Semantic search

Jump to navigation Jump to search
 Issue dateTitleTopic
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-93-002, on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased13 January 1993PNO-V-93-002:on 930113,L Marbet Held Press Conference W/ Portland,Or Media & Alleged That NRC Had Inappropriately Authorized Feb 1992 Restart of Plant.Util Announced on 930104 That Operation of Plant Would Be Permanently Ceased
PNO-V-93-001, on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media4 January 1993PNO-V-93-001:on 930104,Licensee Notified Region V That Util Board Decided That Plant Will Not Be Restarted & Currently Shutdown for Insp & Repair of SG Tubes.Licensee Notified Media
PNO-V-92-038, on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety8 December 1992PNO-V-92-038:on 921209,B Roberts Plans to Notify News Media of Request of or Energy Facility Siting Council to Hold Hearing on Utility Steam Generator Safety
PNO-V-92-037, on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart1 December 1992PNO-V-92-037:on 921201,meeting Conducted at Plant to Address 921109 Steam Generator Tube Leak & Licensee Request for Emergency TS Change to Permit Restart
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-92-004, on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 92022725 February 1992PNO-V-92-004:on 920225,Trojan Power Plant Entered Mode 2 After Extended Outage.Plant Currently Critical at Less than 1 Percent Power & Licensee Conducting Low Power Physics Testing.Tests Expected to Be Completed by 920227
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-91-002, on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable5 March 1991PNO-V-91-002:on 910303,Trojan Declared an Unsual Event & Initiated Plant Shutdown Due to Inability to Meet Requirements of TS 3.8.2.1,which Requires That Four 120 Volts AC Preferred Instrument Busses Be Operable
PNO-V-90-045, State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference7 November 1990PNO-V-90-045:State of or Measure 4 Re Closure of Facility Defeated in 901106 Vote.Util Will Hold News Conference
PNO-V-90-038, A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations27 September 1990PNO-V-90-038-A:on 900927,main Generator Trip Resulted in Unplanned Plant Shutdown.Transient Caused 140 MW Excursion on Grid,Tripped Off Nearby Substation & Shook Turbine Bldg Deck.Ge Contacted for Recommendations
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-90-032, on 900711,steam Dumps Did Not Automatically Open to Pick Up Load Lost from Turbine During Performance of Turbine Test.Operators Took Manual Control & Stabilized Plant.Plant Shutdown to Investigate Event11 July 1990PNO-V-90-032:on 900711,steam Dumps Did Not Automatically Open to Pick Up Load Lost from Turbine During Performance of Turbine Test.Operators Took Manual Control & Stabilized Plant.Plant Shutdown to Investigate Event
PNO-V-90-010, on 900320,facility Entered TS 3.0.3 After Engineering Organization Determined Main Steam Flow Trip Setpoints Were Incorrect & Nonconservative.Plant Shutdown Began IAW TSs20 March 1990PNO-V-90-010:on 900320,facility Entered TS 3.0.3 After Engineering Organization Determined Main Steam Flow Trip Setpoints Were Incorrect & Nonconservative.Plant Shutdown Began IAW TSs
PNO-V-90-011, on 900919,Vice President Nuclear DW Cockfield Announced Resignation After Being in Position Since March 1987.TD Walt Will Serve as Vice President-Nuclear Until Licensee Identify Replacement20 March 1990PNO-V-90-011:on 900919,Vice President Nuclear DW Cockfield Announced Resignation After Being in Position Since March 1987.TD Walt Will Serve as Vice President-Nuclear Until Licensee Identify Replacement
PNO-V-89-048, on 890809,plant Tripped on Overtemp Differential Temp.Caused by Spurious Trip Signal Received from Other Channel.Reactor Shutdown in Mode 3 in Order for Licensee to Attempt to Identify Source & Cause of Signal10 August 1989PNO-V-89-048:on 890809,plant Tripped on Overtemp Differential Temp.Caused by Spurious Trip Signal Received from Other Channel.Reactor Shutdown in Mode 3 in Order for Licensee to Attempt to Identify Source & Cause of Signal
ML20245G61016 June 1989PNS-V-89-005:on 890615,licensee Informed NRC of Possible Onsite Use & Sale of Marijuana & Cocaine by Five Contract Employees,Employed by Northwest Energy Svcs Co.Employees Interviewed,Searched & Given Urinanalyses on 890616
PNO-V-88-060, on 881113,turbine Trip/Reactor Trip on hi-hi Steam Generator Level Occurred.Caused by Faulty Controller for Feedwater Regulation Valve on Steam Generator B.Licensee Developing Actions to Address Problems15 November 1988PNO-V-88-060:on 881113,turbine Trip/Reactor Trip on hi-hi Steam Generator Level Occurred.Caused by Faulty Controller for Feedwater Regulation Valve on Steam Generator B.Licensee Developing Actions to Address Problems
PNO-V-88-057, on 880916,while Verifying Pressure Transmitter PT-458,bistables Tripped.Caused by Technician Error & Exceeding Shutdown by More than 48 H.Problems Encountered During Reactor Startup Listed19 September 1988PNO-V-88-057:on 880916,while Verifying Pressure Transmitter PT-458,bistables Tripped.Caused by Technician Error & Exceeding Shutdown by More than 48 H.Problems Encountered During Reactor Startup Listed
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-88-031, on 880512,engineering Walkdowns of Pipe Whip Restraints Identified That Pressurizer Surge Line in Contact W/Upper Shim Pack of Pipe Whip Restraint 1.2.Possibly Caused by Difference Between Pressurizer & Hot Leg12 May 1988PNO-V-88-031:on 880512,engineering Walkdowns of Pipe Whip Restraints Identified That Pressurizer Surge Line in Contact W/Upper Shim Pack of Pipe Whip Restraint 1.2.Possibly Caused by Difference Between Pressurizer & Hot Leg
PNO-V-88-026, on 880418,workers Removed Flange from Pressurizer Relief Tank,Releasing Radioactive Noble Gas. Level of Activity Resulted in Containment Purge Isolation Signal.Release Caused by Inadequate Procedural Control19 April 1988PNO-V-88-026:on 880418,workers Removed Flange from Pressurizer Relief Tank,Releasing Radioactive Noble Gas. Level of Activity Resulted in Containment Purge Isolation Signal.Release Caused by Inadequate Procedural Control
PNO-V-88-001, on 880108,reactor Trip/Turbine Trip Occurred & Plant Shutdown for Greater than 48 H.Caused by Dirty Contact in Cable Connection to pre-amplifier.Containment Leakage Also Discovered.Manway Cover Bolts Torqued12 January 1988PNO-V-88-001:on 880108,reactor Trip/Turbine Trip Occurred & Plant Shutdown for Greater than 48 H.Caused by Dirty Contact in Cable Connection to pre-amplifier.Containment Leakage Also Discovered.Manway Cover Bolts Torqued
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-87-081, on 871209,indication of Increased Leakage in Containment Identified.Caused by Leakage from Charging Sys Valve & Steam Generator Tubesheet Drain Valve Due to Abnormal Seal Performance.Seals Examined & Valves Repaired10 December 1987PNO-V-87-081:on 871209,indication of Increased Leakage in Containment Identified.Caused by Leakage from Charging Sys Valve & Steam Generator Tubesheet Drain Valve Due to Abnormal Seal Performance.Seals Examined & Valves Repaired
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-87-062, on 870928,unit Shut Down to Repair Boron Injection Tank Leaking Pressure Relief Valve Psv 8852. Leaking Relief Valve Removed & Blank Flange Put Over Line. Plant Remains in Shutdown Status29 September 1987PNO-V-87-062:on 870928,unit Shut Down to Repair Boron Injection Tank Leaking Pressure Relief Valve Psv 8852. Leaking Relief Valve Removed & Blank Flange Put Over Line. Plant Remains in Shutdown Status
PNO-V-87-057, on 870824,Oregon State Agreement Program Director,R Paris,Informed NRC That State Employee Union Voted to Strike on 870913.If Settlement Not Reached Prior to Walk Out,Managers Will Handle Radioactive Matls Program24 August 1987PNO-V-87-057:on 870824,Oregon State Agreement Program Director,R Paris,Informed NRC That State Employee Union Voted to Strike on 870913.If Settlement Not Reached Prior to Walk Out,Managers Will Handle Radioactive Matls Program
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
PNO-V-87-048A, on 870702,significant Unexpected Erosion on Straight Sections of safety-related Feed Sys Piping Identified.Licensee Plans to Replace Piping Prior to Restart.Inpo Requested to Distribute Findings Via Network7 July 1987PNO-V-87-048A:on 870702,significant Unexpected Erosion on Straight Sections of safety-related Feed Sys Piping Identified.Licensee Plans to Replace Piping Prior to Restart.Inpo Requested to Distribute Findings Via Network
PNO-V-87-048, during Insp of Main Feedwater Sys in June 1987, Licensee Found Some Indications of Pipe Wall Thinning.Caused by Flow Transition & Turbulence.Licensee Replacing All Piping W/Below Min Wall Thickness Indications30 June 1987PNO-V-87-048:during Insp of Main Feedwater Sys in June 1987, Licensee Found Some Indications of Pipe Wall Thinning.Caused by Flow Transition & Turbulence.Licensee Replacing All Piping W/Below Min Wall Thickness IndicationsNondestructive Examination
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-87-045, licensee Discovered Seperation Between Base Plate Grout & Concrete on Support SS-81 on Main Steam Line B.On 870616,dynamic Analysis Reperformed for Main Steam Supports.Supports Reinstalled W/Proper Design Loads16 June 1987PNO-V-87-045:licensee Discovered Seperation Between Base Plate Grout & Concrete on Support SS-81 on Main Steam Line B.On 870616,dynamic Analysis Reperformed for Main Steam Supports.Supports Reinstalled W/Proper Design Loads
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
PNO-V-87-040, on 870523,360 Degrees Circumferential Break of SI Accumulator a Fill Line Occurred While Transferring Water from SI Accumulator a to D.Caused by Low Cycle,High Fatigue. Util Conducting Analyses to Determine Force & Fatigue Cycl26 May 1987PNO-V-87-040:on 870523,360 Degrees Circumferential Break of SI Accumulator a Fill Line Occurred While Transferring Water from SI Accumulator a to D.Caused by Low Cycle,High Fatigue. Util Conducting Analyses to Determine Force & Fatigue CyclHydrostatic
PNO-V-87-037, on 870512,fatigue Fracture Occurred on 1-inch Safety Injection Fill Line on Accumulator Tank a & 2,000 Gallons of 2,000 Ppm Borated Water Drained Onto Containment Floor.By 870514,two Addl Accumulator Tanks Found W/Cracks14 May 1987PNO-V-87-037:on 870512,fatigue Fracture Occurred on 1-inch Safety Injection Fill Line on Accumulator Tank a & 2,000 Gallons of 2,000 Ppm Borated Water Drained Onto Containment Floor.By 870514,two Addl Accumulator Tanks Found W/Cracks
PNO-V-87-038, on 870513,female Air Lock Operator Received Injury to Neck While Opening Air Lock Door to Transfer Matl from Containment.Operator Transported Offsite for Medical Attention.No Serious Injuries or Contamination Found14 May 1987PNO-V-87-038:on 870513,female Air Lock Operator Received Injury to Neck While Opening Air Lock Door to Transfer Matl from Containment.Operator Transported Offsite for Medical Attention.No Serious Injuries or Contamination Found
PNO-V-87-035, on 870507,individual W/Contamination Level of 160,000 Dpm/Square Centimeters on Knees Became Ill While Removing Protective Clothing Worn for Decontaminating Equipment.Individual Transported to Hosp & Decontaminated8 May 1987PNO-V-87-035:on 870507,individual W/Contamination Level of 160,000 Dpm/Square Centimeters on Knees Became Ill While Removing Protective Clothing Worn for Decontaminating Equipment.Individual Transported to Hosp & Decontaminated
PNO-V-87-031A, on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Staff Retrained in Precautions to Minimize Exposure from Radioactive Matl & Appropriate Radiological Control Started29 April 1987PNO-V-87-031A:on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Staff Retrained in Precautions to Minimize Exposure from Radioactive Matl & Appropriate Radiological Control Started
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-87-031, on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Caused by Dispersal of Irradiated Fuel Fragments.Work Stopped in Containment Bldg.Investigation Initiated17 April 1987PNO-V-87-031:on 870417,licensee Reported Potential Foot Exposure of Plant Worker Exceeding 18.75 Rem Limit.Caused by Dispersal of Irradiated Fuel Fragments.Work Stopped in Containment Bldg.Investigation Initiated
PNO-V-87-029A, on 870414,licensee Reported That Degraded Pellet Between Reactor Vessel & Head Flange Source of Radioactive Contamination of Area & Personnel Inside Containment Bldg on 870409.Decontamination Efforts Ongoing14 April 1987PNO-V-87-029A:on 870414,licensee Reported That Degraded Pellet Between Reactor Vessel & Head Flange Source of Radioactive Contamination of Area & Personnel Inside Containment Bldg on 870409.Decontamination Efforts Ongoing
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-87-029, on 870409,while Installing Reactor Stud Plugs, Release of Radioactivity Occurred Resulting in 21 Workers Experiencing Personal Contamination.Work in Reactor Cavity Stopped Until Source of Problem Identified10 April 1987PNO-V-87-029:on 870409,while Installing Reactor Stud Plugs, Release of Radioactivity Occurred Resulting in 21 Workers Experiencing Personal Contamination.Work in Reactor Cavity Stopped Until Source of Problem Identified
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
Retrieved from "https://kanterella.com/Special:Ask/-5B-5BCategory:PRELIMINARY-20NOTIFICATION-20OF-20EVENT-20OR-20OCCURRENCE-20(PNO-5D-5D-20-5B-5BSite::Diablo-20Canyon-7C-7CTrojan-5D-5D/-3FIssue-20date/-3FTitle/-3FTopic/mainlabel%3D/order%3D-20descending/sort%3D-20Issue-20date/offset%3D0/format%3Dtable/searchlabel%3D-5BTable-20view-5D"