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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Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves secured.W/930628 Ltr ML20045B1731993-06-0909 June 1993 LER 92-013-00:on 921209,identified Deficiency Involving Check Valve Test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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P O box 128 S AN CLE M E NTE, C ALIFORNIA 92674 0128 R W. KRIEG ER E 9 T E LE PHON E v,c. .......N, m. n . ..n .
hvCL am Otm nAftom U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-362 Voluntary Report Licensee Event Report No.93-007 San Onofre Nuclear Generating Station, Unit 3 i Pursuant to 10 CFR 73(d), this submittal provides a voluntary written Licensee Event Report (LER) for an occurrence involving a Roto test switch terminal bolt failure. Neither the health nor the safety of plant personnel or the public was affected by this occurrence or condition.
If you require any additional information, please so advise. I Sincerely, M
N* hfl } r
Enclosure:
LER No.93-007 cc: L. J. Callan, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region V J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 and 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 &3 Institute of Nuclear Power Operations (INPO) 030107 (I 9405040099 940426
{DR ADOCK 05000362 Ik PDR
l LICENSEE EVENT CEPC3T (LER)
Facility kame (1) Docket Number (2) Page v3)
SAN ONOFRE NUCLEAR CENERATING STATION UNIT 3 01 51 01 01 01 31 61 2 1 I of 0 3 Title (4)
ROTO TEST SWITCH BOLT FAILURE, VOLUNTARY REPORT EVENT DATE (5) LER NUMBER (6) REPORT DATE (7) OTHER FACILITIFS INVOLVED (8)
Month Day Year Year /// Sequential /// Revision Month Day Year Facility Names Docket Number (s)
/// Nunber /// Nunber UNIT 2 015101010131611 1 11 21 8 91 3 91 3 01017 0l0 0l4 21 6 91 4 015101Gi01 I l OPhRATING THih REPORT IS buBM. TIED PURSUANT TO 'HE REQUIREMENTS OF 10CFR MODE (9) (Check one or more of the following) (11) 5 _ 20.402(b) _ 20.405(c) _ 50.73(a)(2)(iv) _ 73.71(b)
Poa _ 20.405(a)(1)(1) __ 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c)
LEVEL _ 20.405(a)(1)(li) 50.36(c)(2) _ 50.73(a)(2)(vil) JL, other (Specify in (10) 01 01 0 _
20,405(a)(1)(iii) __ 50.73(a)(2)(1) _ 50.73(a)(2)(viii)(A) Abstract below and l
l //////////i////////////// _ 20.405(a)(1)(iv) _ 50.73(a)(2)(ii) _ 50.73(a)(2)(viii)(B) in text) l ///////////////////////// _ 20.405(a)(1Mv) _ 50.73(a)(2)(iii) _ 50.73(a)(2)(x) VOLUNTARY REPORT l /////////////////////////
f,f///////////////////////
l LICENSEE CONTACI FOR THIS LER (12)
Name TELEPHONE NUMBER AREA CODE R. W. Krieger. Vice President. Nulcear Generation 7l1 l4 316181-l6121515 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THlb REPORT (13s CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE / "'// CAUSE SYSTEM COMPONENT MANUFAC- REPORTABLE //////
TURER TO NPRDS //, / TURER TO NPRDS //////
B EIA I [HIS Ml21812 Y /////// l l l I I I I //////
I l 1 l l l 1 /////// l l l l l l I //////
SUPPLEMENTAL REPOR' EXPECTED (14) Month Day Year Expected Submission Yes (If ves, complete EXPECTED SUBMISSION DATE)
I IXX NO Date (15) l l l ABSTRACT (Limit to 1400 spaces, i.e., approximately fifteen single-space typewritten lines) (16)
On November 28, 1993, with Unit 3 in Mode 5 in a refueling outage, during Engineered Safety Features (JE) testing, Unit 3 Emergency Diesel Generator (EDG) [EK) 3G002 output breaker tripped. Emergency Diesel Generator 3G002 tripped because the output breaker had closed but immediately reopened on high differential current signal. Edison investigated and determined that a Roto test switch (RTS-2) (EA) terminal bolt had failed which had caused the EDG 3G002 output breaker to reopen. An Edison root cause evaluation of this failure concluded that the terminal bolt failed due to a manufacturing defect.
While this event is not reportable in accordance with 10CFR50.73, Edison is submitting a voluntary report due to potential industry interest.
On November 29, 1993, Edison replaced RTS-2 for Unit 3 EDG 3G002. Emergency Diesel Generator 3G002 was tested satisfactorily and declared operable on December 1, 1993.
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4 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION I SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE l UNIT 3 05000362 93-007-00 2 of 3 DESCRIPTION OF THE EVENT:
Plant San Onofre Nuclear Generation Station, Unit 3
, Reactor Vendor: Combustion Engineering Event Dates November 28, 1993 Modes 5, Cold Shutdown on November 28, 1993, with Unit 3 in Mode 5 in a refueling outage, during Engineered Safety Features (JE) testing, Unit 3 Emergency Diesel Generator (EDG) (EK] 3G002 output breaker tripped. Emergency Diesel Generator 3G002 tripped because the output breaker had closed but hnmediately reopened on high dif ferential current signal.
I Following the EDG 3G002 output breaker trip, Edison investigated and determined that a Roto test switch (RTS-2) (EA) terminal bolt had failed which had causad the EDG 3G002 output breaker to reopen. An Edison root cause evaluation of this failure concluded that the terminal bolt failed due to a manufacturing defect.
San onofre Units 2 and 3 each have two Emergenef Diesel Generators, each of which is sufficient to provide adequate electric power to allow safe shutdown of the plant in the event of a loss of offsite power coincident with worst case post accident conditions.
To allow the Emergency Diesel Generators to be isolated during testing, each Emergency Diesel Generator train is equipped with 14 Roto test switches. Twelve of the 14 Roto test switches are on circuits which are for indication only or are automatically bypassed in the event a safety Injection Actuation Signal is received. The remaining two Roto test Ewitches (RTS-1 and RTS-2) are not bypassed following receipt of a safety Injection Actuation Signal. Thus, failure of RTS-1 or RTS-2 may trip the Emergency Diesel Generator output breaker, and prevent reclosure.
Subsequent inspections were performed of all Roto test switches in the Emergency Diesel Generator traine for Units 2 and 3. One additional bolt (RTS-9) used in an automatically bypassed Roto test switch for Unit 2 EDG 2G003 was found broken. Other Roto test switches used in the Unit Auxiliary Transformers (EA), the Reserve Auxiliary Transformers (EA), and the Emergency Chillers [KM) control modules were visually inspected on December 21, 1993, and no broken bolts were detected.
While this event is not reportable in accordance with 10CFR50.73, Edison is submitting a voluntary report due to industry interest.
CAUSE OF THE EVENT:
Laboratory analysis of the two failed bolts identified the root cause as a lot-specific manufacturing defect in the bolt material. The defect caused them to fracture under mechanical loading. Specifically, the bolts were made of a highly brittle brass with extreme cold working around the base of the head. Cracks around the base of the head and in the threads were introduced during manufacturing which ultimately caused the bolts to fracture 'ander normal mechanical loading.
CORRECTIVE ACTIONS:
On November 29, 1993, Edison replaced RTS-2 for Unit 3 EDG 3G002. Emergency Diesel Generator 3G002 was tested satisfactorily and declared operable on December 1, 1993. On December 21, 1993, Edison replaced the failed bolt in RTS-9 for Unit 2 EDG 2G002.
Emergency Diesel Generator 2G002 was tested satisfactorily and declared operable on December 22, 1993.
After determining the Roto test switch terminal disengagement force to be approximately 5 pounds, Edison pull tested each Roto test switch terminal bolt to approximctely 10 pounds. The pull tests confirmed that the remaining bolts in the 14 Roto test switches for each Emergency Diosel Generator at Units 2 and 3 were acceptable. The Reto test switches for the Unit Auxiliary Transformers, the Reserve Auxiliary Transformens and the Emergency Chillers were visually inspected on December 21, 1993, with no indicaLion of fractured bolts.
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 3 05000362 93-007-00 3 of 3 As a conservative measure, Edison will replace RTS-1 and RTS-2 for each Emergency Diesel i Generator and the Roto test switches for the Emergency Chillers prior to the end of the l Cycle 8 refueling outage for each Unit (currently scheduled for early 1995 and mid 1995 for Units 2 and 3 respectively). Similar upgrades for the remaining EDG Roto test switches and the Roto test switches for the Unit Auxiliary Transformers and the Reserve Auxiliary Transformers will be completed prior to the end of the Cycle 9 outage for each Unit.
Edison has nctitled the vendor about this bolt failure. Additionally, prior to j replacing the Hoto test switches as described above, Edison will verify that the 1 replacement Roto test switches are not similarly affected.
SAFETY SIGNIFICANCE:
The failed RTS-2 terminal bolt failed during the performance of a ESF surveillance test.
Emergency Diesel Generator 3G002 had been satisfactorily tested and successfully operated the previous hour and, therefore, the terminal bolt in RTS-2 was operable at that time. During subsequent investigation, Edison determined: (1) manual operation of the switch places approximately five pounds of force on the bolt; and (2) the forces to which the terminal bolt in RTS-2 could have been subject during a design basis earthquake (DBE) (based on the weight of the bolt assembly and the DBE acceleration) would have been less than two pounds. In accordance with the guidance in NUREG-1022, the bolt is assumed to have failed at the time the output breaker for EDG 3G002 opened, and there was no safety significance to the bolt failure.
Due to the nature and cause of the Roto test switch bolt failures, Edison contacted the Roto test switch supplier, ABB Switchgear Division, and provided ABB with the root cause evaluation of the failure. ABB replied, in a letter dated February 11, 1994, stating that they believe Edison was the only utility to procure class lE qualified Roto test switches. However, other nuclear utilities could have this problem if they upgraded commercial grade switches. The failure of switches from a specific manufacturing lot minimizes the potential that bad parts were supplied to other nuclear utilities.
ADDITIONAL INFORMATION:
A review of previous LERs did not reveal any previous similar occurrences.
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