Xe-133

Isotope Xe - 133

	Start date	Site	Title	Topic
ML26033A255	2 February 2026	99902117 05000614	Enclosure 2: PSAR Subsection 2.4.13 Accidental Releases of Liquid Effluents Into Ground and Surface Waters
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	Nuclear Generating Plant, Units 1 and 2 - Issuance of Amendments Nos. 249 and 237 Revise Technical Specifications to Adopt TSTF-554, Revise Reactor Coolant Leakage Requirements (EPID L-2025-LLA-0142)	Safeguards Contingency Plan Pressure Boundary Leakage Unidentified leakage Operational leakage
CNL-25-048, Units 1 and 2, 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	Units 1 and 2, 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
ML25351A015	30 December 2025	Vogtle	Units 3 and 4 - Issuance of Amendment to Increase Flexibility in Mode Restraints (EPID No. L-2024-LLA-0171)	Grab sample Post Accident Monitoring Probabilistic Risk Assessment Significance Determination Process Power change
L-2025-190, Unit 1, Corrected Amendment 33 to the Updated Final Safety Analysis Report, Chapter 12, Radiation Protection	29 December 2025	Saint Lucie	Unit 1, 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
NL-25-0336, Units 3 and 4, License Amendment Request Revise Technical Specification 3.4.10, Reactor Coolant System (RCS) Specific Activity	22 December 2025	Vogtle	Units 3 and 4, License Amendment Request Revise Technical Specification 3.4.10, Reactor Coolant System (RCS) Specific Activity	Power change
ML25328A120	9 December 2025	Watts Bar Sequoyah	Nuclear Plant, Units 1 and 2; Watts Bar Nuclear Plant, Units 1 and 2 - Issuance of Amendment Nos. 373, 368; 177, and 82 Regarding Use of Online Monitoring Methodology (EPID L-2024-LLA-0147)	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
ML25339A083	8 December 2025	Vogtle	December 4, 2025, Summary of Observation Pre-Submittal Meeting Held with Southern Nuclear Operating Company, Inc., Regarding a Proposed License Amendment Request to Revise Technical Specification 3.4.10 for Vogtle Electric Generating Plant,	Pre-submittal
ML25330A089	4 December 2025	05000026 05000025	SNC Slides - Vogtle 3 and 4 - TSTF-490 LAR - Pre-Submittal Meeting - December 4 2025 (EPID L-202-LRM-0142)	Pre-submittal
ML25338A079	4 December 2025	Vogtle	SNC Slides - Vogtle 3 and 4 - TSYF-490 LAR - Pre-Submittal Meeting December 4, 2025	Pre-submittal
ML25336A066	2 December 2025	Vogtle	SNC Slides - Vogtle 3 and 4 - TSYF-490 LAR - Pre-Submittal Meeting December 4, 2025	Pre-submittal
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
PMNS20251170, Pre-Submittal Meeting - Vogtle, Units 3 and 4 - Proposed LAR to Revise Technical Specification (TS) 3.4.10, Reactor Coolant System (RCS) Specific Activity for Xe-133 Out of Limits - Completion Time Extension (TSTF-490)	17 November 2025	Vogtle	Pre-Submittal Meeting - Vogtle, Units 3 and 4 - Proposed LAR to Revise Technical Specification (TS) 3.4.10, Reactor Coolant System (RCS) Specific Activity for Xe-133 Out of Limits - Completion Time Extension (TSTF-490)	Pre-submittal
ML25304A104	31 October 2025	Crane	Crane Clean Energy Center - Emergency Action Levels	Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Fire Barrier Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action Loss of Offsite Power Safeguards Contingency Plan Earthquake Fuel cladding Pressure Boundary Leakage Core Exit Thermocouple Unidentified leakage Spill
ML25304A101	31 October 2025	Crane	Crane Clean Energy Center - Emergency Action Levels	Safe Shutdown High winds Shutdown Margin Reactor Vessel Water Level Ultimate heat sink Fire Barrier Safe Shutdown Earthquake Operating Basis Earthquake Operator Manual Action Loss of Offsite Power Safeguards Contingency Plan Earthquake Fuel cladding Pressure Boundary Leakage Core Exit Thermocouple Unidentified leakage Spill
ML25307A024	30 October 2025	Cook	Units 1 and 2 - 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	Units 1 and 2 - 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)
ML25307A053	30 October 2025	Cook	Units 1 and 2 - Updated Final Safety Analysis Report (Ufsar), Revision 33, Chapter 11, Tables	Boric Acid
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
ML25307A078	30 October 2025	Cook	Units 1 and 2 - 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
L-2025-170, Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1 and 2, Seabrook, Unit 1 - Fleet License Amendment Request 25-01, Adopt Topical Report AMS-TR-0720R2-A. Online Monitoring Program	29 October 2025	Saint Lucie Point Beach Seabrook Turkey Point	Units 3 and 4, St. Lucie, Units 1 and 2, Point Beach, Units 1 and 2, Seabrook, Unit 1 - Fleet License Amendment Request 25-01, Adopt Topical Report AMS-TR-0720R2-A. Online Monitoring Program	Safe Shutdown Shutdown Margin Packing leak Anticipated operational occurrence Post Accident Monitoring Surveillance Frequency Control Program Process Control Program Pressure Boundary Leakage Core Exit Thermocouple Unidentified leakage Power Uprate High range area radiation monitor
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
ML25290A083	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.2, Liquid Waste Management Systems	Grab sample Anticipated operational occurrence Spill
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
ML25290A080	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - 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
ML25290A078	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 11, Section 11.1, Source Terms	Stress corrosion cracking Fuel cladding Power Uprate Spill
ML25290A100	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 15, Section 15.7, Radioactive Release from Subsystems and Components	Earthquake Control Room Habitability Spill
ML25290A108	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - 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
ML25290A079	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - 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
ML25290A102	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - 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
ML25290A087	13 October 2025	Susquehanna	Susquehanna, Units 1 and 2 - Updated Final Safety Analysis Report, Rev. 72, Chapter 12, Section 12.2, Radiation Sources	Feedwater Heater Process Control Program Power Uprate
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
ML25283A007	9 October 2025	Point Beach	Units 1 and 2, 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	Units 1 and 2, 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	Units 3 and 4, 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	Units 3 and 4, 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	Units 3 and 4, Updated Final Safety Analysis Report, Chapter 14, Appendices 14A-14G	Shutdown Margin
L-2025-142, Units 3 and 4, Technical Requirements Manual (Trm), Revision 1	6 October 2025	Turkey Point	Units 3 and 4, Technical Requirements Manual (Trm), Revision 1	Safe Shutdown Boric Acid Shutdown Margin Grab sample Post Accident Monitoring Incorporated by reference Loss of Offsite Power Commercial Grade Recently irradiated fuel Power change Core Exit Thermocouple Metamic
ML25247A026	3 September 2025	Prairie Island	Nuclear Generating Plant, Units 1 and 2 - 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
ML25226A101	8 August 2025	Dresden	Nuclear Power Station, Units 1, 2, and 3, 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
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
ML25182A196	30 June 2025	Sequoyah	Nuclear Plant, Units 1 and 2, Revisions to the Technical Requirements Manual	Unanalyzed Condition Boric Acid Time of Discovery Shutdown Margin Grab sample Anticipated operational occurrence Safe Shutdown Earthquake Probabilistic Risk Assessment Operating Basis Earthquake Functionality Assessment Incorporated by reference Design basis earthquake Operability Determination Earthquake Maintenance Rule Program Core Exit Thermocouple Pressure Temperature Limits Report
ML25160A107	9 June 2025	Calvert Cliffs	Units 1 and 2, and Calvert Cliffs Independent Spent Fuel Storage Installation - Annual Radioactive Effluent Release Report	Offsite Dose Calculation Manual Annual Radioactive Effluent Release Report Annual Radiological Environmental Operating Report Process Control Program
ML25085A418	22 May 2025	05200050	SDAA - FSER Chapter 12 - Radiation Protection	Boric Acid High Radiation Area Ultimate heat sink Anticipated operational occurrence Probabilistic Risk Assessment Incorporated by reference Locked High Radiation Area Containment high range radiation monitor Exemption Request Earthquake Fuel cladding Pressure Boundary Leakage Overexposure Spill
ML25085A422	22 May 2025	05200050	SDAA - FSER Chapter 16 - Technical Specifications	Safe Shutdown Boric Acid Shutdown Margin High Radiation Area Ultimate heat sink Offsite Dose Calculation Manual Stroke time Anticipated operational occurrence Water Inventory Control Probabilistic Risk Assessment Incorporated by reference High Energy Line Break Missed surveillance Surveillance Frequency Control Program Open Phase Condition Local Leak Rate Testing Shift Technical Advisor Annual Radiological Environmental Operating Report Exemption Request Earthquake Power-Operated Valves Pressure Boundary Leakage Power change Unidentified leakage Operational leakage Loss of condenser vacuum Control Room Habitability Spent fuel rack Gas accumulation Operational convenience Leak-Before-Break Pressure Temperature Limits Report
ML25136A297	16 May 2025	Surry North Anna	Units 1 and 2 & Surry Power Station, Units 1 and 2 - 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	Nuclear Power Station, 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
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