| | Start date | Site | Title | Topic |
|---|
| 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 |
| 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 |
| ML26016A620 | 23 February 2026 | Grand Gulf
Arkansas Nuclear
River Bend
Waterford | Issuance of Amendments Related to Adoption of TSTF-596, Revision 2 | Shutdown Margin
High Radiation Area
Offsite Dose Calculation Manual
Hydrostatic
Probabilistic Risk Assessment
Surveillance Frequency Control Program
Loss of Offsite Power
Safeguards Contingency Plan
Operational leakage
Metamic
Gas accumulation |
| ML26035A141 | 10 February 2026 | Beaver Valley
Davis Besse
Perry
Comanche Peak | Issuance of Amendments | Shutdown Margin
Anticipated operational occurrence
Surveillance Frequency Control Program
Pressure Boundary Leakage
Unidentified leakage |
| ML26040A346 | 9 February 2026 | Wolf Creek | License Amendment Request to Revise Technical Specification 1.1 and Add 5.5.20 to Use Online Monitoring Methodology | Safe Shutdown
Shutdown Margin
Stroke time
Anticipated operational occurrence
Post Accident Monitoring
Surveillance Frequency Control Program
Core Exit Thermocouple
Unidentified leakage
Operational leakage
Pressure Temperature Limits Report |
| 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 |
| 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 |
| 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 |
| 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 |
| 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
Restart |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 | Safe Shutdown
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Incorporated by reference
Surveillance Frequency Control Program
Containment high range radiation monitor
Fuel cladding
Pressure Boundary Leakage
Fire Protection Program
Core Exit Thermocouple
Unidentified leakage |
| 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
Moisture Carryover
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 |
| 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 |
| 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 |
| 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 |
| 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 |
| NL-25-0146, Annual Radioactive Effluent Release Report and Annual Non-Radiological Environmental Operating Report for 2024 | 30 April 2025 | Hatch | Annual Radioactive Effluent Release Report and Annual Non-Radiological Environmental Operating Report for 2024 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
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 |
| 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 |
| 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 |
| ML25119A063 | 29 April 2025 | Surry | Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Spill |
| U-604831, 2024 Annual Radioactive Effluent Release Report | 29 April 2025 | Clinton | 2024 Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |
| LG-25-069, Attachment 1: 2024 Limerick Generating Station Annual Radioactive Effluent Release Report No. 50 | 29 April 2025 | Limerick | Attachment 1: 2024 Limerick Generating Station Annual Radioactive Effluent Release Report No. 50 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| ML25118A102 | 28 April 2025 | Peach Bottom
Wolf Creek | 2024 Annual Radioactive Effluent Release Report - Report 48 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |
| ML25113A044 | 23 April 2025 | Grand Gulf | Annual Radioactive Effluent Release Report (ARERR) | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Spill |
| ML25115A201 | 22 April 2025 | Palo Verde | Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report 2024 | Boric Acid
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Power change
Spill |
| ML25111A232 | 21 April 2025 | Arkansas Nuclear | Radioactive Effluent Release Report for the 2024 Calendar Year | Time of Discovery
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Sewage Treatment Plant
Annual Radiological Environmental Operating Report
Process Control Program
Main Steam Line Radiation Monitor
Annual Radiological Effluent Release Report
Operational convenience
Spill
Restart |
| RBG-48333, 2024 Annual Radioactive Effluent Release Report | 16 April 2025 | River Bend | 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
Tritium
Spill |
| ML25099A263 | 9 April 2025 | 05200050 | LLC - Part 2, Chapter 12, Radiation Protection, Revision 2 | Loop seal
High Radiation Area
Ultimate heat sink
Grab sample
Anticipated operational occurrence
Coatings
Emergency Lighting
Fuel cladding
Control Room Habitability
Spent fuel rack
Spill |
| ML25099A279 | 9 April 2025 | 05200050 | LLC - Part 4, US460 Generic Technical Specifications, Revision 2, Volume 1 - Specifications | Safe Shutdown
Boric Acid
Time of Discovery
Shutdown Margin
High Radiation Area
Ultimate heat sink
Offsite Dose Calculation Manual
Hydrostatic
Nondestructive Examination
Surveillance Frequency Control Program
Annual Radiological Environmental Operating Report
Process Control Program
Stress corrosion cracking
Pressure Boundary Leakage
Fire Protection Program
Power change
Unidentified leakage
Operational leakage
Pressure Temperature Limits Report |
| PNP 2025-015, Annual Radioactive Effluent Release Report | 31 March 2025 | Palisades | Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Radiological Environmental Operating Report
Spill
Restart |
| NMP1L3630, Errata and Corrections to the 2022 NMP1 and NMP2 Annual Radioactive Effluent Release Reports (Arerrs) | 19 March 2025 | Nine Mile Point | Errata and Corrections to the 2022 NMP1 and NMP2 Annual Radioactive Effluent Release Reports (Arerrs) | Annual Radioactive Effluent Release Report |
| ML25043A149 | 26 February 2025 | Wolf Creek | Issuance of Amendment No. 243 Revision to Technical Specifications to Adopt TSTF-569, Revision 2, Revise Response Time Testing Definition | Shutdown Margin
Anticipated operational occurrence |
| ML25008A049 | 14 December 2024 | Diablo Canyon | Comment (20) of Francene Mcclintock on Pacific Gas and Electric Company; Diablo Canyon Nuclear Power Plant, Units 1 and 2; Draft Supplemental Environmental Impact Statement | Ultimate heat sink
Internal Flooding
License Renewal
Earthquake
Chernobyl
Overdose
Spill |