L-23-073, Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-23-016, Twenty-Eighth Refueling Outage Inservice Inspection Summary Report
L-22-193, Request for Exemption from Specific Provisions in 10 CFR 50 Appendix H
L-22-286, Supplement to Request for an Amendment to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time
L-23-058, 180-Day Steam Generator Tube Inspection Report
L-23-036, Report of Facility Changes, Tests and Experiments
L-23-053, 2022 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations
L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations
L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological
L-23-125, Cycle 24 Core Operating Limits Report
L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report
L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report
L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports
L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models
L-24-164, BV-2, Post Accident Monitor Report
L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule
L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair
L-24-082, Withdrawal of Exemption Request
L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions
L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)
L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations
L-24-021, Cycle 30 Core Operating Limits Report
L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report
L-23-241, Submittal of the Updated Final Safety Analysis Report, Revision 27
05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function
05000412/LER-2023-004, Condition Prohibited by Technical Specification and Loss of Safety Function Due to Emergency Diesel Generator Lube Oil Contamination by Fuel Oil
05000412/LER-2023-003, Missile Barrier Door Left Open Resulting in a Loss of Safety Function
05000412/LER-2023-002, Automatic Actuation of Auxiliary Feedwater System
05000412/LER-2023-001, Indications Identified During Reactor Vessel Head Inspection
L-24-254, Cycle 25 Core Operating Limits Report
L-25-024, 10 CFR 50.55a Request BV-ISI-2025-01, Quench Spray Pinhole Leak
L-25-049, Submittal of Report of Facility Changes, Tests and Experiments
L-25-068, Twenty-Fourth Refueling Outage Inservice Inspection Summary Report
L-25-050, Report of Facility Changes, Tests and Experiments
05000412/LER-2025-001, Automatic Reactor Trip and Automatic Actuation of the Auxiliary Feedwater System Due to Loose Feedback Linkage on Feedwater Regulating Valve
L-23-087, Supplement to Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair (L-2023-LLA-0027)
L-23-086, Response to Request for Additional Information for Emergency License Amendment Request for Technical Specification 3.5.2 Regarding One-Time Action for Valve Leak Repair
L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References
L-23-198, Independent Spent Fuel Storage Installation - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control
05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping
05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation
05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification
L-25-029, Steam Generator Inspection Reports - Fall 2024 Refueling Outage
L-25-084, Notification of Deviation from MRP-227, Revision 1-A, Section 7.5 Regarding the Disposition of Examination Results for Thermal Shield Flexures
L-25-074, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models
L-25-083, Containment Liner Random and Non-Random Examinations Report
L-25-107, Response to NRC Regulatory Issue Summary 2025-03, Preparation and Scheduling of Operator Licensing Examinations
L-25-096, Submittal of 2024 Annual Radioactive Effluent Release Report, 2024 Annual Radiological Environmental Operating Report, (Non-Radiological)
L-25-072, Day Steam Generator Tube Inspection Report
L-25-151, Spent Fuel Storage Cask Registration
L-25-189, Submittal of Post Accident Monitor Report
L-25-757, Response to Request for Additional Information (RAI) for 180-Day Steam Generator Tube Inspection Report
L-25-135, License Amendment Request to Adopt TSTF-258-A, Revision 4, Regarding Changes to Technical Specification Section 5.7, High Radiation Area