release Report (ARERR) for 2025 | 26 February 2026 | Turkey Point | Annual Radioactive Effluent Release Report (ARERR) for 2025 | Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| ULNRC-06922, Enclosure 8: Evaluation of Changes for AST RE-Analysis for an Increase in Fuel Burnup | 28 January 2026 | Callaway | Enclosure 8: Evaluation of Changes for AST RE-Analysis for an Increase in Fuel Burnup | Loss of Offsite Power
Deep Dose Equivalent
Accident Tolerant Fuel
Pre-submittal
Spent fuel rack
Leak-Before-Break |
| ML26015A145 | 27 January 2026 | Prairie Island | Issuance of Amendments Nos. 249 and 237 Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements | Safeguards Contingency Plan
Pressure Boundary Leakage
Unidentified leakage
Operational leakage |
| CNL-25-048, Application to Revise Technical Specification 5.5.3 Radioactive Effluent Controls Program to Support Revision of the Offsite Dose Calculation Manual That Accounts for Radionuclides Generated When Using Potassium Hydroxide | 15 January 2026 | Sequoyah | Application to Revise Technical Specification 5.5.3 Radioactive Effluent Controls Program to Support Revision of the Offsite Dose Calculation Manual That Accounts for Radionuclides Generated When Using Potassium Hydroxide | Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
License Renewal |
| IR 05000237/2025003 | 31 December 2025 | Dresden | Integrated Inspection Report 05000237/2025003 and 05000249/2025003 and Exercise of Enforcement Discretion | Time of Discovery
Mission time
Offsite Dose Calculation Manual
Past operability
Enforcement Discretion
Probabilistic Risk Assessment
Functionality Assessment
Condition Adverse to Quality
FLEX
Significance Determination Process
Feedwater Heater
Annual Radiological Environmental Operating Report
Large early release frequency
Loss of Offsite Power
Operability Determination
Fire Protection Program
Power change
Downpower
Eddy Current Test
Reactive Inspection |
| L-2025-190, Corrected Amendment 33 to the Updated Final Safety Analysis Report, Chapter 12, Radiation Protection | 29 December 2025 | Saint Lucie | Corrected Amendment 33 to the Updated Final Safety Analysis Report, Chapter 12, Radiation Protection | Boric Acid
Loop seal
High Radiation Area
Grab sample
Anticipated operational occurrence
Coatings
Fuel cladding
Power Uprate
Overexposure
Spent fuel rack
Spill |
| ML25328A120 | 9 December 2025 | Watts Bar
Sequoyah | Issuance of Amendment Nos. 373, 368; 177, and 82 Regarding Use of Online Monitoring Methodology | Safe Shutdown
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Cyber Security
Surveillance Frequency Control Program
Safeguards Contingency Plan
Pressure Boundary Leakage
Fire Protection Program
Unidentified leakage
Pressure Temperature Limits Report |
| ML25324A041 | 20 November 2025 | Salem
Hope Creek | Enclosure 3 - Salem Generating Station, Unit 1, Technical Specification Bases | Safe Shutdown
Boric Acid
Shutdown Margin
High Radiation Area
Anticipated operational occurrence
Hydrostatic
Nondestructive Examination
Aging Management
Missed surveillance
Surveillance Frequency Control Program
Loss of Offsite Power
Fuel cladding
Pressure Boundary Leakage
Offsite Circuit
Power change
Core Exit Thermocouple
Coast down
Unidentified leakage
Operational leakage
Control Room Habitability |
| LR-N25-0078, Enclosure 4 - Salem Generating Station, Unit 2, Technical Specification Bases | 20 November 2025 | Salem
Hope Creek | Enclosure 4 - Salem Generating Station, Unit 2, Technical Specification Bases | Safe Shutdown
Boric Acid
Shutdown Margin
High Radiation Area
Anticipated operational occurrence
Hydrostatic
Nondestructive Examination
Aging Management
Missed surveillance
Surveillance Frequency Control Program
Loss of Offsite Power
Fuel cladding
Pressure Boundary Leakage
Offsite Circuit
Power change
Core Exit Thermocouple
Coast down
Unidentified leakage
Operational leakage
Control Room Habitability |
| ML25307A011 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 14, Section 14.3, Tables 14.3.1-1 to 14.3.9-23, 14.A.1-1 to 14.G-3 (Unit 1) | Boric Acid
Loop seal
Fire Barrier
Coatings
Spill |
| ML25307A024 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 14, Section 14.2, Standby Safeguards Analysis (Unit 1) | Boric Acid
Shutdown Margin
Loss of Offsite Power
Earthquake
Fuel cladding
Power Uprate
Control Room Habitability
Spent fuel rack |
| ML25307A032 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 14, Section 14.2, Tables 14.2.1-2 to 14.2.7-1 (Unit 1) | |
| ML25307A049 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 14, Section 14.1, Tables 14.1-1 to 14.1.13-1 (Unit 1) | Loss of Offsite Power
Turbine Missile
Power Uprate |
| ML25307A053 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 11, Tables | Boric Acid |
| ML25307A078 | 30 October 2025 | Cook | Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 14, Section 14.A-G, Radiation Sources (Appendix 14A) (Unit 1) | Safe Shutdown
Design basis earthquake
Earthquake
Fuel cladding |
| ML25290A119 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 18, Section 18.1, Response to Requirements in NUREG-0737 | Reactor Vessel Water Level
Grab sample
Anticipated operational occurrence
Scram Discharge Volume
Shift Technical Advisor
Loss of Offsite Power
Excess Flow Check Valve
Earthquake
Fuel cladding
Thermal fatigue
Potassium iodide
Control Room Habitability |
| ML25290A113 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Appendix 15b, Accident Dose Model Descriptions | Deep Dose Equivalent
Unidentified leakage
Control Room Habitability |
| ML25290A087 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 12, Section 12.2, Radiation Sources | Feedwater Heater
Process Control Program
Power Uprate |
| ML25290A102 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Section 15.1, Decrease in Reactor Coolant Temperature | Stroke time
Anticipated operational occurrence
Feedwater Heater
Feedwater Controller Failure
Power Uprate |
| ML25290A079 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.5, Process and Effluent Radiolgocial Monitoring and Sampling Systems | Grab sample
Anticipated operational occurrence
Control Room Habitability |
| ML25290A108 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Appendix 15e, Initial Core for SSES, Units 1 and 2, Non-Limiting Events | Feedwater Heater
Feedwater Controller Failure
Loss of condenser vacuum |
| ML25290A100 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Section 15.7, Radioactive Release from Subsystems and Components | Earthquake
Control Room Habitability
Spill |
| ML25290A078 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.1, Source Terms | Stress corrosion cracking
Fuel cladding
Power Uprate
Spill |
| ML25290A080 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.3, Gaseous Waste Management Systems | Grab sample
Anticipated operational occurrence
Safe Shutdown Earthquake
Earthquake
Fuel cladding |
| ML25290A101 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Section 15.6, Decrease in Reactor Coolant Inventory | Safe Shutdown
Safe Shutdown Earthquake
Feedwater Heater
Loss of Offsite Power
Excess Flow Check Valve
Earthquake
Power Uprate |
| ML25290A083 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.2, Liquid Waste Management Systems | Grab sample
Anticipated operational occurrence
Spill |
| ML25290A105 | 13 October 2025 | Susquehanna | Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Section 15.4, Reactivity and Power Distributions Anomalies | Shutdown Margin
Main Steam Line Radiation Monitor
Rod Drop Event
Power Uprate |
| ML25283A007 | 9 October 2025 | Point Beach | Periodic Update of the Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems (Redacted) | Safe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Offsite Dose Calculation Manual
Tornado Missile
Hydrostatic
Probabilistic Risk Assessment
Zebra Mussel
High Energy Line Break
Surveillance Frequency Control Program
Design basis earthquake
Loss of Offsite Power
License Renewal
Earthquake
Control of Heavy Loads
Turbine Missile
Fuel cladding
Fire Protection Program
Power change
GOTHIC
Power Uprate
Overspeed
Potassium iodide
Spent fuel rack
Gas accumulation
Operational convenience
Leak-Before-Break
Pressure locking
Full Core Offload |
| ML25283A010 | 9 October 2025 | Point Beach | Periodic Update of the Updated Final Safety Analysis Report, Chapter 11, Waste Disposal Systems and Radiation Protection | Boric Acid
High Radiation Area
Grab sample
Offsite Dose Calculation Manual
Locked High Radiation Area
Fuel cladding
Mururoa
Power Uprate
Control Room Habitability
Unplanned intake
Spill |
| ML25279A109 | 6 October 2025 | Turkey Point | Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features | Boric Acid
Stroke time
Hydrostatic
High Energy Line Break
Local Leak Rate Testing
Stress corrosion cracking
Integrated leak rate test
Earthquake
Power Operated Valves
Fuel cladding
Liquid penetrant
GOTHIC
Power Uprate
Eddy Current Test
Thermography
Gas accumulation
Leak Before Break
Seal weld
Spill
Pressure locking
Thermal binding |
| ML25279A114 | 6 October 2025 | Turkey Point | Updated Final Safety Analysis Report, Chapter 11, Waste Disposal and Radiation Protection System | High Radiation Area
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Post Accident Monitoring
Probabilistic Risk Assessment
Feedwater Heater
Containment high range radiation monitor
Fuel cladding
Power Uprate
Overexposure
Control Room Habitability |
| ML25279A129 | 6 October 2025 | Turkey Point | Updated Final Safety Analysis Report, Chapter 14, Appendices 14A-14G | Shutdown Margin |
| ML25248A026 | 5 September 2025 | 07109377 | Tn Americas LLC Application for Certificate of Compliance No. 9377 Revision 1 of the TN-32 Transportation Package | Fuel cladding
Loctite
Exclusive Use
Affidavit |
| 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 | Surveillance Frequency Control Program
Pressure Boundary Leakage
Unidentified leakage
Operational leakage
Seal weld |
| ML25241A353 | 29 August 2025 | 99902117
05000614 | Long Mott Generating Station, Environmental Report | Probabilistic Risk Assessment
License Renewal
Fatality |
| SVPLTR 25-0054, Revision to 2024 Annual Radioactive Effluent Release Report | 8 August 2025 | Dresden | Revision to 2024 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Sewage Treatment Plant
Annual Radiological Environmental Operating Report
Process Control Program |
| ML25203A330 | 1 August 2025 | | Methodology for Generating Maccs Site-Specific Input Files to Support Risk-Informed Radiological Consequence Assessment | Probabilistic Risk Assessment
Large early release frequency
Environmental Justice
Fatality |
| ML25150A342 | 1 July 2025 | Farley | Issuance of Amendment Nos. 255 and 252 to Revise Updated Final Safety Analysis Report to Provide a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods | |
| ML25157A133 | 6 June 2025 | 99902103 | Summary of the May 22, 2025, Partially Closed Meeting with Arc Clean Technology | Internal Flooding
Pre-application |
| ML25136A297 | 16 May 2025 | Surry
North Anna | Proposed License Amendment Requests to Update Main Steam Line Break Alternative Source Term Dose Consequences Analyses | Safe Shutdown
Mission time
Probabilistic Risk Assessment
Met Tower
Loss of Offsite Power
Time Critical Operator Action
Earthquake
Deep Dose Equivalent
Operational leakage
Control Room Habitability |
| ML25134A218 | 14 May 2025 | Pilgrim | Annual Radioactive Effluent Release Report, January 1 Through December 31, 2024 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report |
| BVY 25-014, 2024 Radiological Effluent Release Report | 12 May 2025 | Vermont Yankee | 2024 Radiological Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report |
| ML25132A066 | 10 May 2025 | Monticello | 2024 Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |
| ML25121A289 | 1 May 2025 | Dresden | Annual Radioactive Effluent Release Report 2024 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Sewage Treatment Plant
Annual Radiological Environmental Operating Report
Process Control Program |
| ML25121A148 | 1 May 2025 | Browns Ferry | Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program
Power Uprate
Spill |
| SVP-25-022, Radioactive Effluent Release Report for 2024 | 30 April 2025 | Quad Cities | Radioactive Effluent Release Report for 2024 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Spill |
| JAFP-25-0026, 2024 Annual Radioactive Effluent Release Report | 30 April 2025 | FitzPatrick | 2024 Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |
| ML25122A175 | 30 April 2025 | San Onofre | (Songs), Units 1, 2, and 3 - 2024 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Chernobyl |
| NL-25-0144, Annual Radioactive Effluent Release Report and Annual Non-Radiological Environmental Operating Report for 2024 | 30 April 2025 | Farley | Annual Radioactive Effluent Release Report and Annual Non-Radiological Environmental Operating Report for 2024 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |