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 Issue dateTitleTopic
PNO-IV-98-025, on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel16 June 1998PNO-IV-98-025:on 980615,WNP-2 Initiated Plant Shutdown as Result of Traversing Incore Probe That Could Not Be Moved. Licensee Observed Some Drive Cable Damage & Cable Wrapped Around Some Components Under Reactor Vessel
PNO-IV-95-007, on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event21 February 1995PNO-IV-95-007:on 950218,plant Reactor Scrammed from 80% Power Due to Turbine Trip.News Media Was Notified of Event
PNO-V-93-021, on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant2 December 1993PNO-V-93-021:on 931201,chemical Spill in Radwaste Building. Caused by Addition of Oxidizing Agent,Hydrogen Peroxide. Employees Working on Floor Were Moved to Different Part of Plant
PNO-V-93-004, on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release Issued21 January 1993PNO-V-93-004:on 930121,automatic Reactor Scram Received Due to Low Level in Reactor Pressure Vessel.Licensee Estimates That Plant Will Be Shut Down for Repairs & Maint for 3 to 5 Days.Inspector Onsite During Event.Press Release IssuedReactor Vessel Water Level
PNO-V-92-024, on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve13 July 1992PNO-V-92-024:on 920711,while Retesting Main Steam SRV at Approx 14% Reactor Power,Srv 3B Opened When Operated from Control Room But Would Not Close.Reactor Operators Reduced Reactor Pressure in Effort to Reseat Valve
PNO-V-91-031, on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed19 November 1991PNO-V-91-031:on 911119,licensee Declared Unusual Event Following Low Reactor Pressure Vessel Level Condition W/Eccs Injecting.Reactor Tripped on Turbine Trip.All ECCS Sys Responded as Designed
ML20203C22314 June 1991PNO-V-91-04B on 910614,Region V Issued Rev 3 to CAL Concerning Actions to Be Taken by WPPSS Subsequent to Unsuccessful Simulator Requalification Retake Exam Performed 910605-06
PNO-V-90-049, on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion7 December 1990PNO-V-90-049:on 901207,w/plant Operating at Full Power, Explosion Occurred in Area of B Phase Insulator of Plant Main Transformer,Which Caused Turbine & Reactor Trip.Unusual Event Was Declared Due to Explosion
PNO-V-90-041, on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation25 October 1990PNO-V-90-041:on 901024,licensee Declared Unusual Event After Determining That Vital & non-vital Instrument Power Supplies Interconnected Through Certain Sys Instrumentation
PNO-IV-90-028, on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation4 June 1990PNO-IV-90-028:on 900603,while Attempting to Energize Station Normal Auxiliary Power Transformers,Short Circuit Failure in Bus Works for 25 Kv Sys.Fire Brigade Responded But No Fire Was Reported.Event Under Investigation
PNO-V-88-054, on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 Gpm24 August 1988PNO-V-88-054:on 880824,licensee Declared Unusual Event as Result of Increase in Unidentified Leakage to Level Above TS Limit of 5 Gpm.Reactor Was Later Shutdown & Unidentified Leakage Rate Had Correspondingly Decreased to Approx 8 GpmGrab sample
PNO-V-88-013, on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation16 February 1988PNO-V-88-013:on 880213,plant Experienced Condenser Tube Failure & Shut Down Manually Scramming Plant from 35% Power. on 880214,reactor Bldg Air Supply Fan Started W/O Trip Circuit Being Energized.Cause Under Investigation
PNO-V-87-079, on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & Shut27 November 1987PNO-V-87-079:on 871126,digital Voltmeter Connected to Wrong Terminal Resulting in Inadvertent Opening of Safety Relief Valve 2D.Caused by Technician Error.Position of Safety Relief Valve Identified & ShutReactor Vessel Water Level
ML20236G37926 October 1987PNS-V-87-008:on 871024,licensed Plant Operator Reportedly Arrested by Kennewick City Police Dept & Charged W/Discharge of Firearm within City Limits & Reckless Endangerment. Licensee Suspended Employee Unescorted Access to Plant
PNO-V-87-024A, on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 87032425 March 1987PNO-V-87-024A:on 870322,reactor Manually Tripped Due to Loss of Feedwater.Caused by Mechanical Failure of 1/4-amp Fuse in Feedwater Control Sys.Rcic Sys Operated Properly.Plant Restarted on 870324
PNO-V-87-024, on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending23 March 1987PNO-V-87-024:on 870322,both Main Feedwater Pumps Lost Suction Pressure & Tripped.Plant Operator Manually Tripped Reactor Upon Losing All Feedwater Flow.Reactor Vessel Level Restored & Heat Manually Removed.Investigation Pending
PNO-V-87-022, on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing20 March 1987PNO-V-87-022:on 870319,licensee Found Pressure Switch on Discharge Side of RHR Sys Pump B Isolated.Licensee Unisolated Switch & Restored Sys to Full Operability.Region V Followup Continuing
PNO-V-87-015, on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days20 February 1987PNO-V-87-015:on 870220,shutdown Commenced Due to Decreasing Lubrication Oil Pressure to Turbine Bearings.Caused by Flange or Pipe Leak Inside Lube Oil Reservoir.Shutdown Will Continue for Approx 4 to 6 Days
PNO-V-86-084, on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 86112520 November 1986PNO-V-86-084:on 861120,plant Shut Down Due to Inoperability of Acoustic Monitor for Safety Relief Valve 5c.Caused by Lack of Environ Qualification Documentation for Connector. Investigation Underway.Plant Will Be Restarted on 861125
PNO-V-86-078, on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level12 November 1986PNO-V-86-078:on 861107 & 09 Increased Vibration from Reactor Recirculating Water Pump a Occurred.Licensee Reduced Reactor Power & Shifted Pumps Into Low Frequency Operation, Decreasing Vibration Level
PNO-V-86-064, on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also Reported18 September 1986PNO-V-86-064:on 860918,licensee Declared Unusual Event Due to High Winds of 85 Mph.Svc Water Pump B out-of-svc Resulting in Emergency Diesel Generator B Being out-of-svc. Rupture in Low Pressure Fire Main Also ReportedHigh winds
PNO-V-86-064A, on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header Pressure18 September 1986PNO-V-86-064A:on 860918,licensee Declared Alert Due to Tornado Warnings & High Winds.Train a Svc Water Sys out-of- Svc Due to Fire in Svc Water Pump House.Licensee Also Experiencing Low Fire Main Header PressureHigh winds
PNO-V-86-060, on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway4 September 1986PNO-V-86-060:on 860903,reactor Feedwater Pump B Tripped Due to Failure of Overspeed Controls.Caused by Partial Control Valve Closure Re Tripping of Hydraulic Power Units. Investigation Underway
PNO-V-86-034, on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements23 June 1986PNO-V-86-034:on 860620,licensee Measured 1.3 Gpm Leakage Into RHR Sys B.Caused by Leak Through LPCI Injection Valve 53B.Util Repairing Valve.Startup Will Be Delayed Until 860629 Due to BPA Load Requirements
PNO-V-86-031, on 860609,operation Resumed After Completing First Refueling Outage.Licensee Plans to Complete post-refueling Startup Testing & Fuel Preconditioning. Facility May Be Placed in Reserve Shutdown Status11 June 1986PNO-V-86-031:on 860609,operation Resumed After Completing First Refueling Outage.Licensee Plans to Complete post-refueling Startup Testing & Fuel Preconditioning. Facility May Be Placed in Reserve Shutdown Status
PNO-V-85-077, on 851113,blown Fuse in Water Level Control Sys Resulted in Reactor Feedpumps Overfeeding & Reactor Trip.Caused by Faulty Inverter.Facility Shut Down to Allow Installation of Instrumentation to Monitor Vibrations13 November 1985PNO-V-85-077:on 851113,blown Fuse in Water Level Control Sys Resulted in Reactor Feedpumps Overfeeding & Reactor Trip.Caused by Faulty Inverter.Facility Shut Down to Allow Installation of Instrumentation to Monitor VibrationsReactor Vessel Water Level