| 05000220/FIN-2012005-03 | 31 December 2012 23:59:59 | Nine Mile Point | Assessment of Containment Leakage Due to Containment Isolation Valve Failure | Primary containment |
| 05000220/FIN-2013003-05 | 30 June 2013 23:59:59 | Nine Mile Point | Containment Leakage Exceeds Technical Specification 3.3.3 Limits | Reactor Coolant System
Primary containment |
| 05000244/LER-2006-003 | | Ginna | Inoperability of Two Channels of Flow Instrumentation | Reactor Protection System
Residual Heat Removal
Containment Spray |
| 05000247/LER-2006-002 | 24 July 2006 | Indian Point | Technical Specification Prohibited Condition for Two Inoperable Channels of PAM Instrumentation | |
| 05000247/LER-2010-008 | | Docket Number | Safety System Functional Failure Due to Inoperable Refueling Water Storage Tank Low- Low Level Alarms | |
| 05000247/LER-2017-002 | 6 February 2017
22 August 2017 | Indian Point | Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration
LER 17-002-00 for Indian Point, Unit 2 Regarding Auxiliary Feedwater Flow Indication Inoperable for Longer Than the Allowed Technical Specification Completion Time Due to Failure of Complete Restoration Following Calibration | Steam Generator
Feedwater
Auxiliary Feedwater
Decay Heat Removal |
| 05000261/FIN-2012002-02 | 31 March 2012 23:59:59 | Robinson | Inadequate Design Change Resulted in Interference and Inoperability of Containment Water Level Indication | Steam Generator
Decay Heat Removal |
| 05000261/FIN-2016008-03 | 30 September 2016 23:59:59 | Robinson | Failure to Comply with TS Requirements for Containment High Range Radiation Monitors | |
| 05000261/LER-2012-003 | | Docket Number | Plant Modification Interfered with the Operation of Containment Wide Range Level Indicator | Steam Generator
Reactor Coolant System
Service water
Residual Heat Removal |
| 05000261/LER-2013-001 | | Robinson | Non-Environmentally-Qualified Splice Rendered Post Accident Monitoring Instrumentation Channel Inoperable | |
| 05000261/LER-2015-002 | 18 March 2015 | Robinson | Pressurizer Power Operated Relief Valve (PORV) Limit Switches' Qualified Life Exceeded Due to Miscalculation | |
| 05000275/FIN-2017001-01 | 31 March 2017 23:59:59 | Diablo Canyon | Licensee-Identified Violation | Reactor Coolant System |
| 05000275/LER-2001-004 | | | | Steam Generator
Feedwater |
| 05000275/LER-2015-002 | 5 October 2015 | Diablo Canyon | Environmental Qualification of Wide Range Resistance Temperature Detectors Wiring Exceeded | Steam Generator
Reactor Coolant System
Decay Heat Removal |
| 05000282/FIN-2017004-02 | 31 December 2017 23:59:59 | Prairie Island | Licensee-Identified Violation | Main Steam Line |
| 05000286/LER-2009-009 | 14 October 2009 | Indian Point | Loss of Single Train Neutron Flux Detector N-38 Required for Plant Shutdown Remote From the Control Room Due to a Power Supply Failure | Reactor Protection System
Remote shutdown
Main Steam Line
Control Rod |
| 05000305/LER-2012-003 | | Docket | Nuclear Instruments Inoperable for Longer Period Than Allowed by Technical Specifications | Reactor Protection System
Control Rod |
| 05000305/LER-2012-008 | | Docket | Residual Heat Removal System Interlock Surveillance Not Met Due to Improper Setpoint | Reactor Coolant System
Residual Heat Removal
Emergency Core Cooling System
Decay Heat Removal
Containment Spray |
| 05000306/LER-2006-002 | | Docket Numberrev | | |
| 05000316/LER-1985-043, Resubmitted LER 85-043-00:on 851227,auxiliary Bldg Ventilation Grab Sample Not Obtained within Tech Spec Time Constraints.Caused by Personnel Error.Administrative Action Taken W/Individual Involved | 20 March 1986 | Cook | Resubmitted LER 85-043-00:on 851227,auxiliary Bldg Ventilation Grab Sample Not Obtained within Tech Spec Time Constraints.Caused by Personnel Error.Administrative Action Taken W/Individual Involved | |
| 05000323/LER-2001-003 | | | | |
| 05000338/LER-2002-001 | 25 June 2002 | Document Numbersequential Revisionmonth Day Year Year Month Day Year North Anna Power Station, Unit 2 05000-339Number Number | | |
| 05000352/FIN-2015001-03 | 31 March 2015 23:59:59 | Limerick | Operability of High Pressure Coolant Injection and Entries into Operational Conditions at Low Reactor Pressures with High Reactor Water Level Trip Actuated | High Pressure Coolant Injection
Emergency Core Cooling System |
| 05000352/LER-2013-002 | | Limerick | Condition That Could Have Prevented Fulfillment of the Offsite Power Safety Function | Emergency Diesel Generator
Emergency Core Cooling System |
| 05000353/LER-2014-005 | 24 April 2014 | Limerick | High Pressure Coolant Injection System Inoperability Due to ECCS Actuation Instrument Channel Setpoint Drift | High Pressure Coolant Injection
Reactor Core Isolation Cooling
Emergency Core Cooling System |
| 05000364/LER-1982-027, Corrected LER 82-027/03L-0:on 820622,steam Jet Air Ejector Noble Gas Activity Monitor Declared Inoperable When Pegged High While All Other Indications Normal.Caused by Faulty Detector.Detector Replaced & Declared Operable on 82 | 12 July 1982 | Farley | Corrected LER 82-027/03L-0:on 820622,steam Jet Air Ejector Noble Gas Activity Monitor Declared Inoperable When Pegged High While All Other Indications Normal.Caused by Faulty Detector.Detector Replaced & Declared Operable on 820622 | Steam Jet Air Ejector |
| 05000390/LER-2003-002 | | Watts Bar | Failure in Power Distribution Panel in Reactor Protection Panel 1-R-9 | Reactor Coolant System
Reactor Protection System
Containment Spray |
| 05000390/LER-2006-001 | 13 January 2006 | | Entrained Air in Essential Raw Cooling Water (ERCW) Piping | Steam Generator
Reactor Coolant System
Auxiliary Feedwater |
| 05000395/LER-1982-011, Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | 27 October 1982 | Summer | Forwards LER 82-011/03L-0.Detailed Event Analysis Encl | Remote shutdown |
| 05000395/LER-1982-028, Forwards LER 82-028/03L-0.Detailed Event Analysis Encl | 19 November 1982 | Summer | Forwards LER 82-028/03L-0.Detailed Event Analysis Encl | |
| 05000395/LER-1982-035, Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | 2 December 1982 | Summer | Forwards LER 82-035/03L-0.Detailed Event Analysis Encl | Remote shutdown |
| 05000395/LER-1982-036, Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | 2 December 1982 | Summer | Forwards LER 82-036/03L-0.Detailed Event Analysis Encl | Reactor Coolant System
Remote shutdown |
| 05000395/LER-1982-054, Forwards LER 82-054/03L-0.Detailed Event Analysis Encl | 6 January 1983 | Summer | Forwards LER 82-054/03L-0.Detailed Event Analysis Encl | Steam Generator |
| 05000423/LER-1990-022 | 16 July 1990 | Millstone | LER 90-022-00:on 900618,discovered That Hourly Fire Watch Patrol Had Not Been Established in Battery 4 Inverter Room. Caused by Procedural Deficiency.Hourly Fire Watch Established.Procedures revised.W/900716 Ltr | |
| 05000424/FIN-2014004-06 | 30 September 2014 23:59:59 | Vogtle | Licensee-Identified Violation | Decay Heat Removal |
| 05000424/LER-2006-002 | 26 July 2006 | Vogtle | Three Technical Specification (TS) instruments were determined to be in a condition which was prohibited by TS. | Steam Generator
Reactor Coolant System
Auxiliary Feedwater |
| 05000482/FIN-2017007-02 | 30 June 2017 23:59:59 | Wolf Creek | Licensee-Identified Violation | |
| 05000482/LER-2003-002 | 25 March 2003 | Wolf Creek | REACTOR VESSEL LEVEL INDICATING SYSTEM INOPERABLE FOR PERIOD LONGER THAN ALLOWED BY TECH. SPEC. | Reactor Coolant System |
| 05000499/LER-2002-001 | 7 January 2001 | Texas Unit 2 -South | 1 OF 3 | |
| 05000528/LER-2011-005 | 22 November 2011 | | Unit 1 Manual Reactor Trip due to Slipped Control Element Assemblies | Steam Generator
Reactor Coolant System
Reactor Protection System
Auxiliary Feedwater |
| 0CAN089607, Semi-Annual Radioactive Effluent Release Rept for First & Second Quarters of 1996 | 30 August 1996 | Arkansas Nuclear | Semi-Annual Radioactive Effluent Release Rept for First & Second Quarters of 1996 | Steam Generator
Reactor Coolant System
Feedwater
Main Steam Safety Valve
Control Rod
Main Steam |
| 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation | 31 October 2022 | Arkansas Nuclear | Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Main Turbine
Emergency Core Cooling System
Decay Heat Removal
Control Rod |
| 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 | 11 January 2024 | Arkansas Nuclear | Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Control Room Emergency Ventilation
Main Steam Line
Main Steam
Containment Spray |
| 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 | 5 April 2023 | Arkansas Nuclear | License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 | Steam Generator
Reactor Coolant System
Feedwater
Service water
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Main Turbine
Shutdown Cooling
HVAC
Control Room Emergency Ventilation
Main Steam Safety Valve
Emergency Core Cooling System
Decay Heat Removal
Main Steam Line
Containment Spray |
| 3F0485-20, Special Rept 85-01:on 850317,during Performance of Refueling Interval Surveillance,All Three Triaxial Peak Accelographs Required by Tech Specs Discovered Inoperable.Cause Undetermined.Accelographs Will Be Repaired | 26 April 1985 | Crystal River | Special Rept 85-01:on 850317,during Performance of Refueling Interval Surveillance,All Three Triaxial Peak Accelographs Required by Tech Specs Discovered Inoperable.Cause Undetermined.Accelographs Will Be Repaired | Steam Generator |
| 3F0502-06, Technical Specifications Bases Control Program | 31 May 2002 | Crystal River | Technical Specifications Bases Control Program | Steam Generator
Reactor Coolant System
Feedwater
Service water
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Main Turbine
Control Room Emergency Ventilation
Circulating Water System
Main Steam Safety Valve
Remote shutdown
Emergency Core Cooling System
Emergency Feedwater Initiation and Control
Decay Heat Removal
Main Steam Line
Main Condenser
Control Rod
Main Steam
Containment Spray |
| 3F0591-02, Special Rept 91-001:on 910320,waste Gas Analyzer Removed from Svc to Allow Isolation of Waste Gas Compressor from Maint.Moisture Discovered in Sample Tubing.Work Request to Correct Moisture Intrusion in Analyzer Sample Lines Written | 1 May 1991 | Crystal River | Special Rept 91-001:on 910320,waste Gas Analyzer Removed from Svc to Allow Isolation of Waste Gas Compressor from Maint.Moisture Discovered in Sample Tubing.Work Request to Correct Moisture Intrusion in Analyzer Sample Lines Written | |
| 3F0687-16, Forwards Control Room Habitability Evaluation Rept.Rept Reflects Post Refuel VI Mod Outage Scheduled to Begin Sept 1987 Per NUREG 0737,Item III.D.3.4.Items from 870609 NRC Meeting Addressed | 30 June 1987 | Crystal River | Forwards Control Room Habitability Evaluation Rept.Rept Reflects Post Refuel VI Mod Outage Scheduled to Begin Sept 1987 Per NUREG 0737,Item III.D.3.4.Items from 870609 NRC Meeting Addressed | Control Room Envelope |
| 3F0692-10, Special Rept 92-02:on 920514,waste Gas Decay Tank Hydrogen & Oxygen Monitoring Channels Removed from Svc & Not Returned to Operable Status within 14 Days.Caused by Need to Facilitate Maint.Ts Amend Will Be in Place by Sept 1992 | 12 June 1992 | Crystal River | Special Rept 92-02:on 920514,waste Gas Decay Tank Hydrogen & Oxygen Monitoring Channels Removed from Svc & Not Returned to Operable Status within 14 Days.Caused by Need to Facilitate Maint.Ts Amend Will Be in Place by Sept 1992 | |
| 3F1093-12, Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS | 15 October 1993 | Crystal River | Proposed Tech Specs Reflecting Results of Numerous Meetings Re Improved TS | Steam Generator
Reactor Coolant System
Feedwater
Reactor Protection System
Emergency Diesel Generator
Main Steam Isolation Valve
Auxiliary Feedwater
Main Turbine
Control Room Emergency Ventilation
Main Steam Safety Valve
Remote shutdown
Emergency Core Cooling System
Emergency Feedwater Initiation and Control
Decay Heat Removal
Main Steam Line
Control Rod
Main Steam
Emergency Feedwater System |