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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029D1621994-04-26026 April 1994 LER 93-007-00:on 931128,EDG 3G002 Output Breaker Tripped. Caused by Two Failed Bolts.Corrective Action:Failed Bolts Were Replaced & tested.W/940426 Ltr ML20046C5531993-08-0303 August 1993 LER 93-004-00:on 930705,reactor Tripped Due to Loss of Vacuum.Replaced Failed Instrument Air Tubing & Inspected Tubing for Units 2 & 3.W/930803 Ltr ML20045F0021993-07-0101 July 1993 LER 91-007-01:on 910410,reactor Manually Tripped on Indication of Complete Loss of Controlled Bleedoff Flow from RCP P004.Caused by Wear on Seal & Rotating Baffle.Baffle Repaired & Baffle Bolts Replaced W/New Bolts ML20045E6981993-06-28028 June 1993 LER 93-003-00:on 930527,discovered Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves secured.W/930628 Ltr ML20045B1731993-06-0909 June 1993 LER 92-013-00:on 921209,identified Deficiency Involving Check Valve Test Methodology.Applicable Check Valve Procedure Modified.Applicable SONGS Units 2 & 3 IST Implementing Procedures Will Be Evaluated ML20024H0791991-05-13013 May 1991 LER 91-002-00:on 910412,inadvertent Opening of Containment Purge Sys Isolation Valve Occurred.Caused by Opening of 3HV-9821 Using CR Handswitch for Valve.Valve Closed. Surveillance Procedure revised.W/910513 Ltr ML20024H0451991-05-10010 May 1991 LER 91-007-00:on 910410,reactor Manually Tripped on Indication of Complete Loss of Controlled Bleedoff from Rcp. Caused by Shift in Position of RCP Rotating Baffle.Baffle Inspected,Repaired & re-installed W/New bolts.W/910510 Ltr ML20024G7431991-04-24024 April 1991 LER 91-006-00:on 910325,toxic Gas Isolation Sys Train a Actuated on High Ammonia Gas Level While Troubleshooting 910324 Failure of Channel.Caused by Location of Jumper Used to Bypass Circuitry.Jumper Will Be relocated.W/910424 Ltr ML20029A6811991-02-25025 February 1991 LER 91-001-00:from 910119-21,fuel Movements Performed within Spent Fuel Storage Pool W/O Concurrent Operation of post-accident Cleanup Unit.On 910125,heater Pilot Switch Mispositioned.Caused by Inadequate review.W/910225 Ltr ML20028H6861991-01-22022 January 1991 LER 90-014-00:on 901223,containment Spray Sys Train B Pump Discharge Pressure Indicator 3PI-0303-2 Did Not Display Correct Pressure Reading.Caused by Metallic Particle Near Feedback Coil.Transmitter replaced.W/910122 Ltr ML19332C7921989-11-20020 November 1989 LER 88-035-01:on 881216,determined That Plant Operated at Estimated Actual Power in Excess of 102% from 831223-840104. Caused by Mfg Defect of Feedwater Flow Venturi Tap.Venturi Repaired & Subsequently replaced.W/891120 Ltr ML20024E4251983-08-0505 August 1983 LER 83-067/01T-0:on 830718,determined That Routine 6-month Surveillance Conducted in Feb 1983 Had Not Demonstrated Operability of Fire Panel 3L-198.Caused by Inoperability of Fire Detection instrumentation.W/830805 Ltr ML20024E4721983-08-0202 August 1983 LER 83-076/03L-0:on 830703,during Mode 5,pilot Flames of Trains a & B Toxic Gas Isolation Sys Butane/Propane Monitors Found Extinguished.Caused by Low Alarm Setpoint.Low Alarm Setpoints raised.W/830802 Ltr ML20024E4231983-08-0101 August 1983 LER 83-066/03L-0:on 830701,during Creacus Surveillance Testing,Train B Declared Inoperable After Emergency Chilled Water Unit E-335 Failed to Start.Caused by Malfunction of Control Circuitry or Power Supply breaker.W/830801 Ltr ML20024E4611983-08-0101 August 1983 LER 83-046/01T-0:on 830714,review of Incomplete Abnormal Valve Alignment Record Revealed That Valves MU-075 & MU-076 Improperly Closed During Fuel Transfer.Caused by Improper Execution of Administrative controls.W/830801 Ltr ML20024D8981983-07-29029 July 1983 LER 83-073/01T-0:on 830714,discovered That Certain Core Protection Calculator Addressable Constants in Channels B & D Did Not Comply W/Most Recent Values in Log.Caused by Default Constants Being Left in channels.W/830729 Ltr ML20024D5531983-07-27027 July 1983 LER 83-044/01T-0:on 830711,2-inch Manual Isolation Valve Opened to Provide Svc Air to Support Work in Containment. Caused by Personnel Ignorance of Tech Specs.Personnel disciplined.W/830727 Ltr ML20024D5681983-07-25025 July 1983 LER 83-043/01T-0:on 830708,train B Emergency Chiller E-335 Declared Inoperable,Rendering Equipment Inoperable in Rooms Where Chilled Water Provided.Caused by Control Circuitry or Mechanical Malfunction in Power Supply breaker.W/830725 Ltr ML20024D6031983-07-21021 July 1983 LER 83-071/03L-0:on 830621,during Surveillance Testing, Diesel Generator 2G002 Declared Inoperable When Generator Failed to Start.Caused by Closed Air Supply Valve MU082. Valve opened.W/830721 Ltr ML20024C7611983-06-28028 June 1983 LER 83-061/03L-0:on 830529,core Protection Calculator Channel C Declared Inoperable.Caused by Loop 2A Cold Leg Temp Resistor to Current Converter 2TT-9179-3 Out of calibr.T-cold Loop recalibr.W/830628 Ltr ML20023B8521983-03-31031 March 1983 Revised LER 83-005/01X-1:on 830222,observed Loose Snubbers & Hangers Associated W/Two Sampling Valves (3HV508 & 3HV517) of Rcs.Caused by Removal for Maint Performed on Associated Components.Snubbers Reconnected ML20028F4291983-01-13013 January 1983 LER 82-170/03L-0:on 821214,review of Chart Recordings of RCS Cold Leg Temp Indicated Heatup/Cooldown Rate Limits Exceeded on Three Occasions.Caused by Inability to Properly Control Shutdown Cooling Sys Flow.Personnel Counseled ML20028F3661983-01-11011 January 1983 LER 82-168/03L-0:on 821212,indicated Position for Shutdown Control Element Assembly 12 Went from 148 Inches to 120 Inches Resulting in Reactor Trip.Caused by Failure of Reed Switch.Switch Replaced.No Further Corrective Action Planned ML20028D9531983-01-0808 January 1983 LER 82-007/03L-0:on 821211,during Mode 5,review of Strip Chart Recordings of RCS Temps During Filling & Venting Operations on 821210 Indicated RCS Heatup Rate Exceeded. Caused by Inadequate Attention to Heatup Restrictions ML20028D9611983-01-0707 January 1983 LER 82-165/03L-0:on 821209,while in Mode 1,discovered Two Snubbers,Components of Pipe Support S2-FW-189-HO13,damaged & Inoperable.Cause Undeterminable.Engineering Analysis Performed Satisfactorily.Snubbers Replaced ML20028D8981983-01-0707 January 1983 LER 82-163/03L-0:on 821208,during Mode 1, Auxiliary Feedwater Pump 2P-140 Tripped on Overspeed.Caused by Failure of Resistor in Pump Speed Sensor Circuitry. Resistor Replaced ML20028D8471983-01-0606 January 1983 LER 82-162/03L-0:on 821207,w/plant in Mode 1,low Pressure Tubine Stop Valve 2UV-2200V on Low Pressure Turbine 3 Failed to Fully Close.Caused by Excessive Galling Between Disc Stub Shaft & Casing Bore.Stub Shaft Cleaned ML20028D9171983-01-0505 January 1983 LER 82-155/03L-0:on 821206,two Fire Spray Sys in Cable Spreading Room Declared Inoperable in Order to Repair Leaking Valve.Caused by Minor Leakage Due to Damaged Seating Surfaces of Manual Shutoff Valve SA2301MU121.Valve Replaced ML20028D9471983-01-0505 January 1983 LER 82-161/03L-0:on 821206,condensation Storage Tank T-120 Water Level Fell Below Tech Spec.Caused by Inadequate Makeup Water Control.Operators Reinstructed.Engineering Evaluation Underway ML20028D9481983-01-0404 January 1983 LER 82-005/03L-0:on 821205,during Mode 5,diesel Generator 3GOO3 Taken Out of Svc Leaving Boration Flow Paths W/O Emergency Power Sources.Caused by Personnel Error Due to Failure to Recognize Consequences.Personnel Counseled ML20028D2991982-12-29029 December 1982 LER 82-153/03L-0:on 821130,following Turbine Trip,Low Pressure Turbine Stop Valve 2UV-2200R Failed to Close.Caused by Excessive Galling Between Disc Stub Shafts & Casing Bore. Clearance Between Shaft & Bore Increased ML20028D3031982-12-29029 December 1982 LER 82-154/03L-0:on 821130,following Turbine Trip,Low Pressure Turbine Stop Valve 2UV-2200R Failed to Close.Caused by Excessive Galling Between Disc Stub Shafts & Casing Bore. Clearance Between Shaft & Bore Increased ML20028D3011982-12-23023 December 1982 LER 82-157/03L-0:on 821124,samples from Control Room Emergency Air Cleanup Sys Train a Charcoal Absorber Failed to Satisfy Methyl Iodine Removal Capability.Caused by Activated Charcoal Degradation.Charcoal Replaced ML20028D3041982-12-23023 December 1982 LER 82-004/03L-0:on 821124,samples from Control Room Emergency Air Cleanup Sys Train a Charcoal Absorber Failed to Satisfy Methyl Iodine Removal Capability.Caused by Activated Charcoal Degradation.Charcoal Replaced ML20028B9211982-11-18018 November 1982 LER 82-131/03L-0:on 821020,auxiliary Feedwater Pump 2P-141 Declared Inoperable.Caused by Dirt on Oil Filter Preventing Valve 2HV4731 from Stroking Fully Open.Oil Filter Replaced & Valve Tested Successfully ML20027C9611982-10-19019 October 1982 LER 82-114/01T-0:on 821017,during Surveillance Testing in Mode 4,containment Cooling Fan 2E-402 Failed to Start. Caused by Faulty Fan Breaker.Breaker Replaced ML20027C1641982-09-30030 September 1982 LER 82-105/03L-0:on 820831,during Mode 2 Operation,Auxiliary Feedwater Pump 2P-504 Declared Inoperable.Caused by Leaky Threaded Plug on Pump Discharge Casing.Threads Cleaned, Graffoil Applied & Plug Reinstalled ML20052H5911982-05-10010 May 1982 LER 82-011/01T-0:on 820313,only Operable Control Room Airborne Radiation Monitor Removed from Svc,Violating Tech Spec 3.3.2.b for Approx 2-h.Caused by Personnel Error. Personnel Cautioned ML20050L1931982-03-30030 March 1982 LER 82-003/01T-0:on 820314,unplanned Dilution of RCS Resulted When Operators Were Trying to Restore Shutdown Cooling Flow.Caused by Two Manual Valves Being Partially Open Simultaneously While One Being Opened & Other Closed ML20050L1861982-03-30030 March 1982 LER 82-002/01T-0:on 820314,shutdown Cooling Lost.Caused by Sys Malfunction or Operator Error,Allowing Pressurized Nitrogen to Enter Shutdown Cooling Pump Suction Line When Purification Sys Filter Was Backflushed.Procedures Revised ML20049J9241982-03-12012 March 1982 LER 82-001/03L-0:on 820214,during Initial Fuel Load,Control Room Emergency Air Cleanup Sys Charcoal Filters (E-419 & A-206) Were Saturated W/Water.Caused by Operator Opening Isolation Valve.Filters Replaced & Sys Returned to Svc 1994-04-26
[Table view] Category:RO)
MONTHYEARML20029D1621994-04-26026 April 1994 LER 93-007-00:on 931128,EDG 3G002 Output Breaker Tripped. Caused by Two Failed Bolts.Corrective Action:Failed Bolts Were Replaced & tested.W/940426 Ltr ML20046C5531993-08-0303 August 1993 LER 93-004-00:on 930705,reactor Tripped Due to Loss of Vacuum.Replaced Failed Instrument Air Tubing & Inspected Tubing for Units 2 & 3.W/930803 Ltr ML20045F0021993-07-0101 July 1993 LER 91-007-01:on 910410,reactor Manually Tripped on Indication of Complete Loss of Controlled Bleedoff Flow from RCP P004.Caused by Wear on Seal & Rotating Baffle.Baffle Repaired & Baffle Bolts Replaced W/New Bolts ML20045E6981993-06-28028 June 1993 LER 93-003-00:on 930527,discovered Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves secured.W/930628 Ltr ML20045B1731993-06-0909 June 1993 LER 92-013-00:on 921209,identified Deficiency Involving Check Valve Test Methodology.Applicable Check Valve Procedure Modified.Applicable SONGS Units 2 & 3 IST Implementing Procedures Will Be Evaluated ML20024H0791991-05-13013 May 1991 LER 91-002-00:on 910412,inadvertent Opening of Containment Purge Sys Isolation Valve Occurred.Caused by Opening of 3HV-9821 Using CR Handswitch for Valve.Valve Closed. Surveillance Procedure revised.W/910513 Ltr ML20024H0451991-05-10010 May 1991 LER 91-007-00:on 910410,reactor Manually Tripped on Indication of Complete Loss of Controlled Bleedoff from Rcp. Caused by Shift in Position of RCP Rotating Baffle.Baffle Inspected,Repaired & re-installed W/New bolts.W/910510 Ltr ML20024G7431991-04-24024 April 1991 LER 91-006-00:on 910325,toxic Gas Isolation Sys Train a Actuated on High Ammonia Gas Level While Troubleshooting 910324 Failure of Channel.Caused by Location of Jumper Used to Bypass Circuitry.Jumper Will Be relocated.W/910424 Ltr ML20029A6811991-02-25025 February 1991 LER 91-001-00:from 910119-21,fuel Movements Performed within Spent Fuel Storage Pool W/O Concurrent Operation of post-accident Cleanup Unit.On 910125,heater Pilot Switch Mispositioned.Caused by Inadequate review.W/910225 Ltr ML20028H6861991-01-22022 January 1991 LER 90-014-00:on 901223,containment Spray Sys Train B Pump Discharge Pressure Indicator 3PI-0303-2 Did Not Display Correct Pressure Reading.Caused by Metallic Particle Near Feedback Coil.Transmitter replaced.W/910122 Ltr ML19332C7921989-11-20020 November 1989 LER 88-035-01:on 881216,determined That Plant Operated at Estimated Actual Power in Excess of 102% from 831223-840104. Caused by Mfg Defect of Feedwater Flow Venturi Tap.Venturi Repaired & Subsequently replaced.W/891120 Ltr ML20024E4251983-08-0505 August 1983 LER 83-067/01T-0:on 830718,determined That Routine 6-month Surveillance Conducted in Feb 1983 Had Not Demonstrated Operability of Fire Panel 3L-198.Caused by Inoperability of Fire Detection instrumentation.W/830805 Ltr ML20024E4721983-08-0202 August 1983 LER 83-076/03L-0:on 830703,during Mode 5,pilot Flames of Trains a & B Toxic Gas Isolation Sys Butane/Propane Monitors Found Extinguished.Caused by Low Alarm Setpoint.Low Alarm Setpoints raised.W/830802 Ltr ML20024E4231983-08-0101 August 1983 LER 83-066/03L-0:on 830701,during Creacus Surveillance Testing,Train B Declared Inoperable After Emergency Chilled Water Unit E-335 Failed to Start.Caused by Malfunction of Control Circuitry or Power Supply breaker.W/830801 Ltr ML20024E4611983-08-0101 August 1983 LER 83-046/01T-0:on 830714,review of Incomplete Abnormal Valve Alignment Record Revealed That Valves MU-075 & MU-076 Improperly Closed During Fuel Transfer.Caused by Improper Execution of Administrative controls.W/830801 Ltr ML20024D8981983-07-29029 July 1983 LER 83-073/01T-0:on 830714,discovered That Certain Core Protection Calculator Addressable Constants in Channels B & D Did Not Comply W/Most Recent Values in Log.Caused by Default Constants Being Left in channels.W/830729 Ltr ML20024D5531983-07-27027 July 1983 LER 83-044/01T-0:on 830711,2-inch Manual Isolation Valve Opened to Provide Svc Air to Support Work in Containment. Caused by Personnel Ignorance of Tech Specs.Personnel disciplined.W/830727 Ltr ML20024D5681983-07-25025 July 1983 LER 83-043/01T-0:on 830708,train B Emergency Chiller E-335 Declared Inoperable,Rendering Equipment Inoperable in Rooms Where Chilled Water Provided.Caused by Control Circuitry or Mechanical Malfunction in Power Supply breaker.W/830725 Ltr ML20024D6031983-07-21021 July 1983 LER 83-071/03L-0:on 830621,during Surveillance Testing, Diesel Generator 2G002 Declared Inoperable When Generator Failed to Start.Caused by Closed Air Supply Valve MU082. Valve opened.W/830721 Ltr ML20024C7611983-06-28028 June 1983 LER 83-061/03L-0:on 830529,core Protection Calculator Channel C Declared Inoperable.Caused by Loop 2A Cold Leg Temp Resistor to Current Converter 2TT-9179-3 Out of calibr.T-cold Loop recalibr.W/830628 Ltr ML20023B8521983-03-31031 March 1983 Revised LER 83-005/01X-1:on 830222,observed Loose Snubbers & Hangers Associated W/Two Sampling Valves (3HV508 & 3HV517) of Rcs.Caused by Removal for Maint Performed on Associated Components.Snubbers Reconnected ML20028F4291983-01-13013 January 1983 LER 82-170/03L-0:on 821214,review of Chart Recordings of RCS Cold Leg Temp Indicated Heatup/Cooldown Rate Limits Exceeded on Three Occasions.Caused by Inability to Properly Control Shutdown Cooling Sys Flow.Personnel Counseled ML20028F3661983-01-11011 January 1983 LER 82-168/03L-0:on 821212,indicated Position for Shutdown Control Element Assembly 12 Went from 148 Inches to 120 Inches Resulting in Reactor Trip.Caused by Failure of Reed Switch.Switch Replaced.No Further Corrective Action Planned ML20028D9531983-01-0808 January 1983 LER 82-007/03L-0:on 821211,during Mode 5,review of Strip Chart Recordings of RCS Temps During Filling & Venting Operations on 821210 Indicated RCS Heatup Rate Exceeded. Caused by Inadequate Attention to Heatup Restrictions ML20028D9611983-01-0707 January 1983 LER 82-165/03L-0:on 821209,while in Mode 1,discovered Two Snubbers,Components of Pipe Support S2-FW-189-HO13,damaged & Inoperable.Cause Undeterminable.Engineering Analysis Performed Satisfactorily.Snubbers Replaced ML20028D8981983-01-0707 January 1983 LER 82-163/03L-0:on 821208,during Mode 1, Auxiliary Feedwater Pump 2P-140 Tripped on Overspeed.Caused by Failure of Resistor in Pump Speed Sensor Circuitry. Resistor Replaced ML20028D8471983-01-0606 January 1983 LER 82-162/03L-0:on 821207,w/plant in Mode 1,low Pressure Tubine Stop Valve 2UV-2200V on Low Pressure Turbine 3 Failed to Fully Close.Caused by Excessive Galling Between Disc Stub Shaft & Casing Bore.Stub Shaft Cleaned ML20028D9171983-01-0505 January 1983 LER 82-155/03L-0:on 821206,two Fire Spray Sys in Cable Spreading Room Declared Inoperable in Order to Repair Leaking Valve.Caused by Minor Leakage Due to Damaged Seating Surfaces of Manual Shutoff Valve SA2301MU121.Valve Replaced ML20028D9471983-01-0505 January 1983 LER 82-161/03L-0:on 821206,condensation Storage Tank T-120 Water Level Fell Below Tech Spec.Caused by Inadequate Makeup Water Control.Operators Reinstructed.Engineering Evaluation Underway ML20028D9481983-01-0404 January 1983 LER 82-005/03L-0:on 821205,during Mode 5,diesel Generator 3GOO3 Taken Out of Svc Leaving Boration Flow Paths W/O Emergency Power Sources.Caused by Personnel Error Due to Failure to Recognize Consequences.Personnel Counseled ML20028D2991982-12-29029 December 1982 LER 82-153/03L-0:on 821130,following Turbine Trip,Low Pressure Turbine Stop Valve 2UV-2200R Failed to Close.Caused by Excessive Galling Between Disc Stub Shafts & Casing Bore. Clearance Between Shaft & Bore Increased ML20028D3031982-12-29029 December 1982 LER 82-154/03L-0:on 821130,following Turbine Trip,Low Pressure Turbine Stop Valve 2UV-2200R Failed to Close.Caused by Excessive Galling Between Disc Stub Shafts & Casing Bore. Clearance Between Shaft & Bore Increased ML20028D3011982-12-23023 December 1982 LER 82-157/03L-0:on 821124,samples from Control Room Emergency Air Cleanup Sys Train a Charcoal Absorber Failed to Satisfy Methyl Iodine Removal Capability.Caused by Activated Charcoal Degradation.Charcoal Replaced ML20028D3041982-12-23023 December 1982 LER 82-004/03L-0:on 821124,samples from Control Room Emergency Air Cleanup Sys Train a Charcoal Absorber Failed to Satisfy Methyl Iodine Removal Capability.Caused by Activated Charcoal Degradation.Charcoal Replaced ML20028B9211982-11-18018 November 1982 LER 82-131/03L-0:on 821020,auxiliary Feedwater Pump 2P-141 Declared Inoperable.Caused by Dirt on Oil Filter Preventing Valve 2HV4731 from Stroking Fully Open.Oil Filter Replaced & Valve Tested Successfully ML20027C9611982-10-19019 October 1982 LER 82-114/01T-0:on 821017,during Surveillance Testing in Mode 4,containment Cooling Fan 2E-402 Failed to Start. Caused by Faulty Fan Breaker.Breaker Replaced ML20027C1641982-09-30030 September 1982 LER 82-105/03L-0:on 820831,during Mode 2 Operation,Auxiliary Feedwater Pump 2P-504 Declared Inoperable.Caused by Leaky Threaded Plug on Pump Discharge Casing.Threads Cleaned, Graffoil Applied & Plug Reinstalled ML20052H5911982-05-10010 May 1982 LER 82-011/01T-0:on 820313,only Operable Control Room Airborne Radiation Monitor Removed from Svc,Violating Tech Spec 3.3.2.b for Approx 2-h.Caused by Personnel Error. Personnel Cautioned ML20050L1931982-03-30030 March 1982 LER 82-003/01T-0:on 820314,unplanned Dilution of RCS Resulted When Operators Were Trying to Restore Shutdown Cooling Flow.Caused by Two Manual Valves Being Partially Open Simultaneously While One Being Opened & Other Closed ML20050L1861982-03-30030 March 1982 LER 82-002/01T-0:on 820314,shutdown Cooling Lost.Caused by Sys Malfunction or Operator Error,Allowing Pressurized Nitrogen to Enter Shutdown Cooling Pump Suction Line When Purification Sys Filter Was Backflushed.Procedures Revised ML20049J9241982-03-12012 March 1982 LER 82-001/03L-0:on 820214,during Initial Fuel Load,Control Room Emergency Air Cleanup Sys Charcoal Filters (E-419 & A-206) Were Saturated W/Water.Caused by Operator Opening Isolation Valve.Filters Replaced & Sys Returned to Svc 1994-04-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 ML20204F8101999-02-28028 February 1999 Monthly Operating Repts for Songs,Units 2 & 3.With ML20203J1981999-02-12012 February 1999 Safety Evaluation Supporting Amends 149 & 141 to Licenses NPF-10 & NPF-15,respectively ML20202F7041999-01-21021 January 1999 Special Rept:On 990106,SCE Began to Modify 2RT-7865.2RT-7865 to Allow Monitor to Provide Input to New Radiation Monitoring Data Acquisition Sys.Monitor Found to Exceeds 72 H Allowed Bt LCS 3.3.102.Alternate Monitoring Established ML20199F0771998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Songs,Units 2 & 3 ML20206H2101998-12-31031 December 1998 SCE 1998 Annual Rept ML20198A6731998-12-11011 December 1998 Special Rept:On 981124,meteorological Sys Wind Direction Sensor Was Observed to Be Inoperable.Caused by Loss of Communication from Tower to Cr.Sensor Was Replaced & Sys Was Declared Operable on 981204 ML20196D8901998-11-30030 November 1998 Non-proprietary Reload Analysis Methodology for Songs,Units 2 & 3 ML20198C3471998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Songs,Units 2 & 3 ML20195H2471998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Songs,Units 2 & 3 ML20154B7211998-10-0101 October 1998 Safety Evaluation Approving Licensee Request to Implement Alternatives Contained in Code Case N-546 for Current Interval at Songs,Units 2 & 3 Until Code Case Approved by Ref in Reg Guide 1.147 ML20154M7921998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Songs,Units 2 & 3 ML20155F6081998-09-17017 September 1998 Non-proprietary Version of San Onofre 2 & 3 Replacement LP Rotors ML20151Z9851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Songs,Units 2 & 3 ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20198G4491998-07-31031 July 1998 Rev 1 to WCAP-15015, Specific Application of Laser Welded Sleeves for SCE San Onofre Units 2 & 3 Sgs ML20237B8571998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Songs,Units 2 & 3 ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML20236R1031998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Songs,Units 2 & 3 ML20249A9431998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Songs,Units 2 & 3 ML20248B8981998-05-26026 May 1998 Updated SG Run Time Analysis Cycle 9 ML20248B9221998-04-30030 April 1998 Rev 0 to AES 98033327-1-1, Updated Probabilistic Operational Assessment for SONGS Unit 2,Second Mid Cycle Operating Period,Cycle 9 ML20247L5181998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Songs,Units 2 & 3 05000361/LER-1998-003, LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003)1998-04-0606 April 1998 LOCA Evaluation of Safety Significance of Failure of Emergency Sump Valve Linestarter (LER 1998-003) ML20217Q6161998-04-0505 April 1998 Failure Analysis Rept 98-005,Failure Analysis of 2HV9305 Motor Starter ML20217A0141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Songs,Units 2 & 3 ML20217D4701998-03-0202 March 1998 Rev 1 to 90459, Failure Modes & Effects Analysis DG Cross- Tie,DCP7048.00SE ML20216J3551998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Songs,Units 2 & 3 ML20203E7301998-02-17017 February 1998 SER Accepting 980105 Request to Use Mechanical Nozzle Seal Assembly as Alternate Repair Method,Per 10CFR50.55a(a)(3)(1) for Plant,Units 2 & 3 ML20203K9141998-02-0303 February 1998 Rev 0 to ESFAS Radiation Monitor Single Failure Analysis. W/96 Foldout Drawings ML20202F9731998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Songs,Units 2 & 3 1999-09-30
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Southom Califomia Edison Company tiAN ONOFHL NUCLL Aft OLNE,n AfING tit Al TON F.O E10K 1ra liAN CL l.D.4t'N16~ C.AL6FORNI A b2t174 0120 H W. KRit:GC R t yg tp.gyng.
IITATKJN MANACAF R g 7 se, ; egg eggg April 24, 1991 U. S. Nuclear Regulatory Commission Document Control Desh Wainington, D.C. 20$$$
Subj ect: Docket No. 50 361 30 Day Report Licensee Event Report No. 91 006 San Onofre Nuclear Generating Station, Unit 2 Pursuant to 10 CFR 50.73(d), this submittal provides the required 30 day written Licensee Event Report (LER) for an occurrence involving the Toxic Cas Isolation System (TGIS). Since this occurrence involves areas common to both in Units 2 and 3, a single report for Unit 2 is being submitted in accordance with INREG-1022. Neither the health nor the safety of plant personnel or the -
public was affected by this occurrence.
If you require any additional information, please so advise.
Incerely, T
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Enclosure:
LER No.91-006 cc: C. W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3)
J. B. Martin (Regional Administrator, USNRC Region V)
Institute of Nuclear Power Operations (INPO) 9104290234 910.';24 fffQ PDR ADOCK 0".000361 i S PDR /// I
LICENEEE ETENT REfVRT (LER)
F ullsty henie (1) Du ket h mter (2) lfAu 3) f' AN ONDFTE N'K'Ita OtNRATIN3 f'T AT1DN. UNIT 2 Ol *l Ol 0} Ol Sl fI 1
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INADVERTENT TOK10 GAS Istt.ATION SYCTEM (TGIS) ACTUATION DURING f t:I IE!.Tol>RNCE OF t%1NTENANCE TROUT 1LIIl100 TING
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'#( Nnth Day Year Day Year Year fj'f f Month fj fDNGS. UNIT 3 01 $l 01 Ol Ol 31 fl 2 O!7 I!S 9!1 Nl Od.i _Ed._E - Ed . 4 NL..NL O!I!O!O!O! ! !
, .THIS IllVh bVD?t TTI.D IVhSUANT 10 MUI. kEQUlktMLNIS OF 10Clis I A ,(Q1tte er t'or e t f the f ollowir e.) til) 1 ,,,,,,,,, 20.402(b) ,,,,,,
20,40$(s) ,L $0.)3(a)(2)(tv) ,,,,, / J . 71(L. )
IVWLk ,,,,, 20.40$(a)(1)(1) ,,,,,,, 50.36(c)(1) _ 50.73(a)(2)(v) ,,,,, FL 71(c)
LEVEL 20.40$(e)(1)(11) ,,,,,,, 50.36(c)(2) ,,,,,, 50.73(a)(2)(vii) ,,,,,,,
Ot.he r ( t;pe c i f y in 50.73(a)(2)(1) Abs t r ac t 1.e Low and
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_10) .Ol 6. 1 _,,,,,,,,20,40S(a)(1)(iii) 20.40$(a)(1)(tv) 50,73(a)(2)(11)
,,,,,, 50.73(a)(2)(vitt)(A) 50.73(a)(2)(vt!!)(t) in tut)
///////////////////////// _ ,,,,,,,
///////////////////////// ,,,,,,,,,,,,, 20.40$(e)(1)(v) _ 50.7)(e)(2)(tit) ,,,, 50.73(a)(2)(x)
/////////////////////////
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t!CEN"EE CONTACT FOR T!!!B LER (12)
Hjl)V_ b"?tM k I;*** _MA I CODE R. W. rgigpr. f t st ion Peneru 7l1 14 .1(1Pl-l6121311 Cat!'LETE ONE LINE r0R f.ACl! cCitPONENT FAILll! DESCRIEED IN THIS Ill0RT (13)
FlPORTAELE I # CAUSE SYETEH C3tPON!'.NT FRNUTAC- ETFORTAELE CAUSE SYSTEM COMIONENT MANUTAC-Tuf2R TO NPITS /////// TVETR TO NilW L //////
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$UFF1.EMENTAL REIVRT EXPECTED (14) Nnth Day for Expected Suter.is s ion
_1gg (1f ten. ettr(9te EXFECTFD TUPMISSION DATI) _ND Date (15) l, l l AB. thAct (Lia.it to 1400 spaces , i .e . , opproxtmately tiltsen single-space typewritten lines) (16)
At 1530 on March 25, 1991, wit.h Unit 2 at 60% power and Unit 3 at 100% power, Toxic Gas Isolation System (TGIS) Train "A" actuated on high ammonia gas level, All TGIS Train "A" components were verified to have actuated as required.
The actuation occurred while troubleshooting was being performed on the Train "A" ammonia channel, which had failed on March 24, 1991. A Maintenance technician inadvertently bumped the jumper used to bypass the TGIS actuation circuitry, resulting in the jumper being inomentarily dislodged. Since the ammonia level had been increased above the actuation setpoint to perform the troubleshooting, an actuation on high ammonia occurred.
The root cause of this event is that the location of the jumper used for bypassing the TGIS actuation circuitry was adjacent to the area requiring access during maintenance activities. Therefore, a potential existed for disturbance of the jumper during these activities, for corrective actions: 1) appropriate disciplinary action has been administered to the technician involved in this event, 2) this event has been reviewed with appropriate Maintenance personnel, and 3) the bypass jumper, when installed in the future, will be relocated to an area less likely to be affected by maintenance activities.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 2 0500036] 91-006 00 2 of 4 Plant: San Onofre Nuclear Generating Station Units: Two e,nd Three Reactor Vendor: Combustion Engineering Event Date: 03 25 91 A. CONDITIONS AT TIME OF Tile EVENT:
Mode: 1, Power Operation (Units 2 and 3)
B. BACKGROUND INFOR!iAT10N:
The common Unit 2 and 3 control room is designed to be automatically isolated by the Control Room Emergency Air Cleanup System (CREACUS) [VI) to prote::t personnel f rom potential outside airborne radiation or toxic gas contaminat. ion. CREACUS is started in the isointion mode when the Toxic Cas Isolation System (TGIS) [VI] detects chlorine, ammonia or butane (hydrocarbon) gas in the outside air intake. Technical Specification Limiting Condition for Operation (LCO) 3.3.2, " Engineered Safety Features Actuation System," er.tablishes TGIS operability requirements.
There are two independent trains of both CRrJsCUS and TGIS. Each train io actuated by either a remote manual puah button switch (PB) [IIS), a gas concentration sensed by any of the gas detectors (DET) which is above the actuation setpoint, or a loss of power. Each CREACUS train closes all control room air intake and exhaust pathways [DMP), and recirculates the air inside the control room spaces through HEPA filters [FLT] and charcoal adsorbers [AD5;.
C. DESCRIPTION OF Tile EVENT:
- 1. Event:
At 1530 on March 25, 1991, with Unit 2 at 60% power and Unit 3 at 100% power, TCIS Train "A" actuated on high ammonia gas level. All TCIS Train "A" components were verified to have actuated as required.
At the time of the actuation, troableshooting was being performed on the Train "A" ammonia channel, which had failed low on March 24, 1991. Specifically, a Maintenance technician (utility, non-licenood) was disconnecting the Digital Multimeter (DRM) used during troubleshooting from its connection locations internal to the TGIS cabinet. During this process, the technician inadvertently bumped one of the connections of the jumper used to bypass the TGIS actuation circuitry. This resulted in the jumper becoming momentarily dislodged. The technician quickly re connected the jumper; however, since the ammonia level had been increased above
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1.1CENSEE EVENT REPORT (LER) TF.XT C0!iTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UglT 2 05000361 91 006-00 3 of 4 the actuation setpoint to perform the troubleshooting, an actuation on high ammonia occurred.
- 2. Inoperable Structures, Systems or Components that Contributed to the Event:
Not spplicable.
- 3. Sequence of Events:
DATE TIME ACTION 3/24/91 0800 TGIS Train "A* ammonta channel fails low.
3/25/91 1530 TOIS Train "A" actuation on high ammonia leswl during troubleshooting.
3/25/91 1600 Control room ventilation lineup returned to normal.
3/26/91 0330 TGIS Train "A" returned to service.
- 4. Method of Discovery:
Control room alarms and inGications alerted the operators of the TGIS actuation.
- 5. Personnel Actions and Analysis of Actions:
The operators responded properly to the TOIS netuation by 1) verifying proper system operation and 2) determining that the ammonia level was normal prior to returning TGIS to the " standby" mode and restoring normal control room ventilation.
- 6. Safety System Responses:
The TOIS and CREACUS systems functioned in accordance with their design.
D. CAUSE OF Tile EVENT:
- 1. Immediate cause:
During troubleshooting of the TGIS Train "A" ammonia channel, the Maintenance technician inadvertently bumped one of the connections of the jumper used to bypass the actuation circuitry. This resulted
- in the jumper being momentarily dislodged. Since the ammonia level had been increased above the actuation setpoint to perform the troubleshooting, an actuation on high ammonia occurred, i
LICENSEE EVENT rep 0RT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER pAGE UNIT 2 ;QhB00361__ 91 006 00 4 of 4
- 2. Root Cause:
'The location of the jumper used for bypassing the TGIS actuation circuitry was adjacent to the area requiring access during maintenance activities. Therefore, a potential existed for disturbance of the jumper during these activities.
E. CORRECTIVE ACTIONS: r l l
- 1. Corrective Actions taken:,
- a. Appropriate disciplinary action has been administered to the technician involved in this event. >
- b. This event has been reviewed with appropriate Maintenance personnel. t
- 2. Planned Corrective Action:
?
The bypas's jumper, when installed in the future, will be relocated '
to an area less-likely to be affected by maintenance activities.
Specifically, the inputs on the terminal strip to which the oypass jumper is connected will be relocated to the opposite side of the strip. When this is completed, al1~the terminal strip inputs used for connecting test equipm6nt will be on one side of the terminal strip and the bypass jumper will be on the other, Therefore, installation and removal of the test equipment (such as a DKM) should not interfere with the bypass jumper.
F. . SAFETY SIGNIFICANCE OF THE EVENT:
There is no safety significance to this event since all TGIS and CREACUS components operated as designed.
- 0. ADDITIONAL INFORMATION;-
L 1. Component Failure Information:
f
- Not applicable.
2, Previous LERs for Similar Events:
LER $6 034 (Docket No. 50 361) reported two TGIS actuations caused by the bypass jumper being dislodged during the performance of maintenance activities. As a result of these actuations, the design-
- of the bypass jumper was changed and the location of the jumper was moved to minimize recurrence. The event being reported in this LER _ '
is the first TGIS actuation caused by the bypass jumper since these corrective actions.
a - -..-__ .-. - -- - - - - . _ - - . _ _ _ - - - _ _ - - . . - - . . .. . _ _ _ _ _ _ . _ .