|
---|
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
-y -
'
'
.,
= ;, .
'
,,
f n ,1-
?*
. Dukeher Com;>any ' M4)!M McGuirr Nuclear Station
l Ito But 45$ 1 Cornebar NC 280310458 '
.L DUKEPOWER October 19, 1989 i
U.S. Nuclear Regulatory Comenission
.
, . Document Control. Desk L
Washington, D.C. . 20555 >
L
Subject:
M Guire Nuclear Station Units 1 and 2 i
Docket No. 50-369 5 p Licensee Event Report 369/89-26 j
'
t: .
,
Gentlemen: '
!
Pursuant to 10 CFR 50.73 Sections (a)(1) and (d), attached is Licensee Event i Report 369/89-26 concerning both trains of the Control Area Ventilation System t being inoperable because of Design Deficiency. This report'is being submitted in !
accordance with 10 CFR 50.73(a)(2)(i). This event is considered to be of no significance with respect to the health and safety of the public. ;
,
!
Very truly yours, !
-b) do k ksAf T.L. McConnell '
DVE/ADJ/cb1 Attachment
- i xc
- Mr. S.D; Ebneter American Nuclear lnsurers
.
{
Administrator, Region II c/o Dottie Sherman, ANI Library !
U.S. Nuclear Regulatory Comission The Exchange, Suit 245 ;
101 Marietta St. NW, Suite 2900 270 Farmington Avenue 't Atlanta, GA 30323 Farmington, CT 06032 l INPO Records Center Mr. Darl Hood Suite 1500 U.S. Nuclear Regulatory Commission
, 1100 Circle 75 Parkway Office of Nuclear Reactor Regulation !
Atlanta, GA 30339 Washington, D.C. 20555 !
'
M&M Nuclear Consultants Mr. P.K. Van Doorn ,
,
1221 Avenue of the Americas NRC Resident Inspector
'
New York, NY 10020 [
McGuire Nuclear Station
!
!
8910250328 891019 PDR ADOCK 05000369 79- ;
S P DC.
i
'
et
'
4 7
'
O
I;' LIR
" Cover Letter Page 2
'
.
bact B.W. Bline A.S. Daughtridge y- R.C. Futrell R.L. Gill R.M. Glover (CNS) 7.D. Curtis (ONS).
P.R. Herran S.S. Kilborn ()[)
S.E. LeRoy R.E. Lopez-Ibanez J.J. Maher R.O. Sharpe (MNS) s G.B. Swindlehurst K.D. Thomas ,
L.E. Weaver R.L. Weber J.D. Wylie (PSD)
J.W. Willis QA Tech. Services NRC Coordinator (EC 12/55)
MC-815-04
. (20)
.
__ 4- , , - --
r
__ ._. - -
p
'
,
Q jr.
go set .
vt auctt. .vt. toe, emmes.o=
'***a **ve
. .
-
LH:ENSEE EVENT REPORT ILERI
..m.,, .e t nl oocutseventa m .. -
McGuire Nuclear Station, Unit 1 o ls ;o io iol3 65 i 9 3 jopj o i9
"'t Both Train's Of The Control Area Ventilation System Were Inoperable Enemune Of A Damien Deficiency That Deleted A check D=-ar tve=1 n i ua muus . ici atro.1 ti n iti or tn enciut n inve6vte ei
..w,..... poca n g ,t a,.,
mouva o., v4.. v4.a 'a= ;.6 ll',= uo.a. o., ,t..
McGuire, Unit 2 o ,sio,ogo,3,7,0
-
0] 7 2l 0 89 8l9 0 l 2l6 0l0 1l 0 1l9 8l 9
-
o,5,o,o,o, , ,
TM. Repeat e sugas,tttD PV88U.Nt 10 TMt kleuimtutNtl Of te ep h 6 ICneca e.e se meg e, one fenoeg nti
,,,,,,,,,
"8M #8 M e tle M eetel es tateH2Hei 73 ?tle
_ _ _
a M ettwH1HG ta hleHit te theHSHet _
?3 ?t tel
_ _ _
nei i i n anninHe _
w mi.im
_
m nieHan.w _ ga g s g .,ge g
.wedt
_
M 456eH1Hel 1 M tholta;to
_
to.theH3Hviellt.1
. n H H n.,
= 4 .in H. i
_
mn.e Hw _
_
, M eSD4eH1Hel M ?SteH2Het to.?3isitt Hal OctNett coast.ct von tugt Lam etti NAt itLtPMONE kvwsta amt.copt Alan Sipe, Chairman, McGuire Safety Review Group 7, O i 4 8,7 i 5, ,4 ,1,8,3 C0eePLtil CN4 UNE SOR I.CN COMPONENT f.4Lupt patcmesp sN tMis atPoet tsp 8vstle Coup 0 Nth? n}P0g,1,ag,l gaygg g y gg g, egy,oggg, p.Ngg.C n4Pog,1,agg p
t C.WSt "'"${.C- o I I I I l i I I I i 1 l l I l l l I i l l I I I I I l l MONin p. . tam SuPPLlutNT.L mtPont IRPictID ttei vtS 199 von remeen $KpfCTfD $VOttl5SION De tti %Q l l l t . .ct ,o~, ,e .. .e. . ,w . ,s . e..,-. . ,, , . - , n.1 On July 20, 1989, Performance personnel began Post Modification Testing (PMT) to functionally verify the operation of the Outside Air Pressure Filter Train (OAPFT) fan on Train B of the Control Area Ventilation (VC) system. The OAPFT was originally designed with two 50 percent capacity fans. Because of maintenance anst reliability problems and space limitations, a Nuclear Station Modification (NSM) was written to change these fans to one 100 percent capacity fan. While performing the PMT, Performance personnel determined that both VC system Trains A and B may have been inoperable becaur,e the NSM deleted a check damper on Train B. With this check damper removed and the VC system in certain operating modes, a condition could exist where more air could be recirculated through the failed OAPFT rather than air being pulled in f rom outside. This would decrease the ability of the operating OAPFT fan to pressurire the Control Room. On September 19, 1989, Design Engineering (DE) personnel confirmed that the VC system Train A could not be justified operable with the check damper removed and isolation dampers open on Train B. Unit I was in Mode 1 (Power Operation) at 100 percent power and Unit 2
-
was in No Mode (Core Unloaded) at the time this event was discovered. This event is assigned a cause of Design Deficiency because of an unanticipated interaction of components ano a mechanical functional design deficiency. The original check damper was reinstalled in OAPFT fan on Train B. ,
.
g,. m - - - _ . -- .- . ..
.,
-
J
, g,' .a .o.
'. *
,
'
UCENSEE EVENT REPORT RER) TEXT CONTINUAT60N .
,
.
-
sem swa um.= m n am . u. u . , .... . 3
'saa b'X.' 6 Mt !
l McGuire Nuclear Station, Unit 1 anca as,wnn olslclolol3l6l9 8l9 0l2l6 0l0 0l2 OF 0 l9 j vers u . .mm >
EVALUATION:
!
Background
l There are two independent trains of the Control Area Ventilation [EIIS:VI) (VC) !
system which are designed to maintain the habitable environment in the Control Room l
[EIIS:NA), Control Room Area, and Switchgear Rooms, during normal end accident conditions. Based on these criteria, the system is designed as an Engineered i Safety Features (EST) (EIIS JE] system with absolute and carbon filtration in the ;
outside air intakes and with equipment redundancies for use as conditions require.
The Control Room is designed to be maintained at a positive pressure during an i
'
accident to prevent entry of contaminants. Prior to implementation of NSM MG-52009 each VC filter [EIIS:FLT] train assembly consisted of two 50 percent capacity ;
Control Room pressurization fans [EIIS FAN} and one filter train. Each filter !
train consisted of a pre-filter, a HEPA filter, a carbon absorber [EIIS: ABS), i controls, ductwork [EIIS DUCT), isolation dampers [EIIS:DMP), and two check dampers
[EIIS:UDMP] (see drawing on page 8 of 9). All of these components are mounted on a ,
common steel channel [EIIS:CHA) base.
.
NSM MG-52009 documented replacing the existing two 50 percent capacity fans bought l from Brad-McClung-Pace, Inc. that serve each of the two redundant OAPFTs. The i frames for the 50 percent capacity fans were weakening from stress cracks, and ;
bearing replacements were common. Based on the fact that the fans saw limited run l
- time and had preventative maintenance performed on them but still failed '
frequently, the fans were considered unreliable. Therefore, two commercial grade 50 percent capacity fans were replaced wit _h one nuclear grade 100 percent capacity fan. This modification also deleted the check damper mounted at the discharge of each OAPFT fan. The new 100 percent capacity Control Room pressurization fans supply 2000 cubic feet per minute (CFM) each, one per train. The OAPFT is provided .
'
to filter the outside air used for pressurization of the Control Room and the air .
'
l recirculated from the Control Room before being returned through the Control Room Ventalation fans (see drawing on page 9 of 9). ;
!
l Technical Specification (TS) 3/4.7.6 addresses the requirement where two , '
'
independent VC systems shall be operable in all modes. In Mode 1, Mode 2 ;
(Startup), Mode 3 (Hot Standby), and Mode 4 (Hot Shutdown), the TS requires that ;
with one train of the VC system inoperable, the inoperable train must be restored ;
to operable status within seven days or be in at least Hot Standby.within the next !
six hours, and in Cold Shutdown within the next thirty hours. In Modes 5 (Cold Shutdown), and Mode 6 (Refueling) the TS requires the following:
- a. With one VC system train inoperable, restore the inoperable train to Operable status within 7 days or initiate and maintain operation of the remaining operable VC system train in recirculation mode; and
- b. With both VC system trains inoperable or with the operable VC system train, required to be in the recirculation mode by Action a., not capable of being powered by an operable emergency power source, suspend all operations involving core alterations or positive reactivity changes.
= aces w m -
@O . _ . _ _ _ , - _ _ _ -.__,...m, ,_ - __ _ .. ,,
..,_'5-' . * ,_* __ _ __ _ _"
- -
.
.
mc men u e evetean ...u c tonv co==in
i
'
- UCENSEE EVENT REPORT (LER) TEXT CONTINUATION
maovio one wo me-me e
, (KPenet. 410m pac 6LITY esae84 m oocaat wuesten m ten wumsta tai t.00 01
" *a " $'O'.' ' ' ' S*J:
'
McGuire Nuclear Station, Unit 1 o l6 l o l 0 l c l 3 ; 6l 9 8l 9 ven; mi 0l 2l 6 0l 0 0l3 or 0 l9
. s== =ac w ana w on TS 3/4.7.6 applies to both Unit 1 and Unit 2 because the VC system is shared by both units. Also, TS 3/4.7.6 includes requirements that two independent VC trains shall be demonstrated operable at least once each 18 months by verifying a system flow rate of 2000 CFM +/- 10 percent and a Control Room positive pressure of >/=
0.125 inches water gauge, rel4tive to outside atmosphere.
On May 12, 1989, the NRC issued Amendment Number 95 to Facility opera' ting License NPF-9 and Amendment Number 77 to Facility Operating License NPF-17 for the McGuire Nuclear Station (MNS) Unit 1 and Unit 2. These amendments changed the TSs to authorize a one time extension of the allowed outage time for the VC system to provide for system modification. The allowed outage time extension was 21 days for each train, with one train inoperable at a time and one of the two MNS units in a re-fueling outage with no transport of toxic gas containers on site.
Description of Event On July 6, 1989, the VC system Train A was tested satisfactorily in accordance with procedure pT/0/A/4450/080, Control Area Ventilation Performance Test. This allowed Train B to be taken out of service for implementation of modifications. On July 10, 1989, work request 96690 was signed by Operations (OPS) personnel for NSM MG-52009 to be implemented on Train B. Train B was declared inoperable on July 9, 1989 at 1900. During implementation of the NSM, Trains A and B of the VC system were isolated from each other. On July 14, 1989, the NSM work on Train B was completed by the Bahnson Service Company. VC Trains A and B were then unisolated from each other. Unit 2 was in Mode 6 from July 14, 1989 until July 19, 1989. On July 19, 1989, Unit 2 entered No Mode.
On July 20, 1989 at 0600, Performance personnel began PMT for the Train B OAPFT fan as required by procedure TT/0/A/9100/334, Post-Modification Testing of CRA-0APFT-2 After Implementation Of NSM MG-11905, Revision 0 and NSM MG-52009, Revision 0. At 0730, the VC system had trouble maintaining the Control Room pressure in accordance with the requirements of the test procedure. At 0845, Performance personnel began 1 troubleshooting to determine if any alignment existed for which enough outside air could be pulled in to pressurize the Control Room. With Train A.OAPFT fans not operating and isolation dampers failed open, DP measurements were taken on Train A ]
OAPFT package with both check dampers closed and while holding both check dampers open. With the Train B fan operating, Performance personnel observed reverse flow through the Train A filter package.
,
This reverse flow is a flow path of lower j resistance as compared to the outside intakes. Initial reverse flow through the i filter Train A with the check damper closed was approximately 200 CFM and reverso l flow with the check damper open was approximately 675 CFM. Performance personnel !
reviewed this data with Station Management and DE personnel. Performance personnel emphasized their concern of operability which may arise if the modification is continued and irrplemented on Train A with deletion of the check damper on Train A.
With the NSM complete on Train B, the new fan without the check damper was capable of pressurizing the Control Room; however, in the condition where one OAPFT fan was operating and the other OAPFT fan had a pneumatic or power failure, the condition existed with the check damper deleted where there would not be enough outside air pulled in to pressurize the Control Room. During PMT on VC Train B, the Train B check damper was deleted; however, Train A check dampers remained installed.
l ac mm . .....m,r.. m
.
@- . . _ . . . _ - _ . _ _
__ - _ _ _ . _
^
. l 1
g' -
c.,um.....vu, .
'
UCENSEE EVENT REPORT (LER) TEXT CONTINUAT ON
-
emme o .e p-e*
,
.
sei.u w e
)
f acfLtYv toads. np D. cast asuesbet es Ltm souneen m PA.t tai !
I*a a
" t ' , "' ?.O l
!
McGuire Nucicar Station, Unit 1 ten u o l5 l 0 l 0 l 0 l 3 l 6l 9 8l 9 -
0l 2l 6 0l 0 0l4 of 0l9 I
. w. .asm mic a.-ama w on I
!
l On July 20, 1989, at 2200, OPS personnel were notified by Performance personnel {
that a possible condition on the Train A OAPFT, the operable train at the time, '
existed where reverse flow through Train B OAPFT could occur. Therefore, at 2315, the manual volume dampers were positioned to ensure the operability of VC Train A :
would be maintained while Train B was still inoperable. The red tags associated l with Removal and Restoration (R&R) number 09-876 were added to the VC Train B work '
request to ensure that when Train B was completely checked out the manual volume i dampers would be restored to their proper operable status. '
Construction and Maintenance Department (CMD) personnel initiated a Variation Notice MC-2145 on July 21, 1989, to re-install the original check damper in the VC Train B OAPTT fan. At 2030, the check damper was re-installed and checkout was completed by Instrumentation and Electrical personnel. At 2210, OPS personnel cleared the red tags and repositioned the manual volume dampers according to R&R 09-876, thereby ensuring VC Train A operability. VC Train B check damper was then ,
able to limit backflow through Trein B OAPFT if Train A OAPFT was operating. On July 23, 1989, at 0914 VC Train B was declared operable thereby allowing the modifications to begin on VC Train A.
DE personnel completed their evaluation of this condition on September 19, 1989 and determined that Train A VC could not be justified operable with the check damper removed and the isolation dampers opened or Train b VC. Therefore, it was determined that TS 3.7.6 had been violated because both VC trains were inoperable from July 14, 1989 to July 20, 1989.
Conclusion This event is assigned a cause of Design Deficiency because of an unanticipated interaction of components and a mechanical functional design deficiency. DE personnel deleted the check dampers because of an oversight. The review by DE personnel of the deletion of the two 50 percent capacity fans on each OAPFT and the replacement of one 100 percent capacity fan on each OAPFT determined that the check dampers were unnecessary. The check damper's original design criteria was twofold
- to prevent air from shott-cycling between the two 50 percent fans, and to prevent reverse flow through the filter train.
Cycling between the 50 percent fans could only occur when the adjoining fan had failed. In this case, only one fan providing 1000 CFM of air was available. This amount of air was not adequate to maintain the habitability of the Control Ro e.
The station had always considered a filter train inoperable if one of two associated 50 percent fans had failed. Because the NSM replaced the two 50 percent fans with one 100 percent fan, a check damper would not be needed to prevent short-cycling.
The second check damper design criteria was to prevent reverse flow through the OAPFT. When an OAPFT was not in operation, isolation dampers located at the OAPFT inlet and at each fan discharge prevented flow through the train. During normal plant operation, the filter train was not operated and the isolation dampers were closed. Upon fan start, the isolation dampers automatically opened. The isolation dampers " fail safe" position is open, to allow filtered air into the Control Room.
l
,ow m, *v.s. un n e r
o I I,nc e pe,e sea
- y3 esucttaa at;utatoav conomissions
, UCEj;SEE EVENT REPORT (LER) TEXT C2NTINUAT60N ***aovio one ~o mo-oios
, amats. we FactuTV hetet m occatt ,#uedSth tal g g a gymagg, ,,, pagg 43,
"** " b'A "%*.O McGuire Nuclear Station, Unit 1 o p lololol 3l 6l 9 8l 9 or 0 l9 text u . w. . min = =ne s maavim
-
0l 2l 6 -
0l 0 0 [5
,
Only during an emergency condition concurrent with a fan mechanical failure or power failure would the check dampers be required to prevent reverse flow through the failed filter train. With the modification, this condition was not known to exist until the PMT was performed.
The decision made by DE personnel to delete the check dampers on NSM MG-52009 was based on damper construction, damper quality, and pressure restriction through the filter. The check dampers are Ruskin model CBS4. They are of lightweight ;
construction, and have no internal seals. The check dampers only restrict reverse flow through the filter train, not the recirculation from the Control Room duct.
With a flow of 2000 CFM, the pressure drop through the filter train varies from 3 !
to 4.5 inches of water. Because of this pressure restriction, DE personnel stated that recirculation through the inoperable VC train recirculation duct would occur more easily than flow through the failed filter train (with or without the check damper (s)). This configuration with the manual volume dampers in the recirculation duct open, had been previously tested satisfactorily. The decision to delete the check dampers took all of these points into consideration.
,
'
If this problem had not been discovered and NSM MG-52009 was completed as designed dampers on both Train A and Train B would have been deleted. If a VC OAPFT fan was operating because of an EST actuation and the other VC OAPTT fan had a mechanical ,
failure with the isolation dampers in a fail-safe open position, this would have '
caused a condition to exist where there would be reverse flow t.? tough the failed OAPFT fan. This would have degraded the ability of the operating OAPFT fan to maintain the required Control Room pressurization of + 0.125 inches of water gauge or greater.
The original check dampers were re-installed in both OAPFT fans for Trains A and B according to Variation Notices written under NSM MG-52009.
Also, NSM MG-52282 was initiated for DE personnel to replace the check dampers with new check dampers with blade or jamb seals or both, and suitable frame and blade construction. These new check dampers would leak less than the existing dampers, thereby aiding system balancing. The amount of outside air provided to the Control Room will increase as recirculation air decreases and thereby increase the margin to maintain the positive pressure in the Control Room.
A review of McGuire Licensee Event Reports (LERs) for the past 12 months revealed two TS violation events on ventilation systems, LER 369/88-19 and LER 369/89-15, with a root cause or contributing cause of Design Oversight. Therefore, this event is considered recurring. LER 369/88-19 documented an event concerning the Hydrogen Skimmer System dampern. Corrective actions as a result of this event would not have prevented this event from occurring. LER 369/89-15 documented an event on the VC system and was discovered during the same PMT testing of NSM MG-52009 as was this event. The corrective actions as a result of LER 369/89-15 would not have prevented this current event from occurring.
LERs 369/89-06 documented a misplaced solenoid [EIIS: SOL] arrangement of valve
[EIIS:V] 1NV-459, Main Letdown Orifice Isolation, because of a Design Deficiency.
LER 369/88-28 documented misplaced solenoid valves on the Main Steam [EIIS:SB) l l
w o e n u sees 'v* * '"' "
.@,
, _ _ __ _ _ _ _ - - - - - - - - . - - -
. !
-
me. u .auctsaa ateve.tonvca ise ,
- 8 UCENSEE EVENT REPORT (LER) TEXT C NTINUATION
--
, lxPsht$. t@m Pectuft esmedt m D0ce641 wutette m Lin edWas00R fel P&OS (Si naa " t'X.' ' 'WJ McGuire Nuclear Station, Unit 1 texte.; . sm.wanca anam m o ls g o l o l o l 3 l 6l 9 8l 9 -
0l2l6 -
0l 0 0l 6 or 0l9 Isolation valves [EIIS:ISV) because of incorrect instrument detail drawings. LER 369/89-07 documented misplaced solenoid valves on the Chilled Water system
[EIIS:KM] and the Nuclear Service Water system [EIIS:BI] because of a Design Deficiency because Design Engineering personnel approved unqualified material for installation. LER 369/88-36 documented a deficiency functional design of the I'1esel Generator Starting Air [EIIS:LC] and Instrument Air [EIIS:LD] systems because of a Design Deficiency. LER 369/89-27 documented a Design Deficiency because the wrong setpoint for a DP switch in the Annulus Ventilation System
[EIJS VD) was selected. Events caused by Design Deficiencies are considered recurring problem's.
As a result of other events involving Ventilation System problems caused by Design Deficiencies, the problem of TS violations caused by Desigr. Deficiencies in general is considered to be recurring.
DE personnel are documenting the Design Bases of Safety Related Systems which included ventilation systems. This has enabled DE personnel to identify, evaluate and correct Design Deficiencies.
This event is not Nuclear Plant Reliability Data System (NPRDS) reportable.
There were no personnel injuries radiation overexposures, or releases of radioactive material as a result of this event.
CORRECTIVE ACTIONS:
Immediate: OPS personnel positioned dampers to ensure operability of VC Train A.
Subsequent: 1) CMD personnel reinstalled the original check damper in OAPFT !
fan on Train B according to Variation Notice MC-2145 ,
- 2) OPS personnel repositioned the dampers on VC Train B and maintained VC Train A operable.
- 3) CMD personnel reinstalled the original' check damper l'n OAPFT fan on Train A according to McGuire Nuclear Production Variation Notice, MPVN-999. .
Planned: 1) According to NSM MG-52282, DE will purchase check dampers with blade or jamb seals or both, and suitable frame and blade construction which will meet required specifications.
2)- Project Services personnel will ensure the new check dampers will be installed.
.
SAFETY ANALYSIS:
The function of the OAPFT fans is to maintain a positive pressure in the Control Room to prevent in-leakage of potentially contaminated (unfiltered) air. The OAPM
.
OUshe $ $ '? ' '
O t3h ___ , , ._ -- . . , - - -- - --
I 0*.
GIRC Pe.m 3364 US. afuCLt'a L 80VLOTORY COMasemeces
"' '
.
,
-
UCENSEE EVENT REPORT (LER) TEXT CENTINUATION awaovio oue no mo-oio.
. to.nis.s w a PaceLifv estaat to: 00 Cast seuessem m Len wunasen e Pact tai
"*a " 22. "'Mt McGuire Nuclear Station, Unit 1 o ls lo j o lo l3 l 6l9 8l9 -
0l2l6 0l0 0l7 or 0 l9 vent en . .e - aac e amm on fans provide outside air (required for pressutization) through the Control Room filter package. {
.
During an accident requiring pressurization of the Control Room, both trains of OAPFT receive an automatic start signal. The VC system is designed to pressurize ,
the Control Room with either train operating. The post modification testing was ;
designed to verify the proper operation of the VC system af ter modifying the i
- system. The post modification test determined that one OAPFT fan would not fully pressurize the Control Room with the check dampers removed. Therefore, the B train '
check damper was reinstalled prior to returning Train B 0/.PFT to service.
During the time that Train B OAPFT was being tested, no design basis events i
'
occurred. Had a design basis event occurred, Train A OAPFT would have been available to provide air to the Control Room for pressurization. It is unknown whether Train A OAPFT would have fully pressurized the Control Room with Train B OAPFT check damper removed. However, had a design basis event occurred while Train B OAPFT was being tested. Train B OAPFT could have been made available for ,
operation, in which case the removed check damper would not have had any impact on ;
either train's performance. ,
The principle contaminant in air leaking into the Control Room is assumed to be ,
iodine which is very conservatively modeled in dose calculations. Very low amounts of iodine would be expected to reach the area around the Control Room since this required passage through either Auxiliary or Turbine Building ventilation systems ,
or passageways.
Control Room Operator dose would be further reduced by operation of the Auxiliary .
,
Building Ventilation system which is not safety related, but has been maintained to safety standards. ?
In the event that Control Room atmosphere became unbreathable, self contained breathing apparatus respirators provided in the Control Room area could be employed. Radiation monitors in the Control Room would alert Control Room personnel of high radiation levels.
'
Had a design basis accident occurred during the post modification testing of Train !
B OAPFT, the dose to Control Room personnel would have been well within 10CFR100 limits.
The health and safety of the public were not affected by this event.
.cc ,:.n . .v . s . m , n , . - -.4 we
_ _____
_
_,
_
.
! g
-
4 .
-
']>
i
-
ORIGINAL DESIGN OF THE VC OAPFT SYSTEM PRIOR TO INSTALLATION 1
.'
E 5 g .,I Or usn Mc-szoo, i l
,
E 3
<
,
i e
- %~O R g)*"" '
[
} Ny Isolation Damper h
% l/ -
g
"
!
i eck l
{ Isolation f 8,8
, To Control Room aspe Damper F
%,,
yog ,, g g n
.
i W' **
,
1
- + - -
1 through Control Manual MM D E y R Room Area Air Volume Isolation Damper h Handling Unit A Control Room Damper Filter Unit o g
i .
Plenue "E -
h-- an Train A OAPFT
- Check Damper
/ !
l e
'
O -
l
' g e 9 a
=
3 -
O
- w 0 Train 8 OAPFT Isolation
-
I Damper
- To Control Room (8y Isolation Damper
- , Damper d C through Control E h 3 Room Area Air W *
)' Handling Unit B '
Check -
Macual l 5*
Y ""'
f Filter Unit o J Manyal c
-
Volumed K * - 5
g
..
ir
-
n2 UB -
1 I
3
'
,
i
[El Manual d Volume A
Isolation O e h=
gk [
0
'
e E g
- I -
- -.
,
t____ __._ ._______...-_ _ _ ______i-e_ + _e -._____m ,_ **_-w- w. - - , - _ _ _ - - _m _*_-.--e-ec__.w, -e,e w-_.--e.-e_ w-e--s--_.e--ws-- -
-s -e- ==_-e-
o iI -
.
]aA 5 3 , O@2df, 1 l 8 {4I g .6+ -
, . _
,
. - l _
-
.
5la g c8 B 5 h. -
js 3 JI 8
"
, ,
, ,
.
-
.
5tQ. yo e* e"ga,e*
. e- 7- e,te** n e_ e l
_e '
no R* o- o- -
' g.I B Ig
--
.
_
. - _
-
i A
r hr ,
..
.
.
.
.
.
4 .
1 .
e t t
S e n P1J 1
~ -
~
_
l e E hE5 e e
/t e t,\
t.a, t-lr e .
e oa s=
-
-
c 1 I t t I=
t..#. 0 N i n
i h n .
.
. a.
nv
[M
'
U l
r e
t t l
r e
IM
-
.
-
_
_
& i F
i F
.
.
-
.
T T F
F A
F F
h
.
.-
O '
O
-
A M n B .
.
E i n 1
39 T0 a
r i
a -
T r .
~
S92 T .
T5 .
F-FC AN -
O -
M CS VW EF
r e
p m -
-
.
.
HO
.
a T D -
N -
FO 8 n OI " I gg o -
T ' i NA t GL
.
a .
_
IL SA [* g g e \lo g
.
_
ET DS I
-
_
TI N I' m a .
N f Qg ER 3E 5 D
.
rT l. k -
uF e. c 1Nepm CA e. e -
nt h p*3 SC 1 . .
_ o. ~
( M .
nv .
~
-
g -
o -
o[
i m l
I o r o .
.
n
.
_ o a ml .
.
.
- C oe rr Ft m
o - n o . .
- F r C m l A m l 5
_
o o
o r t R
o o
o rrt tli
-
R t
_
_
l n n o U l nan o U .
o C e Caeg r - g r t h t hrn i n 1 n o u 1 o n l .
C o C omd r ron o 'h o hoa .
T t T tRM .
-
-
.
-
t
.
s* I .," 3;:~ a
, j jj j ' !:'!;!ij* a : i