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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
[Table view] |
Text
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, bake her Conpany 000MM J: ,
, McGuirr Nuclear Station ,*
12700 Hagers krry Road -
Huntersville, AC280iH985 DUKE POWER t
February 23, 1990 i
4 U.S. Nuclear Regulatory Commission !
Document Control Desk
! Washington, D.C. 20555 :
I (r- .
h Subjecta McGuire Nuclear Station Units 1 and 2 l Docket No. 50-369 :
L: Licensee Event. Report 369/90-02 J i i.
! Gentlemen:
Pursuant.to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Evenc e Report 369/90-02 concerning loose holddown screws on Sylvania contactors in Motor =
Control Centers. This report is being submitted.as a voluntary report. This event is considered to be of no significance with respect to the health and safety of ,
the public. ,
Very truly yours, b (- DL"> '
7L j T.L. McConnell 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 ;
I- 1100 Circle 75 Parkway Office of Nuclear Reactor Regulation Atlanta, GA 30339 Washington, D.C. 20555 M&M Nuclear Consultants Mr. P.L Van Doorn 1221 Avenue of the Americas NRC Resident Inspector ,
New York, NY 10020 McGuire Nuclear Station
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! bxc: B.W. Bline ll A.S. Daughtridge J.S. Warren 7 R.L. Gill R.M. Glover (CNS)
T.D. Curtis:(ONS) i P.R. Herran
.S.S. Kilborn (W)
R.E. Lopez-Ibanez
, M.A. Mullen
[ R.O. Sharpe (MNS) ;
G.B. Swindlehurst (
l- K.D. Thomas !
M.S. Tuckman o L.E. Weaver '
f R.L. Weber J.D. Wylie (PSD)-
3 J.W. Willis
-QA Tech. Services NRC Coordinator (EC 12/55)
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McGuire Nuclear Station, Unit 1 o is to ro lol3 i6 l 9 t lor l 0l6 l Hold Down Screws On Sylvania Contactors In Motor Control Centers Were Found Loose Because Of A Manufacturina Deficienev ivtant Dart (81 Ltn asuaabtR lei htP0mt Dart (t) OTMth 8 ACILiteit INv0LytD (4) 88$yi$
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On January 17, 1990, McGuire Nuclear Station (MNS) personnel were notified by Catawba Nuclear Station (CNS) personnel of a problem identified at CNS with hold down screws on Sylvania (Clark) Contactor types TM 00, TM 1, and TM 2 becoming loose. This problem could potentially cause improper contactor operation. Based on this information, MNS Maintenance Engineering Services, and Instrumentation and Electrical personnel initiated an inspection of the Safety Related Motor Control Centers at MNS to identify any contactors with loose hold down screws. Subsequent inspection revealed 14 contactors with loose hold down screws. However, no safety l related contactors were found to be inoperable. This incident has been assigned a
! cause of Manufacturing Deficiency because of poor material selection. Unit I was l in Mode 5 (Cold Shutdown) and Unit 2 was in Mode 1 (Power Operation) at 100% power l
at the time this incident was discovered. All contactor screws found loose were tightened according to manufacturer recommendations after inspection. All hold down screws will be replaced with another type to prevent recurrence of this problem. This report is being submitted as a voluntary LER.
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UCENSEE EVENT REPORT (LER) TEXT CONTINUATION amovio oue wo mo-oio. !
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EVALUATION:
Background
-The 600 volt Essential Motor Control Center (EPE) system [EIIS:ED) is made up of two completely redundant and independent networks, designated Tre.in A and Train B.
Train A and Trais B feed identical loads that perform the same #. unction. Either :
the Train A or Train B EPE system can power all of the necessary essential loads.
The Motor Control Centers (MCCs) are made up of breaker compartments containing combination full voltage reversing and non-reversing starters, combination full volt ge non-reversing contactors (EIIS:CNTR), and feeder breakers [EIIS:52] which feed the various loads, The combination full voltage non-reversing contactor is a remote control magnetic switching device used to energize electrical equipment. The contacts are mounted on a moveable carrier held in place by two hold down screws. Spring tension holds the contacts in the open position until a remote signal energizes a magnetic coil to close them and therefore, energize the equipment.
Description of Event On January 4, 1990, CNS personnel discovered a problem with Sylvania (Clark)
Contactor hold down screws becoming loose. This problem was addressed by CNS Problem Investigation Report (PIR) number 0-C90-0008. -
6.
On January 17, 1990, MNS personnel were notified of the problem and the possibility for improper operation of similar contactors at MNS. Based on this information,
- Maintenance Engineering Services (MES) personnel initiated work requests 69765, 69766, 69767, and 69768 to perform a visual inspection of the two contactor hold down screws on Sylvania (Clark) MCC Contactor types TM 00, TM 1, and TM 2 to ensure that they were tight. This inspection was to be performed on all safety related
! contactors of this type at MNS.
At 1430 on January 17, 1990, Instrumentation and Electrical (IAE) personnel discovered one of the contactor hold down screws on cubical R02F at MCC 2EMXF to be backed out approximately one inch and the other screw to be loose. The loose screws were on a normally open contactor which controls valve [EIIS:V] 2RN-174B, Diesel Generator [EIIS:DG) 20 Meat Exchanger (EIIS:HX] Control. Emergency Work Request 69764 was generated to repair the problem with the contactor.
l MES personnel also initiated PIR 0-M90-0024 to resolve the problem of loose I
contactor hold down screws.
IAE personnel tested the operation of the contactor in question by first taking resistance readings across the contacts and then having Operations personnel close the breaker and cycle the valve. No problems were noted. IAE personnel then torqued the hold down screws per manufacturer recommendation. Again, IAE personnel took resistance readings and had the valve cycled. No differences were noted.
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Subsequent inspections were periormed by 1AE personnel of all safety related MCC '
compartments with Sylvania (Clark) type TM 00, TM 1, and TM 2 contactors. The following is a list of the compartments found with loose hold down screws and the corrective work request number for each. '
i MCC Inspection Corrective Cubical Work Reg. No. Work Req. No.
1 UNIT 1 Train 1A a 1EMXH-5A 69765 69774 1EMXA4-2A 69765 69776 1EMXH1-1B 69765 69777 1EMXA2-3A 69765 69775 IEMXA2-3B 69765 69775 3
Train IB .
1EMXB2-F3C 69766 69785 UNIT 2 Train 2A 2EMXE-R2D 69767 69786 2EMXE-F3D 69767 69786 Train 2B 2EMXB2-F3A 69768 69770 2EMXB2-R2C 69768 69771 2EMXB2-RIA 69768 69772 2EMXB2-F3C 69768 69769 2EMXH-R3D 69768 69773 2EMXF-R2F 69768 69764 All contactors were repaired and the inspection was completed on January 22, 1990.
Design Engineering (DE) personnel reviewed the actions taken by MES and IAE personnel and stated that they had uatisfactorily tested the contactors and proved operability prior to correcting the problem. DE personnel also performed a seismic
) operability calculation and concluded that the contactors were operable.
Project Services personnel generated McGuire Exempt Variation Notice (MEVN) 2174 to add attachments to Nelson Electric Vendor Manual, MCM-1314.01-166, to specify vendor supplied torque specifications for Sylvania (Clark) contactor hold down screws. . This facilitated repair of the loose screws.
New screws with a 1/4 inch nylon patch on the bottom threads were ordered as a replacement for all the hold down screws presently in use. These screws should prevent recurrence of the problem since the nylon patch on the bottom threads will prevent the screw from becoming loose, g$4awsena .v. .. m, i ...noo.., oev o
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Conclusion 1 l
This incident is assigned a cause of Manufacturing Deficiency because the contactor 1 hold down screws used in the original design of the Sylvania (Clark) type TM 00, TM 1, and TM 2 contactors were not adequate fasteners. Therefore, the potential exists for vibration to cause the hold down screws to back out of position over a i period of time.
l CNS personnel discovered a contactor which had both hold down screws out and, j therefore, had allowed the cor. tact carrier to fall out of position rendering the ;
contactor inoperable. No safety related contactors were found in this condition at i MNS. This is probably because MNS has a preventative maintenance program ongoing >
which should correct many of these problems. This preventative maintenance assures that all screws are tight at the time it is performed. However, the Preventative ;
Maintenance inspections, while adequate under norma'l circumstances, are performed '
at long enough intervals (5 years) to have al W d roite of the screws to loosen.
All safety related contactors inspected at HNS were found to be operable and any screws found loose were tightened and torqued based on additional information obtained from the vendor.
Prior to the discovery of the problem by CNS personnel, MNS personnel who are experienced with the contactors in question stated that on several occasions hold down screws had been found backed out at MNS. These incidents were few and l occurred over a long period of time. Therefore, the problem was not considered to be recurring and no PIR was % erated. Immediately on finding the inoperable ;
contactor at CNS, a PIk was generated at CNS and a follow-up inspection was l initiated at MNS.
As a result of this incident, work requests were written to replace all hold down screws in safety related contactors of this type with screws having a 1/4 inch j nylon patch to prevent them from backing out. Also, torque requirements were added to the Nelson Electric Vendor Manual, MCM-1314.01-166. This will ensure that all screws will be tightened properly in the future and should prevent recurrence of this problem. In addition, an inspection is in progress of all non-safety related contactors of this type to correct any discrepancies of a similar nature.
A review of the Operating Experience Program data base for the past twelve months prior to this incident revealed 3 events that were assigned a root cause of Design, Manufacturing, Construction / Installation Deficiency because of poor material design selection. These events involved material selection deficiencies by DE personnel and not by the manufacturer. Therefore, the incident is not considered to be recurring.
This incident is not Nuclear Plant Reliability Data System (NPRDS) reportable.
4 There were no personnel injuries, radiation overexposures, or uncontrolled releases of radioactive material as a result of this incident.
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Immediate: 1) IAE personnel began inspection of all safety related Sylvania (Clark) contactor types TM 00, TM 1, and TM 2. 1
- 2) MES and 1AE personnel initiated emergency werk requests to repair contactors found with loose hold down screws. >
- 3) IAE personnel tightened and torqued loose hold down screws according to manufacturer specifications.
Subsequent: 1) DE personnel performed an evaluation of the action taken by MNS :
personnel and concluded that they had performed adequate testing to ensure operability of the contactors.
+
- 2) DE personnel performed a seismic operability evaluation and '
concluded that the contactors were operable with one screw loose.
- 3) MES personnel initiated work requests to replace the present '
contactor hold down screws with screws having a 1/4 inch nylon patch to prevent recurrence of the problem.
! 4) Project Services personnel generated MEVN 2174 to add l attachm ts to Nelson Electric Vendor Manual, MCM-1314.01-166 ,
l to speci torque requirements so that repair of the loose I contactor hold down screws could be completed. ;
l '
Planned: 1) IAE personnel will replace contactor hold down screws on safety l
related contactors for Unit 1 presently in use with new ones I
incorporating a 1/4 inch nylon patch on the bottom threads.
- 2) IAE personnel will replace contactor hold down screws on safety related'contactors for Unit 2 presently in use with new ones incorporating a 1/4 inch nylon patch on the bottom threads.
- 3) MES and IAE personnel are in the process of inspecting and repairing similar non-safety related contactors for botb units.
SAFETY ANALYSIS:
The EPE system contactors in question supply voltage to feed various safety related equipment. There were no safety related contactors found during the course of this inspection to be inoperable or in any way incapable of supplying voltage to their respective devices. The worst case found was that one safety related contactor hold down screw was backed out approximately one inch and the other screw was loose. Upon evaluation and after testing, it has been proven that the operability of the contactor carriage plate does not change because one screw is missing. The reason for this is that the carriage plate is captured within a support system that l
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only allows motion in and out and not from side to side. Therefore, this incident had no.effect on the' operation of any safety related device.
This incident'did not affect the health and safety of the public. I
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