|
---|
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
NT' A g e-( ' (.
s
, 1 . .
'*' !) uke l$urr Company
SI'#
~ Coloube Nuclear Station 6 - PO thr256 Clover. S C 23710 '
- DUKEPOWER March.9, 1990-i t
h[
p . .
1 -Document':Controi Desk i U. . S. : Muclear Regulatory CommissiGn
. Washington, D. C.' 20555-N '
Subject:
Catawba Nuclear Station Docket No.,50-413 LER 413/90-08
- - Gentlemen
- :
F.
Attached'is Licensee Event Report 413/90-08, concerning TECHNICAL SPECIFICATION VIOLATION.FOR INOPERABILITY OF A FIRE BARRIER-
. PENETRATION DUE TO DESIGN OVERSIGHT.
cThis event'was considered to be of no significance with respect'to the
. health and' safety of the public.
m _Very truly yours,
+ Tony B.-Owen Station Manager g,
keb\LER-NRC.TBO
=xc: Mr. S. D. Ebneter American Nuclear Insurers
+ Regional Adminintrator, Region 11 c/o Dottie Sherman, ANI Library U..S. Nuclear Regulator Commission The. Exchange, Fu.ite 245
- 101 Marietta Stroet, NW, Suite 2900 270 Farmington Avenue
' Atlanta, GA 30323 Farmington,- CT 06032 Mr. K. Jabbour )
M & M Huclear Consultants I 1221 Avenues of the Americas U. S. Nuclear Regulatory Commission New York,-NY 10020 Office of Nuclear Reactor Regulation Washington, D C. 20555 INPO Records Center Suite 1500 Mr. W. T. Orders
-1100 Circle 75 Parkway NRC Resident Inspector f Catawba Nuclear Station J Atlanta, GA 30339
)
. 9003160345 900309
, ;hDR- ADOCK.05000413 jj gj '
PDC 9
kerAi 30s . U S. NUCLEiJ " _EOULATOR
. Y COMM19840N
- APPROvtD OM8 NO 31e00108 1 . LICENSEE EVENT REPORT (LER) ' "a " '' O PACIL4TY 88A804 til DOCEFT asVMBER (2) PAGE m Catawba Nuclear Station, Unit 1 0 l5 l 010 l 0 l 4l 113 1 loFl 0l 9
"'' Technical Specification Violation For Inoperability Of A ,
Fire Barrier Penetration Due To Design Oversight tytNT DATE (Si Ltn NUMetRtel REPORT DAf t 171 OTHER F ACILiflES INVOLVED let MONTH DAY YEAR YEAR **NNh*' ",'Jf,$ MONTM DAY YEAR **Ciut v Names DOCatf NUMetRtsi N/A 0l5l0l0l0; i l
~ -
' 0\ 2 0 l3 9 0 9l0 0l0 l 8 0l 0 0l3 0l9 9l 0 0 # 5 1 0 lO toi l l OPE R ATING THIS RIPORT IS SUSMITTED PUR8vANT TO THE RtoulREMENTS OF 10 CFR 5. (Chera eae er more e'she fe/****adt lill
5 20 402ini 20 40sisi 30.7 ieH2H i 73 riini R 20 406tell1H6) D0.38teH1) 30. Thel (2Het 71711el ,
1101 Of010 80 asi H1Hei
- 0.wi Hei s0 7meH2Hvai gMtgsg A*;ry,r,,,
-i 20 405teH1 Hail g 90,73tel(2ilil to.73aeH2pivaiHA) M A1 f , 20 406teH1Hevt 60.73teH21(el 90.73teH2Hv6HH01 s 20 40SleH1 Hut 50.73teH2Hio) 60.73teH2Hal LICENSEE CONT ACT FOR TMit LER (12)
NiME TELEPHONE NUU8tR ARE A QQQE R.M. Glover, Compliance Manager 810 13 ft 3111- l 3121 31-7 COMPLif t ONE LINE FOR E ACM COMPONENT F AILURE OtsCatetD IN TMit REPORT l131 At' "' ##E CAust sYsitM COMPONE NT Ma% AC. TO NPR CAU48 SY$ TEM COMPONENT g "fC NPR 1 1 1 I I I I I I i i 1 I I I I I I I I I I I I I i l I SUPPLEMialTAL REPORT EXPECTED tt46 MONTH DAY YEAR l 4tS 450 yes, eennooere fM9fCTRO SUO60l$$ TON QA Til NO l l l ASSTX ACT (& amer to I400 speces i e , soproverewy Mmen senrespece typeentree hees/ (16e ,
On February 3, 1990, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, Mechanical Maintenance firestop technicians noticed that insulation had been removed from the Main Steam to Auxiliary _
l Equipment (SA) piping to the Auxiliary Feedwater Pump Turbine (CAPT). A 3/4 -
inch annular gap between the SA pipe and the calcium silicate insulation installed through firestop C-AX-217-F-26 was also noted. The firestop technicians recognized that the firestop was rendered inoperable and promotly installed cerafiber bulk material in the opening to return the fire barrier to
! operable status per Work Request 4859 SWR. The firestop was rendered inoperable when insulation removal began on January 31, 1990, to support replacement of the Electrical Heat Tracing on the SA pipe. Unit I was in Mode 5, Cold Shutdown, from the time of occurrence of the degraded firestop until the firestop was discovered to be inoperable. Previous repair and alteration of the firestop allowed the penetration to be rendered inoperable by removal of insulation adjacent to the firestop ;2netration. This incident is attributed to design oversight due to unanticipated interaction of systems and components. The Firestop Installation Specification and/or Maintenance procedure will be revised to prevent recurrence.
gC, , ... =
5 gegIC Pw m MSA
- U.S. NUCLEM C ElUL* TORY COMM19810N LICENSEE EVENT REPORT (LER) TEXT CONTINUATION uenovro oMe no. mo-oio. I L -
EXPIRES; 8'31Q -
FActLITY haast (13 DOCKtt Nue40th (21 j viaa LER NUMSER tt)
" W!'.'. ' ~
71*.3 PAGE (36 C2tawba Nuclear Station, Unit 1 0 l5 jo lo l0 l Al l l 3 TtX1 & neste essse 4 empened, use espoone r MC perm Jmd W (1h 9 l0 - Oj 0]8 -
0 j0 0l2 oF 0l9 BACKGROUND Technical Specification 3.7.11 states that all fire barrier _ penetrations
[EIIS: PEN] separating safety related areas shall be operable at all times. With ,
any of the required fire barrier penetration or sealing devices inoperable, l
within one hour either establish a continuous fire watch on at least one side of the~affected penetration, or verify the operability of fire detectors'[EIIS:XT]
on at least one side of the inoperable penetration and establish an hourly fire l
~ watch patrol.
The Fire Detection [EIIS:IC] (EFA) System monitors unattended areas of the plant for smoke or fire, and alerts personnel of the existence and location of a fire.
The EFA System is equipped with a' Central Fire Detection Panel that alerts Operators, via an alarm [EIIS: ANN], for specific zones within the plant.
Specification number CNS-1206.03-01-0002, Installation Specification-for Mechanical Piping Penetration Firestops, specifies installation methods and 8 approved materials for the construction of fire barriers for mechanical penetrations. Typically, piping [EIIS: PSP], duct, conduit,-etc. that penetrates i walls, floors and ceilings of fire barriers is smaller in diameter than the .
penetration opening. The void between the penetrating pipe conduit or duct and the penetration opening is filled with an approved silicone foam sealant' material (see Figure 1). Temporary dam materials are utilized to form the firestop during' application of the silicone foam and removed following curing.
The manufacturer of the Dow Corning RTV silicone foam used at Catawba Nuclear Station states that degradation of the foam may occur if it is exposed to temperatures greater than 400 degrees F for long term (greater than 10 days).
The' manufacturer also states that surfaces contacting the foam must be maintained between 50 and 100 degrees F for at least 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> following disbursement of the RTV silicone foam. These temperature parameters were added to Specification CNS-1206-03-01-0002-following the issuance of Problem Investigation Report (PIR) 0-C88-0263 per exempt variation notice CE-2364.
Firestop C-AX-217-F-26 is located in the floor / ceiling fire boundary between the Unit 1 Auxiliary Feedwater (CA) [EIIS:BA] Pump [EIIS:P] Room and the Auxiliary Feedwater Pump Turbine [EIIS:TRB] (CAPT) #1 Pit. Firestop C-AX-200-W-33 is located in the fire barrier wall between the Unit 1 Mechanical Penetration Room and the Unit 1 CA Pump Room. These firestops allow penetration of the Main Steam to Auxiliary Equipment [EIIS:SA) (SA) System piping to the CAPT #1. The CAPT is a part of the Emergency Core Cooling System to supply sufficient feedwater to the Steam Generators [EIIS:HX] to maintain decay heat removal to place the plant in shutdown conditions following loss of normal feedwater and essential power to the Motor [EIIS:M0] Driven CA pumps. The SA lines to the CAPT are insulated and equipped with Electrical Heat Trace [EIIS:FD] (EHT) elements arranged 90 degrees apart on the outside of the SA pipe under the insulation. The purpose of the EHT is to prevent condensate accumulation in the m , n u. . ,,, ,,
X "" .u...
[ _ _ _ _ _
u _
senc Pwen attA *
'** U.S. NUCLt3 iEIULATORY COMMrt$104 P '.
{
LICENSEE EVENT REPORT (LER) TEXT CONTINUAT13N uraovto oms No. ano+o.
. EXPIRES: 8131C 9AcaLITY esAME til DOCKET NUMDER (21 ggn Nympen tai paos (si y ~- "w :.n P
'Cztawba Nuclear Station, Unit 1 0 ls l0 j o l0 l 4l1 l 3 9 l0 Oj 0l 8 0 j0 0 l3 oF 0l9 TEXT W more gnose As segwest ass, : _ _ NMC /ome MCsAilh
- normally depressurized SA line that might cause damage or trip of the CAPT on'an g automatic start. The EHT controllers are set at 550 degrees F to maintain the
- pipe at the normal steam supply temperature to prevent thermal stresses. The SA EHT is required to maintain SA line temperature above 220 degrees F to consider the CAPT operable.
On August 24, 1988, with Unit 1 in Mode 4, Hot Shutdown, smoke was discovered in the CA Pump Room. .The smoke was originating from the Dow Corning 3-6548
- silicone foam firestop material in fire barrier penetration number C-AX-217-F-26. Mechanical Maintenance firestop personnel were contacted to
' investigate and repair the firestop per the penetration and firestop standing !
work request 4859 SWR. The Maintenance personnel found that the firestop foam ;
would flame up when the firestop dam board was removed. The dam board was replaced and the fire brigade was dispatched to extinguish the burning foam so- l that removal of the firestop could proceed. After the fire brigade extinguished the burning foam, a fire watch was established and the firestop material was removed. The problem was determined to be caused by excessive EHT temperature at the penetration _during the curing of the firestop material that was replaced nine days earlier on August 15, 1989 per 4859 SWR. After consulting with Design Engineering, it was decided to insulate the SA line through the penetration with .
calcium silicate insulation material which had previously stopped at the l firestop boundaries. This was accomplished using an exempt variation notice modification to allow insulation to penetrate the firestop. The firestop specification was revised to allow insulation to pass through the firestop on ,
piping with temperatures greater than 400 degrees F. (Firestop C-AX-217-F-26 l' was the only firestop modified in this manner prior to February 1990.) By August 25, the SA line had been insulated through the penetration and RTV ;
L silicone foam was applied in the remainder of the penetration (around the l insulation) per Work Request 4859 SWR. The fire watch was secured following the ;
curing of_the foam in the penetration, f I
On August 24, 1988, Problem Investigation Report (PIR) 0-C88-0263 was originated L -by_ Maintenance Engineering Services (MES) Production Specialist A, responsible l-for fire barrier penetrations, to investigate the problem with firestop C-AX-217-F-26 burning. The corresponding firestop on Unit 2 was inspected and i
l i no problem was found. A follow-up investigation by DE was documented on the PIR '
j' resolution on September 20, 1988, following discussions with the silicone RTV l foam manufacturer. DE indicated that Specification CNS-1206.03-01-0002 would be !
l revised to require that surfaces contacting the foam be within 50-100 degrees F during and at least 12-hours following the disbursement of the foam. The foam i
I y
manufacturer also stated that degradation of the foam could occur if the foam l was exposed to temperatures greater than 400 degrees F for an extended period (greater than 10 days). The PIR resolution recommended the initiation of a ,
l design study to identify all foamed penetrations that are affected by this temperature limit and propose a solution. Based on the information the MES Production Specialist A perceived this problem to be restricted to excessive l
l l
.a m, an m -
_ ge ,anu a
n eenc P., anna * -
' U S. NUCL & An EEIUL?t0RY C0putesiON p '"*'. , ,- OCENSEE EVENT REPORT (LER) TEXT CSNTINUATION maovt0 ous No me.oio4
)- '
3:St.t$: t'3C pace 6tTV esAut 4,#
DuCRETNUMetR Gi Lin NVMetR lts PAGE tal
"*a "MP '
_ M
- Catawba Nuclear Station, Unit 1 c o l5 l0 l0 j o l 4l1 l 3 9 l0 oF sans w, w e .emo. n.
0l 0l 8 -
0 [0 0l4 -0l9 f a ncro-> m ren m heat present during the curing of the penetration on August 15,'1988. Tho 400 ^
degrees F temperature limit was not considered to be a problem since the SA-piping isometric drawings indicated the piping at this penetration was
'L electrically heat traced to maintain the pipe. surface temperature at 220 degrees F.' The MES Production Specialist A was not aware that the EHT drawings specify
' a 550 degrees F EHT controller setpoint on the SA line at this penetration.
Also,_since previous problems of this nature had not been experienced with the.
SA line firestops, the problem was attributed to the temperature of the SA piping during cure time. PIR-0-C88-0263 was not evaluated to be reportable to ,
the NRC since the action requirements of Technical Specification 3.7.11 was complied with. +
r -EVENT DESCRIPTION E
u On January 31,:1990, Unit I was in Mode 5, Cold Shutdown, for the End of Cycle 4 (E004) refueling outage. At 0736 hours0.00852 days <br />0.204 hours <br />0.00122 weeks <br />2.80048e-4 months <br />, vendor insulation craft personnel ;
entered the CA Pump Room to begin insulation removal from the SA lines per Work Request 5088 SWR, The insulation removal was required in order to complete Work
, Request 3276 PLN to replace EHT elements on the SA lines to the CAPT. Fire barrier penetration C-AX-217-F-26 became technically inoperable when the insulation removal began due to an approximately 3/4 inch annular opening >
between the SA pipe and the calcium silicate insulation at the fire barrier penetration. This opening was made necessary due to the diameter of the four heat trace elements that are spaced 90 degrees apart around the circumference of the pipe (see Figure 2). After contacting MES Production Specialist A, the vendor insulation craft supervisor was instructed to leave the insulation in-penetration C-AX-217-F-26 and was told the firestop technicians would remove the
-insulation and foam in the firestop later. The insulation crew followed these-instructions, however they did not recognize that the fire barrier was rendered inoperable due to the removal of the insulation-up to the fire barrier penetration. The insulation removal was completed on February 2, 1990.
L On February 3, 1990, at 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />, with Unit 1 in Mode 5, firestop technicians 1-working in the CA Pump Room noticed that insulation had been removed from the SA piping'and~that there was a 3/4 inch annular gap between the SA pipe and the l
' calcium silicate insulation installed in the firestop. The firestop technicians recognized the fire barrier penetration as inoperable and promptly installed cerafiber bulk in the opening per Work Request 4859 SWR to return the fire barrier to operable status. The fire barrier was subsequently removed and i-reinstalled on February 14, 1990, to facilitate the replacement of the EHT element. During the reinstallation, cerafiber bulk was installed between the L insulation and the SA pipe to prevent recurrence of the problem due to insulation removal. This problem was documented on PIR 1-C90-0041 on February 9, 1990, and was evaluated to be reportable to the NRC since a fire watch was not established when the insulation was removed.
,, .m .. e r -. - -
194L A
y esac Perm 394A'
' U 8. NUCLEIR EEIULATORY COMMIS$lON
"*'. i ' . , -
' LICENSEE EVENT REPORT (LER) TEXT CONTINUATION movio oue ao am-om Cr.PIRES: S/31r')
PACitiTV NAME On - DOCKET NUM96R W
"^a
( "ML '"tr##
Catawba Nuclear Station, Unit 1 0l6l0jol0l4l1[3 9 [0 oF TEXT f# mene speep de msgured use eMapas/ NRC %m JOH W flh 0l 0l 8 -
0 l0 0l5 0l9 On February 23, 1990, Unit I was in Mode 0, Defueled, when firestop technicians P discovered damaged firestop foam at penetration C-AX-200-W-33 during removal of e the firestop for EHT replacement. A fire watch was established and a Technical c Specification Operability Notification Sheet was issued to Operations for the ,
inoperable fire barrier penetration. The damaged firestop foam had become hard >
and brittle due to the high EHT temperature. The fire barrier penetration was subsequently repaired by-installing 4 inches of calcium silicate insulation and cerafiber bulk in the penetration between the EHT element and the foam. This is not a reportable event as corrective action was taken upon discovery of the problem. However, to incorporate the necessary corrective actions for both events, it was included in this report.
CONCLUSION This incident is attributed to unanticipated interaction of system or component to design oversight in that the Installation Specification for Mechanical Piping Penetration firestops did not include allowable, sustained temperature limits for' the materials used in Mechanical Firestop penetrations nor teaiperature limits for foam installation and curing. These temperature limits were added to the specification on September 17, 1989, per Exempt Variation Notice CE-2364 following the issuance of PIR 0-C88-0263. It should be noted that the firestop material is capable of withstanding much greater short term temperature which are induced during testing for the required 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire rating. The remaining SA'line fire barrier penetrations are being reinstalled with insulation and cerafiber bulk extending through the penetration. A design study is being initiated to determine if any other mechanical firestop penetrations are L exceeding the 400 degrees F long term temperature limitation.
L In addition to the original Design oversight involving the long term temperature l
limits of the RTV Silicone foam material, Design oversight was involved in the L subsequent alteration on August 24, 1988, of the fire barrier to correct the temperature problem at firestop C-AX-217-F-26. The annular space between the calcium silicate insulation and the SA line, which was caused by the interference'of the EHT elements, was not recognized by DE or MES Production Specialist A as a potential problem if the insulation was removed adjacent to the firestop. This discrepancy was also not noted by the firestop technicians since after vendor insulation personnel insulated the line through the penetration the discrepancy was not visible when the firestop was sealed with !
foam. The Firestop Installation Specification and/or the Firestop Maintenance Procedure will be revised to specifically address the installation of insulated pipes through firestops. Also, other penetrations had not been identified as having the potential for high, long term temperature leading to degradation of sealant foam.
.g~ w . : . s . ev>. u n .w. w. um
ane . .m.4-- . u a aucteu sstutafony ca.urssion
~"
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION ***:ovio ous no sino-oio4 exeints; ersic FACILITY NAMG (il - DOCKET NUMSGM (2)
Lin NUMetR 16) PA06 (31 s ngy lo ' vtan .
a }iag p
f4 C2tawbaNuclearS'tatdon, Unit 1 o l5 l0 lo lo l 4l1 l 3 9 l0 -
0l 0l 8 -
0 l0 0l 6 oF 0l9 rm e --. .- a --< - ,w =c w as.ml The insulation crew responded properly by consulting MES about who would be f responsible for insulation removal in the penetration because the discrepancy was not identified ~by the insulators during insulation removal up to the fire boundary, vendor insulation personnel have received instruction on
-identification and reporting of fire barrier discrepancies.
A review of the Operating Experience Program Database during the preceeding 24 months shows that four previous Technical Specification violations have occurred ,
due to missed' fire watches (see.LER 413/88-001,413/88-021,413/89-008, 413/89-024). These LERs, with the exception of LER 413/89-024, were attributed to' inappropriate action and management deficiencies. LER 413/89-024 was ;
attributed to design deficiency due to the design selection of a fire door latch bolt mechanism that was not capable of withstanding the frequent use encountered in the door application. This design deficiency is not related to this incident, therefore this design deficiency is not considered to be a recurring.
problem.
McGuire and Oconee Nuclear Stations have been advised of this event.
CORRECTIVE ACTION SUBSEQUENT
- 1) The discrepancy in-firestop C-AX-217-F-26 was repaired using cerafiber bulk firestop material per Work Request 4859 SWR. 1 After the discovery of the discrepancy in firestop C-AX-200-W-33, a :
- 2) '
fire watch was' established and the EHT in the penetration was insulated and-the firestop was reinstalled. l
-3) The insulation' supervisor discussed this incident with the insulation-crew to report indication of fire barrier discrepa'ncies and re-emphasized the need to contact MES when working around fire-barrier- i penetrations. .
PLANNED
- 1) All four remaining heat traced SA penetrations on Units 1 and-2 will be insulated through the penetrations to prevent sustained temperature damage. q
- 2) Steam Generator Blowdown [EIIS:WI] and Nuclear Sampling [EIIS:KN]
System penetrations in the Mechanical Penetration Room will be evaluated to determine if firestop temperature limitations are affecting these penetrations.
" w.s. m, w.w.u. ~
. N' * * "
l afRC Peron W
- U S. t:UCLEAQ 3.51ULATORY C004asitet00s
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Areaovan ove no. m-oio.
EXPtT,ES: 3/31/0 FACILify 8saast (it DOCILEi NUGASER (28 LER NUGASER ($1 PA04 (31 vs'a " 20's '. '
"E*.3
- Catawba Nuclear Station, Unit 1- 0 l6 j o l0 l0 l 4l1 l 3 9 l0 -
0] 0l 8 -
0 {0 0l 7 oF - 0l9 texun . ,.,,, 0, mc r m.v on .
.3) A design study will be initiated to determine if other firestop penetrations are affected by the 400 degrees F sustained temperature limit due to system design temperature or EHT temperature and propose resolution to any problem found.
- 4) Revision of Specification CNS-1206.03-01-0002, Installation Specification for Mechanical Piping Penetration Firestops, to provide specific information regarding the installation of insulated high temperature firestops particularly with regard ~to filling of voids between the insulation and the pipe will be evaluated.
- 5) : Revision of MP/0/A/7650/09, Installation and Maintenance of Fire Boundaries ~, to provide more specific instruction with regard to installation of insulated high temperature firestops will be evaluated.
SAFETY ANALYSIS.
With respect to the fire impairment caused by insulation removal from the SA line which affected firestop C-AX-217-F-26, the firestop is conservatively assumed to be inoperable from the beginning of insulation removal on January 31, 1990,-until impairment discovery and repair on February 3, 1990. During this time,' Unit I was in Mode 5 and Mode 6 where operability of.the CA components is not required, Also the fire detection and monitoring were operational during
-this period.in the affected rooms as well as the carbon dioxide fire extinguishing system. For these reasons the likelihood of fire spread through this firestop discrepancy was small. With respect to firestop C-AX-200-W-33 a fire watch _was established upon discovery of the degraded firestop, therefore the_ Technical Specification action was complied with. Therefore, the health and safety of_the public were unaffected by this incident.
a u ! 6
'~ ,
- -c .m t
1 g.; * , --
g 4- '1
- .14C 80em Ste. . .
U B NUCLEAS LSIULETORY COMMIS$80es U "!
.' # LICENSEE EVENT REPORT (LER) TEXT C*NTINUATION ' .araoveo ove no 3ito-oio ~ -
sc " fxPIMtB: t/31/W '
?P. . .urv ni o==.1 v a m
- b. ti. v .. . .. u, r
e ,,,,, ..oo~,..<
.u ..
.. ~
m ..o. . -
j t ..-.
.- :C uswba Nuclear Station. Unit-1 0 pi l 0 l 0 l 01411 l 3 910 OF 0 l0 l 8 -
010 Ol8 ' 0l 9 4- ssxs tu m a n, < me e.eewwenc m sauv nn it n- '
O :
I FIGURE 1 .
i-g 4
4 WMt
~
_-- 4
>- s a e,e 7 >
.e<
. e. .o g t e,, . ** e. =
7o.
1
, *O
) O f
, .+e... . .
B N. /Pd 1 , . . . s.s k.
>- 'e. e . . . . . .6*
- l. ,
l- , , s. o , 6 >, e ,
> Q ,*o% 0 6 **
1 ms e,o o e*
i
., e .e , t> =* *
}--
i l-I T
h 4Q,$, QFyg [$$M ej jQ e$$.$ i O$Q FQ
us v
(8 eRC Poe NSA , U.S. teUCLEAR KEIULAt0AY ComensISBices
_4 . ,.
- UCENSEE EVENT REPORT (LER) TEXT CONTINUATION arenoveo owe No. sino-oio.
/ EXPtRES: 8/3115 -
j\ PADILITV teassa til DOCKtt sounasta G) _ Lin eeunasta ten PA05 (3) 7 vtan 58 gT,',a k 4p. Qao=ep
'? .
,.Cetawba Nucicar Station,' Unit;I OF
} o l5 l0 l0 l0 l4 l 1l3 910 -
0l0 l8 -
0-l 0 0l 9 0l9
- terr w . <. .as w=ac r mmew nn J- FIGURE 2 y.
Y$b
$ricieelealcJssurica hT / .w,- u~ _
v
/ Zumuon se.,o _& . .
?eneltn jaa Ok>shy (A.o cir<Ae b
/ 54=plieNy .)
I p
i q
x ;p 3e ,
QQ Oh0 j
N
@.OA av e o%.L O
s Oh .
C7EO oo Oc[
D cso
\~ >/ .
K e fare;<< Wa#
) RT/ Fooo-r
[vrsa,iy %mersrioa or S7 b,,e Wu) .n.sato hoa fossy Throuph fireslop