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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
- PNO-II-08-007, Tennessee Valley Authority, Unit 1 Shutdown Due to Main Generator Stator Cooling Water Leak + (PNO-II-08-007: Tennessee Valley Authority, Unit 1 Shutdown Due to Main Generator Stator Cooling Water Leak)
- PNO-II-08-008, McGuire, Unit 1, Shutdown Due to Loss of 1B Reactor Coolant Pump + (PNO-II-08-008: McGuire, Unit 1, Shutdown Due to Loss of 1B Reactor Coolant Pump)
- PNO-II-08-009, Turkey Point, Unit 4, Shutdown to Repair Piping Leak + (PNO-II-08-009 - Turkey Point, Unit 4, Shutdown to Repair Piping Leak)
- PNO-II-08-010, Florida Power and Light Company, Unit 1 Shutdown Due to Out of Specification Steam Generator Water Chemistry + (PNO-II-08-010 - Florida Power and Light Company, Unit 1 Shutdown Due to Out of Specification Steam Generator Water Chemistry)
- PNO-II-09-006, Fire within Protected Area of V. C. Summer Nuclear Station + (PNO-II-09-006 - Fire within Protected Area of V. C. Summer Nuclear Station)
- PNO-II-10-001, Catawba Nuclear Station Unit 1, RCS Pressure Boundary Leakage Identified on RTD Weld + (PNO-II-10-001, Catawba Nuclear Station Unit 1, RCS Pressure Boundary Leakage Identified on RTD Weld)
- PNO-II-10-002, H.B. Robinson Steam Electric Plant - Fires Affecting Safety Related Equipment + (PNO-II-10-002: H.B. Robinson Steam Electric Plant - Fires Affecting Safety Related Equipment)
- PNO-II-10-004, Oconee Unit 3 - Notification of Unusual Event Due to Loss of Annunciators + (PNO-II-10-004 - Oconee Unit 3 - Notification of Unusual Event Due to Loss of Annunciators)
- PNO-II-10-005, Hydrofluoric Acid Release at the Honeywell Uranium Conversion Facility + (PNO-II-10-005, Hydrofluoric Acid Release at the Honeywell Uranium Conversion Facility)
- PNO-II-11-002, Notification of Unusual Event Due to Loss of Offsite Power + (PNO-II-11-002: Notification of Unusual Event Due to Loss of Offsite Power)
- PNO-II-11-002A, Surry, Units 1 and 2, Notification of Unusual Event Due to Loss of Offsite Power + (PNO-II-11-002A - Surry, Units 1 and 2, Notification of Unusual Event Due to Loss of Offsite Power)
- PNO-II-11-003, Preliminary Notification of Event or Unusual Occurence + (PNO-II-11-003 - Preliminary Notification of Event or Unusual Occurence)
- PNO-II-11-003A, Preliminary Notification of Unusual Event Due to Loss of Offsite Power (Update) + (PNO-II-11-003A - Preliminary Notification of Unusual Event Due to Loss of Offsite Power (Update))
- PNO-II-11-005, North Anna, Emergency Declarations Due to Seismic Event + (PNO-II-11-005: North Anna, Emergency Declarations Due to Seismic Event)
- PNO-II-11-006, Preliminary Notification of Event or Unusual Occurence (Brunswick Unit 2) + (PNO-II-11-006 - Preliminary Notification of Event or Unusual Occurence (Brunswick Unit 2))
- PNO-II-12-001, Notification of Unusual Event Due to Loss of Offsite Power (Catawba) + (PNO-II-12-001 - Notification of Unusual Event Due to Loss of Offsite Power (Catawba))
- PNO-II-12-003, Brunswick Steam Electric Plant, Unit 1, Unplanned Shutdown Greater than 72 Hours on September 16, 2012, Due to Potential 1B Recirculation Pump Seal Failure + (PNO-II-12-003 - Brunswick Steam Electric Plant, Unit 1, Unplanned Shutdown Greater than 72 Hours on September 16, 2012, Due to Potential 1B Recirculation Pump Seal Failure)
- PNO-II-12-004, Shutdown Greater than 72 Hours Due to Decreased Unit 2 a Reactor Coolant Pump (RCP) 1 Seal Leakoff Flow + (PNO-II-12-004 - Shutdown Greater than 72 Hours Due to Decreased Unit 2 a Reactor Coolant Pump (RCP) 1 Seal Leakoff Flow)
- PNO-II-12-004A, Update - Shutdown Greater than 72 Hours Due to Decreased Unit 2 Reactor Coolant Pump (RCP) 1 Seal Leakoff Flow + (PNO-II-12-004A - Update - Shutdown Greater than 72 Hours Due to Decreased Unit 2 Reactor Coolant Pump (RCP) 1 Seal Leakoff Flow)
- PNO-II-12-004, A - Update - Shutdown Greater than 72 Hours Due to Decreased Unit 2 Reactor Coolant Pump (RCP) 1 Seal Leakoff Flow + (PNO-II-12-004A - Update - Shutdown Greater than 72 Hours Due to Decreased Unit 2 Reactor Coolant Pump (RCP) #1 Seal Leakoff Flow)
- PNO-II-13-001, Unplanned Shutdown Greater than 72 Hours Due to High Reactor Coolant Pump Seal Leak Off Rate + (PNO-II-13-001 - Unplanned Shutdown Greater than 72 Hours Due to High Reactor Coolant Pump Seal Leak Off Rate)
- PNO-II-13-003A, Update - Unplanned Shutdown Greater than 72 Hours Due to Closure of B Train Steam Generator Main Steam Isolation Valve + (PNO-II-13-003A: Update - Unplanned Shutdown Greater than 72 Hours Due to Closure of B Train Steam Generator Main Steam Isolation Valve)
- PNO-II-13-004, Unplanned Shutdown Greater than 72 Hours Due to Reactor Feedwater Heater Level Control Line Leak + (PNO-II-13-004 - Unplanned Shutdown Greater than 72 Hours Due to Reactor Feedwater Heater Level Control Line Leak)
- PNO-II-13-005, Notification of Unusual Event Due to Security Incident + (PNO-II-13-005-Notification of Unusual Event Due to Security Incident)
- PNO-II-13-008A, Update: Oconee Unit 1 Shutdown Due to Reactor Coolant System (RCS) Pressure Boundary Leakage + (PNO-II-13-008A: Update: Oconee Unit 1 Shutdown Due to Reactor Coolant System (RCS) Pressure Boundary Leakage)
- PNO-II-14-001, Harris Unit 1 Shutdown and Alert Declared Due to Fire + (PNO-II-14-001- Harris Unit 1 Shutdown and Alert Declared Due to Fire)
- PNO-II-14-004, H. B. Robinson Unit 2 Shutdown Due to Steam Generator Tube Leak + (PNO-II-14-004: H. B. Robinson Unit 2 Shutdown Due to Steam Generator Tube Leak)
- ML14069A350 + (PNO-II-14-004: Robinson, Unit 2 Shutdown Due to Steam Generator Tube Leak)
- PNO-II-14-005, Shutdown Greater than 72 Hours Due to Leaking Pressurizer Safety Valve + (PNO-II-14-005 - Shutdown Greater than 72 Hours Due to Leaking Pressurizer Safety Valve)
- ML14217A390 + (PNO-II-14-006 - Shutdown Greater than 72 Hours Due to Increased Primary Coolant Leakage)
- PNO-II-14-006, A - Shutdown Greater than 72 Hours Due to Increased Primary Coolant Leakage + (PNO-II-14-006A - Shutdown Greater than 72 Hours Due to Increased Primary Coolant Leakage)
- PNO-II-15-001, St. Lucie, Unit 2, Shutdown Greater than 72 Hours Due to Condenser Tube Leak + (PNO-II-15-001 - St. Lucie, Unit 2, Shutdown Greater than 72 Hours Due to Condenser Tube Leak)
- PNO-II-16-001, Oconee Unit 1 Shutdown Greater than 48 Hours Due to Fire/Explosion in the Main Transformer + (PNO-II-16-001 - Oconee Unit 1 Shutdown Greater than 48 Hours Due to Fire/Explosion in the Main Transformer)
- PNO-II-17-002, Watts Bar Unit 2 Shutdown Due to Condenser Failure + (PNO-II-17-002 - Watts Bar Unit 2 Shutdown Due to Condenser Failure)
- PNO-II-19-001, Browns Ferry Unplanned Shutdown Greater than 72 Hours Following a Loss of Offsite Power and Subsequent Reactor Scram + (PNO-II-19-001 - Browns Ferry Unplanned Shutdown Greater than 72 Hours Following a Loss of Offsite Power and Subsequent Reactor Scram)
- ML042920310 + (PNO-II-2004-010 - Shutdown of McGuire, Unit 1 for Greater than 72 Hours)
- PNO-II-75-005, on 751219,J Hollis,Epa Discussed Draft Press Release to Be Made on 751223,stating EPA Position on Paper Presented by L Meyer at Iaea/Erda 751117-21 Intl Symposium on Transuranium Nuclides in Environ + (PNO-II-75-005:on 751219,J Hollis,Epa Discussed Draft Press Release to Be Made on 751223,stating EPA Position on Paper Presented by L Meyer at Iaea/Erda 751117-21 Intl Symposium on Transuranium Nuclides in Environ)
- PNO-II-78-147, on 780818,one of Six Air Compressors Suffered Massive Failure Resulting in Rapid Loss of Control Air Pressure to All Three Units.Caused by Large Hole in Cylinder Head of Failed Compressor.Compressor Was Isolated + (PNO-II-78-147:on 780818,one of Six Air Compressors Suffered Massive Failure Resulting in Rapid Loss of Control Air Pressure to All Three Units.Caused by Large Hole in Cylinder Head of Failed Compressor.Compressor Was Isolated)
- PNO-II-79-001B, licensee Reported That Cause of Overpressurization of Vol Control Tank Was Manual Defeat of Automatic Level Control Sys.Control Switch Was Physically Blocked + (PNO-II-79-001B:licensee Reported That Cause of Overpressurization of Vol Control Tank Was Manual Defeat of Automatic Level Control Sys.Control Switch Was Physically Blocked)
- PNO-II-79-001C, on 791005,completed Investigation Into Cause of Overpressurization of Vol Control Tank & Release of Radioactive Gases Into Bldg.Caused by High Influx of Water from Primary Sys + (PNO-II-79-001C:on 791005,completed Investigation Into Cause of Overpressurization of Vol Control Tank & Release of Radioactive Gases Into Bldg.Caused by High Influx of Water from Primary Sys)
- PNO-II-79-003, on 790923 & 25,radioactive Liquid Waste Discharges Were Made Above Max Permissible Concentration. Caused by Inadequate Dilution Water Flow,Because Keowee Hydro Units Were Out of Svc + (PNO-II-79-003:on 790923 & 25,radioactive Liquid Waste Discharges Were Made Above Max Permissible Concentration. Caused by Inadequate Dilution Water Flow,Because Keowee Hydro Units Were Out of Svc)
- PNO-II-79-005, on 791008,120 Cubic Ft of Gas Containing 17 Mci of Kr-85 Leaked from Waste Gas Sys Valve Into Auxiliary Bldg.Gas Released Into Environ Via Auxiliary Bldg Ventilation Sys.Caused by Maint Work on Valve + (PNO-II-79-005:on 791008,120 Cubic Ft of Gas Containing 17 Mci of Kr-85 Leaked from Waste Gas Sys Valve Into Auxiliary Bldg.Gas Released Into Environ Via Auxiliary Bldg Ventilation Sys.Caused by Maint Work on Valve)
- PNO-II-79-006, on 791006,during Planned Maint on Secondary Steam Sys,Main Steam Valve to Moisture Separator Reheater Stuck Open.Caused by Stray Hex Nut from Main Steam Line Check Valves.All Check Valves Inspected + (PNO-II-79-006:on 791006,during Planned Maint on Secondary Steam Sys,Main Steam Valve to Moisture Separator Reheater Stuck Open.Caused by Stray Hex Nut from Main Steam Line Check Valves.All Check Valves Inspected)
- PNO-II-79-007, on 791007,supporting Chain Holding Tube Bundle from RHR Sys Heat Exchanger Broke,Dropping Bundle Approx 20 Ft Back Into Shell of Heat Exchanger.Rhr Sys Not Required for Operation Prior to Reactor Startup + (PNO-II-79-007:on 791007,supporting Chain Holding Tube Bundle from RHR Sys Heat Exchanger Broke,Dropping Bundle Approx 20 Ft Back Into Shell of Heat Exchanger.Rhr Sys Not Required for Operation Prior to Reactor Startup)
- PNO-II-79-008, on 791010,annual Exercise Will Be Conducted at Facility to Test State of Sc Emergency Plan + (PNO-II-79-008:on 791010,annual Exercise Will Be Conducted at Facility to Test State of Sc Emergency Plan)
- PNO-II-79-009, on 791008,high Differential Pressure Observed on Lower Seal of Reactor Coolant Pump 12B.Caused by Defective Pump Seal.Pump Seal Replacement Underway + (PNO-II-79-009:on 791008,high Differential Pressure Observed on Lower Seal of Reactor Coolant Pump 12B.Caused by Defective Pump Seal.Pump Seal Replacement Underway)
- PNO-II-79-010, on 791015,util Announced That Study Has Been Commisioned to Determine Feasibility of Converting Facilities to Coal Fired Units,Due to Uncertainty of Us Commitment to Nuclear Power + (PNO-II-79-010:on 791015,util Announced That Study Has Been Commisioned to Determine Feasibility of Converting Facilities to Coal Fired Units,Due to Uncertainty of Us Commitment to Nuclear Power)
- PNO-II-79-011, on 791016,while Returning Low Pressure Injection B Train to Svc,About 2000 Gallons of Reactor Coolant Spilled Through Partially Opened Vent Valve Into West Penetration Room.Facility Shut Down for Insp & Repair + (PNO-II-79-011:on 791016,while Returning Low Pressure Injection B Train to Svc,About 2000 Gallons of Reactor Coolant Spilled Through Partially Opened Vent Valve Into West Penetration Room.Facility Shut Down for Insp & Repair)
- PNO-II-79-012, on 791019,high Steam Line Radiation Signal Was Received,Closing Main Steam Isolation Valves & Shutting Down Reactor.Low Level Airborne Radioactivity Detected in Bldg.Reactor Is Cooling Down for Investigation + (PNO-II-79-012:on 791019,high Steam Line Radiation Signal Was Received,Closing Main Steam Isolation Valves & Shutting Down Reactor.Low Level Airborne Radioactivity Detected in Bldg.Reactor Is Cooling Down for Investigation)
- PNO-II-79-012A, on 791019,reactor Shut Down & Coded at 20 F Per Hour Via Reactor Core Isolation Cooling Sys. Reactor Bldg Evacuated W/Gross Beta Gamma Airborne Activities About 30% of Max Permissible Concentration + (PNO-II-79-012A:on 791019,reactor Shut Down & Coded at 20 F Per Hour Via Reactor Core Isolation Cooling Sys. Reactor Bldg Evacuated W/Gross Beta Gamma Airborne Activities About 30% of Max Permissible Concentration)
- PNO-II-79-013, meeting Conducted by 11 Electricians W/Local TVA Station Re Mgt Inability to Control Tool Theft.Locked Boxes Broken Into at Site & Tools Removed + (PNO-II-79-013:meeting Conducted by 11 Electricians W/Local TVA Station Re Mgt Inability to Control Tool Theft.Locked Boxes Broken Into at Site & Tools Removed)