PNO-IIT-85-002B:on 851121,unit Tripped.Preliminary Sequence of Events Encl.Feedwater Leak Identified on B Steam Generator Valve FUS-378.Investigation Expected to Be Completed by 851201| ML20137L392 |
| Person / Time |
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| Site: |
San Onofre  |
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| Issue date: |
11/26/1985 |
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| From: |
Lanning W, Martin T
NRC |
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| To: |
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| References |
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| PNO-IIT-85-002B, PNO-IIT-85-2B, NUDOCS 8512030431 |
| Download: ML20137L392 (5) |
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Category:PRELIMINARY NOTIFICATION OF EVENT OR OCCURRENCE (PNO
MONTHYEARPNO-IV-99-043, on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed1999-10-18018 October 1999
PNO-IV-99-043:on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed
PNO-IV-99-018, on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials1999-03-0505 March 1999
PNO-IV-99-018:on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials
PNO-IV-98-041, on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades1998-09-18018 September 1998
PNO-IV-98-041:on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades
PNO-IV-97-038, on 970629,Unit 2 Entered Mode 3 & Mode 4 in Preparation for Draining to Midloop.Two Charging Lines to RCS Did Not Have Balanced Flow.Same Valve Was Found to Be Partially Stuck Closed in Units 2 & 3.Plant Shutdowned1997-06-30030 June 1997
PNO-IV-97-038:on 970629,Unit 2 Entered Mode 3 & Mode 4 in Preparation for Draining to Midloop.Two Charging Lines to RCS Did Not Have Balanced Flow.Same Valve Was Found to Be Partially Stuck Closed in Units 2 & 3.Plant Shutdowned
PNO-V-93-020, on 931118,eddy Current Insp of Tubes Identified Potential Loose Parts in Four Locations in SG 88 & Three Locations in SG 89.Licensee Evaluating Source of Loose Parts1993-11-18018 November 1993
PNO-V-93-020:on 931118,eddy Current Insp of Tubes Identified Potential Loose Parts in Four Locations in SG 88 & Three Locations in SG 89.Licensee Evaluating Source of Loose Parts
PNO-V-91-016, on 910808,transmitter on Volume Control Tank Failed.Level Transmitter Repaired.Licensee Conducting Confirmatory Testing of Transmitter1991-08-0909 August 1991
PNO-V-91-016:on 910808,transmitter on Volume Control Tank Failed.Level Transmitter Repaired.Licensee Conducting Confirmatory Testing of Transmitter
PNO-V-91-014, on 910715,licensee Inadvertently Drained 7,000 Gallons of Water from Spent Fuel Pool.Caused by Procedural Weakness.Health Physics Personnel Surveyed Area & Found Min Activity.Util Currently Removing Water from Radwaste Bldg1991-07-16016 July 1991
PNO-V-91-014:on 910715,licensee Inadvertently Drained 7,000 Gallons of Water from Spent Fuel Pool.Caused by Procedural Weakness.Health Physics Personnel Surveyed Area & Found Min Activity.Util Currently Removing Water from Radwaste Bldg
PNO-V-90-047B, updates 901120 Occurrence of Inadvertent Actuation of Safety Injection & Containment Spray Sys1990-11-23023 November 1990
PNO-V-90-047B:updates 901120 Occurrence of Inadvertent Actuation of Safety Injection & Containment Spray Sys
PNO-V-90-047A, on 901120,updates Occurrence of Inadvertent Actuation of Safety Injection & Containment Spray Sys1990-11-21021 November 1990
PNO-V-90-047A:on 901120,updates Occurrence of Inadvertent Actuation of Safety Injection & Containment Spray Sys
PNO-V-90-047, on 901120,actuation Signal Initiated by Plant Protection Sys While Testing PPS Channel1990-11-20020 November 1990
PNO-V-90-047:on 901120,actuation Signal Initiated by Plant Protection Sys While Testing PPS Channel
PNO-V-90-036, on 900910,small Amount of Contamination Found on Injured Worker Clothing During Transport to Hosp. Contaminated Clothing Removed Enroute to Hosp & Injuries to Worker Considered Minor.No Press Release Planned1990-09-10010 September 1990
PNO-V-90-036:on 900910,small Amount of Contamination Found on Injured Worker Clothing During Transport to Hosp. Contaminated Clothing Removed Enroute to Hosp & Injuries to Worker Considered Minor.No Press Release Planned
PNO-V-90-035, on 900804,fire Discovered in Noncontaminated Laundry Room in Units 2 & 3 Shared Radwaste Bldg.Caused by Overheated Clothing Dryer.No Radiological Release Resulted from Fire & No safety-related Equipment Affected1990-08-0606 August 1990
PNO-V-90-035:on 900804,fire Discovered in Noncontaminated Laundry Room in Units 2 & 3 Shared Radwaste Bldg.Caused by Overheated Clothing Dryer.No Radiological Release Resulted from Fire & No safety-related Equipment Affected
PNO-V-90-034, on 900728,unit 2 Was Shutdown to Inspect & Repair SG Feedrings,As Result of Degradation Found During Insp of Unit 3 SG Feedrings & Other Listed Work Was Performed1990-07-30030 July 1990
PNO-V-90-034:on 900728,unit 2 Was Shutdown to Inspect & Repair SG Feedrings,As Result of Degradation Found During Insp of Unit 3 SG Feedrings & Other Listed Work Was Performed
PNO-V-88-014, on 880219,inadvertent Safety Injection Actuation Occurred While Testing of Actuation Logic Matrix Was in Progress & W/Unit at 100% Power.Unit Stabilized W/O Complication & Safety Injection Components Restored1988-02-22022 February 1988
PNO-V-88-014:on 880219,inadvertent Safety Injection Actuation Occurred While Testing of Actuation Logic Matrix Was in Progress & W/Unit at 100% Power.Unit Stabilized W/O Complication & Safety Injection Components Restored
PNO-V-88-012, on 880211,moderate Earthquake,Measuring 4.7 on Richter Scale,Hit Whittier,Ca Area.No Seismic Alarms Activated at Plant.No Damage Identified at Site1988-02-11011 February 1988
PNO-V-88-012:on 880211,moderate Earthquake,Measuring 4.7 on Richter Scale,Hit Whittier,Ca Area.No Seismic Alarms Activated at Plant.No Damage Identified at Site
PNO-V-88-002, on 880116,reactor Shutdown Commenced for More than 48 H Due to Alarms on Main Generator Hydrogen Detraining Unit.Caused by Hydrogen Leak Into Stator Cooling Water Sys in Main Generator.Visual & Sonic Insps Performed1988-01-19019 January 1988
PNO-V-88-002:on 880116,reactor Shutdown Commenced for More than 48 H Due to Alarms on Main Generator Hydrogen Detraining Unit.Caused by Hydrogen Leak Into Stator Cooling Water Sys in Main Generator.Visual & Sonic Insps Performed
ML20234D1831987-12-28028 December 1987
PNS-V-87-009A:on 871209,Region V Reported Licensee Investigating Rept of Card Playing in Security Alarm Station.Disiplinary Action:Three Supervisors Terminated & Nine Security Officers Suspended
ML20237A1311987-12-0909 December 1987
PNS-V-87-009:on 871208,NRC Notified That Nine Security Officers & Two Supervisors Under Investigation for Alleged Card Playing While on Duty in Central Alarm Room.Licensee Believes Activity Caused No Degradation in Security Sys
PNO-V-87-076, on 871123-24,two Moderate Earthquakes Centered Near Westmoreland,Ca Occurred,Triggering Seismic Alarms at San Onofre.Unusal Event Declared.Plant Sys & Components Not Adversely Affected.Effects on Other Locations Noted1987-11-24024 November 1987
PNO-V-87-076:on 871123-24,two Moderate Earthquakes Centered Near Westmoreland,Ca Occurred,Triggering Seismic Alarms at San Onofre.Unusal Event Declared.Plant Sys & Components Not Adversely Affected.Effects on Other Locations Noted
PNO-V-87-067, on 871007,licensee Reported That Recently Completed Single Failure Analyses Had Identified Potential Single Failures Which Had Not Previously Been Known.Lists Potential Single Failures Associated W/Esfs1987-10-0808 October 1987
PNO-V-87-067:on 871007,licensee Reported That Recently Completed Single Failure Analyses Had Identified Potential Single Failures Which Had Not Previously Been Known.Lists Potential Single Failures Associated W/Esfs
PNO-V-87-065, on 871004,significant Aftershock Experienced from 871001 Earthquake.Aftershock Registered 5.5 on Richter Scale.Seismic Instruments Actuated at 0.014g at Unit 1.No Damage to Equipment Occurred1987-10-0505 October 1987
PNO-V-87-065:on 871004,significant Aftershock Experienced from 871001 Earthquake.Aftershock Registered 5.5 on Richter Scale.Seismic Instruments Actuated at 0.014g at Unit 1.No Damage to Equipment Occurred
PNO-V-87-063, on 871001,moderate Earthquake Experienced at Plant.Unusual Event Declared.No Damage Identified at Site. Util Headquarters Evacuated to Inspect for Structural Damage1987-10-0101 October 1987
PNO-V-87-063:on 871001,moderate Earthquake Experienced at Plant.Unusual Event Declared.No Damage Identified at Site. Util Headquarters Evacuated to Inspect for Structural Damage
PNO-V-87-059, on 870831,five People Involved in Operating Cooling Suction Valve 2HV-9378 Found Contaminated by I-131 Due to Unisolable Leak in Valve.Caused by Failure of Valve & Valve Packing.Nature of Failure Under Investigation1987-09-0101 September 1987
PNO-V-87-059:on 870831,five People Involved in Operating Cooling Suction Valve 2HV-9378 Found Contaminated by I-131 Due to Unisolable Leak in Valve.Caused by Failure of Valve & Valve Packing.Nature of Failure Under Investigation
PNO-V-87-047A, on 870621,interruption in Power to Phase B of non-1E Uninterruptible Power Supply Caused Sharp Reduction in Feedwater Control Valve for Steam Generator 88,causing Reactor Trip.Update Confirms Operation of Safety Functions1987-06-24024 June 1987
PNO-V-87-047A:on 870621,interruption in Power to Phase B of non-1E Uninterruptible Power Supply Caused Sharp Reduction in Feedwater Control Valve for Steam Generator 88,causing Reactor Trip.Update Confirms Operation of Safety Functions
PNO-V-87-047, on 870621,interruption in Power to Phase B of non-1E Uninterruptable Power Supply Caused Sharp Reduction in Feedwater Flow to Steam Generator 88 & Subsequent Reactor Trip.Caused by Loose Cable Plug Lug.Lugs Inspected1987-06-22022 June 1987
PNO-V-87-047:on 870621,interruption in Power to Phase B of non-1E Uninterruptable Power Supply Caused Sharp Reduction in Feedwater Flow to Steam Generator 88 & Subsequent Reactor Trip.Caused by Loose Cable Plug Lug.Lugs Inspected
PNO-V-87-021, on 870310,reactor Tripped Due to Turbine Trip from Grounded Exciter.Caused by Maint Personnel Dropping Exciter Brush in Rigging.Licensee Plans Shutdown of Unit for 1 Wk to Perform Maint1987-03-11011 March 1987
PNO-V-87-021:on 870310,reactor Tripped Due to Turbine Trip from Grounded Exciter.Caused by Maint Personnel Dropping Exciter Brush in Rigging.Licensee Plans Shutdown of Unit for 1 Wk to Perform Maint
PNO-V-87-017, on 870223,licensee Informed Region V That Press Release Made Re 870221 Discovery of Small Particle of Radioactive Matl in Employee Home.Caused by Exposure to Leaking Fuel Pins.Region Will Conduct Special Insp1987-02-24024 February 1987
PNO-V-87-017:on 870223,licensee Informed Region V That Press Release Made Re 870221 Discovery of Small Particle of Radioactive Matl in Employee Home.Caused by Exposure to Leaking Fuel Pins.Region Will Conduct Special Insp
PNO-V-87-009, on 870202,plant Worker Repeatedly Caused Portal Radiation Monitor to Alarm on Exit from Work Activities in Containment Bldg.Radioactive Matl Found on Inside Sleeve of Shirt.Survey Procedures Improved to Control Exposure1987-02-0505 February 1987
PNO-V-87-009:on 870202,plant Worker Repeatedly Caused Portal Radiation Monitor to Alarm on Exit from Work Activities in Containment Bldg.Radioactive Matl Found on Inside Sleeve of Shirt.Survey Procedures Improved to Control Exposure
PNO-V-86-092B, on 870112,licensee Submitted Rept Stating That Investigation of Potential Hand Exposure Incomplete. Occurrence of Exposure Not Established.Most Likely Exposure Source Would Involve Direct Contact W/Fuel Specks1987-01-13013 January 1987
PNO-V-86-092B:on 870112,licensee Submitted Rept Stating That Investigation of Potential Hand Exposure Incomplete. Occurrence of Exposure Not Established.Most Likely Exposure Source Would Involve Direct Contact W/Fuel Specks
PNO-V-86-092A, on 861216,insp Confirmed Licensee Dedicating Resources & Mgt to Resolve Potential Extremity Exposure. Medical Consultant Conferred W/Licensee Re Biological Indicators.Source Could Be Direct Contact W/Fuel Specks1986-12-17017 December 1986
PNO-V-86-092A:on 861216,insp Confirmed Licensee Dedicating Resources & Mgt to Resolve Potential Extremity Exposure. Medical Consultant Conferred W/Licensee Re Biological Indicators.Source Could Be Direct Contact W/Fuel Specks
PNO-V-86-092, on 861212,reported That Quarterly Exposure Limit for Worker Exceeded.Right Hand Received Dose of 511.99 Rem,Left Hand 160 Mrem & Whole Body 114 Mrem.Worker Involved in Oct 1986 Reactor Coolant Pump Seal Overhaul1986-12-12012 December 1986
PNO-V-86-092:on 861212,reported That Quarterly Exposure Limit for Worker Exceeded.Right Hand Received Dose of 511.99 Rem,Left Hand 160 Mrem & Whole Body 114 Mrem.Worker Involved in Oct 1986 Reactor Coolant Pump Seal Overhaul
PNO-V-86-091, on 861210 Turbine Tripped Due to Interruption of Power to non-1E Instrument Bus,Causing Reactor Trip. Event Under Investigation.Steam Bypass Control Sys Did Not Operate Because of Deenergized Instrument Bus1986-12-11011 December 1986
PNO-V-86-091:on 861210 Turbine Tripped Due to Interruption of Power to non-1E Instrument Bus,Causing Reactor Trip. Event Under Investigation.Steam Bypass Control Sys Did Not Operate Because of Deenergized Instrument Bus
ML20215C7271986-12-0505 December 1986
PNS-V-86-007A:investigation by Corporate Security Personnel of Unauthorized Manipulation of Plant Components Expanded to Approx 62 Individuals.No Indications of Addl Tampering Identified.Region V Inspector Met W/Fbi
ML20214U9571986-12-0303 December 1986
PNS-V-86-007:on 861129,red & Green Indicating Light Lenses Found Reversed for Various Equipment & on 861202,determined That 10 Circuit Breakers Manipulated.Unauthorized Component Manipulation Under Investigation.Fbi Assistance Requested
PNO-V-86-080, on 861113,unit Shut Down to Correct Lube Oil Leak on Inboard Motor Bearing of West Main Feed Pump. Leakage Was Through Labyrinth Seal Associated W/Bearing. Bearing Seal Disassembled for Evaluation1986-11-14014 November 1986
PNO-V-86-080:on 861113,unit Shut Down to Correct Lube Oil Leak on Inboard Motor Bearing of West Main Feed Pump. Leakage Was Through Labyrinth Seal Associated W/Bearing. Bearing Seal Disassembled for Evaluation
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 Progress1986-10-23023 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-86-066, on 860929,shutdown Commenced Due to Excessive Leakage from Reactor Coolant Pump Seal.Seals to Be Replaced & Addl Maint Performed1986-09-30030 September 1986
PNO-V-86-066:on 860929,shutdown Commenced Due to Excessive Leakage from Reactor Coolant Pump Seal.Seals to Be Replaced & Addl Maint Performed
PNO-V-86-052, on 860805,reactor Trip Initiated by Turbine Load Rejection When Control Valves Closed,Causing Insurge of Water Into Pressurizer.Cause Under Investigation1986-08-0505 August 1986
PNO-V-86-052:on 860805,reactor Trip Initiated by Turbine Load Rejection When Control Valves Closed,Causing Insurge of Water Into Pressurizer.Cause Under Investigation
PNO-V-86-049, on 860729 & 30,pressure Transmitter 459 Failed Low Resulting in Steam Flow/Feed Flow Mismatch Trip Circuits Becoming Inoperable.Caused by Failed Electric Card in Pressure Transmitter Amplifier.Amplifier Replaced1986-07-30030 July 1986
PNO-V-86-049:on 860729 & 30,pressure Transmitter 459 Failed Low Resulting in Steam Flow/Feed Flow Mismatch Trip Circuits Becoming Inoperable.Caused by Failed Electric Card in Pressure Transmitter Amplifier.Amplifier Replaced
PNO-V-86-045, on 860717,reactor Trip Occurred from 3% Power. Caused by Momentary Drop in Voltage Through break-before- Make Switch.Momentary Drop Allowed Permissive P7 to Unblock & Trip Signal Went to Reactor Protection Sys1986-07-17017 July 1986
PNO-V-86-045:on 860717,reactor Trip Occurred from 3% Power. Caused by Momentary Drop in Voltage Through break-before- Make Switch.Momentary Drop Allowed Permissive P7 to Unblock & Trip Signal Went to Reactor Protection Sys
PNO-V-86-043, on 860715,criticality Achieved Following Eighth Refueling Outage.Unit Shutdown for 236 Days Following 851121 Loss of Power & Water Hammer Event.Unit Scheduled to Go on-line After Completion of Low Power Physics Testing1986-07-15015 July 1986
PNO-V-86-043:on 860715,criticality Achieved Following Eighth Refueling Outage.Unit Shutdown for 236 Days Following 851121 Loss of Power & Water Hammer Event.Unit Scheduled to Go on-line After Completion of Low Power Physics Testing
PNO-V-86-041, on 860713,earthquake Measuring 5.7 on Richter Scale & Aftershocks Occurred Actuating Seismic Alarms.Insp Procedures Implemented.No Abnormal Condition Noted.Effects Also Felt at Listed Nonpower Reactors1986-07-14014 July 1986
PNO-V-86-041:on 860713,earthquake Measuring 5.7 on Richter Scale & Aftershocks Occurred Actuating Seismic Alarms.Insp Procedures Implemented.No Abnormal Condition Noted.Effects Also Felt at Listed Nonpower Reactors
PNO-V-86-039, on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented1986-07-0808 July 1986
PNO-V-86-039:on 860708,earthquake w/6.0 Reading on Richter Scale Actuated Seismic Alarms & Recording Instruments. Procedures for Visual Insp of Plant Equipment & Start Test of Diesel Generators Implemented
PNO-V-86-032, on 860612,facility Resumed Operation After Second Refueling Outage.Outage Included Replacement of Reactor Coolant Pump Seal Packages & Testing motor-operated Valves Per IE Bulletin 86-0031986-06-16016 June 1986
PNO-V-86-032:on 860612,facility Resumed Operation After Second Refueling Outage.Outage Included Replacement of Reactor Coolant Pump Seal Packages & Testing motor-operated Valves Per IE Bulletin 86-003
PNO-V-86-022, on 860413,reactor Tripped After Achieving Criticality. Caused by Minor Control Rod Misalignments. Incorrect Estimated Critical Position Caused by Incorrect Xenon Tables in Operations Physics Data Summary Book1986-04-24024 April 1986
PNO-V-86-022:on 860413,reactor Tripped After Achieving Criticality. Caused by Minor Control Rod Misalignments. Incorrect Estimated Critical Position Caused by Incorrect Xenon Tables in Operations Physics Data Summary Book
ML20210K7391986-04-22022 April 1986
PNS-V-86-002:on 860421,shots Fired by Unknown Assailant at Contractor Employee Making Routine Motorized Theft Abatement Tour of Controlled Area Known as Mesa.Six Bullets Hit Windshield.Authorities Notified
PNO-V-86-012, on 860327,loss of Both Shutdown Cooling Trains Experienced Due to Loss of Pump Suction & Cavitation.Caused by Reactor Vessel Water Vortexing Causing Air to Be Pulled Into Shutdown Cooling Lines1986-03-28028 March 1986
PNO-V-86-012:on 860327,loss of Both Shutdown Cooling Trains Experienced Due to Loss of Pump Suction & Cavitation.Caused by Reactor Vessel Water Vortexing Causing Air to Be Pulled Into Shutdown Cooling Lines
PNO-V-86-009, on 860227,unusual Event Declared When Small Leak from Pressurizer Instrument Top Weld Discovered. Borating Began to Achieve Necessary Shutdown Margin.Cooldown & Leak Repair Planned1986-02-27027 February 1986
PNO-V-86-009:on 860227,unusual Event Declared When Small Leak from Pressurizer Instrument Top Weld Discovered. Borating Began to Achieve Necessary Shutdown Margin.Cooldown & Leak Repair Planned
PNO-V-85-085, on 851210,reactor Tripped from 100% Power. Caused by Low Steam Generator Water Level Resulting from Main Feedwater Header Containment Isolation Valve Drifting Shut.All ESF Sys Functioned as Required.Reactor Restarted1985-12-11011 December 1985
PNO-V-85-085:on 851210,reactor Tripped from 100% Power. Caused by Low Steam Generator Water Level Resulting from Main Feedwater Header Containment Isolation Valve Drifting Shut.All ESF Sys Functioned as Required.Reactor Restarted
ML20138B4871985-12-10010 December 1985
PNO-IIT-85-002D:on 851121,unit Tripped.Incident Investigation Team Will Complete Remaining Interviews & Review Results of Licensee Investigaton.Prime Hypothesis Explaining Events Described in PNO-IIT-85-002B Encl
1999-03-05
[Table view]
Category:TEXT-INSPECTION & AUDIT & I&E CIRCULARS
MONTHYEARPNO-IV-99-043, on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed1999-10-18018 October 1999
PNO-IV-99-043:on 991016,earthquake of Magnitude 7 Occurred. Plant Operations Were Not Disrupted.Unusual Event Classifications Were Exited within 1 H at Both Facilities.No Damage Was Indicated & No Residual Plant Effects Observed
IR 05000361/19990121999-10-15015 October 1999
Insp Repts 50-361/99-12 & 50-362/99-12 on 990808-0918. Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
IR 05000361/19990091999-08-27027 August 1999
Insp Repts 50-361/99-09 & 50-362/99-09 on 990627-0807. Non-cited Violations Identified.Major Areas Inspected:Maint, Operations,Engineering & Plant Support
IR 05000361/19990081999-07-0909 July 1999
Insp Repts 50-361/99-08 & 50-362/99-08 on 990516-0626.One Violation Noted & Being Treated as Noncited Violation:Major Areas Inspected:Operations,Maint,Engineering & Plant Support
ML20196B5951999-06-0909 June 1999
Errata to Insp Repts 50-361/99-04 & 50-362/99-04.Corrected Pages Replace Pps 14-17 of Insp Repts
IR 05000361/19990061999-06-0808 June 1999
Insp Repts 50-361/99-06 & 50-362/99-06 on 990404-0515.Non- Cited Violations Identified.Major Areas Inspected:Aspects of Licensee Operations,Maint,Engineering & Plant Support
IR 05000361/19980181999-06-0202 June 1999
Revised Pages 1-5,7,10 & 11 for Insp Repts 50-361/98-18 & 50-362/98-18
ML20207E6701999-06-0202 June 1999
Corrected NOV from Insp on 981109-1218.Violations Noted:On 980907,Procedure SO23-1-3.1 Not Implemented by Operators,In That,When Chiller E335 Lube Oil Level Was Out of Sight High in Upper Sight Glass for More than 15
IR 05000361/19990071999-05-18018 May 1999
Partially Withheld Insp Repts 50-361/99-07 & 50-362/99-07 on 990426-29.Major Areas Inspected:Licensee Physical Security Program.Details Withheld (Ref 10CFR2.790)
IR 05000361/19990051999-05-10010 May 1999
Insp Repts 50-361/99-05 & 50-362/99-05 on 990426-30.No Violations Noted.Major Areas Inspected:Plant Support.Failure to Survey Radioactive Matl Prior to Removal from Restricted Area Identified as Unresolved Pending Investigation
IR 05000361/19993011999-05-0606 May 1999
NRC Operator Licensing Exam Repts 50-361/99-301 & 50-362/99-301 Administered on 990416.Exam Results:Two RO & Two SRO Applicants Passed Exam
IR 05000361/19990031999-04-20020 April 1999
Insp Repts 50-361/99-03 & 50-362/99-03 on 990205-0312.One Violation Noted & Being Treated as non-cited Violation.Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support
IR 05000361/19990041999-04-20020 April 1999
Insp Repts 50-361/99-04 & 50-362/99-04 on 990221-0403.Three Violations Noted & Being Treated as non-cited Violations. Major Areas Inspected:Aspects of Licensee Operations,Maint, Engineering & Plant Support
IR 05000361/19990011999-03-30030 March 1999
Insp Repts 50-361/99-01 & 50-362/99-01 on 990103-0220.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
ML20211K4341999-03-26026 March 1999
Partially Withheld Investigation Rept 4-1998-041. Noncompliance Noted.Major Areas Investigated:Coercion & Discrimination Against Access/Ffd Audit Team by SCE Management
ML20204B3471999-03-16016 March 1999
Notice of Violation from Insp on 981109-1218.Violation Noted:Train B Emergency Chilled Water Sys Was Inoperable on Two Separate Periods (980806-26 & 0904-25),while Units 2 & 3 Were in Mode 1.No Action Was Taken to Restore Operability
PNO-IV-99-018, on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials1999-03-0505 March 1999
PNO-IV-99-018:on 990305,declared SONGS Units 2 & 3 Alert Because Potential Bomb Threat Occurred.Device Was 12-inch long,2-inch Diameter Copper Pipe,With Both Ends Capped. Licensee Notified State & Local Officials
ML20211K4421999-02-0505 February 1999
Partially Withheld Investigation Rept 4-1998-043.No Noncompliances Noted.Major Areas Investigated:Discrimination Against Contract Employee by Contract Foreman for Reporting Safety Concerns
IR 05000361/19980191999-01-28028 January 1999
Insp Repts 50-361/98-19 & 50-362/98-19 on 981112-990102.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
ML20211K4511999-01-26026 January 1999
Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program
IA-99-234, Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program1999-01-26026 January 1999
Partially Withheld Investigation Rept 4-1998-045.No Nonconformance Noted.Major Areas Investigated:Discrimination Against Former Contract Employee by Supervisor for Reporting Concerns to Nuclear Safety Concerns Program
ML20199H4481999-01-15015 January 1999
Notice of Violation from Insp on 981109-1218.Violation Noted:On 980907,procedure SO23-1-1.3 Not Implemented by Operators,Therefore Chiller E335 Lube Oil Pump Operating Time Exceeded Approximately 15 Seconds
ML20199H4521999-01-15015 January 1999
Insp Repts 50-361/98-18 & 50-362/98-18 on 981109-1218. Violations Noted.Major Areas Inspected:Operations, Maintenance & Engineering
ML20206R2091999-01-0707 January 1999
Notice of Violation from Insp on 981207-11.Violations Noted:Workers Did Not Inform Health Physics Control Personnel of Work Location Prior to Entry in Radiological Controlled Area
IR 05000361/19980221999-01-0707 January 1999
Insp Repts 50-361/98-22 & 50-362/98-22 on 981207-11. Violations Noted.Major Areas Inspected:Announced Insp Was Conducted to Review Portions of Radiation Protection Program
IR 05000361/19980141999-01-0404 January 1999
Insp Repts 50-361/98-14 & 50-362/98-14 on 981019-1106. Violations Noted.Major Areas Inspected:Review of Design & Licensing Basis for Component CWS & Associated Support Sys & Review of 10CFR50.59 Safety Evaluation Program
ML20198S7971999-01-0404 January 1999
Exam Repts 50-361/98-302 & 50-362/98-302 on 981115-1203.Exam Results:Out of Nine SRO Applicants & Five RO Applicants,Ten Applicants Satisfied Requirements of 10CFR55 & Appropriate Licenses Have Been Issued
ML20198S9171999-01-0404 January 1999
Notice of Violation from Insp on 981019-1106.Violation Noted:As of 981106,appropriate Quality Standards as Described in UFSAR Section 9.2.2.1 & in App 3.2A Not Specified & Included in Design Documents for Electrical
IR 05000361/19980211998-12-30030 December 1998
Insp Repts 50-361/98-21 & 50-362/98-21 on 981207-11. Violations Noted.Major Areas Inspected:Licensee Physical Security Program
ML20198N5221998-12-30030 December 1998
Notice of Violation from Insp on 981207-11.Violation Noted: Approximately 70% of Security Officers Had Not Been Trained or Qualified with 9 Milimeter Rifle Prior to Being Allowed to Perform on-shift Security Duties with That Rifle
IR 05000361/19980201998-12-17017 December 1998
Insp Repts 50-361/98-20 & 50-362/98-20 on 981207-11.No Violations Noted.Major Areas Inspected:Plant Support
IR 05000361/19980171998-12-14014 December 1998
Insp Repts 50-361/98-17 & 50-362/98-17 on 981004-1114.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
IR 05000206/19980191998-12-0404 December 1998
Insp Repts 50-206/98-19 & 50-301/98-19 on 981004.No Violations Noted.Major Areas Inspected:Licensee Operations, Engineering,Maint & Plant Support
ML20203B7051998-11-0404 November 1998
EN-98-065:informs Commission That Staff Intends to Exercise Enforcement Discretion Per Section VII.B.6 of Enforcement Policy & Not Propose Civil Penalty Nor Issue NOV to Licensee for Severity Level III Violation
IR 05000361/19980161998-10-20020 October 1998
Insp Repts 50-361/98-16 & 50-362/98-16 on 980823-1003.No Violations Noted.Major Areas Inspected:Operations, Maintenance,Engineering & Plant Support
ML20154H3131998-10-0707 October 1998
Notice of Violations from Insp on 980713-17.Violations Noted:Licensee Had Not Established Specific Procedures for Employment of Compensatory Measures Resulting from Security Computer Failure
ML20154H3171998-10-0707 October 1998
Insp Repts 50-361/98-12 & 50-362/98-12 on 980713-17. Violations Noted.Major Areas Inspected:Licensee Physical Security Program
IR 05000361/19980151998-09-25025 September 1998
Insp Repts 50-361/98-15 & 50-362/98-15 on 980824-28.No Violations Noted.Major Areas Inspected:Licensee Physical Security Program
PNO-IV-98-041, on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades1998-09-18018 September 1998
PNO-IV-98-041:on 980918,control Room Operators Observed Alarm on One Channel of Main Condenser Steam Jet Air Ejector Radiation Monitoring Equipment,Which Indicated That Activity of Condenser Exhaust Had Increased by About Two Decades
IR 05000361/19980101998-09-0202 September 1998
Insp Repts 50-361/98-10 & 50-362/98-10 on 980817-21.No Violations Noted.Major Areas Inspected:Plant Support
IR 05000361/19980131998-09-0101 September 1998
Insp Repts 50-361/98-13 & 50-362/98-13 on 980712-0822.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
ML20237D7261998-08-21021 August 1998
Insp Repts 50-361/98-11 & 50-362/98-11 on 980720-24.No Violations Noted.Major Areas Inspected:Exposure Controls, Controls of Radioactive Matl & Contamination,Surveying & Monitoring & QA Oversight of Radiation Protection Program
IR 05000361/19980081998-08-19019 August 1998
Insp Repts 50-361/98-08 & 50-362/98-08 on 980727-31.No Violations Noted.Major Areas Inspected:Plant Support
IR 05000361/19980091998-08-0404 August 1998
Insp Repts 50-361/98-09 & 50-362/98-09 on 980709-10.No Violations Noted.Major Areas Inspected:Operational Status of Emergency Preparedness Program,Using Simulator Walkthrough to Focus on Training of Assigned Key Roles for Emergencies
ML20236V6041998-07-22022 July 1998
Notice of Violation from Insp on 980607-0711.Violation Noted:Abnormal Operating Instruction S023-13-3,temporary Change Notice 4-2,not Appropriate for Circumstances in That Procedure Did Not Differentiate Between Various Weather
IR 05000361/19980071998-07-22022 July 1998
Insp Repts 50-361/98-07 & 50-362/98-07 on 980607-0711. Violation Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
IR 05000361/19983011998-07-15015 July 1998
NRC Operator Licensing Exam Repts 50-361/98-301 & 50-362/98-301 Administered on 980614-19.All Applicants Passed Written Exam.Seven of Eight Applicants Passed All Sections of Operating Test
IR 05000361/19980061998-06-30030 June 1998
Insp Repts 50-361/98-06 & 50-362/98-06 on 980426-0606.No Violations Noted.Major Areas Inspected:Operations,Maint, Engineering & Plant Support
IR 05000361/19980011998-05-29029 May 1998
Insp Repts 50-361/98-01 & 50-362/98-01 on 980202-0410.No Violations Noted.Major Areas Inspected:Maintenance, Engineering & Plant Support
ML20248C3611998-05-27027 May 1998
Notice of Violation from Insp on 980315-0425.Violation Noted:Instrument & Control Technicians Failed to Implement Procedure SO123-II-9-3
1999-08-27
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DATE: 11/26/85 PRELIMINARY NOTIFICATION OF EVENT OR UNUSUAL OCCURRENCE--PNO-IIT-85-2B This preliminary notification constitutes EARLY notice of events of POSSIBLE safety or public interest significance. The information presented is preliminary, requires further evaluation and is basically all that is known by the IIT on this date.
FACILITY: Southern California Edison Company Emergency Classification Unit 1 X Notification of Unusual Event Docket No. 50-206 Alert Site Area Emergency General Emergency Not Applicable
SUBJECT:
Status Report from NRC Incident Investigation Team The Incident Investigation Team (IIT) remains onsite gathering data, conducting interviews, inspecting equipment, meeting with the licensee, concurring in licensee action plans and analyzing facts. A preliminary sequence of everits has been developed by the IIT and is attached. A set of preliminary hypr theses e explaining the significant events has been developed by the IIT'and are'being investigated.
All interviews should be completed on November 27, 1985. All licensee action plans for further troubleshooting and uncovering remaining event related information should be. finalized on November 28, 1985. Assuming the combination of information possessed by the IIT and the licensee action plans to uncover additional facts appear adequate to project closure of significant open issues, the IIT intends to depart the site by December 1, 1985, and to reassemble in Bethesda, Maryland.
A final status report'will be issued prior to the IIT's departure from the site.
CONTACT: T. Martin ,
W. Lanning
1714-492-2641 714-492-2641
, ."
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% <*,, N 11/26/85 Rev 2 , - PRELIMINARY SEQUENCE OF EVENTS INCIDENT INVESTIGATION TEAM San Onofre Nuclear Generating Station Unit 1 Plant Trip Initial C*nditions, November 21, 1985 Unit. operating at 60% power-Saltwater leak into main condenser, south circulating water pump stopped and numbers 1 and 4 water boxes removed from service
' Block ~ valves for PORVs closed Troubleshooting of ground on 4160V bus 1C in progress Bus 1C removed from X winding of auxiliary transformer C and being supplied by bus IA which was tied to auxiliary transformer A supplied by main. generator.
, - _ Steam generator blowdown ongoing about 100 gpm per generator Transient Initiator Transformer C differential relay actuates.to de-energize transformer
-04:51 Circuit breakers 4032 and 6032 open to isolate transformer C--
cfrom switchyard.
~ Circuit breaker 12C02 opens to isolate transformer C from bus 2C Bus 2C and vital bus 4 de-energized Systems Response / Operator Actions to Loss of Power
'The following equipment de-energized:
East feedwater pump (G-3A)
Southeast condensate pump .(G-1B) -
Northeast condensate pump (G-1A).
East' heater drain ~ pump (G-36A)
- North turbine plant cooling water pump _
Switchyard supply ~
South saltwater coolng pump Auxiliary' saltwater-cooling pump.
Diesel generator number 2' starts autonatically, ar.d per design.
~
it does not load ,
e 04:51+, Operators manually trip reactor (per procedure); turbine trips -
3 , '
7y, F ' Operators push: unit trip button:(opens main generator output' ~
, ^ 7 5 ;bre'aker and trips, turbine)i w c, .
I h < iTurbinekrivik auidliary' feedwater pump starts' on low' steam
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; m .;_ A 'breakerd,4012-and;6012 open resulting in'. loss ofLall- ^N 0.4:51+.- Circuit
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Diesel'generat$r number 1 starts automatically, and per design does'not load
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A loud " ban.g" is heard
~
' unknown Loqpressurefeedwaterheaterruptured
~
04:53+ Automatic sequencer fails to realign power from busses IC and 2C to busses IA and 2B.
Operator takes actions to realign breakers t
- unknown Foam fire suppression system actuates near' lube oil reservoir
. 04:54+ . Turbine-driven AFW pump delivering 100-150 gpm to each steam generator. (Ti.ne estimated' to be' three minutes after reactor trip.)_
. Operator unable to close circuit breaker 4012
~
unknown 04:55+ Circuit breaker 6012 closed by operator on second attempt i _ Operators b'egan to re-energize busses 1A and IC, IB, and 2C
~
104:56+ : Motor-driven auxiliary feedwater pump starts automatically after
-busses re-energized. Total flow about- 135-150:gpm to each steam:
generator.
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104~:57 ' All 4160 and 480V busses energized g . . Operators respond:to safety _ injection actuation annunicator.
" Operator: verified.no actuation. occurred or required.
J Operators begin'to re-energize' equipment.
, Cooldown of reactor coolant system more rapid than expected.
Low pressurizer level (5%) and pressure (1900 psig)..
~
Operator started south charging pump 7
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harth charging pump starts automatically Suction of both charging pumps switched automatically to RWST Operator stops AFW flow by closing throttle valves "
Operator increased AFk flow to about 25 gpm to each steam c generator Plant equipment operatcr dispatched to close main steam block ___
valves unknown Steam generator blowdown re-established to 100 gpm (radiation ---
monitors reset)
Emergency response by fire brigade -
05:06 Unusual event declared Prompt Notification Report made to NRC A loud " bang" was heard. Plant equipment operator heard water hammer and observed steam on turbine building J=
mezzanine __
05:08 Circuit breaker 4012 closed by operator --
05:15 Started reactor coolant pump "B" Reactor cooling pump "B" high thrust bearing temperature alarm annunciated ""l 05:23 Started reactor coolant pumps "A" and "C" ,,
=.mm Wide range level indication off-scale low in all three steam generators ---
05:25 Operators stopped reactor coolant pump "B" Flow increased to steam generators "A" and "C" from 25 gpm to 40 gpm each -
5:30 Blowdown from steam generators secured Wide range water level indication on-scale in A and C steam generators Personnel wear steam suits in three attempts to identify source '5 of feedwater leak unknown Feedwater leak identified on "B" steam generator from check ==
valve FWS-378 "
06:00 Reactor coolant system cooled down to Mode 4 ---
p 1 , ,
unknown Sandbags are placed at entrance to chemical feed room 4
'08:35' Turbine-driven auxiliary feedwater pump s'ecured .
09:10 RHR suction valve' MOV-813 interlock, fails to clear although RCS pressure below 400 psig 09:12 Containment entry made to isolate hot leg injection 09:18 MOV-813 opened 1
~09:20+ RHR flow establish'ed 1
^9:40 Unusual event terminated. both.RHR pumps in service 10:45 Feedwater leakage manually isolated 15:08 Entered Mode 5 x
unknown Containment entry found damaged pipe' supports and insulation s v a <
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