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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Three Containment Isolation Valves w/motor-operator Switch Setttings Nonconservative,Per GL 89-10.Caused by Using Outdated Configuration.Valves secured.W/930628 Ltr ML20045B1731993-06-0909 June 1993 LER 92-013-00:on 921209,identified Deficiency Involving Check Valve Test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] |
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Southern California Edison Company . ,
, SAN ONOFFIE NUCLEAR GENERATING STAttON P. O. Box 128
- GAN CLEMLNT E, CALIFORNIA 92672 HfE; MORGAN
'f TELEPHONE nunou unaoEn November 20, 1989 avi4> see enai -
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U. S. Nuclear Regulatory Commission! '
Do'cument Control-Desk
. . Washington' D.C. '20555-
Subject:
Docket No.!LO 361
-Supplemental Report 4 Licensee Event Report No.88-035, Revision 1 L
San Onofre Nuclear. Generating _ Station, Unit 2
' Pursuant.to 10 CFR'50.73(d), this submittal provides the supplemental report
-for an occurrence; involving feedwater' flow venturis.- Neither the health and safety of plant personnel or the public was affected by this occurrence.
1.
If you require' any additional information, please so adt'ise.
Sincerely, kD ~'
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Enclosure:
LER No.88-035, Revision 1
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-cc: 'C.'W. Caldwell'(USNRC Senior Resident Inspector, Units 1, 2 and 3)
.1 B. Martin (Regional Administrator, USNRC Region V) .
. Institute of Nuclear Power Operations (INP0) l 891'1290001 891120 PDR.
S ADOCK 05000361 )O L PDC l
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, ,' LICENSEE EVENT REPORT (LER) facility Name (1) Docket Number (2) Psoe L3)
A SAN ONOFRE NUCLEAR GENERATING STATION. UNIT 2 Of 51 Of 01 01 31 61 1 '1lof 0l7 Ittle (4)
PLANT OPERATION ABOVE 102% ESilMATED ACTUAL POWER DUE TO MANUFACTURING DEFECT OF FEEDWATER FLOW VENTURI FWFMT BATF di f ra rmare (6) DFphl'T hATU (7) OTMFD Fatti tf f t f MVnf VFh (R) 5 at on '*#il * "**** O'* "'I Month Day Year Year //f ff , Month Day Year O! 51 01 01 01 l'l NONE 112 213 813 '818 0l3I5 011- 1 i 81 9 of 51 01 Of of ' i 1 TH E REPORT IS 1;UBM.TTtD PURSUAN" TO 'HE REQUIREMLNTS Of 1DCFR OPERATING (Chock one or more of the fotlow no) (11)
MODE (9)- 1 20.402(b) 20.405cc) 50.73(a)(z)(1y) 73.71(b)
POWER LEVEL' Z 20.405(a)(1)(1) 20.405(a)(1)(II)
Z 50.36(c)(1) 50.36(c)(2)
Z 50.73(a)(2)(v)l) 50.73(a)(2)(vi Z 73.71(c)
Other (Specify in (10) i1 01 0 Z 20.405(a)(1)(lit) 50.73(a)(2)(1) Z 50.73(a)(2)(vill)(A) Abstract below and
//////////i////////////// _ 20.405(a)(1)(iv) 20.405(a)(1)(v)
X 50.73(a)(2)(II) 50.73(a)(2)(li t )
_ 50.73(a)(2)(vill)(B) 50.73(a)(2)(x) in text)
///////////////////////// _ _ _.
/$/ b$/b LICENSEE CONTACT FOR THIS LER (12)
TELEPHONE NUMBER N8"' AREA CODE ,
H. E. Moraan. Station Mananer 7l 114 316l81 l6121411 l COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)
/
CAUSE SYSTEM COMPONENT R gE CAUSE SYSTLa' COMPONENT AC- R E l B 5lJ Fl El l XI 91 91 9 Y /////// l l l' I l i I ////// ,
I l l 1 l I l /////// I I 1 l l I I //////
SUPPLEMENTAL REPORT EXPECTED (14) Expected Month Day Year Submission Yes'(If ves. complete EXPECTED SUBMISSit'N DATE) lkklNO Date (15) l l l ABUTRACI (Limit to 1400 spaces, i.e., approximately fifteen single space typewritten lines) (16) l l
Oh December 16,-1988, with Unit 2 at 100% power, after having developed a new U methodology for approximating reactor power and applying it to plant historical l
' data, it was determined.that Unit'2 had operated at an estimated actual power in l excess of 102% from December 23, 1983 to January 4, 1984. The maximum power for '
this period was estimated to be approximately 103%. For many of the design basis accidents discussed in the Final Safety Analysis Report (FSAR), an initial power level of 103% in conjunction with the most limiting set of other initial conditions could result in consequences more severe than those determined in the FSAR, assuming no operator action for the times specified in the analysis.
- The cause of plant operation at an estimated actual power greater than 102% was ;
'_l ~a manufacturing defect of one-of the feedwater flow venturi pressure taps, which
~ resulted in a decreased differential pressure sensed across the venturi. This
' condition resulted in a decrease in indicated feedwater flow (and, therefore, iindicated reactor power) relative to actual feedwater flow (actual power). The operation of the plant at 100% indicated power resulted in estimated actual power exceeding 102%. The flow venturi was repaired in 1984 and subsequently replaced with a newer design in 1985.
No other instances of operation above 102% estimated actual power were identified from the review of Unit 2 and Unit 3 historical power data. The new methodology will continue to be applied to current plant operational data on a l routine basis to reduce the probability of operation above 100% actual power.
1
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- LICENSEE EVENT' REPORT.(LER)LTEXT CONTINUATION SAN ONOFRE NUCLEAR GENERATION STATION ~
DOCKET NUMBER- LER NUMBER PAGE
.? UNIT 2- 05000361 88-035-01: ~ 2 0F m
' Pl ant: San.Onofre Nuclear Generating Station i
< Unit:,Two~
Reactor. Vendor: Combustion Engineering Event Date:. 12/23/83 k Al- CONDITIONS AT TIME OF:THE EVENT:
Mode: 1, Power.0peration
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. . . Bt BACKGROUND INFORMATION:
. 1. Design Basis Maximum Plant Power I
1 '
' Units 2/3' Final Safety Analysis Report (FSAR) section .15.0.3.2,
" Initial Conditions", provides the range of values for each of.the principal process' variables- that were considered in all the accident analyses. The maximum initialicore power for_ these analyses is a
L 102%, thus defining the design basis maximum power of the plant ~
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q T , 2. Calorimetric Power Calculations: g
- During operation, plant power is normally determined:by secondary !
calorimetric calculation, which utilizes various steam plant. O parameters'as inputs. -Feedwater flow is one of the parameters d utilized as~ input to this calculation. This parameter is determined by measuring the-differential pressure across -feedwater flow venturis (JB][FE] in the main feedwater lines; feedwater flow l venturis FE1111- and FE1121 provide indication of feedgater flow to j n the steam generators [SG) and input- to the secondary calorimetric j power calculation.
1
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Plant power can also be determined by primary calor ~imetric l calculation, which utilizes reactor coolant system [AB]' temperatures )
and mass flow rate as inputs.' This calculation is somewhat less
. accurate than the secondary calorimetric, but is determined .;
L independent of steam plant parameter values. t
'C. DESCRIPTION.0F THE EVENT: i
. I '. Event-p 3
~*
During Unit 2 Cycle 1 operation in 1983, a decreasing trend in the i primary calorimetric calculated power relative to the secondary calorimetric calculated power with increased core life was noted to
- j. occur. Feedwater flow venturi fouling was concluded to have been the cause of the trend.
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s LICENSEE EVENT REPORT (LER) TEXT. CONTINUATION- ,
2 SAN ONOFRE NUCLEAR GENERATION STATION DOCKEl NUMBER LER NUMBER PAGE l UNIT 2 05000361 88-035-01 3 0F 7
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The fouling was caused by oxygen in the condensate-[SD).which caused l an electrochemical- reaction in which copper from the. feedwater 1 heater.[SM)[HX) tubes was transported from the heaters and deposited, 1 as a scale on the walls of the venturis, which were constructed of
'l carbon steel with a stainless steel cladding. This scale resulted 1 in' a higher differential pressure being sensed across the venturi,.
which resulted in an increase in indicated feedwater flow-(and, l therefore, indicated reactor power) relative to actual feedwater flow (actual power). Since the plant was. operated at 100% indicated ,
power, actual power was decreased as the venturi fouling increased. I l
In November 1983, after approximately 140 effective full power days '
(EFPD) of operation, Unit 2 was shutdown, during which the feedwater flow venturis were cleaned. . When full power operation was resumed following.this outage, the ratio of primary calorimetric power to secondary calorimetric power was initially approximately 3% larger-than its value prior to the shutdown. This was attributed to the. I venturi cleaning. With continued plant operation, the venturis !
"refouled", and this ratio again decreased.
l Licensee Event Report (LER)88-028 (Docket No. 50-361) describes L sone factors (including feedwater flow venturi fouling) associated with the secondary calorimetric power calculation wnich.resulted in.
the operation of Unit 2 at an estimated actual power slightly in excess of 100%. As one corrective action, the Plant Performance
- Monitoring -Program was enhanced to routinely monitor plant parameters related to the determination of reactor power to further reduce the probability of operation above 100% power. Included in the enhancement of the program was the development of a new u methodology to approximate reactor power based upon calculations
- utilizing empirical data from plant. operation independent of l
- secondary calorimetric inputs. This methodology is acknowledged to contain a larger inherent error than the secondary calorimetric power calculation, and it is intended to be used only as a check
- against secondary calorimetric power. The methodology was validated by' applying it to plant historical data.
l On December 16, 1988, with Unit 2 at 100% power, after applying the aforementioned new methodology for approximating reactor power to plant historical data, a preliminary determination indicated that Unit 2 may have operated at an estimated actual power in excess of i 102% during a portion of the time periods of October 1983 through I
January 1984 and April through June, 1987 (as reported in a letter ',
to the NRC dated 12/19/88). Upon further evaluation utilizing additional data from these time periods, however, it was concluded that Unit 2 had probably operated at an estimated actual power in excess of 102% only during the time period from December 23, 1983 to L January 4, 1984.
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LICENSEE EVENT REPORTf(LER) TEXT _ CONTINUATION
-SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER- LER NUMBER PAGE UNIT 2 05000361 88-035-01 '4 0F'7' ,
Unit 2 was never continually operated at an indicated: power in excess of 100%. . Operation above'102% actual power constitutes a
. condition outside the' design basis of-the plant. The. maximum power at.which the plant may have been operated during this period'was 1
, estimated to_be approximately 103%.
- 2. _ Inoperable Structures, Systems or Components.that Contributed to the
- Event: ;
Refer to Section D, Cause.
- 3. Sequence-of Events:
DATI ACTION ,
-9/83 Feedwater flow venturi fouling was noted to occur.
11/83' Following approximately 140 EFPD, Unit 2 was shutdown, during which the feedwater flow venturis were cleaned.
12/83 - Follnwing the outage, full power operation resumed. .
Primary-to-secondary calorimetric ratio was- i approximately 3% higher than prior to the outage, j 6/84 During a plant shutdown, feedwater flow venturi FE1111
- was' determined to have a' defective low pressure _ tap.
The venturi was repaired prior to returning to power o operation.
10/84 Evaluation performed which concluded that 102% power was not exceeded during Unit 2 Cycle 1 operation.
12/88-1/89 After development of a new methodology for determining' i reactor power and applying it to plant historical data, a determination was made that Unit 2 had probably operated at an estimated actual power in excess of 102%
during the time period from December 23, 1983 to January 4, 1984. ,
p 4. Method of Discovery:
Refer to Section C.1, Event. l
- 5. Personnel Actions and Analysis of Actions:
Not applicable.
- 6. Safety System Responses:
Not applicable.
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LICENSEE EVENT REPORT =(LER) TEXT CONTINUATION o SAN ONOFRE NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE UNIT 2 05000361 88-035-01 5 0F 7
-D.- CAUSE OF THE EVENT:-
4 l '. Immediate Cause:
The cause of plant operation at an estimated actual power greater
.than 102% from December 23,-1983 to January 4, 1984 was determined'
'to have' been a hole in the. low pressure tap of the carbon steel feedwater flow venturi FE1111. This defect resulted in
.decalibration of ~ the venturi with changing feedwater- temperature.
An increased feedwater temperature (such as .for higher power operation) resulted in an erroneously low differential pressure sensed across the venturi. This' condition resulted.in a decreased indicated feedwater-flow (and therefore indicated reactor power) relative to actual- feedwater flow (actual power). When indicated
, power was. increased to 100%, estimated actual power was increased to greater than 102%.
p 2. Root Cause: j o
The defective venturi low pressure tap was determined to be caused by a manufacturing defect. The configuration of the tap's piping internal to the venturi differed from the configuration specified on the design drawing. This deficient configuration contained a weld which was improperly done, causing the hole in the low pressure tap-of the venturi.
- 3. Contributing Cause:
Following the outage in November-December 1983, secondary power was approximately 3% greater than prior to the outage. This difference was attributed to cleaning (and, therefore, defouling) the feedwater flow venturis during the outage. The magnitude of the venturi fouling effect (resulting in a higher indicated power relative to- ,
actual power), however, was such that the defective venturi low ,
- pressure tap (resulting in a lower indicated power relative to- 1 actual power) could not have been identified. ')
i E. CORRECTIVE ACTIONS:
- 1. Corrective Actions Taken:
- a. Feedwater flow venturi FE1111 was repaired following identification of the failure described above. Furthermore, during the first refueling outage (completed in February 1985), the carbon steel feedwater flow venturis were replaced with stainless steel venturis, which have exhibited a lower propensity toward fouling than their carbon steel predecessor.
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~ LICENSEE EVENT REPORT (LER)-TEXT CONTINUATION SAN ONOFRE. NUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE 1 UNIT'2- 05000361 88-035-01~ 6 0F 7 l
~ b. _ The new methodology for approximating reactor power was . l applied to remaining Unit 2 and Unit 3 historical power data, i No other instance of operation above 102% estimated-actual lj power was identified.
- c. ~ The Plant Performance Monitoring Program' has been enhanced to - l
. continue to monitor plant parameters related to the ;
determination of plant power, including: 1) trending-the 'I
~ feedwater venturi flow transmitter outputs to determine when a j venturi or' transmitter is failing;'and 2) application of the o new methodology to approximate.p1 ant power. This will serve j to reduce'the probability of operation _above 100% actual power (thereby reducing the probability'of operation above 102%-
actual power). r
- d. SCE-is pursuing alternatives to address feedwater flow venturi. '(
fouling, including electrical isolation of the venturis to minimize (and potentially eliminate) fouling. j l '
E 'F. SAFETY SIGNIFICANCE OF THE EVENT:
Units 2/3 Final Safety- Analysis Report. (FSAR) section 15.0.3.2, " Initial Conditions", provides the range of values for each of the principal' y
' process variables that were considered in all the accident analyses. The specified maximum allowed initial core power is 102%. For many of the design basis accidents, therefore, an initial power level of- 103% in
' conjunction with the most limiting set of other initial conditions at the time of the initiation of an event could result in consequetces more-severe than those discussed in the FSAR,: assuming no operator action for the times specified in the analysis.
G. ADDITIONAL INFORMATION:
I 1. Differences Between Evaluations of Maximum Power Attained:
Reactor power is determined either by direct measurement of a y parameter (e.g., neutron flux), or by performing calculations utilizing measured parameters (e.g., secondary calorimetric). The accuracy of the power determination depends upon the inherent error of the input parameters.
An evaluation of Unit 2 plant performance performed in October 1984 concluded that 102% power had not been exceeded during Cycle 1 operation. The method utilized in this evaluation determined power based upon certain plant parameters, each of which can contain some amount of inherent error. The newer methodology for approximathg
. reactor power., developed and implemented as described in LER 88-028 (Docket No. 50-361), utilizes a greater number of parameters than L the earlier evaluation; as a result, a greater confidence level of l
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'b LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
, ' SAN ONOFRE WUCLEAR GENERATION STATION DOCKET NUMBER LER NUMBER PAGE g; UNIT 2 -05000361 88-035-01 7 0F 7 s
the: accuracy of the' power determination is achieved. The inherent
' error of the earlier evaluation. led to the. inappropriate conclusion
.that 102%' power-had not been exceeded. The increased accuracy of the . newer methodology led to the opposite conclusion.
2.- . Component Failure =Information:
The feedwater flow venturi was manufactured by Vickery Simms, model FVI L- (20") .
- 3. Previous LERs for Similar Events:
g LER 88-028 (Docket No. 50-361)
Refer to Section C;l (Event).
- 4. Results-of NPRDS Search: ,
A-search of Vickery Simms Inc. venturis found a total of 8 failures.
None oi-the other failures reported included model numbers. j d
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