|
---|
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
.
.ll. l Duke Mn Compa y (704) 875 4 000 ofcGuire Nuclear Station l PO Bat 188 -
,. Cornelius N C 2803104SS -
DUKEPOWER l
December 8,.1989 U.S. Nuclear Regulatory Commission Document Control Desk :
Washington, D.C. 20555
Subject:
McGuire Nuclear Station Unit 2 i Docket No. 50-370 Licensee Event Report 370/89-12 Gentlemen: ;
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 370/89-12 concerning a missed Diesel Generator 2B surveillance. This report is being submitted in accordance with 10 CFR 50.73(a)(2)(i)(B). This event is considered to be of no significance with respect to the health and safety of
- the"public.
Very truly yours, 3 A 't Q
T.L. McConnell DVE/ADJ/cb1 Attachment t
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 j Suite 1500 U.S. Nuclear Regulatory Commission i
1100 circle 75 Parkway Office-of Nuclear Reactor Regulation l' 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 hhh7o MN PDC
.. t
r.
GBR Walm M4 U S 88WCLt14 4 80uk&TOIT COMMI55104 [
an.novtD ous to niwei >
LICENSEE EVENT REPORT (LER) 5"a's : si e )
DOCS tf NQM9th (2) PAGE i3' 8 ACILITY esaast sis McGuire Nuclear Station, Unit 2 o 16lololol3;7 l 0 i jopl 1;i
"' Diesel Generator Surveillance Was Missed Because Of Start Classification Problems Caused By Inadeouste Directives tVtNT Daf t att Lt A humasth top AEPORT DAf t til 07M4R 9 ACILITitt eNyotvsp ist DAv l opcitti Nuve,m si MONTH DAY vtAM vtAR $$U n ",y,*,Q MONTM i t AP. ' AC'6'T v haves N/A ol610lo:ol l l lj 1 0l 8 89 8l9 0 l 1l2 0l0 1l 2 0l8 8] 9 o,3,o,n,n, , ,
Twis atPomT is sueMirTEo Punsu&NT To tMt mLovintMENTs os i0 Con i te*.ce eae e, me o e' rae re"...a,i titt 5 30 4e2169 to 406tel to 736aHtHel 13 71 int a M 48EaaH1Hal 90 asteH1) to 73teHlHet 73.?t iel nei i i n assi.in H.ii so mi.Hsi w ts.Han..i gM8gs,,cga,Ange, 30 aatteH1Heill X to.736aH2Hij to 73saH2ilveHHal Js6Ai
.0 . n n , .0 ,3.H, u., 0 ,. H,u..n.,
30 ewiallittel 50.73 eH2iten) to 73tell211sl LIClis< CONT ACT FOm TMit Ltm titt Niyt TtttPMONE NVMSER j Amt& CODt Alan Sipe, Chairman, McGuire Safety Review Group 7, Og4 8;7; S j ,4 i 1, 8 ; 3 ,
COMPLitt ONE LINE 80m S ACM COMPONENT f AiLURE Ditchitt0 IN TMit AIPORT 113' omf "([g AC A '
CAV$l SYST!M COMPONENT g
AC a{opah CAUSE Sv$7tv COMPONENT D PR El D IG lS II l S X l919l 9 Y I t 1 i f l 1 I l l l l l l l I I I l I 1 SUPPLEMENT AL REPORT SKPECTED tien MONia DAv vtAm I SL8 mis 810N vtS (99,en temovere EMPICTRO Sy060tsstON DA Til NO l l l Auf. ACT ro-., . im . . , .,,,.. ., u . , .u. . mi.u- n ei On July 26, 1989, Diesel Generator (D/G) 2B was started for a fourteen hour run to perform a heat soak and bearing deflection readings which was required because of maintenance on the D/G. The start time was greater than the 11.0 seconds allowed for a successful start. Operations (OPS) personnel classified the start as an Invalid Test, Run for Troubleshooting. On November 8, 1989, an OPS Nuclear, Production Engineer questioned the start classification while working with a Quality Assurance (QA) person on a surveillance of the D/G Logbooks. The start was reclassified as a Valid Failure. Subsequent investigations-had found a speed switch to be out of calibration. On July 27, 1989, at 0237, a Valid Failure l occurred because of two blown fuses on the voltage regulator for D/G 2B. On August t
29, 1989 at 1522, another Valid Failure occurred on D/G iB. Technical Specifications (TSs) require that the surveillance testing frequency be increased from every 31 days to every 7 days following two Valid Failures in the past twenty valid starts.
OPS personnel increased this frequency on August 29, 1989. The frequency should
. have been increased on July 27, 1989, if the start had been classified as a valid I failure. This event is classified as a Management Deficiency because OPS Management Procedure (OMP) 2-6, D/G Logbook, is not clear on how to classify D/G starts following maintenance. No guidance is given on post maintenance testing. Unit 2 was in No Mode for a refueling outage when the event occurred an,d in Mode 1, Power Operations at the time of discovery. A revision will be made to OMP 2-6 to ensure the D/G starts are classified correctly.
E- d' * "'
- a. I
=ne . men vi wuca a ciovetoav comwiesio= l
- i UCENSEE EVENT REPORT (LER) TEXT CENTINUATION .**:ovio ous =o mo-om i
. exrines swa l
. .m. , . .... o , - n u .. .. u . .v . . .., .... . l vs.e i - mempe ?#3:
McGuire Nuclear Station, Unit 2 TEXT f# mas spece e soeuseet wee essesse*uW N4C Few'n W W HM o p j o j o l o l 3 j 7l 0 8l9 __
0l 1l2 --
0l0 01 2 0F 1l1 EVALUATION:
Background
Each unit at McGuire Nuclear Station has two independent D/Gs [EIIS:DGl. As part of the Essential Power System [E11S:EB], they provide standby AC power to the equipment required to safely shutdown the Reactors [EIIS:RCT] in the event of a major accident and to maintain the facility in the shutdown or refueling condition for extended periods of time. The D/Gs are required in a Blackout (loss of normal power) condition as well as a Blackout and Loss of Coolant Accident conditions.
TS 3.8.1.2 requires the following A.C. electrical power sources to be operable in Mode 5 (Cold Shutdown), and Mode 6 (Refueling):
A. One circuit between the offsite transmission network and the Onsite Essential Auxiliary Power System, and B. One D/G. Either D/G is capcble of meeting this requirement.
TS 4.8.1.1.2, in part, requires the D/G to start and accelerate to at least 488 RPM in less than or equal to 11 seconds. The voltage and frequency shall be at least 4160 volts and 57 HZ within 11 seconds after the start signal. This TS also requires that each D/G be demonstrated operable once per 31 days if the number of failures in the last 20 valid tests is one or none. If two or more valid failures have occurred in the last 20 valid tests, the surveillance frequency is increased to once per 7 days.
l '
l OMP 2-6, Diesel Generator Logbook, describes the method used to log all D/G start
( attempts and classify them as " Valid Success", " Valid Failure", " Invalid Test", or
" Invalid Test Failure". Page 10 of 11 shows the D/G Start Classification Guide.
Description of Event On July 9,1989, at 1535, D/G 2B was started, loaded, and run for approximately 30 minutes to deplete the Day Tank of fuel oil prior to maintenance. The D/G was then declared inoperable at 1600 when OPS personnel tagged the D/G out for maintenance.
Unit 2 was in Mode 5, and entered Mode 6, on July 10 at 1750.
From July 10 through July 19, maintenance was performed on D/G 2B. This maintenance included rotating the upper and lower cam bearings, replacing nine cam bearing halves, and replacing two connecting rod bearings. Unit 2 entered No Mode (Core Unloaded) on July 19 at 1729.
On July 25 at 0353, D/G 2B was started for post maintenance testing and run at no load condition for approximately 5 minutes. The time to reach 4160 volts was 11 956 seconds. This slow start was expected because of the extensive maintenance on the D/G. During this run, maintenance personnel discovered and subsequently repaired a fuel oil leak. Maintenance personnel also checked the bearings that had maintenance performed on them, and took temperature readings following each D/G start during the post maintenance break in runs.
.nesoe 2 . v.s. cem i m e . + m
^
GIRC Feenn 36A U.5 tuCLE AR S EQUL& TORY COMul0$lON
,' LICENSEE EVENT CEPORT (LE2) TEXT CONTINUATION unovio ous =o mo-o*
, EXPint$. 61pm 9ACILef t osaast m DOCKET NUtdSER Gl 4th NUM$th ($1 PA08 tai viaa i " E!.W. 0*a*?
McGuire Nuclear Station, Unit 2 0 l5 l 0 l 0 l o l 3 l 7l 0 8l9 .
0l1l2 0l0 0 l3 0F 1 l1 text e . w w ec w me.nm
+
The following table lists post maintenance starts performed on July 25 and recorded in the D/G 2B logbook.
Start Number Run Time Seconds To 4160V 706 15 min. No Load 10.314 707 30 min. No Load 10.39 708 30 min. at 400 kN 10.45 30 min. at 1000 kN 709 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> at 2000 kN 10.83 710 30 min. at 2000 kN 10.87 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 3000 kN 711 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> at 3600 KW 10.11 Each of the above starts was classified as an Invalid Test, Run for Troubleshooting by OPS personnel.
On July 26 at 0249, D/G 2B was started for a 14 hour1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> run to thoroughly heat the D/G and allow maintenance personnel to take deflection readings. This was start number 712 in the D/G logbook. The time to 4160 volts was 11.07 seconds. The start was classified as an Invalid Test, Run for Troubleshooting. OPS work request 136725 was issued to correct the cause of the slow start. Instrument and Electrical personnel (IAE) recalibrated the speed switches [EIIS: SIS) for the D/G and found them slightly out of calibration.
On July 27 at 0237, D/G 2B was started for procedure PT/2/A/4350/36B, D/G 2B 24 Hour Run. At 2024, OPS personnel manually tripped the D/G because of loss of voltage control from the Control Room and from the local panel. This was start number 713 and was classified by OPS personnel as a Valid Failure. Subsequent investigations by IAE personnel revealed two blown fuses [EIIS:FU) in the voltage regulator circuitry. The fuses were replaced and the D/G was tested to ensure the problem was corrected. The testing included procedure PT/2/A/4350/19B, D/G 2B Governor and Voltage Regulator Benchmark Test.
- l. Procedure PT/2/A/4350/02B, D/G 2B Operability Test was successfully performed by l OPS personnel on July 30, at 2228. The work requests were signed complete and D/G 2B was declared operable at 1050 on July 31.
Unit 2 entered Mode 6 from No Mode on July 31 at 1255 by commencing fuel load operations. D/G 2A was declared inoperable and red tagged for maintenance on July 31 at-1605.
Unit 2 entered Mode 5 at 0628 on August 18. D/G 2A was restored to operable status at 1745 on August 24.
On August 24 at 2030, D/G 2B was again declared inoperable for battery [EIIS:BI]
replacement. The operability procedure was run on August 29 at 1102 and the D/G was declared operable at 1400 hours0.0162 days <br />0.389 hours <br />0.00231 weeks <br />5.327e-4 months <br />.
c:C nau ma f .-_...-._"*"'.
4, efftC Feem ageA U $ huCLE3 CELUL'TomY CoMM,gstoni
., UCENSEE E ENT REPORT (LER) TEXT CZNTINUATION <*aono ove =o mo-eion
. EENRES $/31'S 9 ACILIT Y NAMG (1p DOCKET NUtdDER GI L(R hpM$lR ($) PAGE (3)
"aa' " 20. '%*. 70 McGuire Nuclear Station, Unit 2 TEKT I# move assee m segwsar, use asletteeW 44C Form JEraJ tih o l5 l0 l0 l0 l3 l 7l 0 8l9 ._
0l1l2 .-
0l0 0l4 or 1l1 At 1522 on August 29, OPS personnel started D/G 2B for a one hour run as required by che Engineered Safeguards Feature (ESF) test. The time to reach 4160 volts was 11.024 seconds as recorded in the D/G Logbook for start number 730. The start was classified as a valid failure. OPS personnel decided to continue on with the ESF test and formulate a plan for correcting the slow start time. The D/G was declared inoperable at 1655 on August 29. This ESF test was completed satisfactorily.
Upon completion of the ESF test, personnel from Mechanical Maintenance, IAE, and OPS conferred to formulate a plan for determining the cause, and correcting the problem of the slow starts on D/G 28. During the course of this investigation, IAE personnel found the speed sensor had been damaged. The speed sensor was replaced and documented on OPS work request 139534. The speed sensor is manufactured by Airpax Corporation, model number 085-101-0005. The D/G was subsequently retested and declared operable at 2300 on August 31.
Start number 730 for the ESF test was, at that time, the second Valid Failure .
within the last twenty valid starts (reference TS Table 4.8-1, page 11 of 11 of '
this LER). This TS requires the surveillance testing of this D/G to be increased from once per 31 days to once per 7 days. OPS personnel began testing D/G 2B according to this requirement.
In October, QA personnel were conducting QA surveillance 89-46 of the D/G Logbook.
During the course of this surveillance, an OPS Nuclear Production Engineer reclassified start numbers 710 and 711 from Invalid Test, Run for Troubleshooting, to Valid Success. The starting times and load requirements had been met for a Valid Success.
On November 8 at 1100, following a review of past D/G starts, the OPS Engineer and an OPS Manager reclassified start number 712 as a Valid Failure. This was a conservative determination based on the time to reach 4160 volts of 11.07 seconds.
OPS personnel stated they felt the speed sensor was the probable cause of the slow starts but the exact cause of the damage to the speed sensor or when it occurred could not be determined.
With start number 712 reclassified as a Valid Failure, the increased surveillance j should have been started when the fuse failure occurred on July 27, start number l
713. The operability test was run on July 30 at 2228, and again on August 29'at 1102. Under the seven day surveillance requirement, the operability test should have been performed on August 6; therefore, D/G 2B was technically inoperable from August 6 at 2228, until August 29 at 1102. D/G 2A was inoperable for maintenance on the D/G f rom July 31 at 1605, until August 24 at 1745. During part of this time, Busline 2B was removed from service and declared inoperable at 1130 on August
- 3. This Busline was restored to service and declared operable at 0759 on August 19.
Conclusion This event is assigned a cause of Management Deficiency because of Inadequate
! Directives. OMP 2-6 does not provide guidance on when post maintenance testing ends and valid challenges to the D/G begins. OMP 2-6 is written to comply with TS
, , , , , , , , .v. . au w -
a 5~
tent Feengasta U S CUCLE12 ( EIULAT0m? COMMIS$tok 4 UCENSEE EVENT REPORT (LER) TEXT CONTINUATION anaovio owe mo mo-oio.
(KPIRtl t'312 9 ActLity Sumug gis 00CEti NUMDIR L21 LER SfJM$lk t$) PACT (31
McGuire Nuclear Station, Unit 2 o ls l o j o j o l 3 l 7l 0 8l 9 0l 0 0l 5 or 1 l1 0l 1l 2 TEXT N show apace m socirost esas causostW MC Form M1(17) and with NRC Regulatory Guide 1.108, Periodic Testing of D/G Units Used As Onsite Power Systems. Regulatory Guide 1.108 addresses testing of D/G units during plant preoperational test and periodic testing of D/G units during normal plant operation.
On July 26, OPS personnel believed they had correctly classified start number 712 on D/G 2B as an Invalid Test, Run for Troubleshooting, following extensive maintenance. The classification was based on the guidance in OMP 2-6. During a subsequent surveillance of the D/G Logbook, OPS personnel conservatively decided to reclassify the start as a Valid Failure. This decision was made because the time to reach 4160 volts was 11.07 seconds which is greater than the 11.0 seconds allowed by TS. The surveillance of the D/G Logbook was being performed by McGuire Quality Assurance personnel in conjunction with OPS personnel. The reclassification came after extensive discussions over what constituted post maintenance testing as opposed to valid challenges to the D/G. The decision was made to conservatively classify the start as a Valid Failure.
TS 4.8.1.1.2, Table 4.8.1, lists the frequency of testing for a D/G based on the number of Valid Failures. By reclassifying the start performed on July 26 as a Valid Failure, the surveillance frequency for D/G 2B should have been increased to once per 7 days when the fuses failed in the Voltage Regulator circuit on July 27.
The surveillance was performed on July 30 at 2228, and again on August 29 at 1102.
l D/G 2B was technically inoperable from August 6 at 2228, until August 29 at 1102.
l In addition, D/G 2A was inoperable from July 31 at 1605 until August 24 at 1745.
I Neither D/G was technically operable between August 6, 1989 at 2228, and August 24, l
1989 at 1745, although D/G 2B would have started and assumed the required loads if j needed as shown by the operability test performed on August 29, 1989.
l' l Station personnel involved in the evaluation of this event believe the indicated slow times to reach 4160 volts following the maintenance on D/G 2B were a result of the damaged speed sensor discovered on August 31, 1989. A trend of the time to L reach 4160 volts indicates the speed sensor was damaged during or immediately following the maintenance on D/G 2B. The exact cause of the damage to the speed sensor and the time it occurred could not be determined.
A review of the McGuire Licensee Event Reports for the previous twelve months revealed no other events involving missed TS surveillances on the D/Gs because of l Inadequate Directives. Eight events did involve missed TS surveillances, therefore, missed surveillances is recurring.
A review of Special Reports for the previous twelve months shows the failure of the speed sensor to be a Recurring Problem. As documented in Special Report 2-M89-0227, this is the fifth speed sensor known to be damaged from apparent contact with the camshaft gear. Maintenance procedures have been changed to remove the speed sensors before removing or replacing the cam shaft bearing shells. This is documented in PT/0/A/4350/21, D/G Periodic Maintenance, change number 13. .
The missed surveillance on D/G 2B is not NPRDS reportable. The failure of the speed sensor is NPRDS reportable, jdg .:R a u.s. cm. ,,emo7n we
o IIAC De,se maa U.S WUCLEf.R C EIvLITDAY CouestN60N LICENSEE EVENT REPORT (LER) TEXT CONTINUATION waovio ove =0. mo-oio.
reines ew.
FACILif Y Rs4004 tt: DOCkti NUM9th W Ltn WunsetR f61 PAGE (31
'88" fuhm -
kIw*aYa McGuire Nuclear Station, Unit 2 tent a, . .,. we r am4wnn o l5 j o l o j o l 3 l 7l 0 8l 9 -
0l 1l 2 -
0] O Ol6 0F ll 1 3 There were no personnel injuries, radiation overexposures, or uncontrolled releases of radioactive material as a result of this event.
i CORRECTIVE ACTIONS:
Immediate: None Subsequent: 1) The damaged speed sensor was replaced.
- 2) PT/0/A/4350/21, D/G Periodic Maintenance was changed to remove 3 the speed sensor before removing or replacing cam shaft bearing shells.
- 3) IAE personnel changed procedure IP/0/A/3250/16A, D/G Speed Switch Calibration, to increase the gap between the camshaft gear er5d the speed sensor.
Planned: 1) Maintenance personnel will conduct a test at the next available D/G outage to determine how the speed sensor is being damaged by the camshaft gear. Measurements will be taken to determine if the camt. haft gear has sufficient movement to make contact with the speed sensor.
- 2) Operations personnel will revise Operations Management Procedure 2-6, Diesel Generator Logbook, to provide better guidance on classifying D/G starts. This will include post maintenance testing.
- 3) IAE personnel will reset the gap between the speed sensor and the camshaft gear on all McGuire D/Gs.
SAFETY ANALYSIS:
During the time that Busline 2B and D/G 2A were out of service for maintenance, and D/G 2B was technically inoperable, the TS requirement to have one D/G operable during Modes 5 and 6 was not met. Offsite power was available for the entire time through Busline 2A. If this offsite power supply had been lost, D/G 2B was c'apable of starting and assuming the required loads as documented by the operability surveillance test performed on August 29, 1989. The damaged speed sensor may have ;
indicated a slow start time but the D/G would still function to supply emergency power. Also, an additional source of power was available from Unit 1 by way of a crosstie between the 4160 volt distribution centers. This source could have been manually aligned to Unit 2 by the OPS personnel. This source is described in the Final Safety Analysis Report, Section 8.2,1.4.1., Offsite Power System Operational )
Description. ;
i i
uu o.. m. .e . . . m n .. . s , . -
deRC form ateA U S NUCLI A2 8.tIULtTORY COMMIStion
,. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION per.ovio oMe wo. mo-oio. ;
, txeints- e xes ;
- ActLITY esatst tu DoceL47 NUGAGER 821 Lth NUMBERISI Pact (36 v**a' "Ot.;P. $??:
McGuire Nuclear Station, Unit 2 o l5 l 0 l o l o l 3 l 7l 0 8l 9 -
0l 1l 2 -
0l 0 o l7 or i l1 rixt <n = . .e eir. s, - =c rom, m w nn In Modes 1, 2, 3, and 4, TS 3.8.1.1 requires both D/Gs and botr. offsite power sources to be operable. Major maintenance is not performea during these modes of operation; therefore, the problem of post maintenance testing would not have occurred. Major maintenance would require the unit to be in Modes 5 or 6.
The health and safety of the public were not affected by this incident.
l
)
NIC POIM assa op.s. Cros 1996 520 539 00010 W
OfAC Perg 386A U.S IsWCLLin at;ULOT0av C0mMitG104
.. UCENSEE EVENT REPORT (LER) TEXT CONTWUATION Anaovto ove no. siso-oio.
. txPials aves
- ActLITY 4Aug ti 00chti Nunetth tal gga eguusta tel PA05 (31 naa ' " W M't' trai:
McGuire Nuclear Station, Unit 2 olslolojol3l7l0 8l9 ._
0l1l2 --
0l0 o l3 or 3l3 Ten n . w. we % amu w nn SEQUENCE OF EVENTS' Date Time Event 7/6/89 ----
Unit 2 entered Mode 5.
7/9/89 1535 D/G 2B started to deplete the day tank level.
7/10/89 1750 Unit 2 entered Mode 6.
7/10/89 thru Extensive maintenance was. performed on D/G 2B.
7/19/89 7/19/89 1729 Unit 2 core reached No Mode, core unloaded.
7/25/89 0853 D/G 2B began start no. 705 for post maintenance testing - Run 5 min. at no load condition.
1352 D/G 2B began start no. 706 - 15 min. at no load.
1448 D/G 2B began start no. 707 - 30 min. at no load.
1559 D/G 2B began start no. 708 - 30 min at 400 kN
- 30 min. at 1000 kN.
1745 D/G 2B began start no. 709 - I hr. at 2000 kN.
1930 D/G 2B began start no. 710 - 30 min. at 2000 kN
- 2 hrs. at 3000 kN.
2323 D/G 2B began start no. 711 - 2 hrs, at 3600 kN.
7/26/89 0249 D/G 2B began start no. 712 - 14 hrs. at 3000 kN. Start time 11.07 sec. .
N0800 W.R. 136725 was issued to correct cause of slow start.
N2000 IAE recalibrated speed switches.
7/27/89 0237 D/G 2B began start no. 713 for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run.
N2015 D/G 2B experienced voltage control failure.
2024 D/G 2B was manually tripped. ;
7/28/89 ---- IAE discovered and replaced blown fuse in voltage regulator circuit.
- u. s . on. v... . s -+ e
=:c e:aw me.
Geht teem maa U S t UCLLO3 aEDULLTORv COMul88104
,, UCENSEE EVENT CEPORT (LER) TEXT CONTINUATION oraovio ove no mo-oio.
EXPIRES 4'31'88 9 Acthef t haut sie DocatY Numetta 01 ggn wunagan tel tact tai vtaa ' " W it' "'#.?:
McGuire Nuclear Station, Unit 2 o l5 l 0 l 0 l o l 3 ; 7l 0 8l 9 Oj 1l 2 .-
0l 0 ol9 or i l1
-tart u -. . , w wc w as .nni 7/29/89 1336 D/G 2B began start no. 718 for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> run.
7/30/89 2228 D/G 2B began start no. 725 for operability test.
7/31/89 1050 D/G 2B was declared operable.
1255 Unit 2 entered Mode 6 - fuel load commenced.
1605 D/G 2A was declared inoperable and tagged for maintenance.
8/3/89 1130 Busline 2B was tagged and declare inoperable for maintenance.
8/18/89 0628 Unit 2 entered Mode 5.
8/19/89 0759 Busline 2B was restored to operable.
8/24/89 1745 D/G 2A was restored to operable.
2030 D/G 2B was declared inoperable and tagged for D/G battery replacement.
8/29/89 1102 D/G 2B began start no 729 for operability test.
1400 D/G 2B was declared operable.
1522 D/G 2B began start no. 730 for ESF test. Time to 4160V 11.024 sec.
1655 D/G 2B was declared inoperable.
+
N2300 ESF test was completed satisfactorily
, 8/30/89 ----
Mechanical Maintenance, IAE, and OPS personnel met on slow i starts of D/G 2B.
i 8/31/89 ----
D/G 2B Speed sensor was discovered damaged and replaced.
l 2300 D/G 2B was declared operable.
i
' .u... m , i,...uo4.. o m o
. - . . ~ - - . . - . . .~ - ~-.- ---...-..~ - --~- .
. .=
! 088tC esem 3pta U s seuCLL&2 EL3ULATORY COMMitBION
"' ~
UCENSEE EVENT REPORT (LER) TEXT CONTINUATION a Paovie ove =o mo-oio.
, Laping4. S'31/3 Pacetsty eenast att DMalf 8evasta ta) Lin Nuneta
- Pact (3i vtam 5'y' f,' f 6 .
E v eg,*
I Mccuire Nucient Station. Unit 2 0 l6 l0 l 0 l 0 l 317 ! 0 819 -
0 I 11 2 l Ol0 0F 1 l1 110 text a= . v. we wes,w =ac som,amareim 1- ./0 START .LA !FICAT! W .U,.E
. M
l l =
g == g, =
g ;
"" gg.
ll
- =
. =e- =
o o
Es .
ll !I h
m , .. ,. m... - .
gl,{Qg(heBC.i EfrE!! il M'WicMP&P.!R- :
ag,w,y -, . - si . . m1 M- . , - - . , _ . . . . . .
GBRC PernLMSa y & NuCLEA2 $$gy(&TQa? COtAspIGS M 7 ' '
- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION unovto owe =o mo.ew .
, txP hES 8'31's f aci6 tty annant m Docast NuhIDEN Q) ggg gyggggg gg, pggg g,
'I'" 'N Oh -
Ow$Ye*' e McGuire Nuclear Station, Unit 2 o ls l0 l0 l0 [ 3l7 l 0 8l 9 -
0l1l2 -
0 l0 1l 1 or 1 j1 tan u = , . anc w an ,,im DIESEL GENERATOR TEST SCHEDULE NUMBER OF FAILURES NUMER OF FAILURES IN IN LAST 100 VALIO LAST 20 VALIO TESTS
- TEST FREQUENCY i1 14 Once per 31 days 3 &" 15 Once per 7 days t
!
- Criteria for determining number of failures and number of valid tests shall l be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, but determined on a per diesel generator basis.
For the purposes of determining the required test frequency, the previous test failure count may be reduced to zero if a complete diesel overhaul to like-new conditions is completed, provided that the overhaul including appro-priate post-maintenance operation and testing, is specifically approved by the manufacturer and if acceptable reliability has been demonstrated. The reliability criteiTon shall be the successful completion of 14 consecutive tests in a single series. Ten of these tests shall be in accordance with the routine surveillance requirements of Specifications 4.8.1.1.2.a.4 and 4.8.1.1.2.a.5; the remaining four tests in accordance with the 184-day requirements specified in the footnote to Specification 4.8.1.1.2.a.4 and
- Speci fi cation 4. 8.1.1. 2. a. 5. If this criterion is not satisfied during the first series of tests, any alternate criterion to be used to transvalue the failure count to zero requires NRC approval.
- The associated test frequency shall be maintained until seven consecutive failure free demands have been performed and the number of failures in the last 20 valid demands has been reduced to 7 e.
. e . . . m , 1. .. m . . 4 am goxw .
.. . - - - - - _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _