| | Start date | Site | Title | Topic |
|---|
| BW240053, Revised 2022 Annual Radioactive Effluent Release Report | 6 September 2024 | Braidwood | Revised 2022 Annual Radioactive Effluent Release Report | Packing leak
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| NUREG-1437 Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report | 31 August 2024 | | NUREG-1437, Volume 1, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report | Boric Acid
Ultimate heat sink
Offsite Dose Calculation Manual
Safe Shutdown Earthquake
Enforcement Discretion
Probabilistic Risk Assessment
Zebra Mussel
Incorporated by reference
FLEX
Aging Management
Fukushima Dai-Ichi
Annual Radioactive Effluent Release Report
Large early release frequency
Severe Accident Management Guideline
License Renewal
Subsequent License Renewal
Earthquake
Deep Dose Equivalent
COVID-19
Biofouling
Generic Issues Program
Environmental Justice
Uranium Hexafluoride
Fatality
Power Uprate
Depleted uranium |
| NUREG-1437 Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report | 31 August 2024 | | NUREG-1437, Volume 2, Revision 2, Generic Environmental Impact Statement for License Renewal of Nuclear Plants Final Report | Safe Shutdown
Boric Acid
High winds
Ultimate heat sink
Safe Shutdown Earthquake
Internal Flooding
Probabilistic Risk Assessment
Incorporated by reference
FLEX
B.5.b
Aging Management
Fukushima Dai-Ichi
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Intergranular Stress Corrosion Cracking
Large early release frequency
Stress corrosion cracking
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Frazil ice
Open House
License Renewal
Subsequent License Renewal
Earthquake
Nuclear Energy Innovation and Modernization Act
Hardened vent
Chernobyl
COVID-19
Fuel cladding
Accidental discharge
Environment Report
Environmental Justice
Backfit
Weak link
Uranium Hexafluoride
Fatality
Siren
Power Uprate
Stretch Power Uprate
Measurement Uncertainty Recapture
Potassium iodide
Control Room Habitability |
| ML24243A161 | 30 August 2024 | Nuclear Energy Institute | Slide Presentations for High Burnup (Hbu) Workshop V | FLEX
Surveillance Frequency Control Program
License Renewal
Backfit
Accident Tolerant Fuel
Power Uprate
Depleted uranium |
| ML24247A175 | 28 August 2024 | Sequoyah | Enclosure 1: Description and Assessment of the Proposed Changes | Probabilistic Risk Assessment
Surveillance Frequency Control Program
Recently irradiated fuel
Control Room Habitability |
| ENS 57277 | 19 August 2024 04:00:00 | 3M Corporation | Gauge Shutters Found Open Without Command | |
| ML24226B262 | 19 August 2024 | | DG-1425 (RG 1.183 Rev. 2) - Excerpt of Assessment of Consequences of FFRD (ML24226B262) | Earthquake
Fuel cladding |
| ML24214A019 | 31 July 2024 | 07109235 | List of SAR Changes, List of Calculations, SAR Page Changes and Loep, NAC-STC SAR, Revision 24A | Aging Management |
| ML24219A261 | 30 July 2024 | Abilene Christian University | Enclosure 1, Abilene Christian University Construction Permit Application Preliminary Safety Analysis Report Revision 2, July 2024 | Safe Shutdown
High Radiation Area
Ultimate heat sink
Fire Barrier
Anticipated operational occurrence
Tornado Missile
Safe Shutdown Earthquake
Internal Flooding
Hydrostatic
Operating Basis Earthquake
Emergency Lighting
Tornado-Generated Missile
Abnormal operational transient
Design basis earthquake
Earthquake
Nuclear Energy Innovation and Modernization Act
COVID-19
Fire Protection Program
Environmental Justice
Exclusive Use
Operational leakage |
| ML24192A127 | 10 July 2024 | | Scale and Melcor non-LWR Fuel Cycle Demonstration Project - MSR | |
| ML24191A267 | 2 July 2024 | San Onofre | Enclosure 1: SONGS ISFSI-Only Emergency Plan IOEP-1, Revision 4, and IOEP-2, Revision 3 | Fitness for Duty
Exemption Request
Operability Assessment |
| ML24176A124 | 30 June 2024 | | NUREG/KM-0019, Technical and Regulatory Bases for Regulatory Guide 1.236, PWR Control Rod Ejection and BWR Control Rod Drop Accidents | Anticipated operational occurrence
Fuel cladding |
| ML24052A045 | 25 June 2024 | University of Wisconsin | Examination Report Letter No. 50-156/OL-24-01, University of Wisconsin | Shutdown Margin
Deep Dose Equivalent
Fuel cladding |
| ML24165A085 | 13 June 2024 | Nuclear Energy Institute | NEI White Paper - Impact of Higher Source Term Fractions on EQ Doses | Backfit
Power Uprate |
| NUREG/CR-2907 Volume 27, Radioactive Effluents from Nuclear Power Plants: Annual Report 2021 | 31 May 2024 | | NUREG/CR-2907, Vol. 27, Radioactive Effluents from Nuclear Power Plants: Annual Report 2021 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Chernobyl |
| ML24142A440 | 20 May 2024 | Hope Creek | Enclosure 2: Hope Creek Generating Station Improved Technical Specifications Conversion - Volume 12 | Safe Shutdown
Reactor Vessel Water Level
Ultimate heat sink
Offsite Dose Calculation Manual
Surveillance Frequency Control Program
Control of Heavy Loads
Fuel cladding
Recently irradiated fuel
Control Room Habitability |
| L-24-072, Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 | 15 May 2024 | Davis Besse | Combined Annual Radiological Environmental Operating Report and Radioactive Effluent Release Report - 2023 | Safe Shutdown
Boric Acid
High winds
Grab sample
Offsite Dose Calculation Manual
Zebra Mussel
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Integrated leak rate test
Deep Dose Equivalent
Chernobyl
Fuel cladding
Tritium
Uranium Hexafluoride |
| L-MT-24-014, Offsite Dose Calculation Manual, Revision 9 | 14 May 2024 | Monticello | Offsite Dose Calculation Manual, Revision 9 | Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| ML24136A169 | 14 May 2024 | Ginna | and Independent Spent Fuel Storage Installation (ISFSI) - 2023 Annual Radioactive Effluent Release Report and 2023 Annual Radiological Environmental Operating Report | Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power change
Power Uprate |
| ML24135A321 | 14 May 2024 | Pilgrim
Holtec | Annual Radioactive Effluent Release Report, January 1 Through December 31, 2023 | Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Grace period |
| ML24135A085 | 9 May 2024 | Turkey Point | Periodic Update to the Updated Final Safety Analysis Report, Chapter 14, Safety Analysis | Safe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Ultimate heat sink
Anticipated operational occurrence
Feedwater Heater
Stress corrosion cracking
Earthquake
Control of Heavy Loads
Fuel cladding
Coast down
GOTHIC
Power Uprate
Overspeed trip
Overspeed
Loss of condenser vacuum |
| ML24130A239 | 9 May 2024 | Prairie Island | 2023 Annual Radioactive Effluent Report | Grab sample
Offsite Dose Calculation Manual
Aging Management
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report
License Renewal |
| BVY 24-018, 2023 Radiological Effluent Release Report | 5 May 2024 | Vermont Yankee | 2023 Radiological Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program
Annual Radiological Effluent Release Report |
| L-2024-078, 2023 Annual Radioactive Effluent Release Report | 1 May 2024 | Seabrook | 2023 Annual Radioactive Effluent Release Report | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report |
| ML24122A685 | 1 May 2024 | Browns Ferry | 2023 Annual Radioactive Effluent Release Report and Offsite Dose Calculation Manual | Time of Discovery
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 Uprate |
| ML24128A100 | 30 April 2024 | Prairie Island | Updated Safety Analysis Report (Usar), Revision 38, Section 7, Plant Instrumentation and Control System | Safe Shutdown
Boric Acid
Shutdown Margin
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Post Accident Monitoring
Pressure and Temperature Limits Report
Design basis earthquake
Eddy Current Testing
Earthquake
Commercial Grade
Fuel cladding
Fire Protection Program
Power change
Core Exit Thermocouple
Loss of condenser vacuum
Water hammer
Control Room Habitability |
| ML24128A107 | 30 April 2024 | Prairie Island | Updated Safety Analysis Report (Usar), Revision 38, Appendix D, Radioactive Source Bases | Boric Acid
Power Uprate
Measurement Uncertainty Recapture |
| ML24142A385 | 30 April 2024 | Surry | 2023 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
FLEX
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Fire Protection Program
Power change
Operability Assessment |
| ML24127A098 | 30 April 2024 | Dresden | Radioactive Effluent Release Report | |
| NMP1L3581, Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report | 30 April 2024 | Nine Mile Point
07201036 | Independent Spent Fuel Storage Installation (ISFSI) - 2023 Radioactive Effluent Release Report | COVID-19
Tritium |
| ML24128A116 | 30 April 2024 | Prairie Island | Updated Safety Analysis Report (Usar), Revision 38, Section 14, Safety Analysis | Boric Acid
Shutdown Margin
Loop seal
Offsite Dose Calculation Manual
Stroke time
Abnormal operational transient
Feedwater Heater
Stress corrosion cracking
Rod Drop Event
Earthquake
Fuel cladding
Coast down
GOTHIC
Operational leakage
Negative rate trip
Control Room Habitability |
| LG-24-053, Annual Radioactive Effluent Release Report No. 49 | 30 April 2024 | Limerick | Annual Radioactive Effluent Release Report No. 49 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program |
| RA-24-0030, Duke Energy - Annual Radioactive Effluent Release Report - 2023 | 29 April 2024 | Oconee
Mcguire
Catawba
Harris
Brunswick
Robinson
McGuire | Duke Energy - Annual Radioactive Effluent Release Report - 2023 | Time of Discovery
Loop seal
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power change |
| DCL-24-027, 2023 Annual Radioactive Effluent Release Report | 28 April 2024 | Diablo Canyon | 2023 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Met Tower
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report
Recently irradiated fuel
Power change |
| ML24118A003 | 27 April 2024 | Peach Bottom
Wolf Creek | 2023 Annual Radioactive Effluent Release Report - Report 47 | Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Commercial Grade |
| SVP-24-029, Radioactive Effluent Release Report for 2023 | 26 April 2024 | Quad Cities | Radioactive Effluent Release Report for 2023 | |
| RA24-009, 2023 Annual Radioactive Effluent Release Report | 26 April 2024 | LaSalle | 2023 Annual Radioactive Effluent Release Report | Unanalyzed Condition
Time of Discovery
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Deep Dose Equivalent
Power change
Loss of condenser vacuum |
| JAFP-24-0020, 2023 Annual Radioactive Effluent Release Report | 25 April 2024 | FitzPatrick | 2023 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program |
| ML24116A174 | 24 April 2024 | Millstone | Annual Radiological Environmental Operating Report | Annual Radiological Environmental Operating Report
Fuel cladding |
| W3F1-2024-0015, Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure | 24 April 2024 | Waterford | Annual Radioactive Effluent Release Report (ARERR) 2023 with Revised ODCM and Revised Process Control Program Procedure | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Annual Radiological Effluent Release Report |
| ML24114A266 | 24 April 2024 | Millstone | Submittal of 2023 Annual Radioactive Effluent Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report |
| ML24116A208 | 24 April 2024 | Palo Verde | Independent Spent Fuel Storage Installation, Annual Radioactive Effluent Release Report 2023 | Boric Acid
Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Process Control Program |
| ML24120A276 | 23 April 2024 | Peach Bottom | Independent Spent Fuel Storage Installation (ISFSI) Facility - Annual Radioactive Effluent Release Report 66 January 1, 2023 Through December 31, 2023 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| ML24116A060 | 23 April 2024 | 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
License Renewal
Earthquake
Control of Heavy Loads
Turbine Missile
Fuel cladding
Fire Protection Program
Power change
GOTHIC
Power Uprate
Overspeed
Potassium iodide |
| ML24116A049 | 23 April 2024 | Point Beach | Periodic Update of the Updated Final Safety Analysis Report, Chapter 11, Waste Disposal Systems and Radiation Protection (Redacted) | Boric Acid
High Radiation Area
Grab sample
Offsite Dose Calculation Manual
Locked High Radiation Area
Fuel cladding
Mururoa
Power Uprate
Control Room Habitability |
| PNP 2024-008, Annual Radioactive Effluent Release Report | 23 April 2024 | 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 |
| PLA-8094, Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 | 22 April 2024 | Susquehanna | Radioactive Effluent Release Report and Offsite Dose Calculation Manual PLA-8094 | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program
Power Uprate |
| TXX-2402, (CPNPP) - 2023 Annual Radiological Effluents Release Report | 18 April 2024 | Comanche Peak | (CPNPP) - 2023 Annual Radiological Effluents Release Report | Grab sample
Offsite Dose Calculation Manual
Annual Radioactive Effluent Release Report
Annual Radiological Environmental Operating Report
Process Control Program |
| ML24109A096 | 17 April 2024 | Monticello | 1 to the Updated Safety Analysis Report, Chapter 14, Plant Safety Analysis | High winds
Shutdown Margin
Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Probabilistic Risk Assessment
Minimum Critical Power Ratio
Feedwater Heater
Feedwater Controller Failure
MELLLA
Fuel cladding
Pressure Boundary Leakage
Backfit
Power Uprate
Overspeed trip
Simmer margin
Loss of condenser vacuum |
| ML24114A142 | 15 April 2024 | Wolf Creek | Redacted Updated Safety Analysis Report (WCGS Usar), Revision 37, Chapter 12, Radiation Protection | Safe Shutdown
Boric Acid
High Radiation Area
Grab sample
Offsite Dose Calculation Manual
Anticipated operational occurrence
Coatings
Incorporated by reference
Eddy Current Testing
Fuel cladding
Pressure Boundary Leakage
Scaffolding
Overexposure
Control Room Habitability |