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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Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves secured.W/930628 Ltr ML20045B1731993-06-0909 June 1993 LER 92-013-00:on 921209,identified Deficiency Involving Check Valve Test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
[Table view] |
Text
_ _ _ . . . . . . .
9.'-
Southom Califamia Edison Company S AN OtJOf HE NULLE Ali Ot Nt it AlING bl Af 60N f" O (10 8 11 8 S Afd CL i IM NT E . C AL IF UHtU A I4A 6I4 0 9 Ett 2
l',1,7' ['; May 13. 1991 2,C2, U. S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555
Subject:
Docket No. 50-362 30 Day Report Licensee Event Report No.91-002 San Onofre Nuclear Generating Station, Unit 3 Pursuant to 10 CFR 50.73(d), this submittal provides the required 30-day written Licensee Event Report (LER) for an occurrence involving the inadvertent opening of a containment isolation valve. 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.
Sincerely,
/
l .-
Enclosure:
LER No. 91 002 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 (INP0) 9105210133 910313 PDR ADOCK 05000c: A"'
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- LICENSEE EVENT REPORT (LER)
Fatality Name (1) tiock.et Nwnbos (2 ) _ lose M CAN ONOFRt NUNEAR GENERATING ETATION l' NIT 3 Of$l01Ol0131(l2 1 t.f 0 7 ,
Title (4)
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LICENFEE CONTACT FOR THIS LER (12)
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On April 12, 1991, at 1959, an outer containment mini purge isolation valve, 3HV 9821, was discovered open in violation of the requirements of Technical Specification (TS) 3.6.1.7.b. " Containment Ventilation System Limiting Condition for Operation." The valve was promptly closed by Control Room (CR) personnel.
Subsequent investigation determined that 3HV-9821 had been inadvertently opened at approximately 2339 on April 11, 1991 by a Control Operator (CO) (utility, licensed) during reset of the actuation circuitry for 3HV-9821. The actuation circuitry had been armed earlier in the day during surveillance testing of 3RE-7865-1 which had begun at 1030 on April 8. 1991.
3HV 9821 was opened cnd remained open as the result of a rumber of deficiencies in the areas of operator performance, surveillance procedt.res, plant status monitoring systems, and switch labeling, Corrective actions include: 1) the operator received appropriate guidance concerning performance in t.he area of problem solving and plant manipulation; 2) the' surveillance procedure will be revised prior to its next use to prevent a similar inadvertent valve opening during testing; 3) a review of the radiation monitor and containment purge valve logic circuitry is being performed; and 4) the plant status monitoring systems are being evaluated-for possibic enhancements.
There was no safety significance to this event since the inner containment isolation mini-purge valve remained closed at all times. Also, 3HV-9821 would have closed on receipt of 4.a ESFA3 signal or a high radiation signal from the containment purge vent stack radit. tion monitor,
i LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ,
SAN ONorRE NUCLEAR GENERAT' I TATION DOCKET NUMBER LER NUMBER PAGE UNIT 3 05000362 91 002 00 2 of 7 Plant: San Onofre Nuclear Generating Station !
Unit: Three Reactor Vendor: Combustion Engineering Event Date: 04 12 91 Time: 1900 A. CONDITIONS AT TIME OF THE EVENT:
Mode: 1, Power Operation B. BACKGROUND INFORMATION:
- 1. Cost.inment Purge System:
The isntainment purge system is comprised of two sub systems, each having a supply and exhaust unit, which are used under different >
circumstances to reduce airborne radioactivity to provide for personnel habitability inside containment [NH). The normal purge system is used when the unit is shutdown and the mini-purge system is used when the unit is in operation and personnel entry into containment is necessary. For each of these systems, a supply unit fan [ FAN) draws-outside air through a profilter [FLT) and discharges the air through two containment isolation purge valves [lSV) and ducting (DUCT) into the containment building, Each exhaust unit fan draws air from the containment building through ducting and two containment isolation purge valves and discharges the air to the containment purge stack, The mini-purge containment isolation ;
valves are air operated and fail closed.
All containment mini-purge system isolation valves will close automatically on any.one or more of the following Engineered Safeguards Features Actuation System (ESEAS) signals: 1) Containment Purge Isolation Signal (CPIS), 2) Safety Injection Actuation Signal !
(SIAS), and 3) Containment Isolation Actuation Signal (CIAS), All containment normal purge valves will close automatically on a CPIS signal. In addition, the outside containment purge system isolation ;
i valves will close on high radiation from_the Containment Purge Stack
! Radiation Monitor [ MON), RE-7828 (or the Plant Vent Stack Wide Range Gas Monitor, RE 7865-1, when it is aligned to sample the containment purge stack). This non Engineered Safeguards. Feature (ESP) ensures that purge gaseous radiation release limits are not exceeded.
- 2. Radiation Monitors:
3RE 7828 generates an alarm and initiates the closure of the four outside containment purge / mini-purge istlation valves on high .
radiation levels, radiation monitor inst.ument failure, or on loss of power to the monitor.
m._ an __ _____;_.u___._____ _ , _ _ _ . _ , _ . . _ _ , _ _ , _ . ,_ , _ . _ _
- l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR CENERATION STATION DOCKET NUMBER LER NUMBER PACE-UNIT 3 '05000362 91-002 00 3 of 7 l 3RE-7865 1 can be aligned to sample either the plant vent stack or the containment purge stack. If aligned to the plant vent stack, 3RE-7865 1 generates en alarm (AIJt) and initiates closure of the vaste gas discharge header flow control valve [FCV) on high radiation levels, radiation monitor instrument failure, or loss of power to the monitor. If aligned to the containment purge stack, 3RE 78651 generates an alarrn and initiates closure of the four outside containment purge /tnini purge isolation valves on high radiation levels,-radiation monitor instrument failure, or loss of power to the radiation monitor.
- 3. Containment Purge System Isolation Valve Controls .
1 As previously described, the raini purge containment isolation valves l are air operated. Air to open the valves is provided through two l fail closed solenoid valves [FSV) installed in series between the i air supply and the valve actuator for each valve. Or.e of these solenoid valves (which is normally open) is controlled by the selected non ESF radiation monitor. The other solenoid valve (which
. is normally closed) is controlled by the valve's Control Room (CR) handswitch [HS) and the previously discussed ESFAS signals, such that an ESFAS actuation signal (to close the valves) cannot be overridden by a CR handswitch open signal.
Upon a loss of power or a high radiation alarin [RA) to radiation '
monitors, 3RE 7828 or 3RE-7865-1, the non ESF solenoid valves are de energized closing the associated purge valve and a reset switch in the CR is illuminated. When the close signal from the radiation monitor is' cleared, this reset switch allows-the non-ESF radiation >
monitor controlled solenoid valves to be opened. If the other solenoid valve ir. also open, the containment isolation valve will open.
This arrangement assures that an ESFAS signal to the containment purge system will close the outer containment purge isolation valves irres.pective of the position of the non ESF solenoid valve.
4 Technical Specification (TS): '
TS 3.6.1.7.b, " Containment Ventilation System Limiting Condition for
~
l Operation," requires the containment purge supply and exhaust isolation valves to be OPERABLE, and each 8 inch containment mini-purge and supply isolation valve to be closed to the maximum extent practicablo. -These valves may be open for purgo system operation for pressure control, for ALARA and respirable air quality considerations for personnel entry, and for surveillance tests that require the valve to be open.
TS 3.6.1.7 action "a.2" requires that with the 8-inch containment =
l mini-purge supply and/or exhaust isolation valve (s) open for reasons l other than as stated in Specification 3.6.1.7.b, the open valve (s)
-.- - - - - . - . _ - . , , . - . . , . - - . . - . . . - . - , - - . ~ . . - . - - . . - - - . . - . - - - . . - _ - - . _ - , , - .
l .
i LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ,
SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUrCER PAGE UNIT 3 , 05000362 91 002 00 4 of 7 must be closed or isolated by a blind flange within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the plant must be taken to 110T STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SilUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Y t
C. DESCRIPTION OF Ti!E EVENT:
- 1. Event:
On April 12, 1991, at 1959, an outer containment mini purge isolation valve, 318V 9821, was discovered open contrary to the requirements of TS 3.6.1.7.b. The valve was promptly closed by ,
Control Room (CR) personnel (utility, licensed) after determining ,
that no activity was in progress which required it to be open.
- Subsequent investigation determined that 311V 9821 had been inadvertently opened at approximately 2339 on April 11, 1991 by a Control Operator (CO)-(utility, licensed) during reset of the actuation circuitry for 311V 9821. The actuation circuitry had been armed earlier in the day during surveillance testing of 3RE 78651 which had begun at 1030 on April 8, 1991. i
- 2. Inoperable Structures, Systems or Components that Contributed to the Event:
Not applicable.
3, Sequence of Events:
DAIE IIt1E ACTION 4-8 91 -1030 3RE 7865 surveillance initiated.
4 11 91 1812 311V 9821 opened. for loss o! power test on 3RE 7865 1, 4 11 91 1813 31tV 9821 closed upon receipt of a loss of power signal from 3RE 7865-1, 4-11-91 ~1900 surveillance test of 3RE 7865-1 is completed for the shift.
4 11-91 2339 Unit 3 CD depresses the reset switch for 311S 7828 and 311V 9821 opens.
4-12-91 1959 31tV 9821 is discovered open and is closed.
4 14 91 1800 3RE-7865 1 su;veillance is completed.
. - .- .. - . -. - . - - . - . - - . - . - . , . . - . - . - . . . . - - . . - - . . . - - . . , -.,a..-.--- --
~,
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ON0FRE NUCL" EAR GENERATION STATION DOCKET NUtiBER LER NUMBER PAGE UNIT 3 0,1000362 91 002 00 5 of 7
- 4. Method of Discovery:
CR personnel discovered 3HV 9821 open during routine control board walkdowns.
- 5. Personnel Actions and Analysis of Action:
Upon discovery of the opened valve, CR personnel promptly closed 3HV 9821-
- 6. Safety System Responses:
Not applicable.
D. CAUSE OF THE EVENT:
SCE's investigation of this event to nd that during surveillance testing of 3RE 78651, 3HV 9a21 tas opened ec 1812 on 41191 using the CR handswitch for.the valv<.. One mitiute later, 3HV-9821 closed as the result of a loss of power signal to 3RE-7865-1 as a part of the surveillance test. Following automatic closure of the mini-purge valve, the 3HV-9821 CR handswitch 5as left in a condition which resulted in the valve opening when the commot reset switch for 3RE 7865 1 and 3RE-7828 was depressed.
Procedure The surveillance procedure did not ensure that the logic.for 3HV 9821 was reset to the normal valve closed' condition by requiring that the CR close handswitch button be depressed immediately after testing the valve closure logic on a-loss of power-to the-radiation monitors, >
Labeling ,
As previously described, the radiation monitor and containment purge isolation valvo logic circuitry design (which controls the containment purge / mini purge valves),-reopens-the non-ESF air supply solenoid valve (s) when the reset. switch _is depressed. The reset switch was labeled
" Containment Purge Stack Radiation Monitor 3HS 7828" indicating that it only affected the one radiation monitor. It did not contain any reference to its reset function with respect to 3RE-7865-1. As a result, prior to depressing the illuminated reset. switch, the CO did not recognize that radiation monitor 3RE 7865 1 could also have actuated-the reset switch.
Operator Performance The CO did not follow established guidance-for operator performance in the areas of problem solving and plant manipulation by 1) not fully investigating all reasons.why the reset light was illuminated and 2) not cor.sulting with other CR personnel who were fully aware of the status of the in progress surveillance and t he consequence of his action.
i t
. )
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 3 05000362 91 002 00 6 of 7 '
In addition, during shift relief, ptocedures direct the operators to check the status of all ESF valves that have main control board indication, which includes this valve. This review was inadequately performed during the next two shifts and.as a result the misalignment of 3RV 9821 was not detected during this period.
Plant Status Monitoring When the reset switch was depressed, the change in 3HV 9821 po.ition was indicated on the main control panel, the valve position status indication on one of the display pages of the Critical Functions Monitoring System (CFMS) and as an entry on the Plant Monitoring System (PHS) computer. The design of these systems does not initiate an audible alarm which would
, have alerted the operators to the change of valve position.
l E. CORRECTIVE ACTIONS:
- 1. Corrective Actions Taken:
- a. The CO who depressed the reset switch received appropriate guidance concerning performance in the area of problem solving and plant manipulation.
- b. A sign was posted adjacent _ to _ the reset switch warning CR personnel to check purge / mini purge valves after resetting the
-reset switch to insure they are in the required position for the plant mode-or evolution.
- 2. Planned Corrective Actions:
- a. Applicable radiation monitor surveillance procedures will.be revised prior to their next use to require that the containment purge isolation valve open signal be removed at the handswitch immediately after each test of valve closure by a signal from a radiation monitor,
- b. A review of the radiation monitor and valve logic circuitry which controls the main-purge / mini-purge valves is in progress to evaluate a design enhancement to eliminate valve reopening upon reset of the radiation monitor,
- c. As a result of a corrective action described in LER 90 010 (Docket-Nos. 50 362), an engineering evaluation is being i- performed to identify critical Engineered Core Cooling System L valves and Containment Spray system valves not having audiblo annunciation of misalignment whose initial position is critical to component or system operability. As a result of the late discovery of_the misalignment of 3HV 9821, the_ scope i of this evaluation is being expanded to include other valves l
l 1
___ a LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
' SAN ONOFRE NUCLEAR GFM'lATION STATION DOCKET hdMBER LER NUMBER PAGE 1 UNIT 3- 05000362 91-002-00 7 of 7 which can be remotely positioned from the CR and can impact the containment isolation function. Appropriate corrective
-action will be implemented.
- d. The reset switch and the adjacent warning label will be relabeled to fully identify all equipment affected,
- e. This event will be reviewed with CR personnel emphasizing the function of the reset switch, shift turnover requirements, valve indication status, and CR communications,
- f. The existing computer based data systems are being evaluated to deteraine if they can be modified to provide the Operations staff with greater visibility of the status of critical valves. This evaluation is a result of a corrective action described in LER 90 010 (Docket Nos. 50 362).
F. SAFETY SIGNIFICANCE OF THE EVEhT:
There was no safety significance to this event since the Janer containment isolation mini-purge valve renained closed at all times. Also, 3HV-9821 would have closed on receipt cf a CPIS, SIAS, CIAS or a high ra 'intion signal from the_ radiation monitor.
G. ADDITIONAL INFORMATION:
- 1. Component Failure Information:
Not applicable.
2-. Previous LERs for Similar Events:
None, l
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