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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
List of results
- ML031750549 + (Re Public Meeting 08/25/03)
- ML032240605 + (Re Public Meeting Concerning Source Term Reduction Program)
- ML033430065 + (Re Public Meeting Notice Region III Office to Discuss Licensee Improvement Plans Relating to Corrective Action Program Implementation)
- ML032930100 + (Re Public Meeting to Discuss Operation Above the Licensed Thermal Power Limits at the Byron Station)
- ML040300958 + (Re Public Meeting to Discuss Prairie Island and Monticello 2003 NRC Initial Operator License Examination High Failure Rates and Training Program Concerns)
- ML050840198 + (Re Public Meeting to Discuss the NRCs License Renewal Inspection at Point Beach)
- ML040300960 + (Re Public Meeting to Discuss the Prairie Island and Monticello 2003 NRC Initial Operator License Examinaton High Failure Rates and Training Program Concerns)
- 05000318/LER-2002-001, Re Pump Flexible Drive Gear Wear Causes Emergency Diesel Generator Inoperability + (Re Pump Flexible Drive Gear Wear Causes Emergency Diesel Generator Inoperability)
- 05000498/LER-2006-005, Re Quadrant Power Tilt Ratio Surveillance Not Performed as Required by TS 3.3.1 Action 2 + (Re Quadrant Power Tilt Ratio Surveillance Not Performed as Required by TS 3.3.1 Action 2)
- ML18241A262 + (Re Question NRO Schedule Milestones for Vogtle LAR 17-037)
- 05000293/LER-2004-004, Re RCIC System Declared Inoperable During Surveillance Testing Due to Flow Controller Potentiometer Oxidation + (Re RCIC System Declared Inoperable During Surveillance Testing Due to Flow Controller Potentiometer Oxidation)
- 05000352/LER-2020-002, Re RCIC Were Not Un-Isolated During Startup Resulting in Technical Specification Violations + (Re RCIC Were Not Un-Isolated During Startup Resulting in Technical Specification Violations)
- 05000530/LER-2003-002, Re RCS Pressure Boundary Leakage Caused by Degraded Inconel Alloy 600 Components + (Re RCS Pressure Boundary Leakage Caused by Degraded Inconel Alloy 600 Components)
- 05000530/LER-2004-001, Re RCS Pressure Boundary Leakage Caused by Degraded Alloy 600 Component + (Re RCS Pressure Boundary Leakage Caused by Degraded Alloy 600 Component)
- 05000280/LER-2005-002, Re Radiation Monitors Inoperable Due to Condensation - Voluntary Special Report + (Re Radiation Monitors Inoperable Due to Condensation - Voluntary Special Report)
- ML031350740 + (Re Radiation Protection Inspection 5/19/03)
- 05000282/LER-2009-009, Re Radioactive Source Inventory Discrepancy + (Re Radioactive Source Inventory Discrepancy)
- ML20274A038 + (Re Re Re Repairs to Leak at the Elbow Sownstream of 1CC-0277 CS PMP 1-011-03 SL Clr CCW Ret)
- ML042310120 + (Re Re-Schedule of Initial Operator License Re-Take Examination)
- ML041200575 + (Re Re-scheduling of Initial Operator License Examinations)
- 05000454/LER-2004-001, Re Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication + (Re Reactor Containment Fan Coolers Flow Rates Below Technical Specification Requirements Due to Inaccurate Flow Indication)
- 05000400/LER-2001-004, Re Reactor Coolant Loops Made 4 Technical Specification Violation + (Re Reactor Coolant Loops Made 4 Technical Specification Violation)
- 05000293/LER-2003-006, Re Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation + (Re Reactor Coolant Pressure Boundary Leakage Due to Reactor Vessel Nozzle Weld Crack Propagation)
- ML033370097 + (Re Reactor Coolant Pump Leakage - Letter to Individual)
- ML033370070 + (Re Reactor Coolant Pump Leakage - Letter to Mr. Gunter of Reactor Watchdog Project, Nuclear Information and Resource Service)
- 05000369/LER-2005-001, Re Reactor Coolant System Leakage Detection Instrumentation Inoperable + (Re Reactor Coolant System Leakage Detection Instrumentation Inoperable)
- 05000414/LER-2004-001, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators + (Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators)
- 05000482/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines + (Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks in Steam Generator Lower Head Bowl Drain Lines)
- 05000336/LER-2005-002, Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve + (Re Reactor Coolant System Pressure Boundary Leakage from PWSCC in a Pressurizer Heater Sleeve)
- 05000266/LER-2020-001, Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications + (Re Reactor Coolant System Pressure Boundary Leak on Steam Generator Bowl Drain Line Results in Operation Prohibited by Technical Specifications)
- 05000318/LER-2013-001, Re Reactor Coolant System Pressure Boundary Leakage in Valve Leakoff Line Weld + (Re Reactor Coolant System Pressure Boundary Leakage in Valve Leakoff Line Weld)
- 05000373/LER-2005-002, Re Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum Pump Discharge Check Valve 1E51-F028 Failed Local Leak Rate Test + (Re Reactor Core Isolation Cooling (RCIC) Barometric Condenser Vacuum Pump Discharge Check Valve 1E51-F028 Failed Local Leak Rate Test)
- 05000373/LER-2003-003, Re Reactor Core Isolation Cooling High Steam Flow Isolation Differential Pressure Switches Failed Due to Torn Diaphragm + (Re Reactor Core Isolation Cooling High Steam Flow Isolation Differential Pressure Switches Failed Due to Torn Diaphragm)
- 05000325/LER-2005-002, Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown + (Re Reactor Core Isolation Cooling System Manual Actuation During Plant Shutdown)
- 05000529/LER-2006-005, Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component + (Re Reactor Head Vent Axial Indications Caused by Degraded Alloy 600 Component)
- 05000423/LER-2007-003, Re Reactor Head Vent Valve Circuits Not Isolated from Control Room During Fire Scenario + (Re Reactor Head Vent Valve Circuits Not Isolated from Control Room During Fire Scenario)
- 05000331/LER-2003-003, Re Reactor Mode Change with LCO in Effect in Violation of Technical Specification 3.0.4 + (Re Reactor Mode Change with LCO in Effect in Violation of Technical Specification 3.0.4)
- 05000454/LER-2011-002, Re Reactor Pressure Vessel Head Penetration Nozzle Weld Flaws Attributed to Primary Water Stress Corrosion Cracking + (Re Reactor Pressure Vessel Head Penetration Nozzle Weld Flaws Attributed to Primary Water Stress Corrosion Cracking)
- 05000255/LER-2006-004, Re Reactor Protection System Actuation + (Re Reactor Protection System Actuation)
- 05000483/LER-2002-004, Re Reactor Protection System Actuation While Performing Main Turbine Shell Warming in Mode 4 + (Re Reactor Protection System Actuation While Performing Main Turbine Shell Warming in Mode 4)
- 05000260/LER-2005-003, Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown + (Re Reactor Protection System Actuation from Scram Discharge Volume High Level While Shutdown)
- 05000443/LER-2005-005, Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6 + (Re Reactor Protection System Actuation on Low Steam Generator Low Level in Mode 6)
- 05000249/LER-2002-006, Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure + (Re Reactor Recirculation Loop a Sensing Line Socket Weld Failure)
- 05000265/LER-2001-001-01, Re Reactor Scram Due to Failure of Main Power Transformer + (Re Reactor Scram Due to Failure of Main Power Transformer)
- 05000416/LER-2002-003, Re Reactor Scram Due to Loss of Service Transformer 21 + (Re Reactor Scram Due to Loss of Service Transformer 21)
- 05000397/LER-2007-004, Re Reactor Scram Due to Tripped Condensate Booster Pump + (Re Reactor Scram Due to Tripped Condensate Booster Pump)
- 05000397/LER-2009-001, Re Reactor Scram Due to Turbine Control System Trip Header Depressurization + (Re Reactor Scram Due to Turbine Control System Trip Header Depressurization)
- 05000397/LER-2005-004, Re Reactor Scram During Plant Startup Due to Reactor Feedwater Pump Trip + (Re Reactor Scram During Plant Startup Due to Reactor Feedwater Pump Trip)
- 05000387/LER-2006-004-01, Re Reactor Scram During Transfer of RPS Power Supplies + (Re Reactor Scram During Transfer of RPS Power Supplies)
- 05000293/LER-2007-005, Re Reactor Scram Resulting from Low Vacuum Turbine Trip + (Re Reactor Scram Resulting from Low Vacuum Turbine Trip)
- 05000260/LER-2004-002, Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2 + (Re Reactor Scram from Main Turbine Trip from Loss of All Speed Feedback. Also Involved Is Browns Ferry Unit 2)