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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr ML18039A6031998-11-0404 November 1998 LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr ML18039A5971998-10-28028 October 1998 LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve ML18039A5171998-09-15015 September 1998 LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls ML18039A3311998-05-0404 May 1998 LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11 ML18039A3141998-04-0909 April 1998 LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions ML18039A3101998-04-0707 April 1998 LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source ML18039A3051998-04-0101 April 1998 LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized ML18039A2041997-12-0303 December 1997 LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges ML18038B9961997-11-25025 November 1997 LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced ML18038B9931997-11-18018 November 1997 LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated ML18038B9861997-11-10010 November 1997 LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped ML18038B9701997-10-0909 October 1997 LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule ML18038B9661997-10-0303 October 1997 LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed ML18038B9321997-08-0707 August 1997 LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated ML18038B9231997-07-25025 July 1997 LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr ML18038B8811997-05-14014 May 1997 LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr ML18038B8801997-05-0808 May 1997 LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr ML18038B8701997-04-29029 April 1997 LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored ML18038B8521997-04-0909 April 1997 LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr ML18038B8511997-04-0909 April 1997 LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified ML18038B8481997-04-0909 April 1997 LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified ML18038B8451997-04-0909 April 1997 LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr ML18038B8551997-04-0404 April 1997 LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays ML18038B8441997-03-26026 March 1997 LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers ML18038B8071997-01-15015 January 1997 LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR ML18038B8041997-01-13013 January 1997 LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited ML18038B7931996-12-0404 December 1996 LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr ML18038B7921996-11-27027 November 1996 LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr ML18038B7911996-11-27027 November 1996 LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised ML18038B7741996-10-15015 October 1996 LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr 1999-09-30
[Table view] Category:RO)
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr ML18039A6031998-11-0404 November 1998 LER 98-004-00:on 981007,primary Containment Allowable Leak Rate Was Exceeded.Caused by Failure of Check Valve to Fully Seat Following Shutdown of Rbbccw Sys for Llrt.Valve Was Retested During Next Refueling Outage.With 981104 Ltr ML18039A5971998-10-28028 October 1998 LER 98-003-00:on 981001,Unit 2 Received Full Automatic Scram from 100% Reactor Power.Caused by Failure of Normally Open Isolation Valve Which Blocked Flow of Stator Cooling Water Through Associated Heat Exchangers.Replaced Failed Valve ML18039A5171998-09-15015 September 1998 LER 98-002-00:on 980816,personnel Observed Both Channels of Rod Block Monitor Sys Bypassed for Cr.Caused by Failure of Gene to Properly Document & Specify Adjustments.Will Implement Necessary Procedure Controls ML18039A3311998-05-0404 May 1998 LER 98-003-00:on 980407,reactor Manually Scrammed to Prevent thermal-hydraulic Instability After Recirculation Pump Runback.Caused by Human Error.Strengthened Controls Associated W/Walkdowns in NEDP-11 ML18039A3141998-04-0909 April 1998 LER 98-002-00:on 980310,ESF Actuation Occurred Due to Failure of Alternate Feeder Breaker Position Switch.Will Continue Testing & Visual Insps on Addl Breaker Position Switches & Will Revise Applicable Maint Instructions ML18039A3101998-04-0707 April 1998 LER 98-001-00:on 980308,ESF Actuations Occurred When 2B RPS Bus Was Transferred to de-energized Source.Caused by Failure of Preparing Clearance to Exercise Proper Attention. 2B RPS Bus Restored to Transformer Source ML18039A3051998-04-0101 April 1998 LER 96-001-00:on 980121,determined That Temp Sensors for Certain HELB May Not Detect All Possible Break Locations. Caused by Differences in Computer Codes Rather than Actual Response.Computer Code Correctly Utilized ML18039A2041997-12-0303 December 1997 LER 97-008-00:on 971104,main Steam Safety/Relief Valves Exceeded TS Setpoint Limit.Caused by Pilot Valve Disc/Seat Bonding.Replaced All 13 Unit 2 Main Steam SRV Pilot Cartridges ML18038B9961997-11-25025 November 1997 LER 97-007-00:on 971028,Unit 2 Automatically Scrammed.Caused by Momentary Pressure Drop in electro-hydraulic Control Sys at Turbine Control Valves.Scram Contactor Replaced ML18038B9931997-11-18018 November 1997 LER 97-006-00:on 971019,declared Unit 2 Hpcis Inoperable. Caused by High Condensate Level in HPCI Turbine Inlet Steam Line Drain Pot.Work Request Initiated ML18038B9861997-11-10010 November 1997 LER 97-005-00:on 971012,ESF Components Were Actuated.Caused by Inadequate Procedure.Cs Pumps Were Secured & Injection Valves Were Closed & Refueling Floor Activities Were Stopped ML18038B9701997-10-0909 October 1997 LER 97-004-00:on 970909,TS Surveillances Were Not Performed During Refueling Outage Timeframe.Caused by Personnel Error. Incorporated Missed Snubber & Vacuum Breaker Surveillances Into Refueling Outage Schedule ML18038B9661997-10-0303 October 1997 LER 97-005-00:on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed ML18038B9321997-08-0707 August 1997 LER 97-003-00:on 970711,determined That HPCI Turbine Speed Lower than Indicated.Caused by Improper Evaluation of Valve Leak.Work Orders to Troubleshoot HPCI Initiated ML18038B9231997-07-25025 July 1997 LER 97-002-00:on 970626,discovered That Four Surveillance Instructions (Sis) Did Not Fully Test All Relay Logic Combinations.Caused by Personnel Error.Verified Relay Contacts Operable & Revised Applicable SIs.W/970725 Ltr ML18038B8811997-05-14014 May 1997 LER 97-004-00:on 970414,unplanned Manual Start of EDG During Scheduled Redundant Start Test Occurred.Caused by Personnel Error.Edg 3D Shutdown & Returned to pre-event Configuration. W/970514 Ltr ML18038B8801997-05-0808 May 1997 LER 97-002-00:on 970410,HPCI Declared Inoperable.Caused by Personnel Error.Operations Personnel Stopped Instrument Mechanics Testing & Returned HPCI to Standby Readiness. W/970508 Ltr ML18038B8701997-04-29029 April 1997 LER 96-004-02:on 960717,loss of ECCS Division I & Division II Instrumentation Renders ECCS Equipment Inoperable.Caused by Loss of Inverter Output.Failed Components Replaced in Atu Inverter Circuitry & Instrumentation Logic Restored ML18038B8521997-04-0909 April 1997 LER 97-003-00:on 970314,Unit 3 Main Steam SRVs Pilot Cartridges Failed Setpoint Tolerance Bench Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Drifting.Main Steam SRV Pilot replaced.W/970409 Ltr ML18038B8511997-04-0909 April 1997 LER 95-003-02:on 950301,Unit 2 Main Steam SRVs Failed Setpoint Acceptance Tests.Caused by Corrosion Bonding of SRV Pilot Disc/Seat Interface Resulting in Upward Setpoint Drift.Valves Currently Being Retested & Recertified ML18038B8481997-04-0909 April 1997 LER 96-004-01:on 960425,Unit 2 SRV Pilot Cartridges Failed Setpoint Acceptance Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints Deviating.Valves Currently Being Retested & Recertified ML18038B8451997-04-0909 April 1997 LER 96-008-01:on 961101,Unit 2 Main Steam SRV Pilot Cartridges Failed Setpoint Tolerence Bench Tests.Caused by SRV Pilot Disc/Seat Bonding Resulting in SRV Setpoints.Srv Pilot Cartridges replaced.W/970409 Ltr ML18038B8551997-04-0404 April 1997 LER 97-001-00:on 970305,loss of Offsite Power on Unit 3 During Refueling Outage Resulted from Shorted Component. Replaced Relays Involved in Event W/Less Sensitive Relays ML18038B8441997-03-26026 March 1997 LER 95-001-02:on 950123,DG Turbocharger Failure Resulted in Noncompliance W/Ts Lco.Instituted Vibration Monitoring Program for EDG Turbochargers ML18038B8071997-01-15015 January 1997 LER 96-008-00:on 961217,loss of ECCS Division II Instrumentation Caused ECCS Equipment to Be Inoperable. Replaced Cleared Fuse & Shorted SCR ML18038B8041997-01-13013 January 1997 LER 96-007-00 on 961213,engineered Safety Feature Actuations Resulting from Inadequate Planning of step-text Work Order Occurred.Tripped Breaker Reset & LCO Condition Exited ML18038B7931996-12-0404 December 1996 LER 96-006-00:on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse performed.W/961204 Ltr ML18038B7921996-11-27027 November 1996 LER 96-008-00:on 961101,MS SR Valves Exceeded TS Required Setpoint Limit as Result of Disc/Seat Bonding.Caused by Corrosion Bonding of SRV Pilot Interface.Replaced All Thirteen Ms SR Valve Pilot cartridges.W/961127 Ltr ML18038B7911996-11-27027 November 1996 LER 96-007-00:on 961029,Unit 2 Scram on Turbine Control Valve Fast Closure Occurred Due to Loss of Excitation to Main Generator.Exciter Brushes Inspected & Replaced & Procedures Revised ML18038B7741996-10-15015 October 1996 LER 96-005-03:on 960915,reactor Scrammed as Required by TSs Due to Trip of Reactor Recirculation Motor Generator Set 3A. Caused by Bus Bar in Generator Armature Circuit Failing. Collector Rings Were replaced.W/961015 Ltr 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML18039A7361999-03-11011 March 1999 Rev 4 to TVA-COLR-BF2C10, Bfnp,Unit 2,Cycle 10 Colr. ML20204C7891999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A6951999-02-19019 February 1999 LER 99-002-00:on 990122,LCO Was Not Entered During Calibration Testing of 3D 480 Volt Rmov Board.Caused by Personnel Error.Tva Has Briefed Operations Personnel to Preclude Recurrence of Event.With 990219 Ltr ML18039A6871999-02-12012 February 1999 LER 99-001-00:on 990114,Unit 3 HPCI Was Noted Inoperable. Caused by Oil Leak on Stop Valve.Corrective Maint Was Performed to Repair Oil Leak.With 990212 Ltr ML18039A6931999-02-0303 February 1999 Rev 3 to TVA-COLR-BF2C10, Bfnp Unit 2 Cycle 10 Colr. ML18039A6941999-02-0303 February 1999 Rev 1 to TVA-COLR-BF3C9, Bfnp Unit 3 Cycle 9 Colr. ML18039A6671998-12-31031 December 1998 LER 98-004-00:on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With 981231 Ltr ML18039A6661998-12-31031 December 1998 Ro:On 981215,HRPCRM 2-RM-90-273C Was Declared Inoperable. Caused by Downscale Indication.Containment RM Will Be Utilized as Planned Alternate Method of Monitoring Until Hrpcrm 2-RM-90-273C Can Be Returned to Operable Status ML20199K8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Browns Ferry Nuclear Plant.With ML20199F2721998-12-31031 December 1998 ISI Summary Rept (NIS-1), for BFN Unit 3,Cycle 8 Operation ML18039A6471998-12-15015 December 1998 LER 98-007-00:on 981116,unplanned ESF Following Loss of 4kV Unit Board 3B Occurred.Caused by Temporary Energization of Lockout Relay on 4kV Unit Board 3B When Resistor on Relay Monitoring Lamp Circuit Shorted.Replaced Resistor ML18039A6371998-12-0707 December 1998 LER 98-006-00:on 981116,MSSR Valves Exceeded TS Setpoint Tolerance.Caused by Pilot Valve Disc/Seat Bonding. Installed SRV Pressure Switches During Unit 3,cycle 8 Outage.With 981207 Ltr ML20199F2791998-12-0303 December 1998 Bfnp Unit 3 Cycle 8 ASME Section XI NIS-2 Data Rept ML20198D9621998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bfn,Units 1,2 & 3. with ML18039A6071998-11-12012 November 1998 LER 98-005-00:on 981014,mode Changes Not Allowed by TS 3.0.4 Were Made During Reactor Startup.Caused by TS LCO 3.0.4 Not Being Properly Applied.Training Info Memo Re Proper Application for TS LCO 3.0.4 Was Prepared.With 981112 Ltr 1999-09-30
[Table view] |
Text
NRC FORH 366 U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESI' MATED BURDEN PER RESPONSE TO COHPLY Wl TH THIS INFORMATION COLLECT ION REQUEST: 50.0 MRS.
LICENSEE EVENT REPORT (LER) FORWARD COHMENTS REGARDING BURDEN ESTIMATE TO THE INFORMATION AHD RECORDS MANAGEMENT BRANCH (MNBB 7714), U.S ~ NUCLEAR REGULATORY COHHISSION, WASHINGTON, DC 20555-0001 AND TO THE PAPERWORK REDUCTION PROJECT (3140-0104), OFFICE OF MANAGEMENT AND BUDGET WASHINGTON DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) PAGE (3)
Bzowns Ferry Nuclear Plant (BFN) Unit 2 05000260 1 OF 8 TITLE (4) Diesel Generator Turbocharger Failure That Resulted In Noncompliance With Technical Specification Limiting Condition For Operation EVENT DATE (5) LER NINBER (6) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)
SEQUENTIAL REVISION FACILITY NAME DOCKET NUHBER HONTH DAY YEAR YEAR MONTH DAY YEAR NA NUHBER NUMBER FACILITY NAME DOCKET NUHBER 01 23 95 95 001 02 3 26 97 NA OPERATING THIS REPORT IS SUBHITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR 5: (Check one or mor e) (11)
HOOE (9) N 20.402(b) 20.405(c) 50.73(a)(2)(iv) 73.71(b)
POWER 20.405(a)(1)(i) 50.36(c)(1) 50 '3(a)(2)(v) 73.71(c)
LEVEL (10) 100 20.405(a)(1)(ii) 50.36(c)(2) 50.73(a)(2)(vii) OTHER 20.405(a) (1) ( i i i ) 50 '3(a)(2)(i) 50.73(a)(2)(viii)(A) 20.405 (a) (1) ( I v) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) 20.405(a)(1)(v) 50.73(a)(2)(ill) 50.73(8)(2)(x)
LICENSEE COHTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Steven W. Austin, Licensing Project Manager (205)729-2070 COMPLETE ONE ZaINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT 13 SYS REPORTABLE REPORTABLE CAUSE CDHPONENT MANUFACTURER CAUSE SYSTEH COHPONENT MAHUFACTURER TEH TO NPRDS TO NPRDS X EK M494 N SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED MONTH DAY YEAR YES SUBHI SS I OH (If yes, complete EXPECTED SUBHISSION DATE).
X NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)
On January 23, 1995 at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, TVA exceeded the Limiting Condition for Operation for an inoperable Emergency Diesel Generator (EDG). At 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, on January 16, 1995, following approximately two hours of operation, EDG C was declared inoperable when failed to go through the proper shutdown sequence after a stop signal was initiated. The it EDG was returned to operable status on January 25, 1995, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />. Failure of the turbocharger planetary gear train initiated the event. The planetary gears supply the motive force for the turbocharger foz engine loads less than 70 percent. At loads greater than 70 percent the exhaust gases provide the motive force foz the turbocharger. During the event, as the engine was unloaded, the amount of available exhaust gas decreased to where the turbocharger would have been driven 'from the planetary gears. However, because the gears had failed, the turbocharger did not supply combustion air, and the engine shutdown. The EDG was repaired and returned to service. TVA's analysis identified bending fatigue of a gear tooth on the turbocharger sun gear as the most probable cause of the turbocharger failure. Subsequent analysis has determined that the gear failed due to fatigue that was the result of quench cracking that occurred during manufacturing.
Therefoxe, the root cause of the failure was a manufacturing defect. TVA has recently instituted vibration monitoring program for the EDG tuzbochargers. The program is being used to identify abnormal operating characteristics of the tuzbochargezs. TVA has provided vendor with the evaluation detailing the component failure mechanism.
9704080111 97032b PDR ADQCK 050002b0 S PDR NRC FORH 366 (5.92)
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HRC FORH 366A U.S. NUCLEAR REGULATORY CQIHISSIOH APPROVED BY OHB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY NI TH THIS INFORIIATION COLLECT ION REQUEST: 50.0 HRS. FORlJARD COHHENTS REGARDIHG BURDEN ESTIHATE TO THE INFORHATION AND RECORDS HANAGEHEHT BRANCH (HHBB 771C), U.S. NUCLEAR REGULATORY COHHISSIOH, LZCENSEE EVENT REPORT DC 20555 0001, AND TO THE PAPERNORK REDUCTION 'ASHINGTON, TEXT CONTINUATION PROJECT (3150.0104), OFFICE OF HANAGEHENT AND BUDGET, NASHINGTOH DC 20503 FACILITY NAHE (1) DOCKET NUHBER (2) LER NUHBER (6) PAGE ( )
'YEAR SEQUENTIAL REVISION NUHBER' NUHBER Browns Ferry Unit 2 05000260. 2 of 8
'TEXT f mo e s ce is r ired use edditions co ies of NRC Form 366A (17)
Z. PLANT COND ZTZONS Unit 2 was in the run mode at 100 percent power or 3293 megawatts thermal. Units 1 and 3 were shutdown and defueled.
On January 16, 1995 at approximately 1535 hours0.0178 days <br />0.426 hours <br />0.00254 weeks <br />5.840675e-4 months <br />, operations commenced the Diesel Generator C Monthly Operability Test. This test is, performed to determine the operability of the Emergency Diesel Generator (EDG)[EK].
ZZ. DESCRZPTZON OF EVENT Event:
On January 23, 1995, at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />, TVA exceeded Limiting Condition for Operation (LCO) 3.9.B.3 for reactor operation with an inoperable EDG. This resulted in Unit 2 being in a condition prohibited by the plants Technical Specification (TS). The details which led to this event are provided below.
On January 16, 1995, at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br /> following approximately two hours of operation, the EDG C was unloaded and given a stop signal. When a stop signal is initiated;, the EDG is designed to decelerate from full speed (900 revolutions per minute (RPM) ) to idle speed (450 RPM) and sustain. the idle speed foz approximately 11.5 minutes then stop. This is necessary to allow the engine, especially turbocharger bearings, to cool. However, when the stop signal'as given, the engine decelerated to approximately 150 RPM and shutdown.
Thus, TVA declared EDG C inoperable and entered a seven day LCO for an inoperable EDG. BFN. Unit 2 TS state that, when one of the Units 1 and 2 Diesel Generator is inoperable, continued reactor power operation is permissible during the next seven days provided two offsite power sources are available and all Core Spray (CS) [BM], Residual Heat Removal (RHR) [BO] (Low Pressure Coolant Injection and Containment Cooling) systems and the remaining Units 1'nd 2 Diesel Generators are operable.
requirement cannot be met, the reactor shall be in cold shutdown If this condition in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Due to the time involved in obtaining the necessary parts and making the repairs, TVA was unable to return the EDG to operable status within the required LCO time limit. Thus, on January 23, 19951 at 2005 hours0.0232 days <br />0.557 hours <br />0.00332 weeks <br />7.629025e-4 months <br />,, TVA exceeded the seven day LCO for the inoperable EDG. Prior to the. LCO time limit expiring,
4l ~I NRC FORM 366A U.S ~ NUCLEAR REGULATORY COMMISSION APPROVED. BY OKB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS. FORWARD COKHEHTS REGARDING BURDEN ESTIHATE TO THE INFORHATIOH AND RECORDS MANAGEHEHT LZCENSEE EVENT .REPORT BRANCH (KNBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555.0001, AND TO THE PAPERWORK REDUCTIOH TEXT CONTINUATION PROJECT (3150-0104), OFFICE OF MANAGEMENT AND BUDGETS
'WASHINGTON DC 20503 FACILITY NAKE (1) DOCKET NUHBER (2) LER IRNBER (6) PAGE ( )
YEAR SEQUENTIAL' REVISIOH NUMBER NUMBER Browns Ferry Unit 2 05000260 3 of 8 TEXT If more s ace is r ired use additiona( co ies of HRC Form 366A (17)
TVA requested and received Discretionary Enforcement from the requirements of the TS. TVA received permission to continue reactor power operation for an- additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while the repairs were being made to the EDG.
On January 25, 1995 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, after completing the necessary repairs and .passing the required post maintenance testing, EDG C was declared operable and the established LCO was .exited.
This event is reportable in accordance with 10 CFR 50.73 (a)(2)(i)(B), as any operation or condition prohibited by the plant's TSs ~
Zno erable Structures, Co onents, or S stems that Contributed to the Event:
None.
C. Dates and A roximate Times of Ma or Occurrences:
January 16, 1995, at 2005 CST EDG C is declared inoperable.
TVA subsequently enters a seven day LCO.
January 23, 1995, at 2005 CST TVA exceeds the seven day LCO for an inoperable EDG.
Previously that day, TVA requested and received Discretionary Enforcement from the requirements of the LCO.
January 25, 1995,, at 1330 CST Repairs were completed and the EDG C is declared operable.
The LCO for an inoperable EDG is exited.
D. Other S stems or Seconda Functions Affected:
None.
Method of Discove Personnel in the EDG room witnessed the failure of the EDG to properly shutdown.
F. erator Actions:
None.
4l I!
NRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSIOH APPROVED BY OHB NO. 3150-0104 (5-92) EXP I RES 5/31/95
'ESTIHATED BURDEN PER RESPONSE TO COHPLY MITH THIS INFORHATION COLLECTION REQUEST: 50.0 HRS. FORNARD COHHENTS REGARDING BURDEN ESTIHATE TO THE INFORHATIOH AND RECORDS HANAGEHENT BRAHCH (HNBB 7714), U.S. NUCLEAR REGULATORY COHHISSION, LZCENSEE EVENT REPORT NASHINGTOH, DC 20555.0001, AND TO THE PAPER'MORK REDUCTION TEXT CONTINUATION PROJECT (3150.0104), OFFICE OF HANAGEHEHT AND BUDGETS, NASHINGTON DC 20503 FACILITY HAHE (1) DOCKET NUHBER (2) LER HUNGER (6) PAGE ( )
YEAR SEQUEHTIAL REVISION HUHBER NUHBER Browns Ferry Unit 2 05000260 4 of 8 TEXT f more s ce is re ired use additions( co es of NRC Form 366 g (17)
Safet S stem Re onses:
None.
zzz. CAUSE OF THE EVENT A. Zmmediate Cause:
The immediate cause of the event;,as the failure of the tuzbocharger which resulted in a failure of EDG C to go through the shutdown sequence.
B. Root Cause:
This event resulted from a failure of the turbocharger planetary gears and sun gear (see attached figure). The root cause of the failure has been determined to be a manufacturing defect.
TVA performed a metallurgical evaluation of the failed turbocharger components. TVA's evaluation identified evidence of fatigue on the sun gear and the planetary gears. TVA also identified signs of overheating, including discoloration and oxide-filled cracks, in these gears. The bearings appeared to have sustained no damage. This analysis found the most probable cause of the gear failures was fatigue; however, due to the extensive thermal and mechanical damage to the sun gear and planetary gears, TVA could not conclusively, determine the root cause of the failure.
Following the analysis of the failed components performed by TVA, a separate metallurgical evaluation of the failed turbocharger components was performed by an independent laboratory.
It was determined during the evaluation that the failure of the components from EDG C was due to quench cracking that occurred during the manufacturer's heat treatment process. The quench cracking was followed by an area of fatigue cracks that propagated across the tooth section of the gears until final catastrophic failure. Therefore, TVA has concluded that the root cause of the failure of EDG C was a manufacturing defect.
The failed components from EDG 3A (See Section II.B, Previous LERs on Similar Events) were also evaluated. The results of the evaluation on EDG 3A components indicated the same failure mechanism as EDG C. That is, the gears failed due to quench cracking that occurred during the manufacturer's heat treatment process. Accordingly,,TVA has concluded that the root cause of the failure of EDG 3A was a manufacturing defect.
I NRC FORH 366A U.S. NUCLEAR REGULATORY COMMISSION APPROVED BY OMB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORHATION COLLECTION REOUEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE INFORHATION AND RECORDS MANAGEHENT BRANCH (HNBB 7714), U.ST NUCLEAR REGULATORY COHMISSION ~
LICENSEE EVENT REPORT WASHINGTON, DC 20555 0001, AND TO THE PAPERWORK REDUCTION TEXT CONTINUATION PROJECT (3150 0104), OFFICE OF MANAGEHENT AND BUDGETS WASHINGTON DC 20503 FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE ( )
YEAR SEOUEHTIAL REVISION NUHBER NUMBER Browns Ferry Unit 2 05000260 5 of 8 TEXT If more s ce is r ired use additions co ies of NRc Form 366A (17)
The turbocharger is driven by a connecting gear train which drives the turbocharger during starting, and light load (less than 70 percent load) conditions'nder these conditions, there is not enough energy in the exhaust gases to drive the turbocharger. When the engine reaches approximately 70 percent load, exhaust gas energy, will drive the turbocharger faster than the gear train. Then the turbocharger will disengage itself from the gear train and be driven by the exhaust gases.
During the event, as the engine was unloaded and the amount of available exhaust gases decreased,,the turbocharger decelerated to a point where it should have been driven from the planetary gear train. The decrease in the exhaust gas resulted in a removal of the driving force to the turbocharger. Because the gear train had failed, combustion air was lost. At this point, the engine shutdown.
During the operability test, the EDG performed as designed. Up to the time the shutdown sequence was initiated, the personnel involved had no indication that the turbocharger failure was about to occur.
In 1986 the EDGs were updated, replacing the turbochargers with high capacity units. The EDG tuzbochargers have been in service since then. TVA has been trending EDG reliability data since mid-1987. The turbocharger for EDG C failed after over 157 starts. Additionally, TVA's maintenance program follows guidance provided 'by the vendor. Therefore, it is highly unlikely that the failure could be attributed to age or improper maintenance.
In addition to the turbocharger replacement, TVA replaced the engine stub shaft assembly with one of a revised design.
However, after the installation, it was determined that the revised stub shaft assembly's oil chamber did not completely match the diesel engine block and the stub shaft assembly would have to be replaced. The stub shaft assembly that was on the engine at the time of the turbocharger failure was refurbished and'eturned to service.
C. Contributin Factors:
None.
IV. ANALYSIS OF THE EVENT The EDGs are part of the standby AC power system that provides a highly reliable source of power as required for Emergency Core Cooling Systems. The EDGs ensure no single credible event can disable the core standby cooling functions.
0
NRC FORM 366A U.S. NUCLEAR'EGULATORY COMMISSION'PPROVED BY OMB HO. 3150-0104
'(5.92) EXPIRES 5/31/95.
ESTIMATED BURDEN PER RESPONSE TO COMPLY'HITH THIS INFORMATIOH COLLECTION REQUEST: 50.0 HRS. .FORlIARD COMMENTS REGARDIHG BURDEN ESTIMATE TO THE INFORMATION AND RECORDS MANAGEMENT BRANCH (MHBB 7714), U.S. NUCLEAR REGULATORY COMMISSION, LICENSEE EVENT REPORT llASHIHGTON, DC 20555-0001, AND TO THE PAPERNDRK REDUCTION TEXT CONTINUATION PROJECT (3150-0104), OFFICE OF MANAGEMENT AHD BUDGET, IJASHINGTON DC 20503 FACILITY KAME (1) DOCKET NUMBER (2) LER NUMBER ( ) PAGE ( )
TEAR SEQUEHT IAL REVI SION NUMBER HUHBER Browns Ferry Unit 2 05000260 6 of'8 TEXT If more s ce is r ired use additional co ies of NRC Form 366A .(17)
EDG C supplies emergency power to- RHR,pump 2B, CS Pump 2B, RHR Service Water Pump B2 (BI], and Emergency Equipment Cooling Water Pump B3
'[BI] .
BFN is analyzed for a seven day allowed outage time (AOT), during which no single failure is assumed to occur in conjunction with a Design Basis Accident. TVA requested Discretionary Enforcement that extended the AOT an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. During that time,, standby auxiliary power for the above equipment was not available from its.
normal EDG. The three remain'ing RHR and'CS pumps weze powered from both the normal offsite power source and, EDGs.
if required, their normal For long term loss of offsite power, EDG 3C could have been manually aligned through existing board tie breakers to supply power to the equipment normally powered by EDG C.
Discussions with the vendor have indicated that the,two failures at BFN are the only incidents of failure of the turbocharger due to planetary gear deterioration in the engines used in a nuclear or nonnuclear applications.'here is no indication that the BFN
.application has exacerbated the gear failures. TVA believes that is highly improbable that multiple failures would occur during a it 100-day period for accident mitigation. TVA, bases this on the large number of .turbochazgers in service with the gears supplied by the same manufacturer. Moreover, BFN has over 1578 starts on the installed turbochargers with no failures to accept and carry loads due to planetary gear train deterioration.
The failure of the EDG turbocharger was discovered during the unloading and shutdown sequence of the EDG. The failure became self-evident upon unloading of the EDG. However, had a failure of this nature occurred during the startup the EDG would not have fulfilled its design function. Because the EDG operated as designed up .to the time when the turbocharger failure occurred, this event did not affect the safety of the plant, its personnel, or the public.
CORRECTIVE ACTIONS A. Immediate Corrective Actions:
EDG C was placed under an administrative hold and secured so could not be started.
it The turbocharger on the EDG was replaced. After completing post maintenance testing, the EDG was returned to standby readiness.
1(
HRC FORH 366A U.S. NUCLEAR REGULATORY COHHISSIOH APPROVED BY OHB NO. 3150-0104 (5-92) EXPIRES 5/31/95 ESTIHATED BURDEN PER RESPONSE TO COHPLY IIITH THIS INFORHATION COLLECT ION REQUEST: 50.0 HRS. FORUARD COHHEHTS REGARDING BURDEN ESTIHATE TO THE INFORHATION AND'ECORDS HANAGEHEHT BRANCH (HNBB 7714), 'U.S. NUCLEAR REGULATORY COHHISSIOH, LZCENSEE EVENT REPORT IIASHIHGTOH, DC 20555.0001, AHD TO THE PAPERUORK REDUCTION TEXT CONTINUATION PROJECT (3150.0104), OFFICE OF HANAGEHEHT AND DC 20503 BUDGET,'ASHINGTON FACILITY NAHE (1) DOCKET RIBBER (2) NLNiBER (6) PAGE ( )
YEAR'ER SEQUENTIAL REVISION NUHBER NUHBER Browns Ferry Unit 2 05000260 7 of 8 TEXT f more s ce is r ired use additional co ies of NRC Form 366A (Tf)
B~ Corrective Actions to Prevent Recurrence:
TVA has recently instituted vibration monitoring program for the EDG tuzbochargers. The program provides valuable information which is being used to identify any abnormal operating characteristics of the turbochazgers.
As previously stated, the vendor has indicated that the two failures at BFN are the only incidents of failure of the turbocharger due to planetary gear deterioration in the engines used in a nuclear application. Th gears involved in the failures discussed were manufactured in 1985. TVA has provided the metallurgy evaluations detailing the component failure mechanism to the vendor foz use in identifying any additional corrective actions'Z.
ADDITIONAL ZNFORMLTZON A. Failed Co nents:
The failed sun gear and planetary gear train aze part of a model 9526867 turbocharger from Power Systems Division of MKW (formally Morrison-Knudsen), supplied as part of a Model 999-20 General Motors (GM) stationary power generating plant.
B. Previous LERs on Similar Events:
There have been no previous LERs issued where an EDG could not be returned to service during the seven day LCO time limit.
However, on two recent occasions, TVA experienced a turbocharger failure on one of the EDGs.
On October 17, 1984, EDG 3A experienced a failure with one of the original capacity turbochazgers. In this instance, the turbocharger itself experienced a failure. TVA believed the cause of this failure to be failure of the compressor bearing assembly,. The turbocharger was replaced and the EDG was returned to service on October 21, 1984, within the allowed LCO time limit.
On August 25, 1992, EDG 3A experienced a failure of one of the high capacity turbochazgezs. The EDG 3A was returned to service on September 1, 1992, within the LCO time limit.
TVA's investigation found that the planetary gear set and the sun gear failed, initiating the event. The turbocharger was shipped to the vendor for failure analysis. It was determined that the cause of the failure was planetary bearing failure, which caused a loss of concentricity within the gear train. The loss of
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NRC EORH 366II U.S. NUCLEAR REGULATORY,CCSHIISSIOH APPROVED BY'CHB NO. 3150-0104 (5-92) EXPIRES 5/31/95
'ESTIHATED BURDEN PER RESPOHSE TO COHPLY IIITH THIS IHFORHATIOH COLLECT ION REQUEST: 50.0 HRS. FORIIARD COHHEHTS REGARD IHG BURDEH ESTIHATE TO THE INFORHATIOH AHD RECORDS HANAGENEH'I BRANCH (HHBB 7714), U.S. HUCLEAR REGULATORY COHHISSIOH, LZCENSEE EVENT 'REPORT WASHINGTON, DC 20555-0001, AND TO THE PAPERlJORK REDUCTION TEXT CONTINUATION PROJECT (3150-0104), OFFICE OF HANAGEHEHT AND BUDGET, IIASHINGTOH DC 20503 FACILITY'AHE (1) DOCKET NIAIBER (2) LER NINBER ( ) PAGE ( )
YEAR SEQUEHTIAL REV IS I OH HUNGER NUHBER Browns Ferry Unit 2 05000260 8 of 8 TEXT f more s ce is r red use additional co ies of N C Form 366A (17) concentricity within the gear train resulted in an improper meshing of the associated gear tee=h. The vendor could not determine the root cause, of the bearing failure; but similar failures have occurred at other utilities due to improper lubrication. However, during disassembly of EDG C, lubricating oil was evident on all bearing surfaces and all drilled oil
,passages appeared'o be clear.
VZZ. Commitments I none TURBOCHARGER PL4NET GEAR TRAIN PLANET CARR(EP. SHAFT IMPELLER PIANET GEAR CARRIER COMARE55OR
~ RAAINQ JOURNAL / EAR CARRIER DRIVE GEAR TURBIN%
5 EAR INQ JOURNAL TUABO
~IDLEA AINQ GEAR QEAR PLANET QEARS SUN TURBO GEAR 0 0 DRIVE GEAR AINQ GEAR
~Fi uue Energy Industry Identification System (EIIS), system and component codes are identified in the text with brackets (e.g , [XX]).
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