| | Start date | Site | Title | Topic |
|---|
| ML26033A033 | 2 February 2026 | Fort Calhoun | FCS Response to Audit Request Q-6 | |
| 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 |
| ML25345A151 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-105, Rev. 0, Industrial Use Scenario with Open Drinking Water Pathway: an Assessment of Impact on Bfm Dcglw/F Values | |
| ML25345A152 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-107, Rev. 0, Industrial Use Scenario with Open Drinking Water Pathway: an Assessment of Impact on Bfm Dcglep Values | |
| ML25345A153 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-108, Rev. 0, Industrial Use Scenario with Open Drinking Water Pathway: an Assessment of Impact on Bfm Dcglbp Values | |
| ML25345A112 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-004, Rev. 0, Resrad Building Surface Dcgl Values | |
| ML25345A150 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-103, Rev. 0, Industrial Use Scenario with Open Drinking Water Pathway: an Assessment of Impact on Dcgl Values for Surface Soil | |
| ML25345A149 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-102, Rev. 0, Dcglbp Values Assuming the Residential Scenario with Drinking Water | |
| ML25345A113 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-006, Rev. 1, Area Factors for Use with Oyster Creek Dcgl Values for Buildings/Structures | |
| ML25345A145 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-101, Rev. 0, Dcglbp Values Assuming the Residential Scenario Without Drinking Water | |
| ML25345A114 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-007, Rev. 0, RESRAD-Onsite Probabilistic Analysis - Industrial Use Scenario | |
| ML25345A115 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-008, Rev. 0, Derived Concentration Guideline Levels Values for Soil - Industrial Use Scenario | |
| ML25345A116 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-009, Rev. 0, Area Factors for Soil - Industrial Use Scenario | |
| ML25345A144 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-096, Rev. 0, Bfm Dcglep Values Assuming the Residential Scenario with Drinking Water | |
| ML25345A098 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Site Radiological Characterization, Revision 1 | Grab sample
Spill |
| ML25345A117 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-012, Rev. 0, Basement Fill Model: Probabilistic Analysis for Instantaneous Release Scenario Assuming Industrial Use Exposure Pathways | |
| ML25345A143 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-093, Rev. 0, Bfm Dcglep Values Assuming the Residential Scenario Without Drinking Water | |
| ML25345A142 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-092, Rev. 0, Bfm Dcgl W/F Values Assuming the Residential Scenario with a Drinking Water Pathway | |
| ML25345A141 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-091, Rev. 0, Bfm Dcgl W/F Values Assuming the Residential Scenario Without Drinking Water | |
| ML25345A140 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-090, Rev. 0, Soil Dcgl Values Assuming the Residential Scenario with Drinking Water | |
| ML25345A139 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 25-089, Rev. 0, Soil Dcgl Values Assuming the Residential Scenario Without Drinking Water | |
| ML25345A138 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-085, Rev. 0, Probabilistic Dose Comparisons: Building Occupancy Scenario Vs. Room Renovation Scenario | |
| ML25345A118 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-013, Rev. 1, Basement Fill Model: Calculation of Dcgl W/F Values Assuming Industrial Use of Scenario Exposure Pathways | |
| ML25345A137 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-111, Rev. 0, Surface/Sub Surface Characterization Survey Plan | Spill |
| ML25345A119 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-014, Rev. 0, Basement Fill Model: Probabilistic Analysis for Embedded Pipes Scenario | |
| ML25345A124 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-015, Rev. 1, Basement Fill Model: Calculation of Embedded Pipe Dcgl Values | |
| ML25345A125 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Calculation ENG-OCS-016, Rev. 0, Calculation of Buried Pipe Dcgl Values | |
| ML25345A127 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-108, Rev. 1, Instrument Efficiency Determination for Use in Min. Detectable Concentration Calculations for Final Status Surveys at OCNGS | Coatings |
| ML25345A129 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-055, Rev. 0, Basement Fill Model: Probabilistic Analyses for the Instantaneous Release Scenario Assuming Industrial Use Exposure Pathways | |
| ML25345A133 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-081, Rev. 2, Groundwater Dose Calculation Methodology to Support the License Termination Plan | |
| ML25345A132 | 11 December 2025 | Oyster Creek | Nuclear Generating Station, Technical Support Document No. 24-062, Rev. 1, Method for Determining Nuclide Fractions and Gross Activity Dcgls | |
| ML25220A249 | 8 December 2025 | Fort Calhoun | Fort Calhoun LTP License Amendment Request EA | License Renewal
Earthquake |
| ML25197A788 | 2 December 2025 | | OMB 3150-0139, 2025 NRC Form 327, NRC Form 327, Special Nuclear Material (SNM) and Source Material (SM) Physical Inventory Summary Report, and NUREG/BR-0096, Instructions and Guidance for Completing Physical Inventory | Depleted uranium |
| ML25307A011 | 30 October 2025 | Cook | Units 1 and 2 - 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 |
| ML25290A113 | 13 October 2025 | Susquehanna | Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Appendix 15b, Accident Dose Model Descriptions | Deep Dose Equivalent
Unidentified leakage
Control Room Habitability |
| ML25290A105 | 13 October 2025 | Susquehanna | Susquehanna, Units 1 and 2 - 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 |
| ML25290A082 | 13 October 2025 | Susquehanna | Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.6, Low Level Radwaste Holding Facility (Llrwhf) | Offsite Dose Calculation Manual
Loss of Offsite Power
Earthquake
Fire Protection Program
Scaffolding
Control Room Habitability |
| ML25290A101 | 13 October 2025 | Susquehanna | Susquehanna, Units 1 and 2 - 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 |
| ML25259A312 | 30 September 2025 | 07109295 | Enclosure 2 - CoC No. 9295, Rev. 8 | |
| ML25260A626 | 26 September 2025 | Erwin | Enclosure 3 NFS Amendment 24 Safety Evaluation Report (Public) | |
| W3F1-2025-0046, Waterford Steam Electric Station, Unit 3 - Resubmittal of Annual Radiological Environmental Operating Report (AREOR) - 2024 | 25 September 2025 | Waterford | Waterford Steam Electric Station, Unit 3 - Resubmittal of Annual Radiological Environmental Operating Report (AREOR) - 2024 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Chernobyl
Spill |
| LIC-25-0011, Fort Calhoun Station, Unit 1, Corrected Page 5-25 to the Supplement of the License Amendment Request (LAR) to Revise License Termination Plan (LTP) | 4 September 2025 | Fort Calhoun | Fort Calhoun Station, Unit 1, Corrected Page 5-25 to the Supplement of the License Amendment Request (LAR) to Revise License Termination Plan (LTP) | |
| ML25237A035 | 18 August 2025 | Erwin | Nuclear Fuel Services, Inc., Biannual Effluent Monitoring Report January to June 2025 | |
| ML25204A128 | 6 August 2025 | 07109288 | Enclosure 1: CoC No. 9288, Revision No. 13 | |
| ML25217A080 | 5 August 2025 | Kewaunee | Nuclear Power Station- License Termination Plan License Amendment Pre-Submittal Meeting August 6, 2025 Licensee Slides | Decommissioning Funding Plan
Sewage Treatment Plant
Chernobyl
Pre-submittal |
| 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 |
| ML25212A112 | 31 July 2025 | 11006064 | Export License Public Issued to Baker Hughes Oilfield Operations, LLC, PXB169.05 | |
| ML25211A145 | 30 July 2025 | 11006082 | Export License Issued to Schlumberger Technology Corporation PXB139.07 | |
| LIC-25-0008, Fort Calhoun, Unit 1, Independent Spent Fuel Storage Installation - Response to Audit Report for Omaha Public Power District Request to Revise License Termination Plan Requirements and Request for Additional Information (EPID L-2024-LLA- | 28 July 2025 | Fort Calhoun | Fort Calhoun, Unit 1, Independent Spent Fuel Storage Installation - Response to Audit Report for Omaha Public Power District Request to Revise License Termination Plan Requirements and Request for Additional Information (EPID L-2024-LLA-009 | |
| ML25169A038 | 16 June 2025 | 11006610 | Export License Issued to Schlumberger Technology Corporation PXB249.00 | |