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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 POWER June 14,-1990 Document Control Desk U. S. Nuclear Regulatory Com'nission '
Washington, D. C. 20555
Subject:
Catawba Nuclear Station Docket No. 50-414 LER 414/90-08 Gentlemen Attached is Licensco Event Report 414/90-08 concerning DEGRADED
' AUXILIARY FEEDWATER FIRE PROTECTION SYSTEM DUE TO CONSTRUCTION /
' INSTALLATION DEFICIENCY DURING INITIAL INSTALLATION AND A DEFICIENT ~
PRE-OPERATIONAL TEST PROCEDURE.
This event'was considered to be of no significance with respect to the health and safety of the public.
Very truly yours, l
Tony B. Owen b Aw Station Manager ken \LER-NRC.TBO xc: Mr. S. D. Ebneter American Nuclear Insurers Regional Administrator, Region II c/o Dottie Sherman, ANI Library
'U. S. Nuclear Regulator Commicsion The Exchange, Suita 245 101 Marietta Street, NW, Suite 2900 270 Farmington Avenue Atlanta, GA 30323 Farmington, CT 06032 M & M Nuclear Consultants Mr. K. Jabbour 1221 Avenues of the Americas U. S. Nuclear Regulatory Commission New York, NY 10020 Office of Nuclear Reactor Regulation Washington, D. C. 205SS INPO Records Center Suite 1500 Mr. W. T. Orders j' 1100 Circle 75 Parkway NRC Resident Inspector i_
Atlanta, GA 30339- Catawba Nuclear Station j l
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On April 21,' 1990, at 14.10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />, with Unit 2 in Mode 1, Power Operation, a high pressure carbon dioxide (CO2) discharge occurred on the Auxiliary Feedwater (CA)
Fire Protection (RFL System. The CO2 discharge occurred as a result of an unexpected steam release in the turbine driven pump pit during efforts to blow out clogged drain lines. With the turbine driven pump pit CO2 discharge header manualf.y isolated, the CO2 discharged into both motor driven pump pits.
However, system desityn is for discharge into only one pit. During investigation the r,olonoids on the three pilot valves were found to be installed backwards, which caused all three pit selector valves to open. This incident is attributed to c. Construction / Installation Deficiency in that the solenoids were installed backwards and that inspections did not identify this condition. This incident is also attributed to a Deficient Procedure in that the pre-operational test procedure did not identify failed pilot valve solenoids. The Unit 2 pilot valve solenoids' orientation was corrected. The similar solenoids on Unit I were inspected and found to be installed correctly. Post-maintenance testing of the Unit 2 solenoids was successfully performed. The present periodic surveillance test methods will be reviewed, llLM PX L 1)
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0l0 0l2 0F 018 BACKGROUND The high pressure carbon dioxide (CO2) system provides fire protection for the Auxiliary Feodwater [EIIS:BA] (CA) System pump [EIIS:P] pits as a function of the station Fire protection [EIIS:KP) (RF) System. Both high pressure CO2 systems, Unite 1 and 2, consist of eighteen high pressure CO2 cylinders arranged in two banks, main and reserve, located in the CA pump room of the Auxiliary Building [EIIS:NF]. In selection of the main or reserve banks, nine high pressure cylinders are aligned to provide fire protection to the one turbine
[EIIS:TRB] driven and two motor (EIIS:MO) driven CA pump pits. Check valves
[EIIS:V) in the manifold discharge header function with the activating system to discharge five cylinders into the turbine driven CA pump pit. All nine cylinders will discharge to a single motor driven CA pump pit. Three selector valves are provided in the discharge header which individually receive an activation signal associated with the pit that is to receive the CO2 discharge.
There is a 60 second time delay from receipt of a fire hazard signal to a CO2 discharge, and the discharge continues until the CO2 supply is exhausted. The system muct be reset before a second discharge is achievable.
The three selector valves, one for each pit, are pilot actuated by CO2 pressure from the CO2 cylinder discharge header. Three pilot and solenoid valve assemblies isolate the CO2 pressure from its associated selector valve until a fire hazard signal is received from a pit. Once a signal is received, the solenoid and pilot will open, allowing CO2 pressure to the top chamber of the selector valve, which then opens to discharge to the appropriate pit. The solenoid valves are two way, normally closed, soft synthetic seat valves manufactured by Skinner Electric Valve, reference number V5L26985 (UL/FM approved).
Technical specification (T/S) 3.7.10.3 requires the high pressure CO2 system to be operab;e whenever equipment protected by the CO2 system is required to be operable. With the CO2 system inoperable, within one hour a continuous fire watch for affected areas where redundant equipment is located must be established. For other affected areas, an hourly fire watch must be established.
EVENT DESCRIPTION During this incident, Unit 2 continuously operated in Mode 1, power Operation.
On April 21, 1990, at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />, operations (OPS) personnel were attempting to pressurize the Unit 2 Auxiliary Steam [EIIS:SA] (SA) supply line to the CA Pump Turbine in order to blow out with steam the debris that was suspected to have accumulated in the SA line drains. The approach to be taken to pressurize the line was reviewed by the Control Room Operators (CRos) and was appropriately identified to all personnel involved, although written procedures did not exist.
A Nuclear Operator Specialist (NOS) verified that the isolation valves in the drain lines that contained the trash were closed. When the SA line was pressurized steam escaped into the turbine driven CA pump pit through a yma .. . . . cm i ... . u. . t,y
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.Catcwba Nuclear Station. Unit 2 0 l6 l0 l0 l0 F l1l 4 9l0 0 l 0l 8 0F var c a . < = =.e mm.u nn 0l0 0l3 0l 8 partially open valve, 2SA008, CA pump No. 2 Steam Supply Drain Orifice Inlet Isolation. The steam release was the result of debris being caught under the seat of 2SA000 preventing it from properly closing, and resulted in an inadvertent actuation of the CA pump pits high pressure CO2 fire protection system. The CO2 system, previously isolated to the turbine driven CA pump pit, discharged to both motor driven CA pump pits. After the room was ventilated and checked with air monitors, a continuous fire watch was established. At 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> on April 21, the CO2 system was switched to the reserve bank of cylinders and the T/S action statement for an inoperablo CO2 system was entered. At 2100 houre, it was observed that 5 of the 9 main bank cylinders had discharged.
On April 22, the high pressure CO2 system was inspected by the Safety Group.
The pilot valve pressure switchs indicated that all three selector valves received pilot pressure for actuation. On April 23, Design Engineering support was requested to assist in determining the cause of the simultaneous actuation of all three selector valves.
On April 24, troubleshooting the CO2 system control cabinet under Work Request (W/R) 46490 ops identified that all solenoids were receiving the correct electrical signals. The solenoid actuation was checked by signals initiated from the control panel and by a heat source on the thermostats in the pump pits.
On all initiating signals, only the appropriate (selector valve) pilot valve solenoid received an actustion signal, indicating that no problems existed within the electrical circuitry of the high pressure CO2 system.
On April 26, W/R 6228 SWR was used to refill the discharged high pressure CO2 cylinders. With the cylinders disconnected from the header (both main and reserve), 700 psig nitrogen (H2) was used to pressure test the system. Without an electrical actuation signal to the pilot solenoids (solenoids closed), it was observed that N2 was escaping from the exhaust vent in the pilot pressure port of the pilot valve. On April 26, W/R 2558 KES was initiated to investigate the failure of the pilot and solenoid valves, 1
On April 30, the three selector valve pilot / solenoid valve assemblies were removed from the system. The valves were pressurized with N2 and the valves i would not prevent the N2 from passing through. A review of the assembly drawing (CNM 1206.08-0093) revealed that the solenoid was installed backwards on the l pilot valve. All three solenoids were reversed and the assemblies were reinstalled into the system. On May 1, a final check out of the system using N2 l pressure indicated that no N2 was escaping from the exhaust vent and that the i pilot / solenoid valve assemblies were isolating properly. l
! l On May 3,1990, Maintenance Engineering Services (KES) initiated pIR 2-C90-0156 J l to evaluate past operability of the high pressure CO2 system, including if thero !
was a sufficient concentration of CO2 to extinguish an actual fire in three CA l l pump pits. A Maintenance Engineering Services (KES) review indicated no work I l had been performed on the pilot / solenoid valve assemblies since initial 1 installation. On May 15, Design Engineering concluded that the required design )
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0l0 Op Ol_8 concentrations could not be achieved with a CO2 discharge into more than one CA pump pit and that the system was inoperable with the pilot valve solenoids installed backwards. Operability-has been restored with the solenoid orientation corrected.
Refilling of the cylinders and repairs to system leaks discovered during the N2 pressure test were complete on May 17. The cylinders were reconnected to the header, and the high pressure CO2 system was returned to service. The T/S action requirements were exited at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> on May 17.
CONCLUSION This incident is attributed to a Construction /In stallation Deficiency in that individuals performing the initial installation of the selector valve pilot / solenoid assemblies installed the solenoids backwards. The final system walkdown inspection also missed identifying that the solenoids had been
[ installed backwards. The assembly drawings used for the initial installation and inspection clearly identify the solenoid valve orientation, with port "P" labeled as the inlet and port "A" labeled as the outlet. The "A" and "P" ports are also clearly stamped into the body of the solenoid. By review of the system i turnover package and the final inspections, it can be concluded that the '
appropriate instructions and information (i.e. drawings) were available to the individuals performing the task, and that the installation was incorrect by those performing the initial installation and inspection. The high pressre CO2 fire protection system was therefore identified as complete and ready for service, and provided to the operating organization in this deficient condition.
As a result of this incident, the Unit I high pressure CO2 system selector valve i pilot / solenoid valve assemblies were inspected. All solenoids were verified to '
be installed correcti,y. Unit I was unaffected by this incident.
This incident is also attributed to a Deficient Procedure in that the Pre- j operational Test Procedure did not adequately test the system for a failed pilot valve solenoid. Procedure TP/2/A/1400/05C, CO2 Fire Protection System-Auxiliary Feedwater Pump Functional Test, requires manual isolation of the discharge headers to all three pits as a prerequisite. The manual isolations remained j closed during the electrical system testing. To verify CO2 concentrations }
during the pre-operational test the manual isolation for the pit being tested '
was opened with the other two manual isolations closed. During the test, there was no verification that the two selector valves, and pilot / solenoids, which did not receive an actuation signal remained in the closed position. l s
The Diesel Generator [EIIS: GEN] (D/G) Fire Protection utilizes a low pressure !
CO2 system of similar design. Procedure TP/l(2)/A/1400/05B, CO2 Fire Protection System-D/G Building Functional Test, was reviewed and found to be adequate in j its test method of verifying pilot valve response. During this test, pressure i gauges were installed at the pilot line connection to the upper chamber of the
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selector valves. During CO2 concentration testing, the appropriate selector valve was verified to open by pressure received through the pilot line. Thu opposite selector valve was verified to remain closed (i.e. that no pressure was received through the pilot valve). During this test, the isolation valve for the D/G Room not receiving a discharge was manually closed (similar to the high pressure CO2 test of the CA Fire Protection System).
The present surveillance testing being performed on the high pressure CO2 system does not include a verification of selector valve response. If the selector valves do not respond properly to a system actuation, the CO2 discharge concentrations could be reduced below that which is required for the hazard area. The N2 pressure test (post-maintenance test) performed during this incident verified that the solenoids and pilot valves would hold pressure and that this incident's failure mode has been corrected. This N2 pressure test and other applicable tests of the selector valves will be evaluated for inclusion in the surveillance testing requirements.
During the past 24 months, there have been no unsuccessful actuations of a fire protection system due to incorrect initial equipment installation or due to deficient pre-operational testing. This incident is considered to be the result of an isolated deficiency within the fire protection system's operational readiness. The deficient pre-operational test procedure and the deficient final system walkdown inspection existed together to lead to this incident. If either had been adequately performed, this incident would have been prevented.
Inspections of the Unit 1 high pressure CO2 system piping (EIIS: PSP] ,
configuration and the Units 1 and 2 low pressure CO2 system pre-operational tests verify that these deficioacies do not exist in similar areas of the fire protection system.
During the past 24 months, there have been no unsuccessful actuations of a nuclear safety system due to incorrect initial equipment installation; however, there has been one incident due to deficient pre-operational testing. As identified in LER 413/89-023, the Control Room Ventilation System failed to provide adequate flow with a single outside air intake open during a normally j scheduled surveillance test. The pre-operational test and previous surveillance '
test were performed with both intakes open. The pre-operational test was found I to be deficient due to not testing all possible modes of system alignment. This i and other incidents related to ventilation systems has lead to developing a task i group to review the adequacy of testing of ventilation systems. Deficient I pre-operational test procedures resulting in unsuccessful actuation of safety ]
systems is considered to be a recurring problem per the Nuclear Safety Assurance guidelines.
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- 1) The electrical actuation signals of the high pressure CO2 system were inspected, and found to be working properly (reference W/R 46490 OPS).
- 2) The high pressure CO2 header was pressure tested using N2, and it was observed that pressure was escaping from the exhaust vent of the pilot valves (reference W/R 6228 SWR).
- 3) The two thermal links in the turbine driven CA pump pit ventilation system dampers were replaced (reference W/R 46490 OPS).
- 4) The solenoid's orientation was corrected on the three pilot valves (reference W/R 2558 MES).
- 5) The Unit 1 solenold's orientation was verified to be installed correctly.
- 6) A post-maintenance N2 pressure test was performed on the high pressure CO2 header, and verified that the solenoids would hold until an !
actuation signal is received (reference W/R 6228 SWR). '
- 7) Performance and Design Engineering met to discuss possible improvements within the high pressure CO2 system design documents and station expertise.
PLANNED
- 1) The present methods of testing the operability of CO2 fire protection systems will be evaluated to datermine if additional testing is necessary, to insure that the surveillance requirements of T/S are being met.
SAFETY ANALYSIS The CO2 system does not perform a safety function, but does provido protection for safety related equipment. If a fire had occurred in the CA turbine driven pump pit, the three hour rated fire barriors separating this pit from the adjacent CA motor driven pump pats would have prevented the fire from spreading.
Safe shutdown would have been assured using the motor driven pumps. Similarly, if a fire would have occurred in one of the motor driven pump pits, the three hour fire barriers would have prevented the spread to the turbine pit. Safe shutdown would have been assured using the turbine pump. The fire boundary wall separating the Unit 2 CA pump has not been degraded such that it cou.'.d not have provided the three hour fire rating requirements.
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- 1) The detection and control system for the high pressure CO2 system remained operable while the mechanical actuation of the system was inoperable. If a '
fire would have occurred, a detector would have operated and a signal would '
have been received in the Control Room. The fire brigade would have responded to effect fire extinguishment. *
- 2) If the CO2 design concentration would not have been achieved, come CO2 '
would have discharged into the affected pit. This should have provided some firme control and slowed the fire some until the fire brigade l responded.
- 3) The discharge of CO2 into all three pits would not have affected operability of any of the pumps. For example, if a fire occurred in the :
turbine pit resu) ting in the discharge of CO2, the CO2 discharged into the other pits woul/ cot render the motor driven pumps inoperable.
The health and sa.- of the public were maintained during this incident.
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