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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] |
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PO Bat 488-V Cornelius, NC 280310488
'DUKEPOWER
!, . October 4',I1989 U;S.' Nuclear' Regulatory Commission Document Control. Desk'
. Washington, D.C.. 20555'
Subject:
McGuire Nuclear Station Unit 1 and 2 Docket No.' 50-369 L
Licensee' Event Report 369/89-15-01 q
t Gentlemen:
Pursuant to 10,CFRL50.73 Sections-(a)(1) and (d), attached is Licensee Event Report 369/89-15 concerning additional information discovered after submission-of the original LER. 'This report is being submitted in accordance with 10 CFR 53.73(a)(2)(1)(B) and (a)(2)(v).~ This. event is considet ' to be of no y ' significance with respect to the health and safety of th public,
+
hO cVery truly yours, l:
C}qnW&
T.L.1McConnell'
!DVF/ADcbl. q L J Attac -o I
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- s. xc: Mr. S.D. Ebneter American Nuclear Insurers P " Administrator, Region II c/o Dottie Sherman, ANI Library q U.S. Nuclear Regulatory Commission The Exchange, Suit 245 101 Marietta St., NW, Suite 2900 270 Farmington Avenue f
' Atlanta, GA 30323 Farmington, CT 06032 ~j
.j
-INPO Records Center Mr. Darl Hood '}
Suite'1500 U.S. Nuclear Regulatory Commission l
1100 Circle 75 Parkway Office of Nuclear Reactor Regulation
? . Atlanta, GA 30339 Washington, D.C. 20555 ;
Mr. P.K. Van Doorn M&M Nuclear Consultants l 1221 Avenue of the Americas NRC Resident Inspector
.New York, NY 10020 McGuire Nuclear Station
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- R.M. Glover (CNS) l T.D.-Curtis_-(ONS)
P.R.-Herran
- S.S. Kilborn-(W)-
S.E. LeRoy-R.E. Lopez-Ibanez s, J.J. Maher- ~
R.C.;Sharpe (MNS)
G.B.:Swindlehurst-K.D. Tht.nr.s-L.E. = Weaver '.
R.L. Weber .
J.D. Wylie_(PSD)-
J.W. Willis .
-QA Tech._ Services NRC Coordinator (EC 12/55)
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LICENSEE EVENT REPORT (LER)
DOCKti ssUnetR (21 raus mi FAcetgTY Naast til .
McGuire Nuclear Station, Unit 1 o l6 l0io l0l3 61 ; 9 1loFl0 l 8
""' The control Room Ventilation System Did Not Meet The Required Positive Pressure
. Because Of A Desian Oversieht SVONT OAft(5) L8R NUMBER tel M8 PORT DAf t (7) OTM4R F ACILITill fNVOLVED IB)
IIG L "8 MONTH DAY vtAR racekiT v Navas DOCIL4T NUMetRts MONTMl DAY vtAR VIAR -
g 'a %f McGuire, Unit 2 o,5go;o,og 3,7 l0 89 1l8 8j 9 0l 7 2l 2 8l9 0 l 1l5 0l1 0l 9 o,o,o,o,o, ; ,
TMit R$ PORT 18 $USMITTED PUR$UANT TO TME RtOUIM8 MENT 8 OF 10 CFR g- (cnece one er me,e e, sne ,osieweg/ 011 OPE RAfissO .
4s005 W 1 20 4021b1 20 406tel 90.78teH2Hevi 73.71thi 73.71(el R
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{ to.73teH2Het 90.73 eH2Hvill not j j 20 4064eH1He) 90.38teH2) _ ## Aage Jeddl N ,.
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[ 90.734eH2HQ 50 7SieH2HesiHA) 30.73teH2HvdiHel 20 4884eH1HNI 90 73teH2He) 20 40$leH1Hel - 90.734e H2H6dl 90.73ieH2Hal LICE 888tt CONTACT FOR TMis Ltm 112, TELEPHONE NVMSER NAME ARE A CODE Alan Sipe, Chairman, McGuire Safety Review Group 7, O i 4 8;7 i 5; ,4 i l83 ig COMPLETE ONE LINE FOR EACM COMPONENT F AILURE OtacRl880 tN TMit REPORT 113)
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CAUSE $48T EM COMPONENT MA%AC-MPO Anggt y CAvst SYST E M COMPONENT y O'
y0 " PR d j-1 I I I i i I I i 1 i I i i l l l l l l l l l l I l l l MONTM DAY YEAR SUPPLEMENTAL REPORT EXPtCTED 114)
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] v E8 in ,..me., exercreo su,4,,ss,0= 04 re, AuTRACT m or,oruo.e, ,..e-s. e.,,e.,.e.,e.<,,. .e. ,,e,. ..,,e.,nei On July 21, 1989, during post inodification flow balancing of outside air pressure filter train - 2, Performance personnel measured Control Room pressure relative to outside atmosphere and discovered that neutral pressure was the best that could be achieved in some required system configurations. The applicable Technical Specification specifies that the Control Room be maintained at a' positive pressure of at least +0.125 inches water gauge relative to outside atmosphere. The Control Room pressurization has been tested relative to the pressure in the Cable Spreading Room since initial testing and startup. This event is assigned a cause of Design Deficiency because of a design oversight. On August 19, 1989, Design Engineering personnel issued an operability evaluation for the Control Area Ventilation system, The operability evaluation stated that the Control Area Ventilation system is conditionally operable if the Control Room doors are taped and all four outside air i intakes remain open at all times. A permanent outside air reference point will be installed to ensure that future testing is accurate. Unit I was in Mode 1, Power 1- Operation, and Unit 2 was in Mode 6, Refueling, at the time this event was l' discovered.
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e 81RC Penn 300A U.e. NUCLEA3100VL AToAY COMMeml08e i, U" " - - LICENSEE EVENT REPORT (LER) TEXT CONTINUATION u ,;.oviooMeNo m so-o m p-Exmes: ews
- PactLSTY NAmt it) DoceLET NUREBtR GI LlR NUMBER fel PAOS Q) va^a -
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-McGuire Nuclear Station, Unit 1 TEXT M mese ausse is regimoit, cap asumener MC Penn WW 117) o ls j o l o l o l 3 l 6l 9 8l9 -
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i EVALUATION:
Background'
-There are two independent trains of the Control Area Ventilation [EIIS:VI] (VC) i system which are designed to maintain a habitable environment in the Control Room
[EIIS:NA), Control Room Area, and Switchgear Rooms during normal and accident '
conditions. The Control Room is designed to be maintained at a positive pressure-during an accident to prevent the ingress of contaminants.- Two 100 percent
-capacity Outside Air Pressure Filter [EIIS:FLT] Trains (OAPFT) pressurize the Control Room by providing approximately 1000 cubic feet per minute (cfm) of filtered outside air in addition to approximately 1000 cfm of filtered recirculated Control Room air.
Technical Specification (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 (WG), relative to outside atmosphere, during system operation. The VC system draws outside air from 2 locations, on the Unit 1 and Unit 2 roof. According to Final Safety Analysis Report, Section 6.4.2, positive s pressure is required to be maintained with outside intakes open at either of the two locations or both.
Description of Event
!0n_ July 20, 1989, Performance personnel began test procedure TT/0/A/9100/334, Post Modification Testing of CRA-0APFT-2, after implementation of Nuclear Station Modification (NSM)-MG-11905 Rev. O and NSM-MG-52009 Rev.0. On July 21, 1989, at 2315,.during troubleshooting and flow balancing, Performance personnel checked the Control Room pressure relative to outside atmosphere and discovered a pressure difference of -0.025 inches WG compared to a +0.15 inches WG with* respect to the cable spreading room. Performance personnel informed Management and Design Engineering personnel of the discrepancy at that time. Performance personnel wrote Problem Investigation Report (PIR) 0-M89-0163 on July 22, 1989 at 0000, concerning the reference point for the Control Room pressurization test. On July 2,4, 1989, _
- Compliance personnel requested that Design Engineering personnel perform an Operability Evaluation for the VC system. On August 5,1989, while testing 0APF"'-1 Performance personnel determined the Interior Doghouse reference point rel.ative to outside atmosphere was neutral. On August 18, 1989, all the Control Room doors except the two doors leading to the Service Building were taped to enhance, sealing capabilities of the Control Room. With the doors taped and all 4 outside air
' intakes open, a positive pressure of >/= 0.125 inches WG was maintained. Design Engineering personnel issued an Operability Evaluation on August 19, 1989, and revised it. on September 14, 1989, stating the VC system was conditionally operable I
i .w ith the conditions of operability being: ,
r l 1) Maintain a tight seal [EIIS: SEAL] on all doors (EIIS:DR] in the Control Room. All of the seams of the Control Room doors (except the two doors l
leading to the Service Building [EIIS:MF], which are pressure doors) are 1 to be t. aped with duct tape. The duct tape can subsequently be removed as a l
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' LICENSEE EVENT REPORT (LER) TEXT C3NTINUAT13N Acenoveo ove no. mo-oio.
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McGuire Nuclear Station, Unit 1 o ls j o j o j o l 3; 6l 9 8l 9 op 0l 1l 5 0l 1 0l3 0 l8 text en . , e sm.an anc s mem on ,
1 1
-long as Control Room pressurization requirements are met. The sealed ,
doors are not normally needed for emergency access and can be retaped if :)
E access:through them is required.
- 2) All four outside air intakes are to remain open except for TS required -
testing. The operating procedure for the VC system is to be modified to-specify all four intakes to be open during nonnal and accident conditions.. The operators will be required to reopen all intakes if they are closed due to the radiation monitor [EIISiHON]-detecting contaminated- I air in the duct (EIIS: DUCT] in order to maintain Control Room ;
pressurization requirements.
l Conclusion
~
This event is assigned a cause of, Design Deficiency because of a design oversight that required testing the Control Room positive pressure with respect to the Cable-
~
Spreading Room and not outside atmosphere. Since startup and initial testing of, the.VC system, Control Room pressurization had been based'cn pressure differential: ,
using the Cable Spreading Room as the reference point for the outside atmosphere ^.
The Cable Spreading Room was chosen by Design Engineering personnel because it was thought to be representative of outside atmosphere because it was not a pressurized area. . Additional reasons that the Cable-Spreading Room was chosen were that it is' relatively unaffected by outside influences, controlled by a safety related ventilation system, and the majority.of'the penetrations [EIIS: PEN] into the Control Room are from the Cable Spreading Room. The reasoning was that this boundary would be the most conservative because any degradation in pressure seals
'would most likely occur in this boundary and would be discovered during >
surveillance testing. -Also, there are no penetrations of the Control Room that communicate directly to the outside atmosphere; therefore, it was thought prudent to measure pressure with respect to interior boundaries leaking to the Control ,
' Room. However, during post modification testing after testing the Control Room relative to outside atmosphere it was discovered that the Cable Spreading Room was slightly negative with respect to outside atmosphere. The Control Room most likely has been at a negative or neutral pressure referenced to outside atmosphere since startup of the VC system. Performance personnel tested the VC system extensively from the time the PIR was written until Design Engineering issued the Operability Evaluation. Design Engineering personnel issued an Operability Evaluation on
. August 19, 1989 for the VC system, requiring the Control Room doors to remain i taped. Operations personnel issued Special Order 89-16 to instruct Operations personnel to ensure all 4 outside .ntakes are open. Operations personnel in accordance'with procedures OP/1/A/1600/10R and.10Q, Annunciator [EIIS: ANN] Response for Annunciator 1 RAD 1 and IRAD2 respectively, will be required to reopen all air intakes if they close because of the radiation monitor detecting contaminated air in the ductwork. The Control Room doors had been taped prior to special order 89-16 during testing of the VC syste:n.
4 On August 29, 1989, a working group consisting of personnel from Design Engineering, Performance, and Mechanical Engineering Services met to determine corrective actions to resolve problems with the Control Room pressurization. The working group identified several items that will improve Control Room NAC FO.W 36ea *U.S. Gto 1985-540-589 00010 V
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- P AIRC Perm Esta U.S. 8eUCLEIR E 4LULiToRY CCe818isse0se j P ~- LICENSEE EVENT REPORT (LER) TEXT CENTINUATION Ae*Rovec ous ao. mo-oio.
EXPIRES: t/31/W P ACILeTY NA484 41) DOCKET NURGER 12) L9R NUhetR (4) PA06 (31
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McGuire Nuclear ~ Station, Unit 1 TEXT M more assee 4 messed, ese adiesenet MAC Form WW I1M o l5 lo lo l0 l3 l 6l 9 8l9 -
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0l1 0 l4 or 0l8 pressurization. Design Engineering personnel and Project Services personnel will coordinate the installation of a permanent stainless steel tubing [EIIS:JBG) to a ,
sheltered outside position to provide an outside atmosphere reference point for the l Control Room. On September 7,1989, Project Services personnel issued Urgent
-Modification MG-52281 to document the installation of the permanent outside air reference point. This reference point will be shielded from the effects of wind and will provide an accurate outside atmosphere reference point to enhance future testing.
To determine if the VC system has problems that diminish air delivery to the ,
Control Room the following items will be done. Mechanical Maintenance personnel J will inspect the tornado valves [EIIS:V) to ensure that no restrictions exist in the outside air intake lines that would restrict free movement and air flow.
Performance personnel will inspect the Control Room Air Handling Unit [EIIS:AHU)
-(AHU) ducts and dampers (EIIS:DMP] for external leakage. The AHUs will be smoke tested from the Control Room AHU discharge and any significant leakage will be corrected. Performance personnel will inspect valves IVC-13 and IVC-14, Outside.
Air Intake Duct Purge Valves to ensure they are closed. Design Engineering
- personnel will evaluate the feasibility of sealing the Control Room penetrations with a non permeable sealant to increase the sealing ability at these penetrations.
The 5 Control Room doors sealed with duct tape will be sealed with RTV to improve sealing capability and seal durability. Administrative controls will be established that will require a Control Room Senior Reactor Operatar's approval prior to accessing the doors or removing the sealant.
Design Engineering and Project Services personnel will evaluate an upgrade to the remaining 4 Control Room doors that require routine access.
The highest priority items identified were replacing the duct tape with RTV and installing an outside air reference point to ensure future testing is accurate.
A review of McGuire Licensee Event Reports (LERs) for the past 12 months revealed one event, LER 369-88/19, 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 dampers. Corrective actions as a result of this event would not have prevented this event from l occurring.
l LERs 369/89-06 documented a misplaced solenoid arrangement on valve INV-459, Main Letdown Orifice Isolation, because of a Design Deficiency. LER 369/88-28 documented misplaced solenoid valves on the Main Steam Isolation valves because of
' incorrect' instrument detail drawings. LER 369/89-07 documented misplaced solenoid l valves ~ on the Chilled Water system and the Nuclear Service Water system because of l a Design Deficiency because Design Engineering personnel approved unqualified ,
material for installation. LER 369/88-36 documented a deficiency functional design !
l I
of the Diesel Generator Starting Air and Instrument Air systems because of a Design l Deficiency. This is considered a recurring problem.
This event is not Nuclear Plant Reliability Data System (NPRDS) reportable. I L a ._.. .m._ _ .
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l TLICENSEE EVENT REPORT ILER) TEXT C'!NTINUATION , A*eawso oMe ao. mo-om -
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, FA00LITY esatst H) ., DOCEST seuedBER (23 ggg g,ygggga ggi pagggg,,
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'McGuire Nuclear Station, Unit l'- o'lsjolo'lcl3l'6[9 8l 9 - ' 0l 1j 5 - Oj 1 0]5 or 0 l8' taxi n a . w. sm.w mac e mmaw nn ,
s 'There were no personnel injuries, radiation overexposures, or releases of radioactive material as a result of this event.
' CORRECTIVE ACTIONS:
Immediate:- None 'y j
?
+
"Sub'equent:
s 1)' The Control Rocs doors were taped.
- 2) Operations personnel revised procedures OP/1/A/1600/10R'and I
'10Q,' Annunciator, Response for Annunciator IRAD1 and IRAD2, to !
instruct Control Room personnel to. ensure all 4 outuide inlets +
are open in-all consitions, q 3)- , Performance personnel inspected the smoke purge _ fan to ensure ,
that no air was being drawn from the Control Room AHU plenum to:
~
the-VA system unfiltered exhaust intake through the smoke purge-exhaust fan. No loss of air was identified.
s
- 4) ' Design Engineering personnel submitted a Station Problem Report to evaluate replacing the OAPFT discharge check dampers with dampers that have improved sealing characteristics.
' Planned: 1) A permanent atmosphere reference-point will be installed in'a sheltered area outside in accordance with Urgent Modification MG-52281. '
- 2) Mechanical Maintenance personnel will inspect the tornado .l valves to ensure no additional restrictions exist in the outside intake lines. ,.
- 3) Performance personnel will inspect Control Room Air Handling Units'A and B duct / dampers for external leakage. }
- 4) Performance personnel will inspect the backflush valves IVC-13 and IVC-14 to ensure they are locked closed.
- 5) Design Engineering and Mechanical Maintenance personnel will evaluate the feasibility of using a non-permeable sealant for cable penetrations into the Control Room.
, 6) Projects, Performance, and Mechanical Maintenance personnel ll will replace the duct tape on the 5 Control Room doors with RTV.
i.
- 7) Design Engineering and Projects personnel will evaluate upgrading Control Room doors to provide a leak tight integrity.
I c NiC FORM 30eA : av.s. CPOi 1989 5D-361 000 70
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- o t. LICENSEE EVENT REPORT (LER) TEXT C3NTINUATION AneRovto on No.pm-om EMPlatt: t/31/3 -
PACILITV es4Mt til DOCKit NUMean t2l Ltm NUnetel te) PAos (3) vIAM 88 $ $ '4 1 7$N McGuire Nuclear Station, Unit 1 o l5 lo l o j o l 3 l 6l 9 8l9 -
0l1l5 -
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-SAFETY ANALYSIS:
During an accident requiring Control Room pressurization, both trains of OAPFT receive an automatic start signal. With both trains in operation-the Control Room would have been pressurized to meet design basis requirements. If one OAPFT had not started automatically, Operations Emergency procedures would have directed Operations personnel to ensure both OAPFTs were operating.
.In the event that one OAPFT was available in an accident, single train operation would have mair.tained the Control Room positive with respect to the Auxiliary Building. Single train operation would limit air ingress to the Control Room except for personnel ingress and egress.
The principle contaminant ~in air leaking into the Control Room is assumed to be iodine which in very conservatively modeled in dose calculations. Very low amounts
'of iodine would be expected to reach the area-around the Control Room since this requires passage through either Auxiliary or Turbine Building Ventilation systemp 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.
L 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.
The health and safety of the public were not affected by this event.
Additional Information is provided as a revision to this LER as a result of both trains of the VC/YC system being declared inoperable on September 4, 1989, and
! again on September 15, 1989.
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, , .. LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A*exoveo ove No. am-om j EXPIRES: 8/31/m DACILITY NAug og DOCEST NUMBER G3 LER huMBER (4) PA06 (36
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ADDITIONAL INFORMATION: ,
.On' September 3, 1989 at 0005, Security personnel received a Forced Entry Alarm on l Control Access Door (CAD) 506. CAD 506 is one of the Control Room doors that was !
required to be taped for the Control Room Ventilation System to be conditionally opa rt.bie . A Security Officer responded to the alarm at 0007, and discovered CAD l 506 open approximately 2 inches, with the duct tape pulled loose. The Security Officer opened CAD 506 at that time to determine if any personnel were on the other side of the door causing the Forced Entry Alarm. The Security Officer found no one )
on the other side of CAD 506 that could have caused the alarm. The Security Officer secured CAD 506 and replaced the duct tape on the door. The Security Officer did not notify Operations personnel.
'On September 4, 1989 at 2200, Operations personnel noticed the duct tape seal on l CAD 506 was broken. Operations personnel declared both trains of the VC/YC system i inoperable and entered Unit 1 into TS 3.0.3. At 2325, Operations personnel using I procedure RP/0/A/5710/10,'NRC Notification Requirements, made a required ,
notification to the NRC. At 2340, Maintenance personnel replaced the duct tape on l CAD 506 and Operations personnel exited Unit I from TS 3.0.3. Unit 2 was in Mode l 5, and was not required to be in TS 3.0.3. , l On September 15, 1989 at 1000, Performance personnel removed the tape from CAD 506 to determine if the Control Room would meet the required positive pressure of 0.125 inches Water Gauge (WG) with the tape missing from CAD 506. Operations personnel declared both trains of VC/YC inoperable and entered Unit I and Unit 2 into TS 3.0.3. Unit I was in Mode 1, and Unit 2 was-in Mode 3. Performance personnel determined that with the tape removed from CAD 506, the Control Room was pressurized to a positive 0.105 inches WG. At 1008, tape on CAD 506 was replaced and Unit 1 and Unit 2 were exited from TS 3.0.3.
Conclusion:
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This event is assigned a cause of Inappropriate Action because unknown personnel l took improper or inadvertent action by opening CAD 506 and breaking the duct tape l seal. The Security Officer that responded to the Forced Entry Alarm sta,ted that I
CAD 506 was open and the duct tape seal was broken when he arrived. The Security Officer opened CAD 506 to determine if any personnel had initiated the. Forced Entry l Alarm from the other side of CAD 506. The Security Officer did not.see any personnel that could have initiated the Forced Entry Alarm. The electrical lock for CAD 506 had been malfunctioning, and CAD 506 was secured by the mechanical i
lock. However, because of the sealing material added to the Control Room doors to l; enhance the sealing capability of the doors, the mechanical locks do not secure the I
doors as designed, and sometimes fail. It is possible that in this event the mechanical lock failed on CAD 506 and unknown personnel pushed CAD 506 open initiating the Forced Entry Alarm. Performance personnel stated that the duct tape could have held without the mechanical lock being engaged. No al'rms a were received c
by Security personnel to indicate CAD 506 was accessed by any station personnel.
CAD 506 was CAD secured and no personnel attempted to access CAD 506 by placing l their security badge in the Card Reader for CAD 506. Also, no alarms were received by Security personnel to indicate personnel used the Emergency Egress Button to NIC PORM 3e6A CPO 1986 4 20-359 00070 m _ 'U.S. . , _
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- LICENSEE EVENT REPORT (LER) TEXT CHNTINUAT13N u aovio ove No maaio.
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stg AL ,. My McGuire Nuclear Station,LUnit 1 o l5 lo lo l o l 3 l 6l 9 8l9 -
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0[1 0l8 or 0l8 l TENT it ausse apsse is supuso( ser esWIussW AIGC Fesse WW(1h open the door. The Security Officer that closed CAD 506 stated that he rescaled the duct tape on the door. Operations personnel subsequently discovered the duct
- tape seal broken on the door. The duct tape sealing capability was probably
' degraded when the Security Officer opened CAD 506 and came unsealed sometime between September 3, 1989 at 0007, and September 4, 1989 at 2200, when Operations personnel discovered the duct tape seal broken.
This ' event is also assigned a cause of Management Deficiency because Security Management personnel failed to-fully communicate the-importance to Security Officers reporting problems with-Control Room doors sealed with duct tape.
Security Management personnel informed Security personnel that tne Control Room doors were taped because of Control Room ventilation prs lems but did not specifically instruct them to inform Operations personnel of problems with the duct tape on the doors.
On September 15, 1989, Station Management personnel made the decision to remove the seal from CAD 506 to determic.e if the Control Room could be demonstrated to ,
maintain a positive pressure relative to outside air of >/= 0.125 inches WG as required by periodic test PT/0/A/4450/08C, Control Area Ventilation Performance Test. If the Control Area Ventilation Performance Test procedure had demonstrated a Control Room positive pressure of >/= 0.125 inches WG, then Unit I would not have actually been in TS 3.0.3 on September 4, 1989. However, the pressure test revealed a positive pressure of 0.105 inches WG, which was less than the acceptance criteria of periodic test PT/0/A/4450/08C, Control Area Ventilation Performance Test. Both trains of the VC/YC system were declared inoperable from September 15, 1989 at 1000, until 1008 when CAD 506 was-resealed with duct tape. On September 18, 1989,- Mechanical Maintenance personnel completed the placement of RTV on the Control Room dcors that previously were sealed with duct tape. On September 19, 1989, Performance personnel completed periodic test, PT/0/A/4450/08C, Control Area Ventilation Performance Test, and determined the Control Room positive pressure to be greater than 0.125 inches WG with the RTV in place.
As a result of this event, Security Management personnel informed Security l personnel that if they detect any damage to the RTV seal on the Control Room doors, <
to inform the Operations Shift Supervisor immediately.
These events are bound by the safety analysis on page 6 of 8.
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NKC FORM 366A NI , . . - . - - , - - - - _ _ -_ __ _ _- . -- - -- ..