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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024J3211994-10-0505 October 1994 LER 94-006-00:on 940909,failure to Perform Slave Relay Test Associated W/One Containment Isolation Valve Due to Improper Work Practices.Reviewed All Slave Relay Test Procedures & Trained All Qualified reviewers.W/941005 Ltr ML20046B5251993-08-0404 August 1993 LER 93-007-00:on 930705,TS Required Surveillance Was Not Performed Because of Inappropriate Action Because of Lack of Attention to Detail.Generated WO 93047633 to Perform Required Surveillance on Unit 1 IPE CA 9010.W/930729 Ltr ML20045H9821993-07-12012 July 1993 LER 93-005-00:on 930612,manual Rt in Unit 1 Occurred Due to Equipment Failure Due to Failure of L-13 Field Cable Between Data Cabinet B & Bulkhead for Undetermined Reasons.Replaced Field cable.W/930709 Ltr ML20045D9681993-06-25025 June 1993 LER 93-006-00:on 930526,discovered That Sample Blower for Radiation Monitor 1 EMF-43B Off & Monitor Declared Inoperable & Ventilation Sys Air Intakes Not Isolated.Caused by Deficient Procedures.Test Procedures Revised ML20045B2811993-06-11011 June 1993 LER 93-004-00:on 930513,both Trains of CR Ventilation Sys Declared Inoperable Due to Equipment Failure.Exact Cause of Failure Could Not Be Determined.Train B Nuclear Svc Water Sys Flow Balance completed.W/930611 Ltr ML20029C2091991-03-21021 March 1991 LER 91-003-00:on 910219,both Trains of Control Room Ventilation Sys Inoperable.Caused by Design Malfunction & Management Deficiency.Temporary Modifications,Removing Automatic Closure Function implemented.W/910321 Ltr ML20028G9561990-09-26026 September 1990 LER 90-025-00:on 900827,Unit 1 Shut Down Because of Unidentified RCS Leakage Exceeding Tech Spec Limits.Caused by Equipment Failure.Procedure AP/1/A/5500/10 Implemented. Valve 1NC-33 Will Be Repacked at Next outage.W/900926 Ltr ML20044A0091990-06-25025 June 1990 LER 90-015-00:on 900524,Tech Spec 3.0.3 Entered Because More than One Power Range Nuclear Instrumentation Channel Exceeded 5% Deviation.Caused by Mgt Deficiency.Boric Acid Added to Coolant sys.W/900625 Ltr ML20043H4991990-06-21021 June 1990 LER 90-012-00:on 900522,loose Matl,Consisting of Masslin Cloths & Stepoff Pad,Discovered in Upper Containment.Caused by Failure to Follow Procedures.Loose Items Removed & Cleanliness Procedures revised.W/900621 Ltr ML20043H2641990-06-20020 June 1990 LER 90-011-00:on 900521,noted That Valve 1RN-69A Auxiliary Feedwater Assured Supply from Train a Nuclear Svc Water Repositioned to Open Position After Start of Pump.Cause Unknown.Pump Shut Down & Valve closed.W/900620 Ltr ML20043F7471990-06-13013 June 1990 LER 90-010-00:on 900427,discovered That Annulus Ventilation & Control Room Ventilation Sys Headers Would Not Operate,As Designed,Under Postulated Operating Conditions. Caused by Design Deficiency.Change submitted.W/900613 Ltr ML20043F5071990-06-11011 June 1990 LER 90-009-00:on 900512,feedwater Isolation Occurred as Result of Steam Generator 1B Reaching hi-hi Level Setpoint of 82% Level.Caused by Inappropriate Action Because of Lack of Attention to Detail.Feedwater Logic reset.W/900611 Ltr ML20043D6541990-05-30030 May 1990 LER 90-007-00:on 881018,during Insp Ice Condenser Basket Found W/Bottom Screws Missing.Caused by Installation Deficiency Because of Improper Matl Selection.Work Request Initiated to Replace Improper screws.W/900530 Ltr ML20043D7121990-05-30030 May 1990 LER 90-006-00:on 900226,discovered Abnormal Degradation on Steel Containment Vessel.Corrosion Caused by Design Deficiency Caused by Unanticipated Environ Interaction. Detailed Insps conducted.W/900529 Ltr ML20043C8041990-05-30030 May 1990 LER 90-008-00:on 900430,radiation Monitor for Contaminated Parts Warehouse Ventilation & Sampler Min Flow Device Declared Inoperable.Caused by Personnel Error.Appropriate Procedures Enhanced to Prevent recurrence.W/900530 Ltr ML20012D1651990-03-19019 March 1990 LER 90-004-00:on 900208,determined That Holes Left in Auxiliary Shutdown Panel Could Allow Water Spray Into Cabinet.Cause Unknown.Holes Covered W/Duct Tape & Repaired. W/900319 Ltr ML20011F4261990-02-16016 February 1990 LER 90-002-00:on 900117,hold Down Screws on Sylvania Contactors in Motor Control Ctrs Found Loose.Caused by Mfg Deficiency.Contactor Screws Tightened.All Hold Down Screws Will Be Replaced W/Another type.W/900223 Ltr ML20006D5571990-02-0707 February 1990 LER 90-001-00:on 900108,reactor Trip Occurred Due to Clogged Strainer on Feedwater Pump a Speed Controller.Caused by Water in Oil Sys.Cause for Water Presence in Sys Unknown. Sludge Minimization Attempts pursued.W/900207 Ltr ML20006A8771990-01-21021 January 1990 LER 89-028-00:on 891204,self-initiated Technical Audit Team Personnel Identified Gap Around Control Room Ventilation Air Handling Unit Access Door.Caused by Possible Const/ Installation Deficiency.Door Sys modified.W/900122 Ltr ML19327C2581989-11-13013 November 1989 LER 89-031-00:on 891012,ac Power Supply Fuse Blew Resulting in Automatic Isolation of Four Outside Air Intakes on Ventilation Sys.Caused by Inappropriate Action.Intake Valves Returned to Svc & Tech Spec 3.3.3.1 exited.W/891113 Ltr ML19324C2031989-11-10010 November 1989 LER 89-024-00:on 890908,MSIV Stroke Timing Periodic Test Performed W/O Air Assistance & Three MSIVs Failed to Close within 5 S.Caused by Brass Guide Screws Excessively Tightened.Set Screws Properly set.W/891106 Ltr ML19324C2011989-10-31031 October 1989 LER 88-019-02:on 880719,damper Compartment Flows Did Not Meet Flow Requirements Due to Closure of Some Sys Dampers. Caused by Defective procedure.As-found Measurements Taken While Operating Fans for Damper positions.W/891030 Ltr ML19327B5611989-10-26026 October 1989 LER 89-030-00:on 890714,visual Insp Revealed 3/4 Inch Open Conduit Connection Which Would Have Prevented Successful Leak Test.Cause Unknown.Connection Removed & Hole Sealed. W/891026 Ltr ML19327B4771989-10-23023 October 1989 LER 89-029-00:on 890922,ESF Actuation Occurred When Diesel Generator 1A Started Due to Momentary Undervoltage Condition on Train a 4,160-volt Essential Switchgear.Cause Unknown. Offsite Power Source Returned to Normal svc.W/891023 Ltr ML19327B1511989-10-19019 October 1989 LER 89-026-00:on 890720,both Trains of Control Area Ventilation Sys Inoperable.Caused by Design Deficiency Because of Unanticipated Interaction of Components.Original Check Damper Reinstalled in Fan on Train B.W/891019 Ltr ML19351A4301989-10-18018 October 1989 LER 89-025-00:on 890918,jumper Came Loose & Inadvertently Made Contact W/Sliding Link B-14 Directly Above Link B-15, Resulting in Turbine Driven Feedwater Pump Automatically Starting.Caused by Inappropriate action.W/891018 Ltr ML19325D4991989-10-16016 October 1989 LER 89-027-00:on 890915,preheaters Did Not Start Because Air Flow Permissive Was Not Made & Cross Connect Dampers Were Closed & Tagged & Ventilation Sys Train a Remained Logged Inoperable.Caused by Design deficiency.W/891016 Ltr ML19325C4871989-09-28028 September 1989 LER 89-018-00:on 890829,both Trains of Control Area Ventilation (VC) & Chilled Water (Yc) Sys Declared Inoperable.Caused by Equipment/Failure Malfunction. Refrigerant Added to Vc/Yc chiller.W/890928 Ltr ML20043D7041989-09-25025 September 1989 LER 89-022-01:on 890826,reactor Trip Occurred Due to Failed Universal Board in Solid State Protection Sys Cabinet A. Caused by Equipment/Malfunction.Universal Board Replaced. W/900530 Ltr ML19325C4731989-09-18018 September 1989 LER 89-015-00:on 890722,discovered That Neutral Pressure Was Best That Could Be Achieved in Some Required Sys Configurations.Caused by Design Deficiency Due to Design Oversight.Outside Air Ref Point installed.W/891004 Ltr ML20024F2791983-08-29029 August 1983 LER 83-066/03L-0:on 830817,invalid Alarm Received for Fire Detection Zone Efa 90 Which Would Not Clear.Caused by Unusual Svc Conditions.Detector Cleaned & replaced.W/830829 Ltr ML20024D8101983-07-29029 July 1983 LER 83-050/03L-0:on 830629,control Area Ventilation Sys Train B Declared Inoperable.Caused by Automatic Reset Preheater Overtemp Cutout Switch Failure.Replacement Switch Will Be installed.W/830729 Ltr ML20024D7531983-07-27027 July 1983 LER 83-048/03L-0:on 830624,control Area Ventilation Sys Train B Declared Inoperable Following Low Refrigerant Temp Alarm Trip of Control Room Chiller B.Caused by Cleaning of Condenser tubes.W/830727 Ltr ML20024D7701983-07-27027 July 1983 LER 83-049/03L-0:on 830624,surveillance Compliance Review Revealed Three Time Response Tests Not Performed.Cause Not Stated.Remaining Channels Will Be Tested During Next refueling.W/830727 Ltr ML20024D8951983-07-27027 July 1983 LER 83-047/03L-0:on 830627,discovered That 18-month Insp of Fire Hose Station 180 Not Performed During Nov 1981.Caused by Order Preventing Personnel from Entering Area Due to High Radiation Levels.Procedural Change instituted.W/830727 Ltr ML20024C4091983-06-28028 June 1983 Updated LER 83-002/03X-1:on 830110,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable.Heat Damage Found at Heat Dissipating Resistor Connections.Caused by Design Defect in Contactor Coil circuit.W/830628 Ltr ML20024C3941983-06-28028 June 1983 LER 83-035/03L-0:on 830515,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable Per Tech Spec 3.4.3.Caused by Blown Fuse in Heater Contactor Control Circuit.Fuse replaced.W/830628 Ltr ML20024C0001983-06-27027 June 1983 LER 83-030/01T-0:on 830526,discovered Monthly Test of Containment Pressure Control Sys Failed to Satisfy Surveillance Requirements to Check Permissive/Termination Setpoint Accuracy.Alarm Modules recalibr.W/830627 Ltr ML20023C4691983-05-0505 May 1983 LER 83-017/03L-0:on 830405,during Draining of Refueling Cavity RHR (Nd) Pumps Began to Cavitate & Eventually Both Nd Pumps Stopped.Caused by Level Gauge Isolation.Cavity Refilled.Nd Sys Vented.Procedures Revised ML20028E0131983-01-10010 January 1983 LER 82-081/03L-0:on 821211,lower Personnel Airlock Declared Inoperable After Reactor Door Found Partially Closed W/Small Seal Ruptured & Large Seal Inflated.Cause Not Known.Seal Not Designed to Withstand Unrestrained Inflationary Forces ML20028A5301982-11-10010 November 1982 LER 82-073/03L-0:on 820403,during QA Audit of Test Procedures,Incore & Nuclear Instrumentation Sys Correlation Monthly Check Found Not Performed.Caused by Incorrect Test Schedule ML20027D3351982-10-22022 October 1982 LER 82-071/03L-0:on 820922,motor Control Ctr Lemxd Lost Power Causing Temporary Inoperability of Several Essential Sys/Components.Caused by Automatic Trip of Feeder Breaker. Breaker Reset & Closed.Power Restored ML20027B5051982-09-10010 September 1982 LER 82-067/03L-0:on 820813,two Auxiliary Feedwater Pump Turbine Low Suction Pressure Switches Failed to Perform During Functional Test.Caused by Switches Being Out of Calibr,Possibly Due to Instrument Drift or Misadjustment ML20027B5521982-09-0808 September 1982 LER 82-064/03L-0:on 820809,vent Flow Monitor Indicated Zero W/Vent in Operation During Process of Returning to Mode 1. Caused by Out of Calibr Differential Pressure Transmitter Due to Instrument Drift.Transmitter Recalibr ML20052H5831982-05-10010 May 1982 LER 82-027/03L-0:on 820326,one Channel of Position Indication for RCS Power Operated Relief Valves NC-32 & NC-36 Declared Inoperable When Closed Indicator Lights Failed.Caused by Loose Fitting Bulb Due to Crack in Socket ML20052G6791982-05-0707 May 1982 LER 82-030/01T-0:on 820423,diesel Generator 1A Declared Inoperable After Failing to Start for Periodic Test.Caused by Failure of Station Design Change Implementation Program to Control Work on Station Mods ML20052H7421982-05-0707 May 1982 LER 82-031/03L-0:on 820408,boric Acid Transfer Pump a Failed to Perform at Capacity & Declared Inoperable.Caused by Reverse Rotation Due to Improperly Connected Windings. Personnel Counseled & Maint Routine Modified ML20052H7481982-05-0606 May 1982 LER 82-029/03L-0:on 820402,investigation of Power Operated Relief Valve (PORV) & Pressurizer Code Safety Discharge Line High Temp Alarms Revealed Indications of Leakage for PORV NC-34.Cause Undetermined.Valve Will Be Repaired ML20052H6091982-04-30030 April 1982 LER 82-028/03L-0:on 820401,during Mode 1 Operation,Radiation Monitors EMF-31 & EMF-33 Lost Power.Caused by Monitor EMF-46 Tripping Circuit Breaker Due to Direct Short Across Power bulb.EMF-46 Isolated & EMF-31 & 33 Returned to Svc ML20052G3611982-04-29029 April 1982 LER 82-025/03L-0:on 820318,vol Control Tank Makeup Frequency Increased & Containment Floor & Equipment Sump 1A Level Increased During RCS Leak Test.Caused by Failure to Verify Isolation Valves Closed Due to Procedural Deficiency 1994-10-05
[Table view] Category:RO)
MONTHYEARML20024J3211994-10-0505 October 1994 LER 94-006-00:on 940909,failure to Perform Slave Relay Test Associated W/One Containment Isolation Valve Due to Improper Work Practices.Reviewed All Slave Relay Test Procedures & Trained All Qualified reviewers.W/941005 Ltr ML20046B5251993-08-0404 August 1993 LER 93-007-00:on 930705,TS Required Surveillance Was Not Performed Because of Inappropriate Action Because of Lack of Attention to Detail.Generated WO 93047633 to Perform Required Surveillance on Unit 1 IPE CA 9010.W/930729 Ltr ML20045H9821993-07-12012 July 1993 LER 93-005-00:on 930612,manual Rt in Unit 1 Occurred Due to Equipment Failure Due to Failure of L-13 Field Cable Between Data Cabinet B & Bulkhead for Undetermined Reasons.Replaced Field cable.W/930709 Ltr ML20045D9681993-06-25025 June 1993 LER 93-006-00:on 930526,discovered That Sample Blower for Radiation Monitor 1 EMF-43B Off & Monitor Declared Inoperable & Ventilation Sys Air Intakes Not Isolated.Caused by Deficient Procedures.Test Procedures Revised ML20045B2811993-06-11011 June 1993 LER 93-004-00:on 930513,both Trains of CR Ventilation Sys Declared Inoperable Due to Equipment Failure.Exact Cause of Failure Could Not Be Determined.Train B Nuclear Svc Water Sys Flow Balance completed.W/930611 Ltr ML20029C2091991-03-21021 March 1991 LER 91-003-00:on 910219,both Trains of Control Room Ventilation Sys Inoperable.Caused by Design Malfunction & Management Deficiency.Temporary Modifications,Removing Automatic Closure Function implemented.W/910321 Ltr ML20028G9561990-09-26026 September 1990 LER 90-025-00:on 900827,Unit 1 Shut Down Because of Unidentified RCS Leakage Exceeding Tech Spec Limits.Caused by Equipment Failure.Procedure AP/1/A/5500/10 Implemented. Valve 1NC-33 Will Be Repacked at Next outage.W/900926 Ltr ML20044A0091990-06-25025 June 1990 LER 90-015-00:on 900524,Tech Spec 3.0.3 Entered Because More than One Power Range Nuclear Instrumentation Channel Exceeded 5% Deviation.Caused by Mgt Deficiency.Boric Acid Added to Coolant sys.W/900625 Ltr ML20043H4991990-06-21021 June 1990 LER 90-012-00:on 900522,loose Matl,Consisting of Masslin Cloths & Stepoff Pad,Discovered in Upper Containment.Caused by Failure to Follow Procedures.Loose Items Removed & Cleanliness Procedures revised.W/900621 Ltr ML20043H2641990-06-20020 June 1990 LER 90-011-00:on 900521,noted That Valve 1RN-69A Auxiliary Feedwater Assured Supply from Train a Nuclear Svc Water Repositioned to Open Position After Start of Pump.Cause Unknown.Pump Shut Down & Valve closed.W/900620 Ltr ML20043F7471990-06-13013 June 1990 LER 90-010-00:on 900427,discovered That Annulus Ventilation & Control Room Ventilation Sys Headers Would Not Operate,As Designed,Under Postulated Operating Conditions. Caused by Design Deficiency.Change submitted.W/900613 Ltr ML20043F5071990-06-11011 June 1990 LER 90-009-00:on 900512,feedwater Isolation Occurred as Result of Steam Generator 1B Reaching hi-hi Level Setpoint of 82% Level.Caused by Inappropriate Action Because of Lack of Attention to Detail.Feedwater Logic reset.W/900611 Ltr ML20043D6541990-05-30030 May 1990 LER 90-007-00:on 881018,during Insp Ice Condenser Basket Found W/Bottom Screws Missing.Caused by Installation Deficiency Because of Improper Matl Selection.Work Request Initiated to Replace Improper screws.W/900530 Ltr ML20043D7121990-05-30030 May 1990 LER 90-006-00:on 900226,discovered Abnormal Degradation on Steel Containment Vessel.Corrosion Caused by Design Deficiency Caused by Unanticipated Environ Interaction. Detailed Insps conducted.W/900529 Ltr ML20043C8041990-05-30030 May 1990 LER 90-008-00:on 900430,radiation Monitor for Contaminated Parts Warehouse Ventilation & Sampler Min Flow Device Declared Inoperable.Caused by Personnel Error.Appropriate Procedures Enhanced to Prevent recurrence.W/900530 Ltr ML20012D1651990-03-19019 March 1990 LER 90-004-00:on 900208,determined That Holes Left in Auxiliary Shutdown Panel Could Allow Water Spray Into Cabinet.Cause Unknown.Holes Covered W/Duct Tape & Repaired. W/900319 Ltr ML20011F4261990-02-16016 February 1990 LER 90-002-00:on 900117,hold Down Screws on Sylvania Contactors in Motor Control Ctrs Found Loose.Caused by Mfg Deficiency.Contactor Screws Tightened.All Hold Down Screws Will Be Replaced W/Another type.W/900223 Ltr ML20006D5571990-02-0707 February 1990 LER 90-001-00:on 900108,reactor Trip Occurred Due to Clogged Strainer on Feedwater Pump a Speed Controller.Caused by Water in Oil Sys.Cause for Water Presence in Sys Unknown. Sludge Minimization Attempts pursued.W/900207 Ltr ML20006A8771990-01-21021 January 1990 LER 89-028-00:on 891204,self-initiated Technical Audit Team Personnel Identified Gap Around Control Room Ventilation Air Handling Unit Access Door.Caused by Possible Const/ Installation Deficiency.Door Sys modified.W/900122 Ltr ML19327C2581989-11-13013 November 1989 LER 89-031-00:on 891012,ac Power Supply Fuse Blew Resulting in Automatic Isolation of Four Outside Air Intakes on Ventilation Sys.Caused by Inappropriate Action.Intake Valves Returned to Svc & Tech Spec 3.3.3.1 exited.W/891113 Ltr ML19324C2031989-11-10010 November 1989 LER 89-024-00:on 890908,MSIV Stroke Timing Periodic Test Performed W/O Air Assistance & Three MSIVs Failed to Close within 5 S.Caused by Brass Guide Screws Excessively Tightened.Set Screws Properly set.W/891106 Ltr ML19324C2011989-10-31031 October 1989 LER 88-019-02:on 880719,damper Compartment Flows Did Not Meet Flow Requirements Due to Closure of Some Sys Dampers. Caused by Defective procedure.As-found Measurements Taken While Operating Fans for Damper positions.W/891030 Ltr ML19327B5611989-10-26026 October 1989 LER 89-030-00:on 890714,visual Insp Revealed 3/4 Inch Open Conduit Connection Which Would Have Prevented Successful Leak Test.Cause Unknown.Connection Removed & Hole Sealed. W/891026 Ltr ML19327B4771989-10-23023 October 1989 LER 89-029-00:on 890922,ESF Actuation Occurred When Diesel Generator 1A Started Due to Momentary Undervoltage Condition on Train a 4,160-volt Essential Switchgear.Cause Unknown. Offsite Power Source Returned to Normal svc.W/891023 Ltr ML19327B1511989-10-19019 October 1989 LER 89-026-00:on 890720,both Trains of Control Area Ventilation Sys Inoperable.Caused by Design Deficiency Because of Unanticipated Interaction of Components.Original Check Damper Reinstalled in Fan on Train B.W/891019 Ltr ML19351A4301989-10-18018 October 1989 LER 89-025-00:on 890918,jumper Came Loose & Inadvertently Made Contact W/Sliding Link B-14 Directly Above Link B-15, Resulting in Turbine Driven Feedwater Pump Automatically Starting.Caused by Inappropriate action.W/891018 Ltr ML19325D4991989-10-16016 October 1989 LER 89-027-00:on 890915,preheaters Did Not Start Because Air Flow Permissive Was Not Made & Cross Connect Dampers Were Closed & Tagged & Ventilation Sys Train a Remained Logged Inoperable.Caused by Design deficiency.W/891016 Ltr ML19325C4871989-09-28028 September 1989 LER 89-018-00:on 890829,both Trains of Control Area Ventilation (VC) & Chilled Water (Yc) Sys Declared Inoperable.Caused by Equipment/Failure Malfunction. Refrigerant Added to Vc/Yc chiller.W/890928 Ltr ML20043D7041989-09-25025 September 1989 LER 89-022-01:on 890826,reactor Trip Occurred Due to Failed Universal Board in Solid State Protection Sys Cabinet A. Caused by Equipment/Malfunction.Universal Board Replaced. W/900530 Ltr ML19325C4731989-09-18018 September 1989 LER 89-015-00:on 890722,discovered That Neutral Pressure Was Best That Could Be Achieved in Some Required Sys Configurations.Caused by Design Deficiency Due to Design Oversight.Outside Air Ref Point installed.W/891004 Ltr ML20024F2791983-08-29029 August 1983 LER 83-066/03L-0:on 830817,invalid Alarm Received for Fire Detection Zone Efa 90 Which Would Not Clear.Caused by Unusual Svc Conditions.Detector Cleaned & replaced.W/830829 Ltr ML20024D8101983-07-29029 July 1983 LER 83-050/03L-0:on 830629,control Area Ventilation Sys Train B Declared Inoperable.Caused by Automatic Reset Preheater Overtemp Cutout Switch Failure.Replacement Switch Will Be installed.W/830729 Ltr ML20024D7531983-07-27027 July 1983 LER 83-048/03L-0:on 830624,control Area Ventilation Sys Train B Declared Inoperable Following Low Refrigerant Temp Alarm Trip of Control Room Chiller B.Caused by Cleaning of Condenser tubes.W/830727 Ltr ML20024D7701983-07-27027 July 1983 LER 83-049/03L-0:on 830624,surveillance Compliance Review Revealed Three Time Response Tests Not Performed.Cause Not Stated.Remaining Channels Will Be Tested During Next refueling.W/830727 Ltr ML20024D8951983-07-27027 July 1983 LER 83-047/03L-0:on 830627,discovered That 18-month Insp of Fire Hose Station 180 Not Performed During Nov 1981.Caused by Order Preventing Personnel from Entering Area Due to High Radiation Levels.Procedural Change instituted.W/830727 Ltr ML20024C4091983-06-28028 June 1983 Updated LER 83-002/03X-1:on 830110,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable.Heat Damage Found at Heat Dissipating Resistor Connections.Caused by Design Defect in Contactor Coil circuit.W/830628 Ltr ML20024C3941983-06-28028 June 1983 LER 83-035/03L-0:on 830515,pressurizer Heater Group 1B Failed to Energize in Manual & Declared Inoperable Per Tech Spec 3.4.3.Caused by Blown Fuse in Heater Contactor Control Circuit.Fuse replaced.W/830628 Ltr ML20024C0001983-06-27027 June 1983 LER 83-030/01T-0:on 830526,discovered Monthly Test of Containment Pressure Control Sys Failed to Satisfy Surveillance Requirements to Check Permissive/Termination Setpoint Accuracy.Alarm Modules recalibr.W/830627 Ltr ML20023C4691983-05-0505 May 1983 LER 83-017/03L-0:on 830405,during Draining of Refueling Cavity RHR (Nd) Pumps Began to Cavitate & Eventually Both Nd Pumps Stopped.Caused by Level Gauge Isolation.Cavity Refilled.Nd Sys Vented.Procedures Revised ML20028E0131983-01-10010 January 1983 LER 82-081/03L-0:on 821211,lower Personnel Airlock Declared Inoperable After Reactor Door Found Partially Closed W/Small Seal Ruptured & Large Seal Inflated.Cause Not Known.Seal Not Designed to Withstand Unrestrained Inflationary Forces ML20028A5301982-11-10010 November 1982 LER 82-073/03L-0:on 820403,during QA Audit of Test Procedures,Incore & Nuclear Instrumentation Sys Correlation Monthly Check Found Not Performed.Caused by Incorrect Test Schedule ML20027D3351982-10-22022 October 1982 LER 82-071/03L-0:on 820922,motor Control Ctr Lemxd Lost Power Causing Temporary Inoperability of Several Essential Sys/Components.Caused by Automatic Trip of Feeder Breaker. Breaker Reset & Closed.Power Restored ML20027B5051982-09-10010 September 1982 LER 82-067/03L-0:on 820813,two Auxiliary Feedwater Pump Turbine Low Suction Pressure Switches Failed to Perform During Functional Test.Caused by Switches Being Out of Calibr,Possibly Due to Instrument Drift or Misadjustment ML20027B5521982-09-0808 September 1982 LER 82-064/03L-0:on 820809,vent Flow Monitor Indicated Zero W/Vent in Operation During Process of Returning to Mode 1. Caused by Out of Calibr Differential Pressure Transmitter Due to Instrument Drift.Transmitter Recalibr ML20052H5831982-05-10010 May 1982 LER 82-027/03L-0:on 820326,one Channel of Position Indication for RCS Power Operated Relief Valves NC-32 & NC-36 Declared Inoperable When Closed Indicator Lights Failed.Caused by Loose Fitting Bulb Due to Crack in Socket ML20052G6791982-05-0707 May 1982 LER 82-030/01T-0:on 820423,diesel Generator 1A Declared Inoperable After Failing to Start for Periodic Test.Caused by Failure of Station Design Change Implementation Program to Control Work on Station Mods ML20052H7421982-05-0707 May 1982 LER 82-031/03L-0:on 820408,boric Acid Transfer Pump a Failed to Perform at Capacity & Declared Inoperable.Caused by Reverse Rotation Due to Improperly Connected Windings. Personnel Counseled & Maint Routine Modified ML20052H7481982-05-0606 May 1982 LER 82-029/03L-0:on 820402,investigation of Power Operated Relief Valve (PORV) & Pressurizer Code Safety Discharge Line High Temp Alarms Revealed Indications of Leakage for PORV NC-34.Cause Undetermined.Valve Will Be Repaired ML20052H6091982-04-30030 April 1982 LER 82-028/03L-0:on 820401,during Mode 1 Operation,Radiation Monitors EMF-31 & EMF-33 Lost Power.Caused by Monitor EMF-46 Tripping Circuit Breaker Due to Direct Short Across Power bulb.EMF-46 Isolated & EMF-31 & 33 Returned to Svc ML20052G3611982-04-29029 April 1982 LER 82-025/03L-0:on 820318,vol Control Tank Makeup Frequency Increased & Containment Floor & Equipment Sump 1A Level Increased During RCS Leak Test.Caused by Failure to Verify Isolation Valves Closed Due to Procedural Deficiency 1994-10-05
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G7951999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for McGuire Nuclear Station,Units 1 & 2 ML20217F3661999-09-22022 September 1999 Rev 18 to McGuire Unit 1 Cycle 14 Colr ML20212D1911999-09-20020 September 1999 SER Accepting Exemption from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Closed System Isolation Valves for McGuire Nuclear Station,Units 1 & 2 ML20216E8851999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20217G8101999-08-31031 August 1999 Revised Monthly Operating Repts for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20211G5261999-08-24024 August 1999 SER Accepting Approval of Second 10-year Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20210S2371999-07-31031 July 1999 Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20216E8951999-07-31031 July 1999 Revised Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209E4361999-07-0909 July 1999 SER Agreeing with Licensee General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196K6631999-07-0707 July 1999 Safety Evaluation Supporting Licensee 990520 Position Re Inoperable Snubbers ML20209H1631999-06-30030 June 1999 Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20210S2491999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for McGuire Nuclear Station,Units 1 & 2 ML20209H1731999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206T4771999-05-31031 May 1999 Rev 3 to UFSAR Chapter 15 Sys Transient Analysis Methodology ML20196L1881999-05-31031 May 1999 Non-proprietary Rev 1 to DPC-NE-3004, Mass & Energy Release & Containment Response Methodology ML20195K3691999-05-31031 May 1999 Monthly Operating Repts for May 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206N3511999-05-11011 May 1999 Safety Evaluation Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety- Related Movs ML20195K3761999-04-30030 April 1999 Revised MORs for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20206R0891999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205L2341999-04-0505 April 1999 SFP Criticality Analysis ML20206R0931999-03-31031 March 1999 Revised Monthly Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P8991999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205C4171999-03-25025 March 1999 Special Rept 99-02:on 801027,Commission Approved for publication,10CFR50.48 & 10CFR50 App R Delineating Certain Fire Protection Provisions for Nuclear Power Plants Licensed to Operate Prior to 790101.Team Draft Findings Reviewed ML20207K2051999-03-0505 March 1999 Special Rept 99-01:on 990128,DG Tripped After 2 H of Operation During Loaded Operation for Monthly Test.Caused by Several Components That Were Degraded or Had Intermittent Problems.Parts Were Replaced & Initial Run Was Performed ML20204C8911999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20205P9021999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2 ML20204C8961999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for McGuire Nuclear Station,Units 1 & 2 ML20199E0301998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for McGuire Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20198A4481998-12-11011 December 1998 Safety Evaluation Concluding That for Relief Request 97-004, Parts 1 & 2,ASME Code Exam Requirements Are Impractical. Request for Relief & Alternative Imposed,Granted ML20198D7561998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199E0491998-11-30030 November 1998 Revised Monthly Operating Rept for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20199E9651998-11-24024 November 1998 Rev 1 to ATI-98-012-T005, DPC Evaluation of McGuire Unit 1 Surveillance Weld Data Credibility ML20196D4171998-11-24024 November 1998 Special Rept 98-02:on 981112,failure to Implement Fire Watches in Rooms Containing Inoperable Fire Barrier Penetrations,Was Determined.Repair of Affected Fire Barriers in Progress ML20196G0581998-11-0606 November 1998 Rev 17 to COLR Cycle 13 for McGuire Unit 1 ML20196G0761998-11-0606 November 1998 Rev 15 to COLR Cycle 12 for McGuire Unit 2 ML20198D7771998-10-31031 October 1998 Revised Monthly Operating Rept for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E5961998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154L6251998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20195E6021998-09-30030 September 1998 Revised Monthly Operating Rept for Sept 1998 for McGuire Nuclear Station,Units 1 & 2 ML20154B4131998-09-22022 September 1998 Rev 0 to ISI Rept for McGuire Nuclear Unit 1 Twelfth Refueling Outage ML20151W3521998-09-0808 September 1998 Special Rept 98-01:on 980819,maint Could Not Be Performed on FPS Due to Isolation Boundary Leakage.Caused by Inadequate Info Provided in Fire Impairment Plan.Isolated Portion of FPS Was Returned to Svc ML20154L6321998-08-31031 August 1998 Rev 1 to MOR for Aug 1998 for McGuire Nuclear Station,Unit 1 ML20153B3741998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236U1601998-07-31031 July 1998 Non-proprietary DPC-NE-2009, DPC W Fuel Transition Rept ML20237B2381998-07-31031 July 1998 Monthly Operating Repts for July 1998 for McGuire Nuclear Station,Units 1 & 2 ML20153B3931998-07-31031 July 1998 Revised Monthly Operating Repts for Jul 1998 for McGuire Nuclear Station,Units 1 & 2 ML20236P0451998-07-0808 July 1998 Part 21 Rept Re non-conformance & Potential Defect in Component of Nordberg Model FS1316HSC Standby Dg.Caused by Outer Spring Valves Mfg from Matl That Did Not Meet Specifications.Will Furnish Written Rept within 60 Days 1999-09-30
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Subject:
McGuire Nuclear Station Unit 2 Docket No. 50-370 Licensee Event Report 370/90-06 Gentlemen Fvrsuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 370/90-06 concerning an inadvertent Unit 2 Train B Engineered Safety Features actuation. This report is being submitted in accordance with 10 C7R 50.73(a)(2)(iv). This event is considered to be of no significance with respect to the health and safety of the public.
Very truly yours, r/q a.mM T.L. McConnell e
DVE/ADJ/cb1 Attachment xc: Mr. S.D. Ebneter American Nuclear Insurers Administrator, Region II c/o Dottie Sherman, ANI Library +
U.S. Nuclear Regulatory Commission The Exchange, Suit 245 101 Marietta St., NW, Suite 2900 270 Farmington Avenue Atlanta, GA 30323 ~ Farmington, CT 06032 INPO Records Center Mr. Darl Hood Suite 1500 U.S. Nuclear Regulatory Commission 1100 Circle 75 Parkway Office of Nuclear Reactor Regulation Atlanta, GA 30339 Washington, D.C. 20555 M&M Nuclear Consultants Mr. P.K. Van Doorn 1221 Avenue of the Americas NRC Resident Inspector ;
New York, NY 10020 McGuire Nuclear Station g
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*LER 370/90-06 Page 2-f + June 18, 1990 bxc B.W. Bline L.G. Bost J.S. Warren R.L. Gill C.L. Hartzell (CNS)
R.S. Matheson (ONS)
P.R. Herran S.S. Kilborn (W)
, R.E. Loper-Ibanez M.A. Mullen R.O. Sharpe (MNS)
G.B. Swindlehurst K.D. Thomas M.S. Tuckman L.E. Weaver R.L.~ Weber J.D. Wylie (PSD)
J.W. Willis QA Tech. Services NRC Coordinator (EC 12/55)
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"' An Inadvertent Unit 2 Train B Engineered Safety Features Actuation Occurred Because Of A Shorted Limht Soeket On The Dienel Generator Load Senneneer Panel IVSNT DAtt een Lim esubstta les RIP 0af Daf t 17e OtMth D ActLiitts INv0Lygp 401 MON T .e Day vtam vl A81 ,D, gNn" 6
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1 On May 17, 1990, at 2321, there was an inadvertent Engineered Safety Features (ESF) l l actuation from the Unit 2 Train B Diesel Generator Load Sequencer. The Unit 2 )
l Train B Motor Driven Auxiliary Feedwater (CA) pump automatically started and l injected water into Steam Generators C and D. Operations personnel immediately
! placed the 2B CA pump in recirculation and wrote an emergency work request for ;
Instrument and Electrical (IAE) personnel to investigate the reason for the 2B CA .
pump automatically starting. IAE personnel determined the cause to be a shorted l light socket in the Diesel Generator Sequencer ; test circuit. No other components l re-aligned due to the sequencer relays closing because of other interlocks on the l associated components or because the components were already energized. Train B 1 components were in service during this event. Unit 2 was in Mode 1 (Power l Operation) at 100 percent power when this event occurred. This event is assigned a l cause of Equipment Failure because the light socket, rated at a nominal 125 VDC, i developed a short. The measured voltage for Train B Bus is 131 VDC. IAE personnel replaced the light socket with an acceptable replacement. A modification is scheduled to replace all light sockets in DC circuits of this nature during the ,
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Background
The Diesel Generator [EIIS DG) Load Sequencing System [C1!S:EK] functioris to energize the necessary Blackout or Loss of Coolant Accideni (LOCA) loads in a prescribed sequence, and in such a manner that the Diesel Generator or auxiliary trensformer [EIIS:XFMR] is not momentarily overloaded. The sequencer is maintained in a standby condition at all times during plant operation and can be actuated by ,
either a LOCA signal from the Solid State Protection System (SSPS) [EIIS:JC] or a 2 !
out of 3 phase Undervoltage signal sensed on the 4.16 KV essential bus (EIIS:EB).
Depending on the accident conditions present (LOCA, Blackout, etc.), the sequencer will operate to energize the loads required for these conditions. The automatic loading is accomplished by timer (EIIS:TMR] relays (EIIS:RLY) through either a committed sequence or an accelerated sequence mode. The time settings on these relays must be properly set to ensi-e the loads will be energized when they are -
needed. Various types of alarms 'T. IS: ALM] are provided to depict system status. l Status indicating lights [EIIS:IL] located on the sequencer panel [EIIStPL] have been provided for testing purposes. Their status during normal sequencer standby ;
conditions or during sequencer actuated conditions have little significance.
The Committed Sequencer timer relay circuit consists of an arrangement of 10 timer relays (see drawing on page 7 of 7). The Committed Sequence Sub Test indicating light indicates that the committed sequence test is enabled and monitors re-closure of test contacts.
On October 31, 1986, Design Engineering personnel completed Design Study MGDS-0084; task 3114B, Cutler-Hammer E29 Indicating Light Units. This Design Study documented that there was a history of light unit failures caused by deteriorated internal composition resistors. As reported in this Design Study, the findings of inspections completed on August 15, 1986 at McGuire Nuclear Station were as follows:
Unit I had Cutler-Hammer E29NM Indicating Light Units. These light units are designed for 125 VDC applications. The 125 Voltage DC system [EIIS:EJ]
normally operates between 132 to 136 VDC measured. There was definite evidence of overheating on the light units.
Unit 2 had Cutler-Hammer E29NY1 Indicating Light U-its. There were no visual signs of deterioration; however, a visual inspectr on would not exclude the possibility of an internal resistance problem exi sting.
Also, this Design Study reviewed all indicator light uait applications at McGuire that use Cutler-Hammer E29NM, E29NM1, and E29NY1 indicator lights.
All of the E29 indicating light units in the Units 1 aid 2 Diesel Generator Load Sequencers are in DC circuits with the exception of a lew devices which are in AC circuits.
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The indicating light used for the Committed Sequence Sub Test light was an E29NY1 rated at 120 VAC/132 VDC with two internal resistors (1200 ohms, I watt and 1800 ohms, 2 watt), and a slide base bulb socket.
As a result of the Design Study, Design Engineering personnel recoc: mended that all Cutler-Hammer type NM, NM1, and NY1 indicating light units should be replaced with Cutler-Hammer E29NY11 units, which are designed to operate at 135 VDC, utilize a bayonet base bulb socket, and fit the existing control panel cut-outs.
Nuclear Station Modifications (NSMs) MG-12139 and MG-22139 were approved by McGuire Projects personnel for Design to begin on May 25, 1988. The purpose of these modifications are to replace all Cutler-Hammer E29 type NM, NM1, and NY1 indicating ,
light units used in Quality Assurance (QA) and non-QA condition DC circuits at McGuire with E29NY11 indicating light units. This is to eliminate the overheating problem of NM and NMI indicating light units which can fail and short with time, causing a unit trip. Also, the purpose is to eliminate the possibility of I electrical shorting of NY1 indicating light units if not properly installed. If ,
the E29NY11 light unit fails due to overheating the result would be the bulb burning out which will leave the circuit open and not closed as in the case of the j shorted light sockets.
i Description of Event On May 17, 1990 at 2321, Operations Control Room (EIIS:NA) personnel received a signal that the 2B CA [EIIS:BA) pump [EIIS:P] automatically started. The 2B CA pump was injecting water into Steam Generators [EIIS:SG) C and D. At 2323, Operations personnel isolated the 2B CA pump flow from Steam Generators C and D.
Operations personnel placed the 2B CA pump in recirculat an flow at 2324.
At 2330, on May 17, 1990, Operations personnel wrote emergency work request 141179 for IAE personnel to investigate and repair the reason that the 2B CA pump automatically started. At approximately 2330, Operations Control Room personnel reviewed the Events Recorder (EIIS:IQ] printout. This identified that the 2B Diesel Generator Sequence load groups had energized. An Operations person was then dispatched to the Diesel Generator Load Sequencer 2B panel and reported to IAE personnel that something smelled as if it was melted inside the panel.
On May 18, 1990, IAE personnel determined that the Committed Sequence Sub Test Indicating light located in the Diesel Generator Load Sequencer panel had shorted.
When the light socket shorted, a voltage drop occurred across the committed sequence timer relays causing the relays to energize. One of the relays signalled the 2B CA pump to auto start. Other components that would have started due to the load sequencer relays closing were already energized since Train B was in service.
Other components that also received a signal from the load sequencer, did not receive an auto start signal because of interlocks with other protection systems (i.e. SSPS) not being satisfied. IAE personnel lifted the lead from the light socket which allowed Operations to re-align the relays in the load sequencer panel back to standby. At 0242 on May 18, 1990, Operations personnel reset the 2B Diesel Generator Load Sequencer and at 0244, Operations personnel turned the 2B CA pump off.
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! On May 18, 1990 at 0252, the NRC was notified of this event as directed by RP/0/A/5700/10, NRC Immediate Notification Requirements.
At 0530, IAE personnel replaced the light socket with an E29NM1 Cutler-Hammer indicating light unit and replaced the lifted lead. Also, IAE personnel wrote work request 600132 to replace three other indicating lights in the Diesel Generator Load Sequencer Panel that lookea charred and were suspect to potential failure. '
Conclusion This ESF Actuation [EIIS:JE] event is assigned a cause of Equipment Failure because the Diesel Generator Load Sequencer Panel Committed Sequence Sub Test Indicating Light Unit failed by shorting. When this indicating light shorted, the timer relays re-aligned and started the timer sequence to load components from Train B.
All components were either already energized or had other interlocks that prevented them from starting except for the 2B CA pump. Therefore, the 2B CA pump auto started.
The type of indicating light that was installed in the Committed Sequence Sub Test Circuit and that failed causing the 2B CA pump to auto start was a Cutler-Hammer E29NY1. IAE personnel replaced the E29NY1 light with an E29NM1 l!ght.
Cutler-Hammer E29 type NM, NM1, and NY1 indicating light units currently installed in McGuire Unit 1 and 2 DC circuits have experienced failures due to overheating.
The E29NY1 and E29NM units have a slide base bulb socket which is subject to electrical shorting if its installed incorrectly. Failures of these Cutler-Hammer E29 light units have resulted in unit trips.
As documented in the Design Study MGDS-0084/00, information based on tests conducted by Transmission Department personnel in 1977 and past experience with Cutler-Hammer indicating light units with internal composition resistors showed i that the resistance values for these light units decrease with time due to heat.
The decrease in resistance is permanent. The composition resistors are made of carbon. Carbon has a negative temperature coefficient of resistance (= -0.0005).
The resistance value will drop with an increase in temperature. As the resistance value decreases, current will increase and cause the temperature in the light unit to rise. With time, the light unit can fail and short due to heat dissipation.
1 NSMs MG-12139 and MG-22139 were Design complete on August 7, 1989 ano January 19, ;
1990 respectively. Both NSMs include replacement of all the indicating lights for both trains of the Diesel Generator Load Sequencer Panels to Cutler-Hammer E29NY11 indicating light units. These modifications are not field complete, but are i scheduled to be complete before the end of the next respective refueling outages.
The use of E29NY1 and E29NM light units had already been prohibited at the station prior to this event and based on the acceptable substitutes list the E29NM are ,
replaced by E29NM1 and E29NY1 are replaced by E29NY11. The Bill of Materiale j required the Committed Sequence Sub Test indicating light to be an E29NM light unit; therefore, the replacement was required to be an E29NM1 light unit which will be replaced when the NSMs MG-12139 and MG-22139 are implemented.
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Ol0 l5 0F p rext m, a . w m== =ac w aser.nm The failed E29NY1 light unit had a manufactured date of May, 1979. This light may have shorted due to length of service which probably caused the breakdown in resistance.
There is not a preventative maintenance (PM) program for replacing these light units. These NSMs will provide a permanent solution for DC circuit light units and the E29NY11 light units will not require a PM program.
A review of the Operating Experience Program data base for the past twenty four months prior to this event revealed 2 events involving ESF actuations with a cause of Equipment Failure. Licensee Event Report (LER) 369/88-21 documented an auto start on the Turbine [EIIS:TRB] Driven CA pump caused by a blown fuse [EIIS:FU).
LER 370/88-07 documented a Feedwater System [EIIS:SJ) isolation caused by a failed signal comparator card. The corrective actions for these LERs were specific to each event. These events involved failures on different components. Therefore, this event is considered not recurring.
The problem of failures on Cutler-Hammer E29NY1 indicating light units is a recognized recurring problem. There have been several failures in the past where
) breakers have opened due to a short in these indicating lights. Recognition of this problem was what initiated the Design Study MGDS-0084/00.
This event is Nuclear Plant Reliability Data System (NPRDS) reportable. Industry reported to NPRDS four light socket failures during replacement of the 'ight units and four light socket failures due to unknown causes. These light sockets were not identified by manufacturer but all failures were listed as light unito shorting.
Only three of the failures were on the Duke Power System and only one at McGuire.
The McGuire failure was on a Load Control Breaker [EIIS:ED) and: caused the Breaker '
Trip Circuit [EIIS:72] to remain energized. The Industry search did not reveal any similar events on Diesel Generator Load sequencers occurring.
There were no personnel injuries, radiation overexposures, or unconirolled releases of radioactive material as a result of this incident.
CORRECTIVE ACTIONS: ;
Immediate: 1) After pushing the CA Modulating Valve Reset button, Operations Control Room personnel manually closed the 2B CA pump discharge valves to the Steam Generators C and D and thereby placed the pump in a recirculation mode. -
Subsequent: 1) Operations reset the Diesel Generator Load Sequencer and returned the 2B CA pump to off. 1
- 2) IAE personnel replaced the failed indicating light E29NY1 on the Diesel Generator Load Sequencer Panel for the Committed Sequence Sub Test light unit documented on work request 141179.
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- 3) IAE personnel wrote work request 600132 to replace three other indicating lights in the Diesel Generator Load Sequencer Panel that looked charred and were suspect to potential failure.
i Planned: 1) Unit 2 NSM MG-22139 will replace all Unit 2 Cutler-Hammer E29 type NM, NM1, and NY1 indicating light units used in QA and non-QA condition DC circuits at McGuire with E29NY11 indicating light units. This includes the Diesel Generator Load Sequencer Panel indicating 11ghts.
- 2) Unit 1 NSM MG-12139 will replace all Unit 1 Cutler-Hammer E29 type NM, NM1, and NY1 indicating light units used in QA and non-QA condition DC circuits at McGuire with E29NY11 indicating light units. This includes the Diesel Generator Load Sequencer Panel indicating lights.
SAFETY ANALYSIS:
Unit 2 was in Mode 1 at 100 percent power with all Train B components in service at the time of the ESF actuation. During this event, the 2B CA Pump did auto-start,
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as designed, upon receipt of the start signal and pumped water into Steam t Generators C and D for approximately 2 minutes. During that time period, Operations personnel isolated the CA flow to Steam Generators C and D and placed the pump in recirculation mode. The 2B CA pump did operate for approximately 3 hours and 23 minutes. A small Reactor Power Mismatch was caused by the CA flow discharging into the Steam Generators; however, the Power Mismatch did not reach an alarm setpoint level of + 2 percent. Steam Generator water levels did not change during this event. The inadvertent actuation of the 2B CA pump did not adversely >
affect any of the Unit 2 equipment or systems.
;This event did not affect the health and safety of the public. ,
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