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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
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- Duke twtr Company yy,y y,4999 Cutatrba NuclearStation (L * /*O thr 2% .
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'\ DUKE POWER L . March.13,.1990 Document Control Desk' U. S. Nuclear Regulatory Commission Washington, D..C. 20555
Subject:
Catawba Nuclear Station Docket No. 50-413 LER 413/90-09 Gentlemen:
Attached is' Licensee Event Report 413/90-09, concerning TECHNICAL SPECIFICATION VIOLATION FOR INOPERABLE CONTAINMENT PURGE SYSTEM DUE TO m INCOMPLETE PROCEDURES.
This event was considered-to bc of no significance with respect to the health and safety of the public.
I ti Very truly yours, q Tony B. Owen Station Manager kob\LER-NRC.TBO i xc: Mr. S. D. Ebneter American Nuclear Insurers Regional Administrator, Region II c/o Dottie Sherman, ANI Library !
U S. Nuclear Regulator Commission The Exchange, Suite 245 j 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue !
Atlanta, GA 30323 Farmington, CT 06032 l l
.M & M Nuclear Consultants Mr. K. Jabbour 1221 Avenues of the Americas U. S. Nuclear Regulatory Commission j New York, NY 10020 ofCice of Nuclear Reactor Regulation. j Washington, D. C. 20555 INPO Records Center Suite 1500 Mr. W. T. Orders 1100 circle 75 Parkway HRC Resident Inspector Atlanta, GA 30339 Catawba Nuclear Station ff 9003220096 900313 m M t PDR ADOCK 05000413 /
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, esRC Poem MS U S. NUCLE AS RE;ULATORY C0edMegetDes APPROVED OMS NO 31E64100 LICENSEE EVENT REPORT (LER) * *a' * 8" )
f ACILITV NanAE (11 DOCKET peua4SER (2) PAGE Gl Catawba Nuclear Station, Unit 1 _ _ _ _ o l 6 l 0 ] 0 l 0 l 4 l 1 l3 1 lorl 0 l5
' " ' ' ' ' ' Technical Specification Violation For inoperable Containment ,
Purge System Due to Incomplete Procedures IVENT DATE (S; LER NUh8SE R ($1 51EPORT DAff 176 OTHER F ACILITIES INVOLVED (0)
MONTH DAY YEAR YEAR uy O ' MONTH DAY YEAR F ACILITv h AMEs DOCKET NUM9ERt$l n ,
CNS, Unit 2 015101010 41 l 114
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NAME TELE. HONE NUM8tR ARE A COD 4 R.M. Glover, Compliance Manager 8 10 13 81311 I l31 21 316 COMPLEf t ONE LINE FOR E ACM COMPONENT F AltS8Rt DESCRiS10 IN THi$ fiEPOts' (13l REPORTA LE p g y MA P TA E s CAUSE 8YSTEM COMPONENT NgfjC.
! I I I I I I I I I I I I I I I I I I I I I I I I I I I SUPPLEMENT AL REPORT EXPECTED E14 MONTH DAY YEAR SUSMiS$10N YES fit v.s. comet. EMPECTED SUOMIS$10N DA TEJ NO l l l A.nRACT,..,...,......,,,,,..,,..,,,,,,,,,,
On February 12, 1990, at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, with Unit 1 in Mode 0, Defueled, and Unit 2 in Mode 1, Power Operation, a Performance and an Operations Engineer noted, during a review of ventilation procedures, that the Containment Purge (VP) System heaters were not being verified to be running during the monthly surveillance required by Technical Specifications. Although the relative humidity (RH) controller, which controls the automatic operation of the beaters, was being adjusted with the intent of automatically running.the heaters, a review of past test data revealed that RH never exceeded 50% (except for the first two tests on Unit 1, and one test on Unit 2). Since the operating band of the controller is 50% to 100% RH, it was evident that the heaters were never energized during the tests, which have been used since initial startup.
This incident is attributed to defective procedures, since the operation of the heaters was not being verified. The Unit 1 VP System was declared inoperable (Unit 2 VP was previously inoperable), and was properly retested. The procedures have been revised to ensure the heaters are operating.
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(XPlRES: $/31/O F ACILITY NAME tti . DOCKLT NUM96R Q1 LtR NUMSER461 PAGE (3#
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0l 0 0l2 oF 0 l5 4 TEXT $/ tmwo apen de segure4 use e#eou/ NAC Fem JESCsJ(1D h BACKGROUND
- s. The Containment Purge [EIIS:VA] (VP) System is designed to maintain the Containment environment within acceptable limits for personnel access during 0 inspection, testing and maintenance activities, and to limit the release of any 1
contamination to the environment. The VP System uses two 50% capacity supply 3
air handling units and two 50% capacity exhaust filter [EIIS:FLT] trains.
During VP operation, purge exhaust heaters [EIIS:EHTR] are automatically staged on as necessary to maintain the relative humidity (RH) of air passing through L cxhaust filters below 70%. Three humidity sensors are located downstream of the
~
purge exhaust heaters. Two of these (instrument loops VP5670 and 5680) function to isolate VP on high (>70%) RH, and the third loop (VP5690) functions to control the purge exhaust heaters.
Technical Specification 3/4.9.4, Containment Building Penetrations, requires I Containment penetrations [EIIS: PEN] to be either closed, or exhausting through an operable VP System using HEPA filters and activated carbon adsorbers, during core alterations or during movement of irradiated fuel within Containment.
Technical Specification Surveillance Requirement 4.9.4.2a states that the VP i I
System is demonstrated to be operable "At least once per 31 days by initiating flow through the HEPA filters and activated carbon adsorbers and verifying that i the system operates for at least 10 continuous hours with the heaters l operating". Technical Specification Bases state that " Operation of the system j with the heaters operating to maintain low humidity using automatic control for at least 10 continuous hours in a 31 day period is sufficient to reduce the i buildup of moisture on the adsorbers and HEPA filters". PT/1(2)/A/4450/01, Containment Purge Periodic Test is used to perform this surveillance. After verifying flow through both filter units, the procedure was to adjust 1(2)
VPP5690, CPFU Entering Air RH Controller [EIIS:XC] from its normal setpoint of approximately 60% RH, to 65% RH, with the intent of automatically running the heaters,1(2)HETR0528. After running VP on the filter mode for a minimum of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, and recording flow, differential pressure (d/p) and RH every two hours, the humidistat, 1(2)VPP5690, was readjusted to its initial setpoint.
EVENT DESCRIPTION.
On February 12, 1990, at approximately 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />, with Unit 1 in Mode 0, Defueled, and Unit 2 in Mode 1, Power Operation, a Performance and an Operations Engineer noted, during a review of VP procedures, that PT/1(2)/A/4450/01 did not ensure that the VP heaters were operating (or would operate) during the monthly surveillance. This procedure review was within the scope of the ongoing effort of the System Expert Program, to review systems and related procedures to ensure that the intent of Technical Specifications and the FSAR is being met. When reviewing past test data, it was found that all tests (except the first two on Unit 1, and one test on Unit 2) recorded less than 50% RH during the test.
Since the heater controller,1(2)VPP5690, has an operating range of 50% to 100%
RH, it was evident that the heaters were not energized during the tests. These procedures have been used since initial startup. By 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />, both A and B i
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EDIRES: 8/31/98 -
FACluTY NAME (11 ,- DOC 9LET NuM.ER (2) g, ggp a -- mm wn C:thwba Nuclear Station, Unit 1 0 l5 l0 j o lo l4 l 1l 3 9l 0 0l0 l 9 oF 0l 0 0l3 0l 5 g- ran a a-. .= = ==w. w =c w.m E
O Trains of the Unit 1 VP System were declared inoperable (both Unit 2 VP Trains
" were already inoperable, due to Unit 2 being in Mode 1, with VP Containment
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Isolation Valves [EIIS:V] failed closed. Technical Specification 3.6.1.9 L requires these valves to be sealed closed in Mode'1, Mode 2, Startup, Mode 3,
< Hot Standby, and Mode 4, Hot Shutdown).
On February 25, 1990, PT/1/A/4450/01 was performed using a revised method:
4 rather than adjusting the controller to attempt to operate the heaters, a high humidity signal was simulated at the heater controller, IVPP5690, and the heaters were verified to be operating every two hours. During the last hour of the 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test, however, a heater contactor failed, and Work Request 11126 IAE was. initiated. After installing another contactor, it was found that the master controller for the heater unit was not maintaining voltage, causing the contacts
. to chatter. The controller was replaced, and PT/1/A/4450/01 was successfully performed on February 26 and 27, prior to refueling. Both trains of the Unit 1
" VP system were restored to operable status by 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />, on February 27.
^
CONCLUSION This incident is. attributed to defective procedures, due to incomplete information. PT/1(2)/A/4450/01 did not contain steps to ensure that the heaters were operating during the continuous 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test. These procedures have been
- revised to include such steps; a high humidity signal is now simulated at 1(2)VPP5690 to ensure that the heaters operate, and current readings are taken every two hours to verify their operation. The revised PT/2/A/4450/01 will be performed to verify Unit 2 VP System operability. Other safety-related ventilation procedures were reviewed.to see if a similar test method was being used, and it was found that heater operation was being properly verified by observing differential temperatures in these procedures. A Station Problem Report (SPR #CNPR-04721) has been initiated to facilitate testing, proposing that heater circuitry _be modified so that all four heater banks of 1HETR0528 are energized when the recirculation damper is fully closed, and that thermometers be_ installed upstream and downstream of the heaters.
A review of the Operating Experience Program shows another event involving VP equipment operation using an incomplete procedure, resulting in a Technical Specification Violation (see LER 414/89-006). This previous event involved the s
automatic opening of the VP Containment Isolation Valves due to a defective l
operating procedure not accurately describing the restart of the VP System.
l Technical Specification violations involving ventilation systems are a recurring l problem, and to deal with this, an extensive review of ventilation systems and l- associated procedures is currently in progress at Catawba, which will verify L that ventilation system testing is meeting the intent of Technical ,
Specifications, the Final Safety Analysis Report (FSAR), and Regulatory Guides dealing with ventilation systems. In LER 414/89-020, which described a Technical Specification 3.0.3 entry due to a clogged air flow monitor, a l comprehensive response was developed to deal with ventilation system problems l, _ __ _
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LICENSEE EVENT REPORT (LER) TEXT C5NTINUATION uri.ovio ou8 uo mo_om ErhRES;8/01/4 f ActuTY NAME O) DOCKET NUMSER (2,
, LER NUM84R (8) PACE (31
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Cttiwba Nuclear Station, Unit 1 o l5 lo jolo 4 llj 3 9l 0 -
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0l 0 0l 4 or 0l5 Tnn tu mm n w. .a w ec r,,,, w,, m, I involving design deficiencies. Although this incident does not involve a design t deficiency, parts of the comprehensive response initiated in LER 414/89-020 will
- r. ensure that ventilation system testing is meeting design requirements:
I, Performance, Operations and Design Engineering will review available plant parameters for addition to the Performance Monitoring Database System to enhance the analysis and trending of ventilation systems performance data. Also, Design 3
L a Engineering will initiate a thorough and systematic review of ventilation system i design requirements and compare them against nominal operating data to ensure consistency with the FSAR and Technical Specification parameters.
CORRECTIVE ACTION SUBSEQUENT
- 1) Unit 1 VP system was declared inoperable.
- 2) Procedures PT/1,2/A/4450/01 were revised to verify that the heaters are on.
- 3) The revised PT/1/A/4450/01 was performed, and the Unit 1 VP System was returned to operability.
, 4) An SPR was initiated, proposing modifications which would facilitate VP testing.
- 5) Other safety-related ventilation procedures were reviewed to see if a similar test method was being used, and it was found that heater operation was being properly verified by observing differential temperatures.
PLANNED
- 1) The revised PT/2/A/4450/01 will be performed to verify Unit 2 VP System operability.
- 2) Performance, Operations, and Design Engineering will review available plant parameters for addition to the Performance Monitoring Database System to enhance the analysis and trending of ventilation systems (as well as other systems) performance data (from Planned Corrective Action 13, LER 414/89-020).
- 3) Design Engineering will initiate a thorough and systematic review of ventilation system design requirements and compare them against nominal operating data to ensure consistency with the FSAR and Technical Specification parameters (from Planned Corrective Action 14, LER 414/89-020).
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3 l 4) An extensive review of ventilation systems and associated procedures is currently in progress at Catawba, which will verify that
. ventilation system testing is meeting the intent of Technical
- Specifications, the FSAR, and Regulatory Guides dealing with ,
ventilation systems. I SAFETY ANALYSIS.
The Bases for Technical Specification 3/4.9.4 state that " Operation of the system with the heaters operating to maintain low humidity using automatic ,
control for at least 10 continuous hours in a 31 day period is sufficient to 3- reduce the buildup of moisture on the adsorbers and HEPA filters". The VP exhaust heaters are used to satisfy this requirement. In addition, during VP operation, the exhaust heaters are automatically staged on as necessary to maintain the RH of air passing through the exhaust filters below 70%.
The design basis of the VP system has not been violated as a result of this incident for the following reasons. Filter unit heaters are mounted on each side of the filters to prevent adsorption of moisture when the VP exhaust fans are shutdown. These heaters automatically energize when the temperature in the vicinity of each respective filter unit decreases below approximately 110 degrees F. Carbon adsorbers are heated as necessary to maintain a suitable
" storage" environment, and high carbon adsorber load RH is alarmed. In addition to the protection provided by these heaters, VP will isolate when RH exceeds 70%. Also, during the performance of PT/1(2)/A/4450/01 in the past, RH has been recorded as being less than 50%.
The design functions of the VP system are outlined in FSAR Section 9.4.5.1: to clean up containment purge exhaust during refueling, to supply fresh air for contamination control when Containment (or incore instrumentation room) is or will be occupied, to exhaust Containment air to the outdoors through the purge exhaust filter trains whenever the VP System is operated, and to assure isolation of the system Containment penetrations. The only function which is safety-related, is the isolation of system Containment penetrations. The VP System will isolate on high radiation or high RH signals. The high RH signals would be generated from instrument loops VP5670 or VP5680, wnich are independent of the exhaust heater control loop in which the controller failed, VP5690. The-exhaust heater control loop, which energizes 1(2)HETR0528, performs no safety function.
The health and safety of the public were not affected by this incident.
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