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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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e Duke huart Conwar. *
(704) 575 4ogy McGuart Nuclear Station
. t0 But 4M Cornelius, N C 2803).04M i
DUKEPOWER 1
October 16, 1989 l
U.S. Nuclear Regulatory Commission I Document Control Desk j Washington, D.C. 20555 1 1
Subject:
McGuire Nuclear Station Unit 1 and 2 i Docket No. 50-369 Licensee Event Report 369/89-27 Gentlemen l Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event Report 369/89-27 concerning the inoperability of the Annulus Ventilation System. [
This report is being submitted in accordance with 10 CFR 50.73(a)(2)(v) and t (a)(2)(i). This event is considered to be of no significance with respect to the !
health and ssfety of the public. .
t Very truly yours, ;
A WYvO T.L. McConnell l t
I DVE/ADJ/cb1 i
Attac'iment ;
xc Mr. S.D. Ebneter American Nuclear Insurers !
Administrator, Region II c/o Dottie Sherman, ANI Library !
U.S. Nuclear Regulatory Commission The Fxchange, Suit 245 ,
101 Marietta St., NW, Suite 2900 270 Farmington Avenue ;
Atlanta, GA 30323 Farmington, CT 06032 i L !
j INPO Records Center Mr. Darl licod l Suite 1500 U.S. Nuclear Regulatory Cotaission '
i 1100 circle 75 Parkway Office of Nuclear Reactor Regulation Atlanta, GA 30339 Washington, D.C. 20555 i
( !
t M&M Nuclear Consultants Mr. P.K. Van Doorn 1221 Avenue of the Americas NRC Resident Inspector New York, h"t 10020 McGuire Nuclear Station i
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't bxc: B.W. Bline l A.S. Daughtridge l R.C. Tutrell i R.L. '.111 1 R.M. Glover (CNS)
T.D. Curtis (ONS) ,
P.R. Herran i S.S. Kilborn (W) !
S.E. LeRoy !
R.E. Lopez-Ibanez J.J. Maher :
R.O. Sharpe (MNS) l G.B. Swindlehurst' ;
K.D. Thomas !
L.E. Weaver 4
R.L. Weber J.D. Wylie (PSD)
J.W. Willis QA Tech. Services NRC Coordinator (EC 12/55) l MC-815-04 (20) I i
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"' The Aunulus Ventilation System Vas Inoperable Because Of A Design Deficiency, A J Manaaement Deficiency And Inappropriate Actions t vtWT Daf t ill LOR.ettiADIA @ htPOa t DATE <Fi OtMt m S ACILifitG IWVOLVID .06 68 Q*y*,'Q wogem Day glam e stative hawas DO;a t t h.w s t e si MONTu Day vtam vlam h'h McGuire, Unit 2 o16tol01 0 13 , 7 t o 0l 9 1l 5 89 8l9 0 l 2j7 0l0 1l 0 1l6 8l 9 ois,o,o,o, , ,
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able. COCE l Alan Sipe, Chairman, McGuire Safety Review Group 7,0,4 8,7; 5, ,4, l B,3 i COMPLif t Okt LINE FOR 4 ACM ComeP0hthf SalLuht DitCnieto i% TMit 8tPORT (138 .
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During performance testing of the Annulus Ventilation System (VE) on September 15, 1989, the preheaters did not start because the air flow permissive was not made.
The cross connect dampers were closed and tagged and the Unit 1 VE Train A remained l logged inoperable. Performance personnel tested the Unit 2 VE system and determined that the same problem existed. The Unit 2 VE Train A was logged inoperable and the cross conne.ct dampers were closed and tagged. Subsequently,
- Design Engineering personnel evaluated the problem and determined that the VE system would be considered conditionally oparable if a lead was lifted on the differential pressure switches. This event ia, a
- signed c,uses of Design Deficiency, Inappropriate Action and Management Deficiency. Unit I was in Mode 1, Power Operation, at 100 percent power and Unit 2 was in Mode 3, Hot Stendby, at the time of this incident. On September 18, 1989 during implementation.of McGuire Exempt Variation Notice (MEVN) 1078, Unit 1 entered Technical Specification 3.0.3 when both trains of the VE system became inoperable. The MEVN was implemented on the Unit 2 VE Train B, and Train B was restored to operability. This event is assigned a cause of Inappropriate Action resulting from deficient communication.
Unit I was in Mode 1, Power Operation, at 100 percent power and Unit 2 was in Mode 2, Startup, at the time of entry into Technical Specifit.ation 3.0.3.
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McGuire Nuclear Station, Unit 1 o l5 j o l 0 l o l 3 } 6l 9 8; 9 0l 2l 7 O; O O l2 0F 0l9 teri w - . w. -, .am =ac e.- m.m im EVALUATION: )
)
Background
The VE system [EIIStVD) serves to produce and maintain a negative pressure in the j Containment Annulus following a Loss of Coolant Accident (LOCA), minimize the ;
release of radioisotopes, and provide long-term fission product removal capability l 1
by decay and filtration. The system consists of two 100 percent capacity trains of j equipment and is actuated by 2 of 4 high-high containment pressure signals.
The VE filter [E1IS:FLT) trains are each equipped with demisters and electric preheaters. The demisters and preheaters are installed to limit the relative ;
humidity of the air entering the filters to below 70 percent to keep the charcoal l in a dried condition, conservatively assuming the entering air is at 100 percent relative humidity. ,
The preheaters are designed to run continuously while the fans [EIIS: FAN) are '
running. Both trains of VE are started automatically by the Solid State Protection System (SSPS) on a 3 psig signal.
- Procedure PT/1,2/A/4450/03A, Annulus Ventilation System Train A Operability Test, ,
and procedure PT/1,2/A/4450/03B, Annulus Ventilation System Train B Operability Test, are required to be performed once every 31 days. The purpose of these procedures is to demonstrate operability of each train of the VE system. These procedures are performed by Operations personnel.
Procedure PT/1/A/4450/03C, Annulus Ventilation System Performance Test, is required to be performed once every 18 months. The purpose of this procedure is to verify :
proper operation of the VE system to maintain a negative pressure in the annulus '
region between the Containment Vessel and the Reactor Building, and to verify leakage integrity of the Annulus barriers. This procedure is performed by Performance personnel.
Procedure PT/1/A/4450/03D, Annulus Filter Train Heaters Dissipation Test, is required to be performed every 18 months. The purpose of the test is to verify the annulus filter train heaters [EIIS:HTR) dissipate the proper power. This test had !
been included in the Annulus Ventilation System Performance Test. It was separated e into a separate procedure in December of 1987. Performance personnel also perform '
this test.
Procedure OP/1/A/6450/02, Annulus Ventilation System, defines the operation of the VE system. ;
As a result of an event on December 2,1987 whf ch was caused by the surveillance '
testing program being inadequate te positively verify operability, the Failed
< Surveillance Analysis Program was developed by Performance personnel. The Failed ,
' Surveillance Analysis Program was adopted as a station requirement. Each technical section has their own customized version to fulfill the station requirements. The purpose of this program was to ensure that any surveillance test affecting equipment operability which fails will be followed by a reevaluation of the y*ou ues .v.s . m ,,,,m ,,, w e
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' ACluvY f.4484 til DoCat) NVtGS A (31 ttR wutIDth 183 PA06 (31 nsa "bt,%'H ;.l,1: i McGuire Nuclear Station, Unit 1 o [s j o l c l e l 3 l 6l 9 8l9 0l2l7 .-
0l0 0 l3 of 0l9 rartaa . = wca mmawin l 1 i
l surveillance interval. The Failed Surveillance Analysis Program was fully !
implemented in October 1988 by the Operations (OPS), Performance, Mechanical :
Maintenanu, Instrument and Electrical (IAE), Chemistry and Radiation Protection :
sections. l Solon pressure switches [EIIS:PS), Catalogt.e number PSIDW, are used in the Auxiliary Building Ventilation System (VA) (EIIS:VF], the Control Area Ventil; tion "
, System (VC) [EIIS:VI), the Diesel Building Ventilation System (VD) [EIIS:VJ) and I the VE system. In the VE system, this type of pressure switch is used as the l differential pressure switch for the carbon bed. The VE differential pressure i switches are identified by Anstrument numbers IMVEPS5180, IMVEPS5190, 2MVEPS$180 ,
and 2MVEPS5190.
l Technical Specification 3.6.1.8 requires that two independent Annulus Ventilation l Systems shall be operable in Mode 1 (Power Operation), Mode 2 (Startup), Mode 3 ,
- I (Hot Standby) and Mode 4 (Hot Shutdown).
Technical Specification 3.0.3 states th t when a Limiting Condition of Operation is not met, except as provided in associated Action Statements, within one hour action must be initiated to place the affected units in a mode in which the specification does not apply.
Description of Event on September 15, 1989, Performance personnel began the Annulus Filter Train Heaters Dissipation Test. At 0850 that day, Unit 1 VE Train A was declart ' and Ic gged -
inoperable for the test. VE Fan IA was started in accordance with tr.c procedure, but the preheaters did not activate. Performance personnel thought the pressure
- switches which measure the differential pressure (DP) across the carbon filters i (and give a preheater start permissive) may be out of calibration and checked the i DP. The DP was 0.4 inches water gauge (in.wg) on VE Train A and 0.4 in.wg on VE Train B. A DP of 0.5 in.wg gives the air flow permissive to activate the preheaters.
While monitoring the differential pressure, Performance personnel noted that the !
cross connect dampers between VE Train A and VE Train B were open. (This is the normal operating alignment.) The Annulus Filter Train Heaters Dissipation Test did ;
not require isolating the cross connect dampers [EIIS:DMP). Subsequently, Performance personnel wrote a procedure change to require closing the cross connect daropers to perform the procedure and decided to write a Problem Investigation Report (PIR) to have the setpoint for the pressure switch changed. During the approval' process for the procedure change, Performance personnel and the OPS Euperintendent discussed the problem. The OPS Superintendent requested that the Performance personnel contact Design Engineering (DE) personnel concerning the ,
problem. The' procedure change was never implemented for Unit 1. The procedure change was implemented for Unit 2 to allow troubleshooting and data collection for ,
DE persortnel.
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McGuire Nuclear Station, Unit 1 o l6 lo lo lc l 3l 6l 7l 9 -l 0] 2l 7 tert * . w =ae a an .nm
The PIR was forwarded to DE personnel for evaluation on September 15, 1989. DE personnel determined that the VE system would be considered conditionally operable i if the preheater differential pressure switches were jumpered out of service. l At 1405 on September 15, 1989, a notification was made to the NRC as required by i procedure RP/0/A/5700/10, NRC Immediate Notification Requirements. The Unit 2 VE system was tested and the determination was made at 1550 that the same problem -
existed. At 1605, Unit 2 VE train A was declared inoperable. The VE Train A cross connect damper was closed and red tagged.
Work requests 96983, 96984, 96985, and 96986 were written on September 15, 1989 to implement MEVNs 1663 and 1694 which addressed changing the setpoint of the pressure .
switches to a lower setting. IAE personnel began work under work request 96983 on the Unit 2 VE Train A. The pressure switches were calibrated to the new settings 1 according to MEVN 1663. The preheaters did not energize. IAE personnel lowered the pressure switches setpoint a second time. Performance personnel tested the preheaters. They energized approximately one minute after the fan started. ;
Performance personnel notified DE personnel. DE personnel determined that this was an unacceptable delay for the preheaters to energize. The decision was made at this time to delete the function of the pressure switches. This modification would ,
result in the preheaters energizing on a fan start rather than energizing on a fan start and the actuation of the pressure switch. McGuire Nuclear Production r Variation Notices (MPVNs) 1077 and 1078 were written on September 16, 1989 to supersede MEVNs 1663 and 1694 for Unit 2 and Unit 1, respectively.
IAE personnel implemented MPVN 1077 for the Unit 2 VE Train A. OPS personnel verified that the preheaters energized by starting the fan. The preheater -
energized and functioned properly. At 1650 on September 15, 1989, the Unit 2 VE 6 Train A was declared operable. At the same time, the Unit 2 VE Train B was declared inoperable for implementation of MPVN 1077 under work request 96984. IAE personnel implemented the changes and worked with OPS personnel to complete the functional verification. At 1740, the Unit 2 VE Train B was declared operable. ;
On September 18, 1989, IAE personnel went to the Control Room to obtain clearance i to begin work under work request 96986. This work request would implement MPVN 1078 for the Unit 1 VE Train B. IAE Technician A discussed the work to be done with' Assistant Shift Supervisor A. Assistant Shift Supervisor A gave clearance to >
begin work,.and declared the Unit 1 VE Train B inoperable at 1615. Subsequently, ;
IAE personnel contacted the Control Room and informed Assistant Shift Supervisor A '
that by allowing IAE personnel to remove the differential pressure switches from the preheater circuit, both trains of VE vere functionally inoperable. With both trains of VE inoperable, Technical Specification 3.0.3 was entered for Unit 1 at 1
1615. 1 IAE personnel implemented the changes required by MPVN 1078, and worked with OPS l personnel to complete the functional verification. At 1655, the Unit 1 VE Train B was declared operable, and Unit I was logged out of Technical Cpecification 3.0.3.
IAE personnel proceeded to implement MPVN 1078 under work request 96985 on the Unit 1 VE Train A. The changes were made and IAE personnel worked with OPS personnel to '
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0l0 0 l5 oF 0l9 l rsxtw . w cP mnawnn complete the functional verification. At 1731, the Unit 1 VE Train A was declared operable.
Conclusion The event resulting in the preheater not starting because of the M fferential pressure air flow permissive not being made is assigned a cause :i thsign ;
Deficiency because the wrong setpoint for the differential prer m - W tch was selected. The setpoint was selected based on available informatP" n t' time, f
This event is clso asiigned a cause of Inappropriate Action resulting in no action being taken when required because of a lack of attention to detail. In March of 1983, work was performed under work requests 84608 and 84609. The wo M involved calibrating pressure switches 2MVEPS5180 and 2MVEPSS190. The pressure switches were set to 0.5 in.wg as specified, but operations specifications co.uld not be ,
achieved. The saitches were reset to 0.4 in.wg (2MVEPS5180) and 0.38 in.wg '
(2MVEPSS190). As documented on the work requests, Performance Engineer A was to notify DE personnel of thiP setpoint change. Performance Engineer A stated that he ,
vaguely remembered this sin.ation, but apparently failed to follow up on the problem. A second Inappropriate Action resulting in no action being taken when required becuse of a lack of attention to detail is also assigned to this event.
IAE General Supervisor A failed to follow up to ensure the setpoint change was adequately documented prior to mproving and closing out the work requests. This occurred in 1983 and personnel recollections are vague. Mitigating circumstances that may have centributed to these inappropriat actions could not be identified during this investigation.
l This event is also assigned a cause of Mana. , . Deficiency resulting from deficient procedure review and maintenance. In November 1983, changes were incorporated in the VE System Operability Test procedures for Unit 1 and Unit 2.
The changes added steps to the procedures to close the crose connect dampers. The reason given for the change was as follows:
" Prevent bypass flou through opposite train which prevents preheaters from operating due to low flow."
The problem sith the preheaters not energizing because of low flou was apparently identified, but the only action taken that could be found during this itivestigativa was the procedure changes.
During the investigstion of this event, the work request history for differential prr sure switches, IMVEPS5180, IMVEPS5:.90, 2MVEPS5180 and 2MVEPSS190, was researched. Eighteen preventative maintenance (PM) work regt.ests were reviewed f or the time period from July 1985 through May 1989. The as found setting for the
, pressure switch in eleven of the eighteen cases was out of calibration. ~
"enteen repair work requests for the time period from December 1982 to September a d9 were eviewed. Eleven of these worx requests were completed in 1987, 1988, or 1989.
Fourteen of the sc- ' teen work requests described problems with the preheaterc nom energizing. Ten L. ..ae fourteen problems resulted because the pressure switch wA out of calibrathn.
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1 In July 1988, Maintenance Engineering Services (MES) personnel performed a Failed Surveillaa.ce Analysir for pressure switch IMVEPS5180 when the switch was found out of calibration during work performed under work request 135093. Six previous work requests dating bacx to August 1985 for the pressure switch were reviewed. Tive of the six work requests documented that the pressure switch was found out of l calibration. Based on this information, MES personnel changed the preventative maintenance frequency from twelve months to eight months. In addition, work request 68230 was written to replace the pressure switch. The basis for this action was that this pressure switch had not been replaced since the failures began in 1985. A second Failed Surveillance Analysis was conducted in December 1988 on pressure switch INVEPS5180 when it was discovered that the switch was out of calibration. Work request 68230 to replace the switch had not been completed at the time of this failure. MES persontel added a step to the work request to have
'the pressure switch returned to MES so that at could be sent to a testing facility.
The work request was completed on March 7, 1989. The switch was not sent to the, testing facility; however, repeatability tests on the switch were conducted by MES personnel. The results were inconclusive.
MES personnel also performed a Failed Surveillance Analysis for pressure switch 1MVEPS5190 in July 1988 when the setpoint was found out of tolerance. Action was taken to decrease the preventative maintenance frequency from 12 months to eight months. In addition, work request 68304 was written to replace the prest,ure switch.
, In .uguat 1989, OPS personnel performed a failure analysis on procedure i
PT/1/A/4450/03A, Annulus Ventilation System Train A operability Test, after the preheaters failed to energize during performince of the test. Operations
- Management Proaedure 1-4 outlines the requitad analysis for failed periodic tects.
l The guidance concerning Surveillance / Equipment History states:
1
" Review past surveillance history or equipirent histoty (whichever is appropriate) over a period of the last 10 curveillances or 2 years whichever is shorter."
OPS personnel based the review on completed periodic operah 'ity tests for VE Train A for the previous two years. No documented failures were identified; therefore, OPS personnel determined that a change in the test frequency was not required.
In 1989, MES personnel began performing a review of Solon pressure switches. There
, have been recurring drift problems with these switches which are used in several ventilation systems (VA, VC, VD, and VE) at McGuire. During this review, PIR 0-M89-0096 was written by MES personnel in April 1989. 'lhe PIR addressed a high rate of out of calibration occurrences for Solon pressure switches. The PIR was assignei to DE personnel for evalu tion. DE personnel evaluated the problem and eluded that there were no appropriately qualified replacement switches suited rb 'entilation system application. DE personnel made recommendations for two
/ jotaible alternative solutions. The PIR was reassigned to MES personnel to evaluate the DE response. If MES personnel determine that leaving the Solen pressure switches in plata is not acceptable, DE personnel recommended that a design study be initiated by the Nuclear Production Department. In addition, MES grosu seen n.e. m,sm ao
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personnel initiated Station Problem Report (SPR) 2770 in August, 1989, which described the problem with pressure switches 1MVEPS5180, IM?EPS5190, 2MVEPS5180 and 2MVEPS5190. The proposed resolution was to lower the setpoint of the switches. !
MEVNs 1663 and 1694 were written to implement SPR 2770. As previously discussed in !
the description of the event, MEVNs 1663 and 1694 were superseded by MPVNs 1077 and ;
1078.
l During the investigation, a possible procedure weakness was identified in procedure ;
PT/1/A/4450/03D, Annulus Filter Train Heaters Dissipation Test. The procedure does not include a prerequisite system condition which specifies VE system alignment for ;
the test. The procedure could be enhanced by adding a prerequisite system condition for VE system alignment. The VE System Expert will evaluate the Annulus Filter Train Heaters Dissipation Test and incorporate enhancements as needed.
Performance personnel stated that they did not remember how the VE system was aligned for the heater dissipation tests performed prior to this event. g A cause of Inappropriate Action resulting from deficient communication is assigned to the event resulting in Unit 1 entering Technical Specification 3.0.3. Assistant Shif t Supervisor A stated that his impression of the work to be done was to place a jumper across the pressure switch which would not make VE Train B inoperable. The actual work involved lifting a lead which functionally made tne Unit 1 VE Train B inoperable. The Unit 1 VE Train A was already inoperable and had been since September 15, 1989, when the problea with the VE preheaters was discovered.
! Assistant Shift Supervisor A stated that he was aware that the Unit 1 VE Train A was inoperable when he gave IAE Technician A parmission to begin work on the Unit 1 VE Train B. I/.E Technician A stated that he was not aware that the Unit 1 VE Train A was inoperable during the time he was discussing the work to be done with l Assistant Shif t Supervisor A. This investigation did not. identify any mitigating l circumstances resulting from human factors problews that contcibuted to the l
inappropriate actions.
A review of the McGuire LER data base for the previous twelve months revealed one i
other event involving a TS violation for the VE system caused by a Design Deficiency. This event, detailed in LEP 369/89-21 involved deficiencies in the temperature-induced difference in the pressure gradients inside and outside the Annulus. The corrective actions were specific to the event and would not have prevented this event from occurring. This event is considered recurring.
The McGuire LER data base was also searched for the previous 12 months for events where TS 3.0.3 was entered. One event, detailed in LER 369/89-01, involved entry lato TS 3.0.3 for the Control Room Ventilation System with a contributing cause of inapproprir.ce action resulting from deficient communications. however, the deficient communications resulted from misunderstood written instructions rather than misunderstood verbal communicati. a. This event is not considered recurring.
As a rest or other events involving Ventilation System problems caused by Design
' Deficiencies, the problem of Technical Specification violations caused by Design Deficiencies 'n general is considered to be recurring.
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This event is reoortable to the Nuclear Plant Reliability Data System (NPRDS) because pressure switch 2MVEPS5180 was found out of calibration during l implementation of MEVN 1664. McGuire has previously reported one failure of a p.easure switch used d.n this application in the VE system to NPRDS.
There were no personnel injuries, radiation overexposures, or releases of radioactive material as a result of this incident.
CORRECTIVE ACTIONS: '
Immediate:
For Event of September 15, 1989:
- 1) A procedure change was written for procedures PT/1,2/A/4450/03D, Annul.us Filter Train Heaters Dissipation Test, to require that the cross conne'ct dampers betw'en VE Train A and B be closed.
- 2) The Unit 1 VE Train A was declared inoperable, and the VE Train A cross connect damper was closed and tagged.
For Event of September 18, 1989:
- 1) MPVN 1078 was implemented for the Unit 1 VE Train B, and VE Train B was .
declared operable.
Subsequent: >
l For Event of September 15, 1989:
- 1) Performance personnel tested the Unit 2 VE system to determine if the same problem existed for Unit 2.
- 2) The Unit 2 VE Train A was declared inoperable, and the VE Train A cross connect damper was closed and tagged.
- 3) Work requests 96983, 96984, 96985, and 96986 were written to implement MEVNs 1663 and 1694.
- 4) MEVNs 1663 and 1694 were superseded by MPVNs 1777 and 1778.
- 5) Work requests 96983, 96994, 96985, and 96986.were completed and MPVNs 1077 and 1078 were implemented.
For Event of September 18, I?89- '
Thic event was discussed with the Operations personnel involved.
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0l0 0l9 0F 0 l9 texw . = wc e am wnn 2 Planned: 1) DE personnel will further evaluate the correctise actions taken to 'I determine if the operation and long term reliability of the VE system can be better enhanced by other alternatives. l
- 2) The VE System Expert will evaluate procedure PT/1/A/4450/03D, l Annulus Filter Train Heaters Dissipation Test, and incorporate appropriate enhancements as needed relative to system alignment.
- 3) Operations personnel will review and incorporate appropriate changes ,
with respect to correct damper position into procedure !
PT/1,2/A/4450/03A, Annulus Ventilation System Tr in A Operability )
Test, and procedure PT/1,2/A/4450/03B, Annulus Ventilation System Train B Operability Test. These changes will be incorporated into ;
each procedure prior to the next scheduled operability test.
- 4) This event will be covered in an OPS Shift Supervisors meeting. The importance of clear communications will be stressed.
- 5) Applicable portions of this event will be covered with appropriate IAE personnel. ,
l SAFETY ANALYSIS:
The Operability Evaluation concluded that the VE system is conditionally operable provided that the function of differential pressure switches is deleted. In addition to the differential pressure switches, there are other preheater and fire safeties provided. The preheater also receives a permissive cignal from the associated VE fan. The differential pressure switch acts as a , safety to protect the heater itself. To address the concern of overheating resulting from low flow across the preheater, there are high temperature alarms and fire alarms downstream of the heater which are .st at 220 degrees-F and 325 degrees-F, respectively. In addition to the high temperature safety switches, low filter train flow (below 6400 CFM) is indicated on the main control board. These safeties provide protection to the heater and filter train, in addition to identifying abnormal operation.
If the preheaters had failed to energize under accident conditions, carbon filter performance may have become degraded which could have resulted in higher radioactive releases through the unit vent. Partial filter fculing is assumed to occur in the accident analytis. Such fouling would result in an inc ease in differential pressure across the filter, which may have been sufficient to energize the heaters. Even if the heaters remained deenergized throughout the event (no credit taken for operator action to energize the heaters), the resulting dose consequences would have remaired within 10CFR100 limits.
The health and safety of the public were not affected by this event.
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