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Issue date | Title | Topic | |
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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 Plant | 9 August 1993 | 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 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 Parkfield | 20 October 1992 | 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 Parkfield | Earthquake |
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 & Core | 7 March 1991 | 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 & 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 Plant | 27 July 1990 | 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 Plant | Boric 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 Fault | 18 July 1988 | 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 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 Restart | 14 December 1987 | 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 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 Out | 10 December 1987 | 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 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 Investigation | 10 November 1987 | 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 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 Parts | 9 November 1987 | 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 Parts | Fire 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 Cleared | 6 October 1987 | 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 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 Procedure | 24 July 1987 | 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 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 Investigation | 14 July 1987 | 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 Investigation | |
ML20215F900 | 17 June 1987 | PNS-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 Weld | 3 June 1987 | 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 Weld | Boric Acid |
ML20209D513 | 23 April 1987 | Updated 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 Encl | 20 April 1987 | 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 Encl | Boric 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 Dispatched | 13 April 1987 | 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 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 Continuing | 6 April 1987 | 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 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 Inspected | 23 March 1987 | 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 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 870217 | 2 March 1987 | 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 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 Problem | 23 February 1987 | 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 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 Wk | 18 February 1987 | 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 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-145 | 6 January 1987 | 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-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 Leak | 5 January 1987 | 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 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 Scale | 8 December 1986 | 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 Scale | Earthquake |
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 Exam | 30 October 1986 | 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 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 Repaired | 30 October 1986 | 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 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 Progress | 23 October 1986 | 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 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 Discovery | 6 October 1986 | 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 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 Position | 1 October 1986 | 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 Position | Fuel 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 Investigation | 18 September 1986 | 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 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 Hearings | 12 September 1986 | 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 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 Racks | 29 August 1986 | 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 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 Reinstalled | 29 August 1986 | 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 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 Recording | 21 July 1986 | 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 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 Conducted | 10 July 1986 | 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 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 Experienced | 7 July 1986 | 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 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 Underway | 7 May 1986 | 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 Underway | Offsite 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 Occurred | 18 April 1986 | 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 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 Valve | 31 March 1986 | 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 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 Removed | 14 March 1986 | 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 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 860313 | 13 March 1986 | 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 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 Faulty | 20 February 1986 | 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 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 Minutes | 3 January 1986 | 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 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 Restarted | 26 December 1985 | 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 Restarted | |
ML20138E194 | 6 December 1985 | PNS-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 Investigation | 3 December 1985 | 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 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 Activated | 2 December 1985 | 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 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 Operations | 29 November 1985 | 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 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 Adjustments | 27 November 1985 | 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 Adjustments |