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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20024J2601994-10-0404 October 1994 LER 94-006-00:on 940913,automatic Reactor/Turbine Trip Occurred on Over Power Differential Temperature.Caused by Equipment Failure.Replaced Relay & Evaluated Failure Rate of Types of relays.W/941004 Ltr ML20029D1011994-04-20020 April 1994 LER 93-003-01:on 930925,reactor Tripped Due to Inadvertent Closure of Msiv.Caused by Inadequate Checking.Corrective Actions:Cros Throttled CA Flow & Entered Procedure EP/2/A/5000/01.W/940420 Ltr ML20046D5871993-08-17017 August 1993 LER 93-008-00:on 930718,reactor Tripped & Auxiliary Feedwater Sys Automatic Start Due to low-low-level in SG 1A. Developed General Troubleshooting procedure.W/930817 Ltr ML20045H2421993-07-12012 July 1993 LER 93-006-00:on 930612,automatic Reactor Trip Initiated by intermediate-range Channel N35 Hi Flux Reactor Trip Bistable.Caused by Blown Fuse in Channel.Entire Drawer Replaced & Channel Placed Back in svc.W/930712 Ltr ML20024G9751991-05-0909 May 1991 LER 91-004-00:on 910410,tech Spec Violation Occurred Re Containment Valve Injection Water Sys Being Inoperable. Caused by Inapropriate Action.Maint Staff Instructed Supervisors & Technicians of Correcting cause.W/910509 Ltr ML20024G7371991-04-18018 April 1991 LER 91-006-00:on 910323,nuclear Svc Water Valves Left W/O Emergency Power Supply.Caused by Inappropriate Action Due to Misreading of Operator Aid Computer (Oac) Graphics.Oac Graphics Training Will Be provided.W/910418 Ltr ML20029A3311991-02-12012 February 1991 LER 91-002-00:on 910113,reactor Exceeded 5% Power Level W/ RHR Sys Pump 1A Inoperable Due to Closed Suction Valve. Caused by Inappropriate Action & Procedural Deficiency. Incident Discussed W/Involved personnel.W/910212 Ltr ML20044B1761990-07-10010 July 1990 LER 90-013-00:on 900611,approx 5,000 Gallons of RCS Water Inadvertently Transferred to Refueling Water Storage Tank. Caused by Inappropriate Action.Proper Sys Parameters Restored & Analysis of Event performed.W/900709 Ltr ML20043G6441990-06-14014 June 1990 LER 90-008-00:on 900430,high Pressure CO2 Discharge Occurred on Auxiliary Feedwater Fire Protection Sys.Caused by Const/ Installation Deficiency in Solenoids.Solenoids Orientation Verified to Be Installed correctly.W/900614 Ltr ML20043C8951990-05-29029 May 1990 LER 89-010-01:on 880314,auxiliary Feedwater Pump 2A Discharge to Steam Generator 2A Isolation Failed to Completely Close.Caused by Design Deficiency.Mods to Actuator Torque Switch Setting increased.W/900524 Ltr ML20042G6301990-05-0909 May 1990 LER 90-025-00:on 900409,unexpected ESFs Actuation Occurred During Performance of Incore Thermocouple Testing.Caused by Deficient Procedure.Procedure Revised & Reviewed W/Personnel Lessons Learned from event.W/900503 Ltr ML20043A9271990-05-0303 May 1990 LER 89-030-01:on 890726,Tech Spec Violation Occurred Due to Shipment of Two Liners of Secondary Bead & Powdex Resin Mixture.On 891215,same Tech Spec Violation Occurred.Caused by Mgt Deficiency.Shipments suspended.W/900503 Ltr ML20042F4721990-05-0303 May 1990 LER 90-015-00:on 900402,Tech Spec 3.0.3 Entered When Both Trains of Containment Valve Injection Water Sys Rendered Inoperable.Caused by Supervisor Incorrectly Denoting Valve Position.Valves 1RN-493 & 494 closed.W/900430 Ltr ML20042F4741990-05-0303 May 1990 LER 90-006-00:on 900321,discovered That Nuclear Svc Water Sys Assured Makeup Source to Containment Valve Injection Water Sys Surge Chamber 2A Would Not Provide Adequate Flow. Caused by Clogged pipe.W/900430 Ltr ML20042E3141990-04-0303 April 1990 LER 90-002-01:on 900103,containment Air Return Fan Failed to Start During Test & Breaker FO1A in Motor Control Ctr Opened.Caused by Inappropriate Action.Measures Taken to Ensure Positions of Breakers verified.W/900409 Ltr ML20012C6881990-03-15015 March 1990 LER 90-011-00:on 900215,discovered That Control Room Doors Were More Difficult to Open than Normal.Ventilation Sys Found to Be Incapable of Maintaining Positive Pressure. Caused by Design Deficiency.Walls sealed.W/900315 Ltr ML20012C6901990-03-15015 March 1990 LER 90-005-01:on 900126,Tech Spec 3.0,3 Entered Due to More than One Power Range Nuclear Instrumentation Channel Exceeding 5% Deviation.Caused by Mgt Deficiency.Operations Procedure revised.W/900314 Ltr ML20012C3741990-03-13013 March 1990 LER 90-012-00:on 900127,central Alarm Station Operator Noted That Controlled Access Door Not Closed.Caused by Inappropriate Action Taken Which Was Unauthorized.Personnel Counseled on Importance of Sys operability.W/900313 Ltr ML20012C5091990-03-13013 March 1990 LER 90-009-00:on 900212,containment Purge Sys Heaters Not Being Verified to Be Running During Monthly Surveillance as Required by Tech Specs.Caused by Defective Procedures,Due to Incomplete Info.Procedures revised.W/900313 Ltr ML20012C5111990-03-12012 March 1990 LER 90-007-01:on 891108,discovered That Transmission Procedures Used to Perform Undervoltage Relay Tests Revealed That Test Acceptance Criteria Did Not Agree W/Tech Specs & Relays Not Being Adjusted as required.W/900316 Ltr ML20012B8121990-03-0909 March 1990 LER 90-008-00:on 900203,discovered That Insulation Removed from Main Steam Auxiliary Equipment Piping to Auxiliary Feedwater Pump Turbine.Caused by Design Oversight Due to Unanticipated Interaction of sys.W/900309 Ltr ML20012C4961990-03-0707 March 1990 LER 90-010-00:on 900205,discovered That Standby Shutdown Facility Wide Range RCS Temp Indications Had Not Been Subj to Monthly Channel Check as Required by Tech Spec 4.7.13.6. Caused by Defective procedure.W/900307 Ltr ML20012A1781990-02-27027 February 1990 LER 90-005-00:on 900126,Tech Spec 3.0.3 Entered Due to Inoperable Power Range Nuclear Instrumentation (Prni) During Unit Shutdown.Caused by Mgt Deficiency.Action Developed to Better Anticipate & Carry Out Prni calibr.W/900227 Ltr ML20006E8231990-02-14014 February 1990 LER 90-004-00:on 900104,contact Carrier Screws in nonsafety- Related Breaker Found Loose & in Bottom of Motor Control Ctr Cubicle.Caused by Mfg Deficiency.Loose Screws Secured. Part 21 related.W/900215 Ltr ML20006D4861990-02-0707 February 1990 LER 90-001-00:on 900105,unexpected Auxiliary Feedwater Automatic Startup Occurred During Periodic Cabinet Test. Caused by Procedure Deficiency.Procedures to Be Revised to Prevent recurrence.W/900207 Ltr ML20011E2281990-02-0202 February 1990 LER 90-002-00:on 900103,containment Air Return Fan 1B Failed to Start During Quarterly Test & Breaker F01A in Motor Control Ctr Discovered Open.Caused by Inappropriate Operator Action.Lockout Breakers closed.W/900202 Ltr ML20011E3951990-02-0202 February 1990 LER 90-001-00:on 891116,potential Concern Identified W/ Pressurizer Safety Valve Blowdown Being Greater than Assumed in Safety Analyses.Caused by Functional Design Deficiency. Also Reportable Per Part 21.W/900202 Ltr ML19354E0191990-01-19019 January 1990 LER 89-020-01:on 891118,Tech Spec 3.0.3 Entered & 5-month Auxiliary Bldg Ventilation Sys Inoperability Occurred as Result of Low Filter Exhaust Flow Condition on 891111.Caused by Design Oversight.Duct Will Be cleaned.W/900119 Ltr ML19354E0931990-01-18018 January 1990 LER 89-025-01:on 890922,power Lost to Condenser Circulating Water Cooling Tower Fans Due to Deenergization of 13.8 Kv Auxiliary Switchgear.Caused by Weather Conditions.Reactor Power Reduced to Maintain Condenser vacuum.W/900119 Ltr ML19354E0201990-01-18018 January 1990 LER 89-016-01:on 890913,generator 1B Power Circuit Breaker Opened,Causing Unit Runback to 54% Power & Failure of Generator Breaker Air Pressure Gauge.Caused by Equipment Failure.Pneumatic Gauge replaced.W/900117 Ltr ML19354D8261990-01-15015 January 1990 LER 89-029-00:on 891213,determined That Max Actuator Torque Switch Setting Insufficient to Overcome Friction Force Due to Age Hardening of Elastomeric Seat Matl on Bif/General Signal Corp Valve.Also Reported Per Part 21.W/900112 Ltr ML20005G4261990-01-12012 January 1990 LER 89-013-00:on 890726,two Carbon Steel Liners,Containing Mixture of Powdex & Bead Resins,Shipped to Barnwell,Sc,In Violation of Process Control Program.Caused by Mgt Deficiency.Shipment suspended.W/900112 Ltr ML20005G3061990-01-0909 January 1990 LER 89-020-00:on 890921,abnormal Degradation of Steel Containment Vessels Observed.Caused by Corrosion by Standing Water in Annulus Areas.Steel Containment Vessels Will Be Recoated During Next Refueling outage.W/900109 Ltr ML20005E4021989-12-29029 December 1989 LER 89-028-00:on 891204,steam Generator 1D Power Operated Relief Valve Did Not Close on Train a Main Steam Isolation Signal During Valve Inservice Test.Caused by Failed Fuse. Fuse replaced.W/891229 Ltr ML20011D3321989-12-20020 December 1989 LER 89-021-00:on 890821,hydrogen Skimmer Fan 2A Declared Inoperable in Order to Replace Breaker,In Response to NRC Bulletin 88-010.On 890825,breaker Tripped & Power Reduction Resumed.Caused by Inappropriate action.W/891222 Ltr ML20011D3351989-12-20020 December 1989 LER 89-027-00:on 891120,chemical & Vol Control Sys Centrifugal Charging Pump 1B Declared Inoperable Due to Inability to Maintain Sufficient Charging Flow.Cause Not determined.Power-range Detector replaced.W/891222 Ltr ML20011D2321989-12-18018 December 1989 LER 89-020-00:on 891111,low Filtered Exhaust Flow Discovered by Control Room Operators During Observation of Indications. Caused by Design Oversight Re Interaction of Sys/Components. Clothes Dryer Filters to Be modified.W/891218 Ltr ML19332E7201989-12-0606 December 1989 LER 89-023-01:on 890915,Tech Spec 3.0.3 Entered as Result of Both Trains of Control Room Area Ventilation Sys Being Inoperable.Caused by Equipment Malfunctions.Control Room & Area Pressurization Flow Rates revised.W/891120 Ltr ML19324B1141989-10-20020 October 1989 LER 89-024-00:on 890920,safety Review Group Staff Member Identified Committed Fire Door S102A as Possibly Inadequate. Caused by Design Deficiency.Fire Watch Established & Door repaired.W/891019 Ltr ML19324B4091989-10-20020 October 1989 LER 89-025-00:on 890922,13.8 Kv Auxiliary Switchgear Deenergized Resulting in Loss of Power to Condenser Circulating Water Cooling Tower Fans.Power Reduction Due to Hurricane Hugo.W/891019 Ltr ML19325C6381989-10-11011 October 1989 LER 89-023-00:on 890915,Tech Spec 3.0.3 Entered Due to Both Trains of Control Room Area Ventilation Sys Being Inoperable.Caused by Defective pre-operational Testing Procedure.Train a Control Room Damper adjusted.W/891011 Ltr ML19325C6401989-10-11011 October 1989 LER 89-016-00:on 890913,four Channels of Power Range Instrumentation Showed Greater than 5% Allowable Mismatch Between Rated Thermal Power & Nuclear Power.Caused by Equipment Failure.Pneumatic Gauge replaced.W/891011 Ltr ML19325C6441989-10-11011 October 1989 LER 89-019-00:on 890912,capability of Switches 2CA-15A & 2CA-18B Disabled Rendering Feedwater Pumps 2A & 2B Inoperable.Caused by Defective Procedure & Inappropriate Actions.Procedure Revised & Update issued.W/891011 Ltr ML19325C1961989-10-0404 October 1989 LER 89-026-00:on 890823,tested Breaker Replaced W/Traceable Breaker in Response to Bulletin 88-010.Breaker Tripped. Caused by Mfg Deficiency.Work Request Written.Item Reportable Per Part 21.W/891003 Ltr ML19327B6071989-09-20020 September 1989 LER 89-025-00:on 890922,auxiliary Switchgear Deenergized, Resulting in Loss of Power to Condenser Circulating Water Cooling Tower Fans.Caused by Inoperable power-range Instrumentation Due to Hurricane Hugo.W/890920 Ltr ML17303B1821986-12-30030 December 1986 LER 86-058-01:on 861111 & 18,overtemp Delta T Reactor Trip Occurred on Increasing Reactor Coolant Temp Rate.Caused by Spike on Potentiometer.Valve Realigned & Unit Returned to Previous status.W/861230 Ltr 1994-04-20
[Table view] Category:RO)
MONTHYEARML20024J2601994-10-0404 October 1994 LER 94-006-00:on 940913,automatic Reactor/Turbine Trip Occurred on Over Power Differential Temperature.Caused by Equipment Failure.Replaced Relay & Evaluated Failure Rate of Types of relays.W/941004 Ltr ML20029D1011994-04-20020 April 1994 LER 93-003-01:on 930925,reactor Tripped Due to Inadvertent Closure of Msiv.Caused by Inadequate Checking.Corrective Actions:Cros Throttled CA Flow & Entered Procedure EP/2/A/5000/01.W/940420 Ltr ML20046D5871993-08-17017 August 1993 LER 93-008-00:on 930718,reactor Tripped & Auxiliary Feedwater Sys Automatic Start Due to low-low-level in SG 1A. Developed General Troubleshooting procedure.W/930817 Ltr ML20045H2421993-07-12012 July 1993 LER 93-006-00:on 930612,automatic Reactor Trip Initiated by intermediate-range Channel N35 Hi Flux Reactor Trip Bistable.Caused by Blown Fuse in Channel.Entire Drawer Replaced & Channel Placed Back in svc.W/930712 Ltr ML20024G9751991-05-0909 May 1991 LER 91-004-00:on 910410,tech Spec Violation Occurred Re Containment Valve Injection Water Sys Being Inoperable. Caused by Inapropriate Action.Maint Staff Instructed Supervisors & Technicians of Correcting cause.W/910509 Ltr ML20024G7371991-04-18018 April 1991 LER 91-006-00:on 910323,nuclear Svc Water Valves Left W/O Emergency Power Supply.Caused by Inappropriate Action Due to Misreading of Operator Aid Computer (Oac) Graphics.Oac Graphics Training Will Be provided.W/910418 Ltr ML20029A3311991-02-12012 February 1991 LER 91-002-00:on 910113,reactor Exceeded 5% Power Level W/ RHR Sys Pump 1A Inoperable Due to Closed Suction Valve. Caused by Inappropriate Action & Procedural Deficiency. Incident Discussed W/Involved personnel.W/910212 Ltr ML20044B1761990-07-10010 July 1990 LER 90-013-00:on 900611,approx 5,000 Gallons of RCS Water Inadvertently Transferred to Refueling Water Storage Tank. Caused by Inappropriate Action.Proper Sys Parameters Restored & Analysis of Event performed.W/900709 Ltr ML20043G6441990-06-14014 June 1990 LER 90-008-00:on 900430,high Pressure CO2 Discharge Occurred on Auxiliary Feedwater Fire Protection Sys.Caused by Const/ Installation Deficiency in Solenoids.Solenoids Orientation Verified to Be Installed correctly.W/900614 Ltr ML20043C8951990-05-29029 May 1990 LER 89-010-01:on 880314,auxiliary Feedwater Pump 2A Discharge to Steam Generator 2A Isolation Failed to Completely Close.Caused by Design Deficiency.Mods to Actuator Torque Switch Setting increased.W/900524 Ltr ML20042G6301990-05-0909 May 1990 LER 90-025-00:on 900409,unexpected ESFs Actuation Occurred During Performance of Incore Thermocouple Testing.Caused by Deficient Procedure.Procedure Revised & Reviewed W/Personnel Lessons Learned from event.W/900503 Ltr ML20043A9271990-05-0303 May 1990 LER 89-030-01:on 890726,Tech Spec Violation Occurred Due to Shipment of Two Liners of Secondary Bead & Powdex Resin Mixture.On 891215,same Tech Spec Violation Occurred.Caused by Mgt Deficiency.Shipments suspended.W/900503 Ltr ML20042F4721990-05-0303 May 1990 LER 90-015-00:on 900402,Tech Spec 3.0.3 Entered When Both Trains of Containment Valve Injection Water Sys Rendered Inoperable.Caused by Supervisor Incorrectly Denoting Valve Position.Valves 1RN-493 & 494 closed.W/900430 Ltr ML20042F4741990-05-0303 May 1990 LER 90-006-00:on 900321,discovered That Nuclear Svc Water Sys Assured Makeup Source to Containment Valve Injection Water Sys Surge Chamber 2A Would Not Provide Adequate Flow. Caused by Clogged pipe.W/900430 Ltr ML20042E3141990-04-0303 April 1990 LER 90-002-01:on 900103,containment Air Return Fan Failed to Start During Test & Breaker FO1A in Motor Control Ctr Opened.Caused by Inappropriate Action.Measures Taken to Ensure Positions of Breakers verified.W/900409 Ltr ML20012C6881990-03-15015 March 1990 LER 90-011-00:on 900215,discovered That Control Room Doors Were More Difficult to Open than Normal.Ventilation Sys Found to Be Incapable of Maintaining Positive Pressure. Caused by Design Deficiency.Walls sealed.W/900315 Ltr ML20012C6901990-03-15015 March 1990 LER 90-005-01:on 900126,Tech Spec 3.0,3 Entered Due to More than One Power Range Nuclear Instrumentation Channel Exceeding 5% Deviation.Caused by Mgt Deficiency.Operations Procedure revised.W/900314 Ltr ML20012C3741990-03-13013 March 1990 LER 90-012-00:on 900127,central Alarm Station Operator Noted That Controlled Access Door Not Closed.Caused by Inappropriate Action Taken Which Was Unauthorized.Personnel Counseled on Importance of Sys operability.W/900313 Ltr ML20012C5091990-03-13013 March 1990 LER 90-009-00:on 900212,containment Purge Sys Heaters Not Being Verified to Be Running During Monthly Surveillance as Required by Tech Specs.Caused by Defective Procedures,Due to Incomplete Info.Procedures revised.W/900313 Ltr ML20012C5111990-03-12012 March 1990 LER 90-007-01:on 891108,discovered That Transmission Procedures Used to Perform Undervoltage Relay Tests Revealed That Test Acceptance Criteria Did Not Agree W/Tech Specs & Relays Not Being Adjusted as required.W/900316 Ltr ML20012B8121990-03-0909 March 1990 LER 90-008-00:on 900203,discovered That Insulation Removed from Main Steam Auxiliary Equipment Piping to Auxiliary Feedwater Pump Turbine.Caused by Design Oversight Due to Unanticipated Interaction of sys.W/900309 Ltr ML20012C4961990-03-0707 March 1990 LER 90-010-00:on 900205,discovered That Standby Shutdown Facility Wide Range RCS Temp Indications Had Not Been Subj to Monthly Channel Check as Required by Tech Spec 4.7.13.6. Caused by Defective procedure.W/900307 Ltr ML20012A1781990-02-27027 February 1990 LER 90-005-00:on 900126,Tech Spec 3.0.3 Entered Due to Inoperable Power Range Nuclear Instrumentation (Prni) During Unit Shutdown.Caused by Mgt Deficiency.Action Developed to Better Anticipate & Carry Out Prni calibr.W/900227 Ltr ML20006E8231990-02-14014 February 1990 LER 90-004-00:on 900104,contact Carrier Screws in nonsafety- Related Breaker Found Loose & in Bottom of Motor Control Ctr Cubicle.Caused by Mfg Deficiency.Loose Screws Secured. Part 21 related.W/900215 Ltr ML20006D4861990-02-0707 February 1990 LER 90-001-00:on 900105,unexpected Auxiliary Feedwater Automatic Startup Occurred During Periodic Cabinet Test. Caused by Procedure Deficiency.Procedures to Be Revised to Prevent recurrence.W/900207 Ltr ML20011E2281990-02-0202 February 1990 LER 90-002-00:on 900103,containment Air Return Fan 1B Failed to Start During Quarterly Test & Breaker F01A in Motor Control Ctr Discovered Open.Caused by Inappropriate Operator Action.Lockout Breakers closed.W/900202 Ltr ML20011E3951990-02-0202 February 1990 LER 90-001-00:on 891116,potential Concern Identified W/ Pressurizer Safety Valve Blowdown Being Greater than Assumed in Safety Analyses.Caused by Functional Design Deficiency. Also Reportable Per Part 21.W/900202 Ltr ML19354E0191990-01-19019 January 1990 LER 89-020-01:on 891118,Tech Spec 3.0.3 Entered & 5-month Auxiliary Bldg Ventilation Sys Inoperability Occurred as Result of Low Filter Exhaust Flow Condition on 891111.Caused by Design Oversight.Duct Will Be cleaned.W/900119 Ltr ML19354E0931990-01-18018 January 1990 LER 89-025-01:on 890922,power Lost to Condenser Circulating Water Cooling Tower Fans Due to Deenergization of 13.8 Kv Auxiliary Switchgear.Caused by Weather Conditions.Reactor Power Reduced to Maintain Condenser vacuum.W/900119 Ltr ML19354E0201990-01-18018 January 1990 LER 89-016-01:on 890913,generator 1B Power Circuit Breaker Opened,Causing Unit Runback to 54% Power & Failure of Generator Breaker Air Pressure Gauge.Caused by Equipment Failure.Pneumatic Gauge replaced.W/900117 Ltr ML19354D8261990-01-15015 January 1990 LER 89-029-00:on 891213,determined That Max Actuator Torque Switch Setting Insufficient to Overcome Friction Force Due to Age Hardening of Elastomeric Seat Matl on Bif/General Signal Corp Valve.Also Reported Per Part 21.W/900112 Ltr ML20005G4261990-01-12012 January 1990 LER 89-013-00:on 890726,two Carbon Steel Liners,Containing Mixture of Powdex & Bead Resins,Shipped to Barnwell,Sc,In Violation of Process Control Program.Caused by Mgt Deficiency.Shipment suspended.W/900112 Ltr ML20005G3061990-01-0909 January 1990 LER 89-020-00:on 890921,abnormal Degradation of Steel Containment Vessels Observed.Caused by Corrosion by Standing Water in Annulus Areas.Steel Containment Vessels Will Be Recoated During Next Refueling outage.W/900109 Ltr ML20005E4021989-12-29029 December 1989 LER 89-028-00:on 891204,steam Generator 1D Power Operated Relief Valve Did Not Close on Train a Main Steam Isolation Signal During Valve Inservice Test.Caused by Failed Fuse. Fuse replaced.W/891229 Ltr ML20011D3321989-12-20020 December 1989 LER 89-021-00:on 890821,hydrogen Skimmer Fan 2A Declared Inoperable in Order to Replace Breaker,In Response to NRC Bulletin 88-010.On 890825,breaker Tripped & Power Reduction Resumed.Caused by Inappropriate action.W/891222 Ltr ML20011D3351989-12-20020 December 1989 LER 89-027-00:on 891120,chemical & Vol Control Sys Centrifugal Charging Pump 1B Declared Inoperable Due to Inability to Maintain Sufficient Charging Flow.Cause Not determined.Power-range Detector replaced.W/891222 Ltr ML20011D2321989-12-18018 December 1989 LER 89-020-00:on 891111,low Filtered Exhaust Flow Discovered by Control Room Operators During Observation of Indications. Caused by Design Oversight Re Interaction of Sys/Components. Clothes Dryer Filters to Be modified.W/891218 Ltr ML19332E7201989-12-0606 December 1989 LER 89-023-01:on 890915,Tech Spec 3.0.3 Entered as Result of Both Trains of Control Room Area Ventilation Sys Being Inoperable.Caused by Equipment Malfunctions.Control Room & Area Pressurization Flow Rates revised.W/891120 Ltr ML19324B1141989-10-20020 October 1989 LER 89-024-00:on 890920,safety Review Group Staff Member Identified Committed Fire Door S102A as Possibly Inadequate. Caused by Design Deficiency.Fire Watch Established & Door repaired.W/891019 Ltr ML19324B4091989-10-20020 October 1989 LER 89-025-00:on 890922,13.8 Kv Auxiliary Switchgear Deenergized Resulting in Loss of Power to Condenser Circulating Water Cooling Tower Fans.Power Reduction Due to Hurricane Hugo.W/891019 Ltr ML19325C6381989-10-11011 October 1989 LER 89-023-00:on 890915,Tech Spec 3.0.3 Entered Due to Both Trains of Control Room Area Ventilation Sys Being Inoperable.Caused by Defective pre-operational Testing Procedure.Train a Control Room Damper adjusted.W/891011 Ltr ML19325C6401989-10-11011 October 1989 LER 89-016-00:on 890913,four Channels of Power Range Instrumentation Showed Greater than 5% Allowable Mismatch Between Rated Thermal Power & Nuclear Power.Caused by Equipment Failure.Pneumatic Gauge replaced.W/891011 Ltr ML19325C6441989-10-11011 October 1989 LER 89-019-00:on 890912,capability of Switches 2CA-15A & 2CA-18B Disabled Rendering Feedwater Pumps 2A & 2B Inoperable.Caused by Defective Procedure & Inappropriate Actions.Procedure Revised & Update issued.W/891011 Ltr ML19325C1961989-10-0404 October 1989 LER 89-026-00:on 890823,tested Breaker Replaced W/Traceable Breaker in Response to Bulletin 88-010.Breaker Tripped. Caused by Mfg Deficiency.Work Request Written.Item Reportable Per Part 21.W/891003 Ltr ML19327B6071989-09-20020 September 1989 LER 89-025-00:on 890922,auxiliary Switchgear Deenergized, Resulting in Loss of Power to Condenser Circulating Water Cooling Tower Fans.Caused by Inoperable power-range Instrumentation Due to Hurricane Hugo.W/890920 Ltr ML17303B1821986-12-30030 December 1986 LER 86-058-01:on 861111 & 18,overtemp Delta T Reactor Trip Occurred on Increasing Reactor Coolant Temp Rate.Caused by Spike on Potentiometer.Valve Realigned & Unit Returned to Previous status.W/861230 Ltr 1994-04-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217H0201999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Catawba Nuclear Station,Units 1 & 2 ML20216E5401999-09-0707 September 1999 Special Rept:On 990826,discovered That Meteorological Sys Upper Wind Speed Cup Set Broken,Causing Upper Wind Channel to Be Inoperable.Cup Set Replaced & Channel Restored to Operable Status on 990826 ML20212B4711999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217H0321999-08-31031 August 1999 Revised Monthly Operating Rept for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20211B1281999-08-31031 August 1999 Dynamic Rod Worth Measurement Using Casmo/Simulate ML20211A9791999-08-20020 August 1999 Safety Evaluation Granting Licensee Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section Xi,For Plant,Unit 2 ML20211F3441999-08-17017 August 1999 Updated non-proprietary Page 2-4 of TR DPC-NE-2009 ML20211C1291999-08-17017 August 1999 ISI Rept Unit 1 Catawba 1999 RFO 11 ML20210R1051999-08-0606 August 1999 Special Rept:On 990628,cathodic Protection Sys Was Declared Inoperable After Sys Did Not Pass Acceptance Criteria of Bimonthly Surveillance.Work Request 98085802 Was Initiated & Connections on Well Anode Were Cleaned or Replaced ML20210S2891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2 ML20212B4871999-07-31031 July 1999 Revised Monthly Operating Rept for July 1999 for Catawba 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 ML20210S2951999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2 ML20209H4561999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Catawba 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 ML20196A0001999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206P5201999-05-14014 May 1999 Safety Evaluation Accepting GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20206N8391999-05-0404 May 1999 Rev 16 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr ML20206R1811999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20196A0041999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20206N8261999-04-22022 April 1999 Rev 15 to CNEI-0400-24, Catawba Unit 1 Cycle 12 Colr. Page 145 of 270 of Incoming Submittal Not Included ML20205S5551999-04-21021 April 1999 Safety Evaluation Accepting Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20205N3651999-04-12012 April 1999 Safety Evaluation Accepting IPE of External Events Submittal ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206R1931999-03-31031 March 1999 Revised Monthly Operating Repts for Apr 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9521999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Catawba Nuclear Station,Units 1 & 2 ML20205P9561999-02-28028 February 1999 Revised Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20204C9111999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Catawba Nuclear Station,Units 1 & 2 ML20203A2581999-02-0505 February 1999 Safety Evaluation of TR DPC-NE-3002-A,Rev 2, UFSAR Chapter 15 Sys Transient Analysis Methodology. Rept Acceptable. Staff Requests Duke Energy Corp to Publish Accepted Version of TR within 3 Months of Receipt of SE ML20204C9161999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Catawba Nuclear Station,Units 1 & 2 ML20199K8711999-01-13013 January 1999 Inservice Insp Rept for Unit 2 Catawba 1998 Refueling Outage 9 ML20199E3071998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Catawba Nuclear Station,Units 1 & 2 ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept ML20205E9441998-12-31031 December 1998 1998 10CFR50.59 Rept for Catawba Nuclear Station,Units 1 & 2, Containing Brief Description of Changes,Tests & Experiments,Including Summary of Ses.With ML20206P2081998-12-31031 December 1998 Special Rept:On 981218,inoperability of Meteorological Monitoring Instrumentation Channels,Was Observed.Caused by Data Logger Overloading Circuit.Replaced & Repaired Temp Signal Processor ML20203A4101998-12-22022 December 1998 Rev 16 to CNEI-0400-25, Catawba Unit 2 Cycle 10 Colr ML20203A4041998-12-22022 December 1998 Rev 14 to CNEI-0400-24, Catawba Unit 1 Cycle 11 Colr ML20198B1341998-12-14014 December 1998 Revised Special Rept:On 980505,discovered That Certain Fire Barriers Appeared to Be Degraded.Caused by Removal of Firestop Damming Boards.Hourly Fire Watches Established in Affected Areas ML20196J8351998-12-0808 December 1998 Safety Evaluation Granting Relief Request Re Relief Valves in Diesel Generator Fuel Oil Sys ML20199E3221998-11-30030 November 1998 Revised MOR for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 Re Personnel Exposure ML20198E3151998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Catawba Nuclear Station,Units 1 & 2 ML20196C0251998-11-27027 November 1998 SER Accepting Clarification on Calibration Tolerances on Trip Setpoints for Catawba Nuclear Station ML20196A6881998-11-25025 November 1998 Safety Evaluation Granting Relief Request 98-02 Re Limited Exam for Three Welds ML20196D4041998-11-19019 November 1998 Rev 1 to Special Rept:On 980618,determined That Method Used to Calibrate Wind Speed Instrumentation Loops of Meteorological Monitoring Instrumentation Sys Does Not Meet TS Definition for Channel Calibration.Procedure Revised ML20195E5521998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20198E3261998-10-31031 October 1998 Revised Monthly Operating Repts for Oct 1998 for Catawba Nuclear Station,Units 1 & 2 ML20154M7661998-10-12012 October 1998 LER 98-S01-00:on 980913,terminated Vendor Employee Entered Protected Area.Caused by Computer Interface Malfunction. Security Retained Vendor Employee Badge to Prevent Further Access & Computer Malfunction Was Repaired.With 1999-09-07
[Table view] |
Text
- P Duke hurr Ccmpany (S03) S3I4000 Catuaba Nusiear Station
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February 15, 1990 Document Control Desk U.,S. Nuclear-Regulatory Commission
- Washington, D. C. 20555
Subject:
Catawba. Nuclear Station Docket No. 50-413 LER 413/90-04 Gentlemen:
Attached is Licensee Event Report 413/90-04, concerning POTENTIAL' DEGRADED POWER SOURCE DUE TO LOOSE STARTER CONTACT CARRIER SCREWS AND A MISSED PART 21 REPORTABILITY DUE TO MANUFACTURER DEFICIENCY. This report is being submitted as a Courtesy LER.
This event was considered to be of no significance with respect to the health and safety of the public.
- Very truly-yciurs, b
Tony . Owen Station Manager keb\LER-NRC.TBO
.xc: Mr. S. D. Ebneter American Nuclear Insurers
-Regional Administrator, Region II c/o Dottle Sherman, ANI Library U. S. Nuclear Regulator Commission The Exchange, Suite 245 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue Atlanta, GA 30323 Farmington, CT 06032 M & M Nuclear Consultants Mr. K. Jabbour 1221 Avenues of the American U. S. Nuclear Regulatory Commission office of Nuclear Reactor Regulation
.New York, NY 10020 Wanhington, D. C. 20555 ;/
INPO Records Center suite 1500- Mr. W. T. Orders 1100 Circle ~15 Parkway NRC Resident Inspector Atlanta, GA 30339 Catawba Nuclear Station 9002260392 900214 PDR- ADOCM 05000413:'
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- 9 ACILITV eshest 11: DOCkti soutett R I:) PAGE 4 C:tawba Nuclear Station, Unit 1 o l5 l 0 l0 l 0 l4 l tl q 1loFlnin
''' Potential Degraded Power Source Due To Loose Starter Contact Carrier Screws l And A Missed Part 21 Reportability Due to Manufacturer Deficiency j SVENT DAf t ($) LIR NUhtSER d6) REPORT DATE 176 OTMgm f ACILITits INVOLytD tti Dav vt Art
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d1 0l4 9 0 9l0 0l 0 l 4 0l0 0l2 1l 4 9l 0 o isl0 l0 io n I l l DPI h ATING THIS AEPORT 18 tutulTTED PVRSuaNT TO THE mtQuintMtNT3 of 10 C' a 5. ' Cwa eae e' **
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Courtesy LER LICEN$tt CONT ACT P0ei Tutt Lin 1121 NAME TELtPMONE NUMBER Amt A COD 6 R.M. Glover. Compliance Mananer 810l3 8 I 3111- l 3121316 COMPLtTE ONE LINE Fon ( ACH COMPONENT 8 AILunt DESCRISED IN TMit #tPORT 113i C2U58 SYSTEM COMPONENT "$%"E pl g t "fo0mT CAUS$ $ Y $T E M COYPONENT N
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t i I ! l I I I I I I I I I I l I l l l l I I I I I I I I SUPPLEMENT AL Ate 80RT E XPICTED (141 MONT ee DAY YEAR 4t$ til yet conces.,e LMPLCTRO SVShel3SION OA TEI NO g l *> 2lg glO AT.ACT-,,,.,...--,,.,.,,,-,,,,,M.,..,n.1 On January 4, 1990, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, with Units 1 and 2 in Mode 1, Power Operation, Maintenance Engineering Services (MES) personnel discovered that the contact carrier screws in a non-safety related breaker, 1MXC-F03C, had become L loose and the contact carrier was found in the bottom of the Motor Control l Center cubicle. A work request was initiated and the loose contact carrier was replaced. An MES Staff member identified five similar incidents in safety i related applications in 1988 and 1989. The vendor identified that loose contact carrier screws were discovered in June 1980, and changed the assembly process to use nylon-patch self-locking screws. On January 10, with Units 1 and 2 in Mode l 1, a Problem Investigation Report was initiated. All safety related contact carriers were inspected. All loose screwr were secured to establish a conditional operability until replacement screws are available. This incident l
is attributed to a Manufacturer's Deficiency for material selection resulting in the loosening of contact carrier screws during normal contactor operation, and l for a lack of communication due to the manufacturer identification in June 1980 l
without notification to the nuclear industry. This report is a Courtesy LER and 10CFR21 reportable.
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"" U3, NUCLEAR LEOULITORY consasesst0N UCENSEE EVENT REPORT (LER) TEXT CONTINUAT!ON APPROVED Ohlt NOS90 0W EXPIRIS: t/31/N f PACILITV esetAt ut DDCtLET NutADER 62)
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F A Nelson Electronic Class 1035U, Motor Control Center (MCC), typically consists of a string of totally enclosed, free-standing, dead front structural assemblies. Each MCC has a main horizontal 3-phase bus, which runs the entire length of the control center. Vertical 3-phase buses are connected to the horizontal bus to feed the breaker [EIIS:BRK] compartments in each structure.
Each compartment has one or more set of contact stabs which engage the vertical
! bus when pushed into place and thereby connecting the bus to the incoming
, terminals of the breaker. Plug-in combination starters and branch breakers are typical. .The starter is equipped with both stationary contacts secured within l the starter and moveable contacts mounted in the contact carrier. The contact t carrier is attached to the starter by two screws (see Attachment I). With the !
MCC bus energized and the breaker closed, the starter uses a magnetic field, l l
energized by control power, to close the contacts and supply power to the load.
Power to motor operated valves [EIIS:V] is supplied from a MCC unit equipped with one breaker and two starters. One starter is used to supply power to move l
the valve in the closed direction when its contacts are closed. Two phases are swapped on the second contact such that when its contacts are closed the valve will move in the open direction.
The starter /contactor assemblies involved in this incident are NEMA size 00, 0, !
1, and 2, manufactured by GTE/Sylvania. The assemblies are presently being supported by Joslyn Clark, Controls Division.
~
i EVENT DESCRIPTION On January 4, 1990, at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, Maintenance Engineering Services (MES) staff '
personnel discovered that the contact carrier screws for non-safety related I- breaker IMXC-F03C had become loose and the contact carrier was found in the l bottom of the Motor Control Center (MCC) cubicle. Unit I was at 100% power in i l Mode 1, Power Operation. Unit 2 was at 55% power in Mode 1, reducing power for t- repairs to valve 2BB-19A, S/G 1B Blowdown Containment Isolation. MES Staff
) personnel were in the process of performing a resistance check on the breaker I load to determine the cause of a malfunction when the loose contact carrier was !
found. Work Request (W/R) 10937 IAE was initiated and the loose contact carrier was replaced.
I On January 5, an MES Staff Member performed a Nuclear Plant Reliability Data System (NPRDS) search to identify Catawba's work history with nuclear safety related MCCs, particularly any problems associated with loose contact carrier screws. Of 71 identified work activities, from as early as 1985 to the l present, 5 work activities were for repairs associated with loose screws occurring in 1988 through 1989. (Reference W/Rs 50629 OPS, 50622 OPS, 39900 OPS, 40619 OPS, and 40575 OPS.) A search of the parts usage database by the MES Staff Member identified three additional work activities where contact carriers
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0l0 0l3 oF 0l8 Ten va== === = =,- v. ==-w wc wma nn were replaced on safety related equipment, however, the reason for the replacements could not be identified. The contact carrier manufacturer was contacted with a request for recommendations on the possible cause of the loosening screws.
On January 9, two General Engineering Documents (GEDs) were received from the t[ manufacturer addressing the loose screw incident. These documents wue used as
[
the manufacturer's internal method of notification, dated June 2 and June 19, 1980, without notification being released to the nuclear industry. The documents identified that after many operations in service the contact carrier screws can potentially loosen on the size 00, 0, 1, and 2 starters and contactors. The manufacturer's short term resolution was to use Loctite 242 on the screw threads with a tightening torque of 15 inch-pounds. The manufacturer's long term resolution was to install replacement screws that utilized a nylon patch on the screw threads as a locking device with a tightening torque of 20 inch-pounds,
- On January 10, an equipment vendor was providing training at Catawba on use of L thermal scanning equipment to-identify potential problems on MCCs. During the y training, non-safety related breakers in MCC IMXW were scanned for loose i connections. A contact carrier screw was found to be loose; one of the screws had disengaged from the contact carrier and had dropped to the bottem of the MCC cubicle. The MES Staff member used two recent incidents, the NPRDS search results, and the manufacturer's supplied information to initiate Problem Investigation Report (PIR) 0-C90-0008 identifying the potential problems.
Design Engineering (DE) was requested to review the information to identify the scope of the problem, and to make recommendations for resolution. At this time, Units 1 and 2 were operating in Mode 1 at 100% and 97% power, res,pectively.
On January 16, DE made recommendations to the station that all similar contact carriers required visual inspection for a gap between the contact carrier and the screw head to insure their operability. W/R 2157 MES was initiated to perform inspections of the 35 nuclear safety-related MCCs containing these types of contact carriers. Each MCC containing contained 7 to 60 combination ,
starters. There were 28 contact carriers found with loose screws, involving 16 of the 35 MCCs. Individual repair W/Rs were initiated to remove the affected contact carriers, inspect them for damage, and replace parts as determined necessary. All repairs were completed on January 18. Similar inspections were performed at McGuire and Oconee Nuclear Stations.
On January 17, an INP0 Nuclear Network entry was made by Duke Power (OE 3767) i identifying for the industry the potential generic concerns with loose screws on l Sylvania contact carriers due to normal operation of the contacts. The notification identified the generic concerns as being a Part 21 reportable item.
[
On January 18, a Design Engineer and an MES Staff member visited the manufacturer to discuss the findings of the Catawba inspections and to come to l
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l terms on a proposed resolution. It was concluded that the 1980 GED i recommendations would serve as the appropriate corrective action. The 20 inch-pound torque recommendat'on was verified through the manufacturer at this time, although it is not stated in any of the manufacturer's literature.
On January 25 DE issued an operability evaluation in response to PIR 0-C90-0008
. identifying all applications utilizing size 00, 0, 1, and 2 Sylvania starters and contactors as being conditionally operable. This determination was based on the results of te initial inspection and tightening activity. The evaluation ,
required that the contactors be inspected monthly to insure continued operable status until the contact carrier screws are replaced with nylon-patched screws.
The evaluation required that the screws be replaced prior to the end of the 1990 refueling outages for their respective Units. The evaluation also concluded that as long as one of the two screws in the contact carrier is tight, the contact is capable of performing its intended function. With two screws loose it becomes difficult to determine if the contacts will function properly. The
The inspection of all non-safety related MCCs was completed on January 25. ,
Parts were replaced as determined necessary and any loose screws were secured.
The nylon-patch self-locking screws were not used during this inspection.
CONCLUSION This incident is attributed to a Manufacturer's Deficiency for material selection resulting in the loosening of contact carrier screws during normal contactor operation. Also, this incident is attributed to a Manufacturer's Deficiency for lack of communication due to the manufacturer's identification of the potential problem in June 1980, but not communicating the information to the nuclear industry. At the time of the original problem identification, the manufacturer initiated the replacement of the contact carrier screw with nylon-patch self-locking screws within the assembly process for the size 00, 0, 1, and 2 contacts. All' size 00, 0, 1, and 2 Sylvania contact carrier screws are to be replaced with the nylon-patch self-locking screws to comply with the manufacturer's recommendations. Contributing to the lack of communication is a Manufacturer's Deficiency due to lack of doct. mentation in that assembly drawings supplied in part as maintenance instructions do not identify the type of screws required, nor do they identify the torque required to secure the screws.
l L
A search of the Operating Experience Program (0EP) Database identified one l previous incident within the past 24 months involving a manufacturer deficiency l relating to material selection (reference LER 413/88-005). Non-environmentally qualified terminal blocks were supplied with the cold leg accumulator discharge isolation valve motor operators. The cause of this incident was attributed to the manufacturer / supplier not meeting the material requirements of an approved Duke Power specification. No similar specification restricted the type of j
screws to be supplied with the Sylvania Contacts, therefore, these incidents are l
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v2 wucttaa tsouutoav commesion UCENSEE EVENT REPORT (LER) TEXT C;NTINUATION movro oue no mo-om LKPinES. $!3UW FAestliv haut tu oocket Nuutta un ggn wyugga ig3 pagg ggi viaa " M W. 'T.?:
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! not conside' red similar. At the purchase of the Sylvania contacts, the manufacturer supplied equipment was expected to be acceptable for service
(
p without any expectations of equipment failure. The manufacturer failed to l properly communicate to the industry upon discovery that the original screws l supplied with their equipment were deficient. A search of the OEP database for the past 24 months did not reveal any similar incidents where a manufacturer l failed to communicate to industry the discovery of a manufacturing deficiency.
A manufacturer lack of communication is not considered to be a recurring problem.
t i A search of the OEP database identified two previous incidents within the past l
24 months involving a manufacturer deficiency relating to deficient documentation (reference Station Report C89-004 and LER 413/89-022). The first j incident involved the Component Cooling Water Surge Tank Level Instrumentation j j which was determined to not meet its equipment environmental qualifications. A
- manufacturer deficiency in not providing accurate, available information on the
! environmental qualification requirements contributed to this incident. The ;
second incident involved a failure of a gasket on a main feedwater valve ;
positioner control air manifold. The gasket failure was attributed to a lack of ;
i torque information in the manufacturer's maintenance instruction and a marginal gasket design. Two recent notifications also addressed manufacturer deficiencies relating to documentation (reference IEN 88-057 and IEN 89-062).
The first notification identified that maintenance instructions were missing critical torque requirements for replacement screws on 25 KVA Invertors, j resulting in a potential loss of safe shutdown equipment. The second notification identified that maintenance instructions were missing critical disc adjustment instructions for swing check valves, resulting in improper seating and excessive seat leakage. A manufacturer's lack of providing complete documentation is considered to be a recurring problem. Design Engineering i performs a review of all information received from manufacturer's, in an attempt
! to verify all information is complete and accurate. The manufacturer's information is made available to the station in controlled documents and is revised as more accurate or complete information is obtained. When it is determined that the provided information is deficient by various methods of identification (station review, design evaluation, vendor notification, industry bulletins, etc.), the affected work groups are notified and the affected
. documents are revised.
This report is submitted as a Courtesy LER in that operability of some safety equipment could be affected (pending the outcome of the ongoing operability evaluations). Pursuant to 10CFR21, in-service Sylvania contact carriers are i considered " basic components"; the potential for carriers screws to loosen is considered a " defect"; and existence of a " substantial safety hazard" is dependent upon the particular equipment affected and its operability.
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CORRECTIVE ACTION f SUBSEQUENT
- 1) PIR 0-C89-0008 was initiated identifying a generic problem with loose I screws on size 00, 0, 1, and 2 Sylvania Contact Carriers.
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- 2) An inspection was performed of all nuclear safety related MCCs and loose screws were secured. 1
$ 3)- Station and General Office Personnel visited the manufacturer to
$ address the generic concerns and develop'a resolution.
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@. 4) DE issued an operability evaluation identifying alt size 00, 0, 1, and ,
5 2 Sylvania Contacts as conditionally operable, identifying compensatory actions for continued operation through the 1990 f? refueling outages on the respective Units.
- 5) Procedure IP/0/A/3850/09, Inspection and Maintenance Procedure For MCC l Breakers, has been revised to identify the nylon-patch self-locking screw for use in the size 00, 0, 1, and 2 Sylvania contact carriers.
, Proper ider,eification of the required torque valve is be included in
,[ the procedure. ,
- PLANNED
- .1) All contact carrier screws in size 00, 0, 1, and 2 Sylvania contacts, in safety and non-safety related applications, are to replaced with the nylon-patch self-locking screws.
- 2) All breakers, where loose screws were discovered during the inspection, will be evaluated for past operability.
- 3) Instruction manual CNM 1314.01-0140 will be revised to identify the nylon-patch self-locking screw for use in the size 00, 0, 1, and 2 Sylvania contact carriers, b 4) The MCC Breaker Testing and Preventive Maintenance Program will be expanded to include all MCCs, and will include inspection for loose screws.
,. 5) The Safety Analysis of this report will be revised upon completion of the Design Engineering Past Operability Review.
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0l0 +0l7 OF 0 l8 SAFETY ANALYSIS During the Design Engineers and MES Staff Member visit at the manufacturing facility on January 18, discussions with their Engineer and Quality Assurance Personnel revealed the following: '
p t 1) Loosening of screws on NEMA size 00 through size 2 contactors was
- documented to have occurred in only two instances.
f L 2) Contact carrier screws will not loosen on NEMA Size 3, and above, r contactors since their design includes a lock washer installed under i the screw head.
I 3) Since beginning the use of screws with a nylon patch on the threads, ,
on approximately June 19, 1980, no instances of loose screws have been reported on contactors equipped with the modified screw design, i The extent that loose contact carrier screws would affect a contactor's ability to perform its function was also discussed with the manufacturer. As long as one screw is tight, the contactor will operate properly. With both screws h loose, but with threads still engaged, it is highly probable that the contactor will function properly, although contact carrier binding can not be totally excluded. It is impossible to conclusively determine if the contactor wili
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function properly with both screws loose or if one screw is missing (no threads
- engaged) and the other is loose. Visual inspection and contactor operation is i the only means to determine operable status if one screw is missing and the other is loose or if both screws are loose.
i The majority of the contact carriers were found to have at least one screw tight during the visual inspection. Through further discussions with the Design Engineer, a screw that turned 1/4 revolution or less during the inspection and
- tightening process is considered to have been sufficiently tight for contactor operation. With this consideration, of the 28 breaker units originally i
identified with loose contact carrier screws, the possibility still existed that 10 breakers might not function properly. Design Engineering is in the process of completing a past operability review for each breaker and associated equipment effected by loose contact carrier screws. This Safety Analysis will be revised upon completion of that review.
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