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PNO-V-93-013, on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant9 August 1993PNO-V-93-013:on 930809,during pre-announced anti-nuclear demonstration,13 Protestors Illegally Entered Plant Access Gate & Immediately Taken Into Custody by Sheriff Deputies. Demonstration Related to CP Recapture Hearings for Plant
PNO-V-92-033, on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near Parkfield20 October 1992PNO-V-92-033:on 921019,US Geological Survey Notified California Governor Ofc of Significant Likelihood That Earthquake of Magnitude 6 Will Occur on San Andreas Fault Near ParkfieldEarthquake
PNO-V-91-003, on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core7 March 1991PNO-V-91-003:on 910307,unit 1 Shutdown for Refueling Operations & Loss of Offsite Power.Licensee Personnel Manually Moved New Module,Still in Mast,Away from Reactor Vessel & Core
PNO-V-90-033, on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring Plant27 July 1990PNO-V-90-033:on 900726,observed Crack in Charging Pump Suction Header Piping Caused by Boric Acid Crystals on Elbow of Pump.Licensee Considers Piping Operable & to Be Repaired W/O Plant Shut Down.Inspector Monitoring PlantBoric Acid
PNO-V-88-048, on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault18 July 1988PNO-V-88-048:on 880717,unit Manually Tripped & Natural Cooldown Commenced as Result of Ground Fault in 12 Kv non- Vital Buses.Event Investigation Team Formed to Determine Location & Cause of Ground Fault
PNO-V-87-083, on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart14 December 1987PNO-V-87-083:on 871213,reactor Tripped.Caused by Loss of Feed Water Pump 1-1.Cause of Trip Under Investigation. Variety of Maint Activities to Be Performed Before Restart
PNO-V-87-082, on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out10 December 1987PNO-V-87-082:on 871210,fire Occurred in Temporary Tool Storage Trailer in Vicinity of Unit 2 Main Generator Transformers.Caused by 120 Volt Junction Box,Possibly Overloaded from Portable Space Heater.Fire Put Out
PNO-V-87-074, on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation10 November 1987PNO-V-87-074:on 871110,county Inadvertently Actuated Emergency Notification Sys(Sirens).Caused by Wrong Sequence Being Entered Into Sys While Performing Weekly Silent Test. Corrective Action Under Investigation
PNO-V-87-073, on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of Parts9 November 1987PNO-V-87-073:on 871107,unit Trip Manually Initiated.Caused by Failure of motor-operated Disconnect in Main Generator 25 Kv Isophase Bus C.Repair & Unit Outage Will Take Between 2 Wks & 2 Months,Depending on Availability of PartsFire Watch
PNO-V-87-066, on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared6 October 1987PNO-V-87-066:on 871006,while Performing Periodic Surveillance Testing of Control Rods at 100% Power,Rod Control Urgent Failure Alarm Received on Shutdown Bank A. Caused by Blown Fuses.Fuses Replaced & Alarm Cleared
PNO-V-87-053, on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure24 July 1987PNO-V-87-053:on 870723,high Radiation Alarm Automatically Diverted Liquid Radwaste Flow to Storage Tank.Licensee Determining Root Cause.Chemical Drain Tank Properly Recirculated & Sampled Prior to Discharge Per Procedure
PNO-V-87-051, on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation14 July 1987PNO-V-87-051:on 870714,reactor Trip & Safety Injection from 12% Power Occurred.Caused by turbine-generator Trip Due to High Steam Generator Water Level & Flickering High Steam Flow Bistables,Respectively.Root Causes Under Investigation
ML20215F90017 June 1987PNS-V-87-005:on 870617,American Protective Svc Notified Util That Security Personnel on Strike Over Monetary Benefits. Licensee Capable to Meet Security Staffing Requirements Through Use of Proprietary Security Personnel
PNO-V-87-041, on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair Weld3 June 1987PNO-V-87-041:on 870602,engineer in Containment Noted Weepage from RHR Sys Line While RHR in Svc.Cause of Effect Undetermined.Licensee Preparing Work Orders to Isolate, Examine & Repair WeldBoric Acid
ML20209D51323 April 1987Updated PNO-V-87-030B:on 870421,onsite Phase of AIT Team Special Insp Into 870410 Loss of Suction to RHR Sys While in half-loop Concluded W/Meeting at Site
PNO-V-87-030A, on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event Encl20 April 1987PNO-V-87-030A:on 870415,Region V Augmented Insp Team Commenced Insp Activities Re 870410 Loss of Suction to RHR While at Half Loop.Team Expects to Stay Onsite Through 870421.Summary of Sequence of Event EnclBoric Acid
PNO-V-87-030, on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched13 April 1987PNO-V-87-030:on 870410,RHR Sys Capability Lost for Approx 90 Minutes.Caused by Entrainment of Air within RHR Pumps When RCS Water Level Dropped Due to Water Leakage Through Two Valves.Augmented Insp Team Dispatched
PNO-V-87-028, on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing6 April 1987PNO-V-87-028:on 870403,reactor Tripped from 12% Power During Shut Down for First Refueling Outage.Caused by Flicker of High Steam Flow Bistables Coincident w/lo-lo T Average.Investigation Continuing
PNO-V-87-025, on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected23 March 1987PNO-V-87-025:on 870321,facility Experienced Safety Injection,Reactor Trip & Unit Trip.Caused by Coincidence of High Steam Flow & Low Steam Generator Pressure Signals Due to Closure of MSIV FCV 41.Piping & Valve Switches Inspected
PNO-V-87-018, on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 8702172 March 1987PNO-V-87-018:on 870301,1-2 Mw/Min Shutdown Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak. Vibration,Induced by Main Generator,Caused Cracking in Welds of Stator Cooling Water Sys Which Occurred on 870217
PNO-V-87-016, on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem23 February 1987PNO-V-87-016:on 870221,shutdown Commenced Due to Train B of Solid State Protection Sys Not Returning to Svc within 2 H. Caused by High Steam Generator Level on Generator 1-4 & Feedwater Flow Instabilities & Valve Position Problem
PNO-V-87-014, on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk18 February 1987PNO-V-87-014:on 870217,slow Shutdown from 100% Power Initiated to Investigate & Repair Main Generator Hydrogen Coolant Leak.Caused by Cracking in Stator Water Cooling Vent Line Due to Vibration.Outage Expected to Last Approx 1 Wk
PNO-V-87-002, on 870105,reactor Trip/Turbine Trip Occurred. Caused by Loss of Turbine Governor/Stop Valve electro- Hydraulic Sys Pressure,Attributed to Leak in Compression Fitting Connection to Steam Lead Stop Valve FCV-1456 January 1987PNO-V-87-002:on 870105,reactor Trip/Turbine Trip Occurred. Caused by Loss of Turbine Governor/Stop Valve electro- Hydraulic Sys Pressure,Attributed to Leak in Compression Fitting Connection to Steam Lead Stop Valve FCV-145
PNO-V-87-001, on 870102,licensee Shut Down Plant.Caused by Fire Near High Pressure Turbine Front Bearing.Licensee Affected Repairs & Examining Bearing Area for Any Signs of Oil Leak5 January 1987PNO-V-87-001:on 870102,licensee Shut Down Plant.Caused by Fire Near High Pressure Turbine Front Bearing.Licensee Affected Repairs & Examining Bearing Area for Any Signs of Oil Leak
PNO-V-86-089, on 861207,plant Seismic Monitor Detected Ground Motion Which Triggered Ripplemental Seismic Monitoring Sys.Ground Motion Measured 2.9 on Richter Scale8 December 1986PNO-V-86-089:on 861207,plant Seismic Monitor Detected Ground Motion Which Triggered Ripplemental Seismic Monitoring Sys.Ground Motion Measured 2.9 on Richter ScaleEarthquake
PNO-V-86-074, on 861028,main Steam Valves Found W/Missing & Loosened Nuts That Secure Valve Disc to Hinge Arm. Deficiencies Discovered During Visual Exam as Part of Inservice Testing Exam30 October 1986PNO-V-86-074:on 861028,main Steam Valves Found W/Missing & Loosened Nuts That Secure Valve Disc to Hinge Arm. Deficiencies Discovered During Visual Exam as Part of Inservice Testing Exam
PNO-V-86-075, on 861029,during Followup Insp of Accumulator Drain Fittings,Pin Hole Leaks Discovered in Accumulators 2-2 & 2-4 in Nonwelded Portion of Fitting.Cause Not Stated.Leaks Repaired30 October 1986PNO-V-86-075:on 861029,during Followup Insp of Accumulator Drain Fittings,Pin Hole Leaks Discovered in Accumulators 2-2 & 2-4 in Nonwelded Portion of Fitting.Cause Not Stated.Leaks Repaired
PNO-V-86-073, GL Mcchain,In Custody by FBI on Parole Violation,Issued Claims of Evading Security Background Checks for 6 Yrs While Working at Listed Facilities & Knows of Falsified Weld Records.Investigation in Progress23 October 1986PNO-V-86-073:GL Mcchain,In Custody by FBI on Parole Violation,Issued Claims of Evading Security Background Checks for 6 Yrs While Working at Listed Facilities & Knows of Falsified Weld Records.Investigation in Progress
PNO-V-86-070, on 861004,discovered Two Snubbers on Charging Sys Mistakenly Removed.Charging Sys Required by Tech Specs for Refueling Boration Flow Path.Snubbers Reinstalled within Hour of Discovery6 October 1986PNO-V-86-070:on 861004,discovered Two Snubbers on Charging Sys Mistakenly Removed.Charging Sys Required by Tech Specs for Refueling Boration Flow Path.Snubbers Reinstalled within Hour of Discovery
PNO-V-86-067, on 861001,fuel Assembly in Vessel Found W/ 10-degree Tilt & Resting Askew Against Core Baffle Plate. Cause Under Investigation.Program & Special Tools Prepared to Return Assembly to Vertical Position1 October 1986PNO-V-86-067:on 861001,fuel Assembly in Vessel Found W/ 10-degree Tilt & Resting Askew Against Core Baffle Plate. Cause Under Investigation.Program & Special Tools Prepared to Return Assembly to Vertical PositionFuel cladding
PNO-V-86-065, on 860918,reactor Tripped Due to Loss of Main Feedwater Pump 2-2 During Maint on Lovejoy Speed Controller Sys.Caused by Steam Flow/Feed Flow Mismatch Coincident W/Low Level on Steam Generators 2 & 4.Cause Under Investigation18 September 1986PNO-V-86-065:on 860918,reactor Tripped Due to Loss of Main Feedwater Pump 2-2 During Maint on Lovejoy Speed Controller Sys.Caused by Steam Flow/Feed Flow Mismatch Coincident W/Low Level on Steam Generators 2 & 4.Cause Under Investigation
PNO-V-86-062, court Decided in Favor of San Luis Obispo Mothers for Peace & Sierra Club Re Spent Fuel Pool Expansion.Util Reinstalling Old Racks & May Use Spent Fuel Pools Prior to Completion of New Hearings12 September 1986PNO-V-86-062:court Decided in Favor of San Luis Obispo Mothers for Peace & Sierra Club Re Spent Fuel Pool Expansion.Util Reinstalling Old Racks & May Use Spent Fuel Pools Prior to Completion of New Hearings
PNO-V-86-056, on 860829,first Refueling Outage Began.Work to Include Copper Reduction & court-ordered Replacement of New High Density Fuel Racks W/Older Low Density Fuel Racks29 August 1986PNO-V-86-056:on 860829,first Refueling Outage Began.Work to Include Copper Reduction & court-ordered Replacement of New High Density Fuel Racks W/Older Low Density Fuel Racks
PNO-V-86-057, reactor Trip Occurred.Caused by Loose Wire on Shunt Coil Relay That Shorted During Surveillance Testing & Opened Reactor Trip Breaker.New High Density Fuel Racks Removed & Older Low Density Racks Reinstalled29 August 1986PNO-V-86-057:reactor Trip Occurred.Caused by Loose Wire on Shunt Coil Relay That Shorted During Surveillance Testing & Opened Reactor Trip Breaker.New High Density Fuel Racks Removed & Older Low Density Racks Reinstalled
PNO-V-86-046, on 860721,two Seismic Events Occurred in Mammoth Lakes Area.Largest Event Measured 6.2 on Richter Scale & Second Measured 4.4.First Event Not Felt at Diablo Canyon.Second Event Triggered Teratec Recording21 July 1986PNO-V-86-046:on 860721,two Seismic Events Occurred in Mammoth Lakes Area.Largest Event Measured 6.2 on Richter Scale & Second Measured 4.4.First Event Not Felt at Diablo Canyon.Second Event Triggered Teratec Recording
PNO-V-86-040, on 860709,reactor Tripped Due to Low Level in Steam Generator Coincident W/Steam Flow Feed Flow Mismatch. Caused by Loss of Main Feed Pump.Pump Repaired & post-trip Review Conducted10 July 1986PNO-V-86-040:on 860709,reactor Tripped Due to Low Level in Steam Generator Coincident W/Steam Flow Feed Flow Mismatch. Caused by Loss of Main Feed Pump.Pump Repaired & post-trip Review Conducted
PNO-V-86-038, on 860703,facility Experienced Reactor Trip & Safety Injection Due to Momentary High Steam Flow Coincident w/lo-lo Tavg Signal from solid-state Protection Sys.On 860706,second Turbine & Reactor Trip Experienced7 July 1986PNO-V-86-038:on 860703,facility Experienced Reactor Trip & Safety Injection Due to Momentary High Steam Flow Coincident w/lo-lo Tavg Signal from solid-state Protection Sys.On 860706,second Turbine & Reactor Trip Experienced
PNO-V-86-027, on 860505,diesel Generator Unexpectedly Started & Loaded on Vital Bus G Undervoltage Condition.Auxiliary Feeder Breaker Tripped on Overcurrent & Startup Power Feeder Breaker Did Not Close In.Investigation Underway7 May 1986PNO-V-86-027:on 860505,diesel Generator Unexpectedly Started & Loaded on Vital Bus G Undervoltage Condition.Auxiliary Feeder Breaker Tripped on Overcurrent & Startup Power Feeder Breaker Did Not Close In.Investigation UnderwayOffsite Circuit
PNO-V-86-019, on 860418,unusual Event Declared on Initiation of Shutdown.On 860417,problems W/Computer Info from in-core Instrumentation for Quadrant Power Tilt Ratio Measurement Occurred18 April 1986PNO-V-86-019:on 860418,unusual Event Declared on Initiation of Shutdown.On 860417,problems W/Computer Info from in-core Instrumentation for Quadrant Power Tilt Ratio Measurement Occurred
PNO-V-86-013, on 860330,while Reducing Power Due to Indications of Condenser Tube Rupture,Operator Initiated Manual Unit Trip Resulting in Safety Injection on High Steam Flow & lo-lo Tavg.Caused by Switch Problem & Stuck Valve31 March 1986PNO-V-86-013:on 860330,while Reducing Power Due to Indications of Condenser Tube Rupture,Operator Initiated Manual Unit Trip Resulting in Safety Injection on High Steam Flow & lo-lo Tavg.Caused by Switch Problem & Stuck Valve
PNO-V-86-011, on 860314,during Main Turbine Testing,Safety Injection & Reactor Trip Occurred from High Steam Flow Signal.Plant Stabilized.Licensee Will Resume Operations Once Event Evaluated & Excess Boron Removed14 March 1986PNO-V-86-011:on 860314,during Main Turbine Testing,Safety Injection & Reactor Trip Occurred from High Steam Flow Signal.Plant Stabilized.Licensee Will Resume Operations Once Event Evaluated & Excess Boron Removed
PNO-V-86-010, on 860312,reactor Brought Critical Following Negative Rate Trip During Net Load Startup Test on 860311. Reactor Declared in Commercial Operation on 86031313 March 1986PNO-V-86-010:on 860312,reactor Brought Critical Following Negative Rate Trip During Net Load Startup Test on 860311. Reactor Declared in Commercial Operation on 860313
PNO-V-86-008, on 860219,unusual Event Declared & Hot Shutdown Initiated After Boron Sample Exceeded 2,200 Ppm.Unusual Event Terminated When Primary Std for Boron Analysis Determined to Be Faulty20 February 1986PNO-V-86-008:on 860219,unusual Event Declared & Hot Shutdown Initiated After Boron Sample Exceeded 2,200 Ppm.Unusual Event Terminated When Primary Std for Boron Analysis Determined to Be Faulty
PNO-V-86-001, on 860102,unusual Event Declared When Reactor Tripped on lo-lo Steam Generator Level Following Feedwater Pump Trip.Caused by Reactor Coolant Pumps Tripping on Undervoltage.Pumps Restarted in 3 to 5 Minutes3 January 1986PNO-V-86-001:on 860102,unusual Event Declared When Reactor Tripped on lo-lo Steam Generator Level Following Feedwater Pump Trip.Caused by Reactor Coolant Pumps Tripping on Undervoltage.Pumps Restarted in 3 to 5 Minutes
PNO-V-85-091, on 851225,during Full Load Rejection Test, Reactor Tripped on lo-lo Steam Generator Level & Coolant Pumps Tripped.Caused by over-responsive Turbine Control Sys & under-responsive Steam Dump Sys.Pumps Restarted26 December 1985PNO-V-85-091:on 851225,during Full Load Rejection Test, Reactor Tripped on lo-lo Steam Generator Level & Coolant Pumps Tripped.Caused by over-responsive Turbine Control Sys & under-responsive Steam Dump Sys.Pumps Restarted
ML20138E1946 December 1985PNS-V-85-006:on 851206,util Notified NRC of Arrest of Five Individuals,Including Three Plant Security Employees,For Use & Sale of Narcotics During 3-wk Period Ending 851205.No Evidence of Use of Narcotics at Plant Site Identified
PNO-V-85-082, on 851202,low Tide Concurrent W/High Seas Caused Kelp to Be Injected Into Condenser Circulating Water Intake Structure.Control RPI Lost & Reactor Manually Tripped.Cause Under Investigation3 December 1985PNO-V-85-082:on 851202,low Tide Concurrent W/High Seas Caused Kelp to Be Injected Into Condenser Circulating Water Intake Structure.Control RPI Lost & Reactor Manually Tripped.Cause Under Investigation
PNO-V-85-081, on 851201,turbine & Reactor Trips Occurred. Caused by High Steam Generator Level Due to Sluggish Automatic Steam Generator Level Control Sys Response.No Safety Injection or ECCS Activated2 December 1985PNO-V-85-081:on 851201,turbine & Reactor Trips Occurred. Caused by High Steam Generator Level Due to Sluggish Automatic Steam Generator Level Control Sys Response.No Safety Injection or ECCS Activated
PNO-V-85-080, on 851128,oscillation of Steam Flow Resulted in Reactor Trip Due to Completion of Steam Generator Low Level Coincident W/Steam Flow/Feedwater Flow Mismatch Logic. Cause Will Be Determined Prior to Resuming Operations29 November 1985PNO-V-85-080:on 851128,oscillation of Steam Flow Resulted in Reactor Trip Due to Completion of Steam Generator Low Level Coincident W/Steam Flow/Feedwater Flow Mismatch Logic. Cause Will Be Determined Prior to Resuming Operations
PNO-V-85-079, on 851126,safety Injection Occurred on High Steam Flow Signal.Cause Under Investigation.Plant Stabilized & Maintaining Hot Standby Conditions.Licensee Plans to Evaluate Data & Make Appropriate Adjustments27 November 1985PNO-V-85-079:on 851126,safety Injection Occurred on High Steam Flow Signal.Cause Under Investigation.Plant Stabilized & Maintaining Hot Standby Conditions.Licensee Plans to Evaluate Data & Make Appropriate Adjustments