| | Start date | Site | Title | Topic |
|---|
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| 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 |
| ML25119A063 | 29 April 2025 | Surry | Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report |
| 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 |
| RA25-011, 2024 Annual Radioactive Effluent Release Report | 25 April 2025 | LaSalle | 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
Power change |
| ML25114A088 | 24 April 2025 | Comanche Peak | Submittal of the 2024 Annual Radiological Effluents Release Report | Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| 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 |
| 3F0425-02, 2024 Annual Radioactive Effluent Release Report | 17 April 2025 | Crystal River | 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 |
| ML25106A134 | 16 April 2025 | | Standard License Conditions | Exemption Request
Brachytherapy
Depleted uranium |
| ML24152A180 | 10 April 2025 | 07000398 | 2 - Enclosure 1 - Special Nuclear Materials-362 License Renewal Safety Evaluation Report - Public | High Radiation Area
Emergency Lighting
Decommissioning Funding Plan
License Renewal
Exemption Request
Fire Protection Program
Fire Watch
Stolen
Uranium Hexafluoride |
| ML24152A181 | 10 April 2025 | 07000398 | 3 - Enclosure 2 - Special Nuclear Materials-362 (Public) | Decommissioning Funding Plan |
| ML25100A181 | 10 April 2025 | Millstone | 2024 Annual Radiological Environmental Operating Report (Reor) | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Fuel cladding |
| ML25099A262 | 9 April 2025 | 05200050 | LLC - Part 2, Chapter 11, Radioactive Waste Management, Revision 2 | Safe Shutdown
Boric Acid
Packing leak
Ultimate heat sink
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Process Control Program
Main Steam Line Radiation Monitor
Manual Operator Action |
| 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 |
| 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 |
| 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 |
| ML25155A465 | 3 March 2025 | 07200020 | TMI-2 ISFSI Biennial Update Report 2025_Redacted | High Radiation Area
Tornado Missile
Coatings
Finite Element Analysis
Aging Management
Tornado Generated Missile
Design basis earthquake
Earthquake
Fuel cladding
Seal weld |
| ML25016A346 | 20 February 2025 | Surry | Issuance of Amendment Nos. 320 and 320, Technical Specification 3.8 Containment Change and Addition of Surveillance Requirement, Temperature, and Pressure Values | Probabilistic Risk Assessment
Surveillance Frequency Control Program
Earthquake |
| ENS 57550 | 14 February 2025 05:00:00 | Mitsubishi Chemical America, Inc. | Damaged Fixed Gauge | Overexposure |
| RS-25-020, Additional Information Regarding License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time | 27 January 2025 | Quad Cities | Additional Information Regarding License Amendment Request for One-Time Extension of Standby Gas Treatment System Technical Specifications Completion Time | GNF3 |
| ENS 57481 | 25 December 2024 02:00:00 | Mitsubishi Chemical America, Inc. | Damaged Safety Instrument | |
| ML24348A217 | 19 December 2024 | | Presentation Slides - Dec 19 ACRS Meeting on Rev 2 RG 1.183 | Probabilistic Risk Assessment
License Renewal
Accident Tolerant Fuel
Control Room Habitability |
| 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 |
| ML24304A864 | 12 November 2024 | | DG-1425 (RG 1.183 Rev 2) Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ACRS Version | Fitness for Duty
High winds
Anticipated operational occurrence
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Nondestructive Examination
Aging Management
Fukushima Dai-Ichi
Seismically rugged
Large early release frequency
Loss of Offsite Power
Exemption Request
Earthquake
Fuel cladding
Accident Tolerant Fuel
Potassium iodide
Control Room Habitability
Leak-Before-Break |
| ML24319A080 | 8 November 2024 | Fermi
07200071 | 5 to the Updated Final Safety Analysis Report, Chapter 12, Radiation Protection | High Radiation Area
Offsite Dose Calculation Manual
Anticipated operational occurrence
Coatings
Feedwater Heater
Loss of Offsite Power
Power Uprate
Measurement Uncertainty Recapture
GNF3 |
| ML24312A315 | 5 November 2024 | Palo Verde | Independent Spent Fuel Storage Installation - Updated Annual Radioactive Effluent Release Report 2023 | Boric Acid
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| 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) | Safe Shutdown
Shutdown Margin
Anticipated operational occurrence
Post Accident Monitoring
Hydrostatic
Surveillance Frequency Control Program
Pressure Boundary Leakage
Unidentified leakage
Pressure Temperature Limits Report |
| ML24306A055 | 1 November 2024 | | NRC Revised Standard License Conditions-Ticket 81117-NRC - Conditions | Exemption Request
Brachytherapy
Depleted uranium |
| RS-24-098, Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality | 23 October 2024 | Byron
Braidwood | Units 1 and 2 - Supplement to License Amendment Request to Revise Technical Specifications 3.7.15, Spent Fuel Pool Boron Concentration, 3.7.16, Spent Fuel Assembly Storage, 4.3.1, Fuel Storage, Criticality | Aging Management
Exclusive Use
Affidavit
Spent fuel rack |
| ML24291A211 | 14 October 2024 | Saint Lucie | Updated Final Safety Analysis Report, Amendment No. 33 - 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 |
| ML24291A201 | 14 October 2024 | Saint Lucie | Updated Final Safety Analysis Report, Amendment No. 33 - Chapter 11, Radioactive Waste Management System | Boric Acid
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report
Fuel cladding
GOTHIC
Power Uprate |
| L-2024-164, Updated Final Safety Analysis Report, Amendment No. 33 - Chapter 1, Introduction and General Description of Plant Site Characteristics | 14 October 2024 | Saint Lucie | Updated Final Safety Analysis Report, Amendment No. 33 - Chapter 1, Introduction and General Description of Plant Site Characteristics | Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Non-Destructive Examination
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Hydrostatic
Incorporated by reference
Design basis earthquake
Feedwater Heater
Earthquake
Turbine Missile
Fuel cladding
Offsite Circuit
Backfit
Power change
Power Uprate
Stretch Power Uprate
Measurement Uncertainty Recapture
Failure to Scram
Overspeed trip
Overspeed
Control Room Habitability |