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Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20046B4041993-07-28028 July 1993 LER 93-004-00:on 930629,identified Noncompliance W/Srs of TS 4.3.2.1,Table 3.3-3.8.b.Caused by Personnel Error.Retest Sucessfully Performed & Personnel Involved Have Taken Part in Discussion of Importance of Review process.W/930728 Ltr ML20046B1601993-07-28028 July 1993 LER 93-003-00:on 930628,TS Violation Occurred Due to Personnel Error Re non-licensed Operator Performing Evolution W/O Consulting Governing Procedure.Reactor Bldg Purge Supply Valves closed.W/930728 Ltr ML20028H4411990-12-27027 December 1990 LER 90-001-01:on 900209,Part 21 Rept Received from Gilbert Commonwealth Re Possible Loss of One Train of Chilled Water Sys in Event of High Energy Line Break.Conceptual Design Developed to Reduce Heat Load on coils.W/901231 Ltr ML20043F3941990-06-0404 June 1990 LER 90-008-00:on 900505,energizing of Sequencer Initiated Undervoltage Sequence Causing ESF Bus a to Deenergize. Caused by Incorrectly Installed Undervoltage Circuit Agastat Relay.Relay rewired.W/900604 Ltr ML20043B6031990-05-23023 May 1990 LER 90-007-00:on 900423,during Offsite Relay Testing,Oil Circuit Breaker Supplying Bus 3 Tripped Open,Resulting in Loss of Power to ESF Train B & Diesel Generator B Start. Caused by Deficient Procedure.Testing stopped.W/900523 Ltr ML20043A4231990-05-10010 May 1990 LER 90-006-00:on 900412,unplanned ESF Actuation Occurred When Train B Emergency Diesel Generator Automatically Started.Caused by Personnel Error.Feeder Breaker from Battery reopened.W/900510 Ltr ML20042G7691990-05-0808 May 1990 LER 90-005-00:on 900410,steam Generator Tube Eddy Current Exam Yielded Insp Category C-3 Results.Caused by Primary Water Stress Corrosion Cracking in Hot Leg Tubesheet Area. Defective Tubes Plugged or repaired.W/900508 Ltr ML20042G1761990-05-0707 May 1990 LER 90-003-00:on 900406,computer Software Error Caused Nonconservative Radiation Monitor Setpoints.Caused by Software Developer Personnel Error.Setpoints Readjusted & Procedures/Software evaluated.W/900507 Ltr ML20042G1791990-05-0707 May 1990 LER 90-004-00:on 881114,investigation Determined That Two Leads for Cabinet XPN-6002 Had Been Previously Disconnected in 881114 Refueling Outage,Rendering Transmitter LT-1976 Inoperable.Caused by Personnel error.W/900507 Ltr ML20042E1601990-04-11011 April 1990 LER 90-002-00:on 900318,inadvertent ESF Actuation Occurred When Emergency Start Signal Reset.Caused by Procedure Inadequacy When Emergency Start Signal Still Present on Train B.Sys Operating Procedure revised.W/900411 Ltr ML20012C4231990-03-12012 March 1990 LER 90-001-00:on 900209,Gilbert/Commonwealth,Inc Informed Util of Vendor Requirement to Rept Design Deficiency Re Failure of Safety Function,Per Part 21.Util Evaluating What Design Mods Can Be Made to Correct deficiency.W/900312 Ltr ML20006B1231990-01-26026 January 1990 LER 89-022-00:on 890913,discovered That Chilled Water Pump B Returned to Svc W/O Performing Adequate Section XI of ASME Boiler & Pressure Vessel Code Required post-maint Operability Test.Caused by Personnel error.W/900126 Ltr ML19354E1641990-01-17017 January 1990 LER 89-021-00:on 891218,when Operator Directed to Stop Svc Water Pump C by Positioning Handswitch to auto-after Stop Position,Pump Started,Causing ESF Actuation.Caused by Failed Circuit Board.Board replaced.W/900117 Ltr ML20005G1511990-01-0808 January 1990 LER 88-008-01:on 880607,AE (Gilbert Assoc) Notified Util of Design Defect Yielding Potential for Steam Propagation Path Which Could Affect Safe Shutdown Equipment.Caused by Design Error.Also Reportable Per Part 21.W/900108 Ltr ML20005E6941990-01-0202 January 1990 LER 89-019-00:on 891203,as Result of Plant Trip on 891202, Results of Reactor Coolant Sample Not Reviewed & Recognized as Being Out of Tolerance.Caused by Personnel Error.Another Sample of RCS Taken & Analyzed,Per Tech Spec.W/900102 Ltr ML20005E6611990-01-0202 January 1990 LER 89-020-00:on 891202,turbine Controls Failed to Respond to Attempt to Counter Loss of Load & Turbine Manually Tripped.Caused by Relay Contact Failure in Turbine Electrohydraulic Control circuitry.W/900102 Ltr ML20011D4691989-12-20020 December 1989 LER 89-015-02:on 890825,presssurizer Safety Valve Body Inlet Temp Increased to Greater than 450 F & Acoustic Leak Monitor Alarmed,Causing RCS to Depressurize & Reactor Trip. Caused by Loss of Loop Seal.Valve replaced.W/891220 Ltr ML19332F0131989-11-30030 November 1989 LER 89-018-00:on 891027,shift Engineer Observed That Control Room Alarm Did Not Occur When Sample Pumps Stopped.On 891031,radiation Monitors RM-A3 & RM-A4 Declared Inoperable. Caused by Inadequate procedures.W/891130 Ltr ML19327B4921989-10-24024 October 1989 LER 89-017-00:on 890918,responsible Engineer Reviewed Plant Parameters & Concluded That Initial Conditions Required by Surveillance Test Procedure 209.001 Not Satisfied.Caused by Personnel Error & Procedural inadequacy.W/891024 Ltr ML19327B3451989-10-24024 October 1989 LER 89-015-01:on 890825,pressurizer Safety Valve Body Inlet a Temp Increased to Greater than 450 F & Plant Shutdown Initiated.Cause Being Evaluated.Plant Parameters Monitored & Stabilized in Mode 3.W/891024 Ltr ML19325C6501989-10-0707 October 1989 LER 89-016-00:on 890908,shutdown Occurred Due to Inoperable Msiv.Caused by Crushed Conduit That Resulted in Short Circuit of Test Circuit Wiring.Conduit/Test Circuit Wiring repaired.W/891006 Ltr ML20006B2751989-06-27027 June 1989 LER 89-011-01:on 890528,manual Reactor Trip Initiated Following Failure of Pressurizer Safety Valve When Valve Became Unseated,Causing Rapid Depressurization of Rcs.Temp Detectors Installed on Safety valve.W/900123 Ltr ML20024F5131983-08-31031 August 1983 LER 83-091/03L-0:on 830802,while in Mode 1,borated Water Vol of Accumulator a Decreased to 7,354 Gallons.Caused by Valve Leakage in ECCS Check Valve Leakage Detection Sys.Valves Verified in Locked Position.Flange installed.W/830831 Ltr ML20024F4551983-08-31031 August 1983 LER 83-090/03L-0:on 830818,while Increasing Reactor/Turbine Power from 14 to 20%,rod Insertion Limit Violated.Caused by Operating Personnel Failure to Establish Plant Parameters. Emergency Boration initiated.W/830831 Ltr ML20024F2221983-08-31031 August 1983 LER 83-093/03L-0:on 830802,refueling Water Storage Tank Level Transmitter LT-991 Failed High.Caused by Internal Component Failure.Transmitter replaced.W/830831 Ltr ML20024F5901983-08-31031 August 1983 LER 83-092/03L-0:on 830817,east Wall Fire Barrier in Control Bldg Room CB-36-02 Declared Degraded When Unsealed Conduit Found in Newly Installed Juction Box.Caused by Personnel error.W/830831 Ltr ML20024D9111983-08-0101 August 1983 LER 83-075/03L-0:on 830703,emergency Feedwater Valve IFV-3536 to Steam Generator a Tripped Shut on High Flow & Failed to Reset.Caused by Signal Comparator Card Failure. Card replaced.W/830801 Ltr ML20024D8301983-08-0101 August 1983 LER 83-078/03L-0:on 830709,Th Inputs to Subcooling Monitor Channel a Declared Inoperable Due to Low Indications.Caused by Intermittent Opening on Input Connections.Connectors tightened.W/830801 Ltr ML20024D7981983-08-0101 August 1983 LER 83-076/03L-0:on 830707,during Mode 1,pressurizer Power Relief Valve PCV-444B-RC Failed to Stroke Fully.Caused by Low Pressure Nitrogen Reservoir Failing to Charge Up to Pressure.Valves Will Be Inspected & readjusted.W/830801 Ltr ML20024D6981983-07-29029 July 1983 LER 83-074/03L-0:on 830603,during Emergency Diesel Generator a Operability Surveillance Test,Normal 115 Kv Power Supply to Vital Bus Lost & Diesel Generator Output Breaker Tripped Open.Caused by Electrical surge.W/830729 Ltr ML20024D8571983-07-28028 July 1983 LER 83-072/03L-0:on 830701,smoke Detector SMK-CB-3,Zone W-W, Would Not Reset at Integrated Fire & Security Panel.Caused by Failure to Teletype Printed Control Board in Cathode Ray Tube Circuitry.Component replaced.W/830728 Ltr ML20024B6801983-07-0606 July 1983 LER 83-055/03L-0:on 830609 & 10,smoke Detectors in Control Bldg Zone a Failed.Caused by Welding in Area.Fire Watch Patrol Initiated & Affected Detectors & Deluge Resettled. W/830706 Ltr ML20024B7091983-07-0606 July 1983 Updated LER 83-054/03L-1:on 830601,power Failure Occurred, Defeating One Gpm Leakage Alarm for Reactor Bldg Sump.Caused by Loose Power Supply Module Fuse Holder Grounding Power Supply.Module replaced.W/830706 Ltr ML20024B7761983-07-0606 July 1983 LER 83-058/03L-0:on 830607,smoke Detector IXA-4993G Failed to Respond to Simulated Alarm.Caused by Broken Base Assembly in Detector Due to Open Circuit Preventing Alarm Condition. Component replaced.W/830706 Ltr ML20024B9821983-07-0101 July 1983 LER 83-056/03L-0:on 830606,feedwater Flow Transmitter (FT-468) Steam Generator B Failed Low.Caused by Failure of Power Supply Card.Card replaced.W/830701 Ltr ML20024C0371983-07-0101 July 1983 LER 83-057/03L-0:on 830606,nitrogen Low Pressure Alarm on Low Pressure Accumulator for PORV Received in Control Room. Caused by Valve Position Indicator Lights Not Showing Full Actual Position.Limit Switches adjusted.W/830701 Ltr ML20024C2601983-06-30030 June 1983 LER 83-54/03L-0:on 830601 Plant Auxiliary Relay Rack XPN-6034 Balance Declared Inoperable Due to Power Failure. Caused by Loose Fuse Holder on Power Supply Module Grounding Supply.Module replaced.W/830630 Ltr ML20024C1031983-06-22022 June 1983 LER 83-051/03L-0:on 830524,control Room Evacuation Panel Pressurizer Relief Tank Level Indicator ILI-470A Removed from Svc Due to Low Readings.Caused by Instrument Drift. Upgraded Electronic Cards installed.W/830622 Ltr ML20023D4561983-05-13013 May 1983 LER 83-036/03L-0:on 830414,during Performance of Channel Calibr,Pressurizer Safety Valve Position Indication on Valves Failed to Function Properly.Caused by Excessive Current Flow During Contact Closure.Switch Assembly Changed ML20023B6481983-04-29029 April 1983 LER 83-032/03L-0:on 830331,detection Zone Nnn in Control Bldg Failed to Respond to Simulated Smoke Condition During Investigation of Alarm.Alarm Previously Received on 830329. Caused by Short in Smoke Detector.Detector Reinstalled ML20023B4391983-04-29029 April 1983 LER 83-033/03L-0:on 830331,while in Mode 5,source Range Detectors N-31 & N-32 Lost for Approx 5 Minutes.Caused by Maint Personnel Error in Placing Trains of Solid State Protection Sys in Wrong Position.Personnel Cautioned ML20028G0861983-02-0101 February 1983 LER 83-001/01T-0:on 830119,w/plant in Mode 1,three Refueling Water Storage Tank Level Transmitters Failed High. Caused by Frozen Instrument Lines.Transmitters Thawed. Insulated Encls Will Be Installed ML20028F4721983-01-21021 January 1983 LER 82-065/03L-0:on 821222,electrical Power Lost to Train a Radiation Monitoring Sys.During Investigation of Loss of Power,Maint Personnel Accidently Short Circuited Train B. Caused by Blown Power Fuses Due to Personnel Error ML20028E0091983-01-14014 January 1983 LER 82-060/03L-0:on 821215,Surveillance Requirement 4.3.3.6 Discovered Unperformed in Modes 1,2 & 3.Caused by Personnel Error.Procedure Revised ML20028E1831983-01-13013 January 1983 LER 82-059/03L-0:on 821215,w/plant in Mode 1,several Fire Doors Not Verified Closed.Caused by Doors Not Being Included in Auxiliary Operator Logs Rev & Therefore Not Checked.Log Being Revised to Ensure That Doors Checked ML20028E1301983-01-13013 January 1983 Revised LER 82-016/03L-2:on 821216,main Control Board Indicator PI-951 for Reactor Bldg Pressure Failed Low.Caused by Failure of Loop Power Supply Circuit Board When Exposed to Ambient Conditions.Circuit Board Replaced ML20028E0771983-01-13013 January 1983 LER 82-058/03L-0:on 821214,urgent Failure Alarm Due to Loss of Power Occurred During Restoration of Rod Control Sys Upon Completion of Power Operational Testing.Caused by Oxidation Between Fuse & Fuse Block Mating Surfaces ML20028E1241983-01-11011 January 1983 LER 82-057/03L-0:on 821213,turbine Bldg Sump Normal Discharge to Site Settling Ponds Temporarily Bypassed Via Auxiliary Pump & Fire Hose.Caused by Sump Pumps Becoming Clogged W/Debris from Const Repair Work Being Done ML20028D3231983-01-0707 January 1983 LER 82-056/03L-0:on 821209,surveillance Test Procedure, Nis Power Range Heat Balance, Not Performed in Specified Intervals.Caused by Personnel Oversight.Administrative Procedures for Control of Surveillances Revised ML20028D1161983-01-0505 January 1983 LER 82-053/03L-0:on 821206,during Mode 1,spurious High & Low Meter Indications Observed on Main Control Board Indicator FI-494 for Steam Generator C Flow.Caused by Failure of Circuit Board FY-494.Board Replaced 1993-07-28
[Table view] Category:RO)
MONTHYEARML20046B4041993-07-28028 July 1993 LER 93-004-00:on 930629,identified Noncompliance W/Srs of TS 4.3.2.1,Table 3.3-3.8.b.Caused by Personnel Error.Retest Sucessfully Performed & Personnel Involved Have Taken Part in Discussion of Importance of Review process.W/930728 Ltr ML20046B1601993-07-28028 July 1993 LER 93-003-00:on 930628,TS Violation Occurred Due to Personnel Error Re non-licensed Operator Performing Evolution W/O Consulting Governing Procedure.Reactor Bldg Purge Supply Valves closed.W/930728 Ltr ML20028H4411990-12-27027 December 1990 LER 90-001-01:on 900209,Part 21 Rept Received from Gilbert Commonwealth Re Possible Loss of One Train of Chilled Water Sys in Event of High Energy Line Break.Conceptual Design Developed to Reduce Heat Load on coils.W/901231 Ltr ML20043F3941990-06-0404 June 1990 LER 90-008-00:on 900505,energizing of Sequencer Initiated Undervoltage Sequence Causing ESF Bus a to Deenergize. Caused by Incorrectly Installed Undervoltage Circuit Agastat Relay.Relay rewired.W/900604 Ltr ML20043B6031990-05-23023 May 1990 LER 90-007-00:on 900423,during Offsite Relay Testing,Oil Circuit Breaker Supplying Bus 3 Tripped Open,Resulting in Loss of Power to ESF Train B & Diesel Generator B Start. Caused by Deficient Procedure.Testing stopped.W/900523 Ltr ML20043A4231990-05-10010 May 1990 LER 90-006-00:on 900412,unplanned ESF Actuation Occurred When Train B Emergency Diesel Generator Automatically Started.Caused by Personnel Error.Feeder Breaker from Battery reopened.W/900510 Ltr ML20042G7691990-05-0808 May 1990 LER 90-005-00:on 900410,steam Generator Tube Eddy Current Exam Yielded Insp Category C-3 Results.Caused by Primary Water Stress Corrosion Cracking in Hot Leg Tubesheet Area. Defective Tubes Plugged or repaired.W/900508 Ltr ML20042G1761990-05-0707 May 1990 LER 90-003-00:on 900406,computer Software Error Caused Nonconservative Radiation Monitor Setpoints.Caused by Software Developer Personnel Error.Setpoints Readjusted & Procedures/Software evaluated.W/900507 Ltr ML20042G1791990-05-0707 May 1990 LER 90-004-00:on 881114,investigation Determined That Two Leads for Cabinet XPN-6002 Had Been Previously Disconnected in 881114 Refueling Outage,Rendering Transmitter LT-1976 Inoperable.Caused by Personnel error.W/900507 Ltr ML20042E1601990-04-11011 April 1990 LER 90-002-00:on 900318,inadvertent ESF Actuation Occurred When Emergency Start Signal Reset.Caused by Procedure Inadequacy When Emergency Start Signal Still Present on Train B.Sys Operating Procedure revised.W/900411 Ltr ML20012C4231990-03-12012 March 1990 LER 90-001-00:on 900209,Gilbert/Commonwealth,Inc Informed Util of Vendor Requirement to Rept Design Deficiency Re Failure of Safety Function,Per Part 21.Util Evaluating What Design Mods Can Be Made to Correct deficiency.W/900312 Ltr ML20006B1231990-01-26026 January 1990 LER 89-022-00:on 890913,discovered That Chilled Water Pump B Returned to Svc W/O Performing Adequate Section XI of ASME Boiler & Pressure Vessel Code Required post-maint Operability Test.Caused by Personnel error.W/900126 Ltr ML19354E1641990-01-17017 January 1990 LER 89-021-00:on 891218,when Operator Directed to Stop Svc Water Pump C by Positioning Handswitch to auto-after Stop Position,Pump Started,Causing ESF Actuation.Caused by Failed Circuit Board.Board replaced.W/900117 Ltr ML20005G1511990-01-0808 January 1990 LER 88-008-01:on 880607,AE (Gilbert Assoc) Notified Util of Design Defect Yielding Potential for Steam Propagation Path Which Could Affect Safe Shutdown Equipment.Caused by Design Error.Also Reportable Per Part 21.W/900108 Ltr ML20005E6941990-01-0202 January 1990 LER 89-019-00:on 891203,as Result of Plant Trip on 891202, Results of Reactor Coolant Sample Not Reviewed & Recognized as Being Out of Tolerance.Caused by Personnel Error.Another Sample of RCS Taken & Analyzed,Per Tech Spec.W/900102 Ltr ML20005E6611990-01-0202 January 1990 LER 89-020-00:on 891202,turbine Controls Failed to Respond to Attempt to Counter Loss of Load & Turbine Manually Tripped.Caused by Relay Contact Failure in Turbine Electrohydraulic Control circuitry.W/900102 Ltr ML20011D4691989-12-20020 December 1989 LER 89-015-02:on 890825,presssurizer Safety Valve Body Inlet Temp Increased to Greater than 450 F & Acoustic Leak Monitor Alarmed,Causing RCS to Depressurize & Reactor Trip. Caused by Loss of Loop Seal.Valve replaced.W/891220 Ltr ML19332F0131989-11-30030 November 1989 LER 89-018-00:on 891027,shift Engineer Observed That Control Room Alarm Did Not Occur When Sample Pumps Stopped.On 891031,radiation Monitors RM-A3 & RM-A4 Declared Inoperable. Caused by Inadequate procedures.W/891130 Ltr ML19327B4921989-10-24024 October 1989 LER 89-017-00:on 890918,responsible Engineer Reviewed Plant Parameters & Concluded That Initial Conditions Required by Surveillance Test Procedure 209.001 Not Satisfied.Caused by Personnel Error & Procedural inadequacy.W/891024 Ltr ML19327B3451989-10-24024 October 1989 LER 89-015-01:on 890825,pressurizer Safety Valve Body Inlet a Temp Increased to Greater than 450 F & Plant Shutdown Initiated.Cause Being Evaluated.Plant Parameters Monitored & Stabilized in Mode 3.W/891024 Ltr ML19325C6501989-10-0707 October 1989 LER 89-016-00:on 890908,shutdown Occurred Due to Inoperable Msiv.Caused by Crushed Conduit That Resulted in Short Circuit of Test Circuit Wiring.Conduit/Test Circuit Wiring repaired.W/891006 Ltr ML20006B2751989-06-27027 June 1989 LER 89-011-01:on 890528,manual Reactor Trip Initiated Following Failure of Pressurizer Safety Valve When Valve Became Unseated,Causing Rapid Depressurization of Rcs.Temp Detectors Installed on Safety valve.W/900123 Ltr ML20024F5131983-08-31031 August 1983 LER 83-091/03L-0:on 830802,while in Mode 1,borated Water Vol of Accumulator a Decreased to 7,354 Gallons.Caused by Valve Leakage in ECCS Check Valve Leakage Detection Sys.Valves Verified in Locked Position.Flange installed.W/830831 Ltr ML20024F4551983-08-31031 August 1983 LER 83-090/03L-0:on 830818,while Increasing Reactor/Turbine Power from 14 to 20%,rod Insertion Limit Violated.Caused by Operating Personnel Failure to Establish Plant Parameters. Emergency Boration initiated.W/830831 Ltr ML20024F2221983-08-31031 August 1983 LER 83-093/03L-0:on 830802,refueling Water Storage Tank Level Transmitter LT-991 Failed High.Caused by Internal Component Failure.Transmitter replaced.W/830831 Ltr ML20024F5901983-08-31031 August 1983 LER 83-092/03L-0:on 830817,east Wall Fire Barrier in Control Bldg Room CB-36-02 Declared Degraded When Unsealed Conduit Found in Newly Installed Juction Box.Caused by Personnel error.W/830831 Ltr ML20024D9111983-08-0101 August 1983 LER 83-075/03L-0:on 830703,emergency Feedwater Valve IFV-3536 to Steam Generator a Tripped Shut on High Flow & Failed to Reset.Caused by Signal Comparator Card Failure. Card replaced.W/830801 Ltr ML20024D8301983-08-0101 August 1983 LER 83-078/03L-0:on 830709,Th Inputs to Subcooling Monitor Channel a Declared Inoperable Due to Low Indications.Caused by Intermittent Opening on Input Connections.Connectors tightened.W/830801 Ltr ML20024D7981983-08-0101 August 1983 LER 83-076/03L-0:on 830707,during Mode 1,pressurizer Power Relief Valve PCV-444B-RC Failed to Stroke Fully.Caused by Low Pressure Nitrogen Reservoir Failing to Charge Up to Pressure.Valves Will Be Inspected & readjusted.W/830801 Ltr ML20024D6981983-07-29029 July 1983 LER 83-074/03L-0:on 830603,during Emergency Diesel Generator a Operability Surveillance Test,Normal 115 Kv Power Supply to Vital Bus Lost & Diesel Generator Output Breaker Tripped Open.Caused by Electrical surge.W/830729 Ltr ML20024D8571983-07-28028 July 1983 LER 83-072/03L-0:on 830701,smoke Detector SMK-CB-3,Zone W-W, Would Not Reset at Integrated Fire & Security Panel.Caused by Failure to Teletype Printed Control Board in Cathode Ray Tube Circuitry.Component replaced.W/830728 Ltr ML20024B6801983-07-0606 July 1983 LER 83-055/03L-0:on 830609 & 10,smoke Detectors in Control Bldg Zone a Failed.Caused by Welding in Area.Fire Watch Patrol Initiated & Affected Detectors & Deluge Resettled. W/830706 Ltr ML20024B7091983-07-0606 July 1983 Updated LER 83-054/03L-1:on 830601,power Failure Occurred, Defeating One Gpm Leakage Alarm for Reactor Bldg Sump.Caused by Loose Power Supply Module Fuse Holder Grounding Power Supply.Module replaced.W/830706 Ltr ML20024B7761983-07-0606 July 1983 LER 83-058/03L-0:on 830607,smoke Detector IXA-4993G Failed to Respond to Simulated Alarm.Caused by Broken Base Assembly in Detector Due to Open Circuit Preventing Alarm Condition. Component replaced.W/830706 Ltr ML20024B9821983-07-0101 July 1983 LER 83-056/03L-0:on 830606,feedwater Flow Transmitter (FT-468) Steam Generator B Failed Low.Caused by Failure of Power Supply Card.Card replaced.W/830701 Ltr ML20024C0371983-07-0101 July 1983 LER 83-057/03L-0:on 830606,nitrogen Low Pressure Alarm on Low Pressure Accumulator for PORV Received in Control Room. Caused by Valve Position Indicator Lights Not Showing Full Actual Position.Limit Switches adjusted.W/830701 Ltr ML20024C2601983-06-30030 June 1983 LER 83-54/03L-0:on 830601 Plant Auxiliary Relay Rack XPN-6034 Balance Declared Inoperable Due to Power Failure. Caused by Loose Fuse Holder on Power Supply Module Grounding Supply.Module replaced.W/830630 Ltr ML20024C1031983-06-22022 June 1983 LER 83-051/03L-0:on 830524,control Room Evacuation Panel Pressurizer Relief Tank Level Indicator ILI-470A Removed from Svc Due to Low Readings.Caused by Instrument Drift. Upgraded Electronic Cards installed.W/830622 Ltr ML20023D4561983-05-13013 May 1983 LER 83-036/03L-0:on 830414,during Performance of Channel Calibr,Pressurizer Safety Valve Position Indication on Valves Failed to Function Properly.Caused by Excessive Current Flow During Contact Closure.Switch Assembly Changed ML20023B6481983-04-29029 April 1983 LER 83-032/03L-0:on 830331,detection Zone Nnn in Control Bldg Failed to Respond to Simulated Smoke Condition During Investigation of Alarm.Alarm Previously Received on 830329. Caused by Short in Smoke Detector.Detector Reinstalled ML20023B4391983-04-29029 April 1983 LER 83-033/03L-0:on 830331,while in Mode 5,source Range Detectors N-31 & N-32 Lost for Approx 5 Minutes.Caused by Maint Personnel Error in Placing Trains of Solid State Protection Sys in Wrong Position.Personnel Cautioned ML20028G0861983-02-0101 February 1983 LER 83-001/01T-0:on 830119,w/plant in Mode 1,three Refueling Water Storage Tank Level Transmitters Failed High. Caused by Frozen Instrument Lines.Transmitters Thawed. Insulated Encls Will Be Installed ML20028F4721983-01-21021 January 1983 LER 82-065/03L-0:on 821222,electrical Power Lost to Train a Radiation Monitoring Sys.During Investigation of Loss of Power,Maint Personnel Accidently Short Circuited Train B. Caused by Blown Power Fuses Due to Personnel Error ML20028E0091983-01-14014 January 1983 LER 82-060/03L-0:on 821215,Surveillance Requirement 4.3.3.6 Discovered Unperformed in Modes 1,2 & 3.Caused by Personnel Error.Procedure Revised ML20028E1831983-01-13013 January 1983 LER 82-059/03L-0:on 821215,w/plant in Mode 1,several Fire Doors Not Verified Closed.Caused by Doors Not Being Included in Auxiliary Operator Logs Rev & Therefore Not Checked.Log Being Revised to Ensure That Doors Checked ML20028E1301983-01-13013 January 1983 Revised LER 82-016/03L-2:on 821216,main Control Board Indicator PI-951 for Reactor Bldg Pressure Failed Low.Caused by Failure of Loop Power Supply Circuit Board When Exposed to Ambient Conditions.Circuit Board Replaced ML20028E0771983-01-13013 January 1983 LER 82-058/03L-0:on 821214,urgent Failure Alarm Due to Loss of Power Occurred During Restoration of Rod Control Sys Upon Completion of Power Operational Testing.Caused by Oxidation Between Fuse & Fuse Block Mating Surfaces ML20028E1241983-01-11011 January 1983 LER 82-057/03L-0:on 821213,turbine Bldg Sump Normal Discharge to Site Settling Ponds Temporarily Bypassed Via Auxiliary Pump & Fire Hose.Caused by Sump Pumps Becoming Clogged W/Debris from Const Repair Work Being Done ML20028D3231983-01-0707 January 1983 LER 82-056/03L-0:on 821209,surveillance Test Procedure, Nis Power Range Heat Balance, Not Performed in Specified Intervals.Caused by Personnel Oversight.Administrative Procedures for Control of Surveillances Revised ML20028D1161983-01-0505 January 1983 LER 82-053/03L-0:on 821206,during Mode 1,spurious High & Low Meter Indications Observed on Main Control Board Indicator FI-494 for Steam Generator C Flow.Caused by Failure of Circuit Board FY-494.Board Replaced 1993-07-28
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217D6401999-10-31031 October 1999 Rev 2 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0202, Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for VC Summer Nuclear Station.With ML20216J4191999-09-24024 September 1999 Part 21 Rept Re 990806 Abb K-Line Breaker Defect After Repair.Vendor Notified of Shunt Trip Wiring Problem & Agreed to Modify Procedure for Refurbishment of Breakers RC-99-0180, Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression1999-09-0808 September 1999 Special Rept on 990807,electric Driven Fire Pump XPP0134A Was Declared Inoperable.Caused by Pump Discharge Relief Valve Failing to Open as Normally Expected.Two Temporary Fire Pumps Were Installed to Provide Backup Suppression RC-99-0183, Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Virgil C Summer Nuclear Station,Unit 1.With ML20211K6161999-08-31031 August 1999 Rev 2 to VC Summer Nuclear Station,Colr for Cycle 12, Dtd Aug 1999 RC-99-0168, Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed1999-08-19019 August 1999 Special Rept:On 990804,electric Driven Fire Pump XPP0134A & Diesel Driven Fire Pump XPP0134B,were Removed from Svc to Allow for Plant Mod.Fire Pumps Were Returned to Operable Condition on 990818,after Mod Was Completed ML20210M7071999-07-31031 July 1999 Rev 1 to VC Summer Nuclear Station COLR for Cycle 12 ML20211C2201999-07-31031 July 1999 Rev 1 to WCAP-15102, VC Summer Unit 1 Heatup & Cooldown Limit Curves for Normal Operation RC-99-0163, Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0137, Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0122, Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for VC Summer Nuclear Station.With ML20206H2971999-05-0505 May 1999 Part 21 Rept Re Common Mode Failure for magne-blast Breakers.Vc Summer Nuclear Station Utilizes These Breakers in Many Applications,Including 7.2-kV EDG Electrical Buses RC-99-0103, Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for VC Summer Nuclear Station.With ML20206K2421999-04-30030 April 1999 Rev 0 to COLR for Cycle 12 for Summer Nuclear Station RC-99-0087, Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory1999-04-15015 April 1999 Part 21 Interim Rept (SSH 99-0001) Re 990218 Failure of Circuit Breaker Located in Cubicle 14 of XSW1DB to Close During Surveillance Testing.Caused by Positive Interlock Angle Was Incorrect.Breaker Was Returned to GE Factory RC-99-0083, Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for VC Summer Nuclear Station,Unit 1.With RC-99-0063, Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced1999-03-26026 March 1999 Special Rept:On 990302 & 16,meteorological Site Number One 10 Meter Temp Element Was Declared Inoperable.Caused by Erratic Operation.Cabling & 10 Meter Electrical Connectors Were Replaced ML20196K5421999-03-22022 March 1999 Rev 2 to VC Summer Nuclear Station,Training Simulator Quadrennial Certification Rept,1996-99, Books 1 & 2. Page 2 of 2 Section 2.4.4 (Rev 2) of Incoming Submittal Were Not Included RC-99-0055, Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 9903121999-03-16016 March 1999 Special Rept:On 990302,Meteorological Site Number One 10 Meter Temp Element (RTD) Was Declared Inoperable Due to Erratic Operation.Cause of Original RTD Failure Is Unknown. Equipment Was Declared Operable on 990312 RC-99-0050, Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for VC Summer Nuclear Station,Units 1.With ML18106B0931999-02-25025 February 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Caused by Crack Due to Improper Location of Heated Bar.Only One Part Out of 7396 Pieces in Forging Lot Was Found to Be Cracked.Affected Util,Notified ML20203F4511999-02-12012 February 1999 SER Finding Licensee Adequately Addressed GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, for Virgil C Summer Nuclear Station ML18106B0551999-02-0101 February 1999 Part 21 Rept Re Possible Matl Defect in Swagelok Pipe Fitting Tee,Part Number SS-6-T.Defect Is Crack in Center of Forging.Analysis of Part Is Continuing & Further Details Will Be Provided IAW Ncr Timetables.Drawing of Part,Encl ML18106B0441999-01-29029 January 1999 Part 21 Rept Re Possible Defect in Swagelok Pipe Fitting Tee Part Number SS-6-T.Caused by Crack in Center of Forging. Continuing Analysis of Part & Will Provide Details in Acoordance with NRC Timetables ML20206R5241998-12-31031 December 1998 Santee Cooper 1998 Annual Rept RC-99-0052, Vsns 1998 Annual Operating Rept. with1998-12-31031 December 1998 Vsns 1998 Annual Operating Rept. with RC-99-0004, Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for VC Summer Nuclear Station,Unit 1.With ML20206R5191998-12-31031 December 1998 Scana Corp 1998 Annual Rept ML20198F4241998-12-18018 December 1998 Safety Evaluation Granting Relief Request for Approval to Repair ASME Code Class 3 Service Water Piping Flaws in Accordance with GL 90-05 for VC Summer Nuclear Station RC-98-0223, Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method1998-12-16016 December 1998 Special Rept 98-001:on 981130,steam Line High Range Gamma Monitor (RMG-19C) Was Declared Inoperable Due to Indeterminate Alarm.Caused by Failures in Detector & Meter Reset Circuitry.Established Preplanned Alternate Method RC-98-0222, Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for VC Summer Nuclear Station,Unit 1.With ML20155G4551998-11-0404 November 1998 Safety Evaluation Accepting Licensee Proposed Alternative to Use Code Case N-416-1 with Licensee Proposed Addl Exams RC-98-0208, Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for VC Summer Nuclear Station,Unit 1.With ML20207J5701998-10-31031 October 1998 Non-proprietary Rev 1 to WCAP-14955, Probabilistic & Economic Evaluation of Rv Closure Head Penetration Integrity for VC Summer Nuclear Plant ML20154Q9571998-10-21021 October 1998 SER Accepting Request Seeking Approval to Use Alternative Rules of ASME Code Case N-498-1 for Class 1,2 or 3 Sys ML20154K7901998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15101, Analysis of Capsule W from Sceg VC Summer Unit 1 Rv Radiation Surveillance Program RC-98-0184, Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for VC Summer Nuclear Station.With ML20154K8041998-09-30030 September 1998 Non-proprietary Rev 0 to WCAP-15103, Evaluation of Pressurized Thermal Shock for VC Summer Unit 1 RC-98-0166, Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for VC Summer Nuclear Station,Unit 1.With ML20237A7181998-08-13013 August 1998 SER Accepting Util Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RC-98-0153, Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 11998-07-31031 July 1998 Monthly Operating Rept for July 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0131, Monthly Operating Rept for June 1998 for VC Summer Nuclear Station1998-06-30030 June 1998 Monthly Operating Rept for June 1998 for VC Summer Nuclear Station ML20248J0191998-06-0404 June 1998 Safety Evaluation Accepting Licensee Inservice Testing Program Interim Pump Relief Request Per 10CFR50.55a(a)(3) (II) RC-98-0113, Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 11998-05-31031 May 1998 Monthly Operating Rept for May 1998 for VC Summer Nuclear Station,Unit 1 RC-98-0100, Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 11998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for VC Summer Nuclear Station,Unit 1 ML20217G7411998-04-22022 April 1998 Rev 1 to VC Summer Nuclear Station COLR for Cycle 11 RC-98-0076, Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure1998-04-17017 April 1998 Final Part 21 Rept Re a DG EG-B for Vsns,As Followup to .Power Control Svcs of Engine Sys,Inc Provided Response on 980318.Evaluation Concludes That Failure of EG-B Is one-time non-repeatable Failure RC-98-0084, Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 11998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Virgil C Summer Nuclear Station,Unit 1 ML20212H1421998-03-0202 March 1998 Interim Part 21 Rept SSH 98-002 Re EG-B Unit That Was Sent to Power Control Svcs for Determination of Instability & Refurbishment of a Dg.Cause of Speed Oscillations Unknown. Completed Hot Bore Checks on Power Case 1999-09-08
[Table view] |
Text
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' 1 10CFR50.73; .
e' SIuth Cer: lina Electele & Gas Company" - ollb $. bradham -
- - P.O. Box 68 - . . Vic) Presid nt J:nkin2ville, SC 29035 '~ Nucbir Operations '
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April 11, 1990 a
1 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555
SUBJECT:
Virgil C.-Summer Nuclear Station N Docket No. 50/395 Operating License No. NPF-12 ,
LER 90-002 '
Gentlemen:
l Attached is Licensee Event Report No.90-002 for'the Virgil C. Summer Nuclear- .,
Station. This report is submitted pursuant to the requirements of '
10CFR50.73(a)(2)(iv).
Should there be any questions, please call us at:your convenience. d Very truly yours, O. S. Bradham-DCH/0SB: led Attachment c c: D. A. Nauman/0. W. Dixon, Jr./T. C. Nichols, Jr.
- E. C. Roberts- .
R. V. Tanner J. C.-Snelson S. D. Ebneter R. L. Prevatte J. J. Hayes, Jr. J. B. Knotts, Jr. '
General Managers INP0 Records Center C. A. Price ANI Library G. J. Taylor Marsh & McLennan '
J.-R. Proper NPCF R. B. Clary NSRC F. H. Zander. RTS (ONO900019)
T. L. Matlosz Files (818.05 &'818.07)
K. E. Nodland l
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. LICENSEE EVENT REPORT (LEM " P '"' ' ' a F ACILITV 8sA486 til 00Casiseuesen un raus m Virgil C. Summer Nuclear Station o is l o io l o l 3g9 g5 ijorl0l3 TITLt tel Inadequate Procedure Leads to an Inadvertant ESF Actuation of a Diesel Generator SVGNT Daf t 158 Lam Nyneth tel AGP0af Datt (7) OTMOR F ACILIT18818ev0LVED les MONTM f actLITv HAM 48 DOCK 4T ecumesmisp DAY YEAR YEAR MONN DAY Ytan 0 181010101 I l
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N1MB YtLEPMONS NUMSSR Am& A C006 W. R. Higgins, Supervisor, Regulatory Compliance 8,0 3 i 3i4i5 , ,4 i0 g ,2 COMPLETE ONS LING FOR SACM C0er0fsGNT F AILUAE D4KR100C IN THIS RSPORT (13)
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y g D El K l Q GI i l l N i i i i I i i I I I I I I I I I I I I I I SuppLttstNTAL REPORT EXPGCTRO lies MONTM DAY YeAm vtS III r.e cowete IXPECTED Sv0 MISSION CATf! NO l l l A T. ACT w. .. , u . .-..e- .,e e .o.~.. . , n .,
On March 18, 1990, at approximately 0230, hours during performance of Surveillance Test Procedure (STP) 170.015, an emergency start signal was present on the "B" train diesel generator and, per the procedure, the operator attempted to reset the emergency start signal. The diesel was disabled by placing the mode selector switch to the maintenance mode; however, when the diesel generator mode selector switch was returned to the operational mode, the diesel started. This start constitutes an inadvertent ESF actuation.
The diesel generator was monitored and verified to achieve proper speed and voltage as required from an emergency start signal. Also, all support systems were verified to function properly.
The "B" diesel generator circuitry is designed such that when the mode selector is in the maintenance mode the emergency start override push button in the main control room is disabled but the local override push button is operable. The procedure specifically referred to the emergency start override push button in the main control room to be used to reset the diesel even though the mode selector was in the maintenance mode. Thus, when the mode selector switch was taken out of the maintenance position, the diesel generator started because the emergency start signal was still present.
The diesel generator was then shut down and placed in standby per the applicable System Operating Procedure and a change to the procedure to require the emergency l
start to be reset locally was init Mted.
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i' l PLANT IDENTIFICATION' Westinghouse - Pressurized Water Reactor EQUIPMENT IDENTIFICATION: ;
Emergency Diesel Generator EIIS-0G JOENTIFICATIONOFEVENT:
An inadequate procedure caused the inadvertent start of "B" train Emergency Diesel l Generator. i i
EVENT TIME AND DATE:
March-18, 1990 at 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br />.
REPORT DATE: l April 11, 1990 This report was initiated by Off-Normal Occurrence Report 90-019.
CONDITIONS PRIOR TO EVENT:
Mode 1,'100% power. 5 DESCRIPTION OF EVENT:
Surveillance Test Procedure (STP) 170.015. " Fire Switch Functional Test.For l d XPP-0043C, CHG/SI Pump.C," verifies the fire switch capability to isolate the "C" Train Charging (CHG)/ Safety Injection-(SI) pump from it-s control circuitry in the control' room. Part of the test involves actuating a relay that would emergency.
start the "C" CHG/SI pump as well as the "B" diesel generator. Because the-scope of this procedure does-not involve starting the diesel generator. the_ procedure directs the ditsel generator mode selector switch to be placed in the maintenance j mode (thispreventsthedieselfromstarting).
On March 18, 1990, at approximately 0230, hours during performance of STP-170.015,
, an operator reset the emergency start signal as described in the procedure; however, when the diesel generator mode selector switch'was taken out of the.
maintenance position, the diesel started.- This start constitutes an inadvertent ESF actuation.
]
The diesel generator was monitored and verified to achieve proper speed and voltage 'l as required from an auto start. Also, all support systems were verified to i function properly. .j.
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- LICENSEE EVENT REPORT (LER) TEXT CONTINUATION- mnoveo ous No aison
- EX*lREg grJ1/85 7 ACILITY Nyt n) DOCKET NUMBER (21 LER NUMetR (s) PAGE (3) naa " =r,;',P -
ur#,T:
- Virgil- C.- Summer Nuclear Station 015 l o l o l o 131915 9 'l 0 -
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it%T lit snore space in tegoed, use s#conalNMC form Jt6Kni Ult CAUSE OF EVENT:
A review was done of STP-170.015 and the control circuitry for the "B" diesel-generator. This review indicated that the_ procedural step that reset-the emergency start signal specifically_ referred to the emergency start override push _ button in the main control room. The review also indicated'.that the "B" diesel generator.
circuitry is designed such that when the mode selector is in the maintenance mode =
the emergency start override push button in the main control room is disabled, but.
the local emergency start override push' button is operable. Therefore, even though-the procedure recognized that-the emergency start signal needed to be reset, the direction given to accomplish this was incorrect.- Thus, when the mode selector 7 switch was taken out of the maintenance position, the diesel generator started .
because the emergency start signal was still present.
ANALYSIS OF EVENT:
The diesel generator was aligned to stand-by conditions with the exception'of the mode selector switch and all support systems were operable. When the mode selector was taken out of the maintenance position, the diesel as well-as all required support systems started normally. With the diesel' generator running, the reliability of the 1E Bus is increased; therefore, no safety consequences occurred as a result of this event.
IMMEDI ATE CORRECTIVE ACTI.0._t!:
The diesel generator was'immediately monitored to verify proper operation.
The diesel gene,ator was then shut down and placed in standby per the applicable System Operating Procedure.
- An immediate change to the procedure to require the emergency! start signal to be reset locally (this will reset the emergency' start signal at all: times) was '
initiated. Also, an additional procedure, which performs a similar test on the "B" charging pump, was revised accordingly.
ADDITIONAL CORRECTIVE ACTION:
A meeting of the Management Review Board was held on April 3, 1990, to review this event. The purpose of the meeting was to assure that management level attention is given to the event such that plant performance is enhanced. The Board recognized that the procedure change process could have possibly identified the procedural deficiency; therefore, as a result, a review for enhancement of the procedure change process will be performed.
l u PRIOR OCCURRENCES:
l l- None.
I Na ponu 3esa