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LER-1979-129, /03L-0:on 791129,while Performing Procedure HNP-2-3303,HPCI Pump Rated Flow,Thermal Overloads of HPCI Auxiliary Oil Pump Breaker Tripped While HPCI Turbine Being Decreased.Caused by Personnel Error.Thermal Overloads Reset |
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| 3661979129R03 - NRC Website |
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40 41 42 43 44 47 CAUSE DESCHIPTION AND CORRECTIVE AC1 TONS h p-~'-l l The f ailure of the IIPCI Auxiliary oil pump van due to personnel error as the IIPCI l
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Reportable Occurrence Report No. 50-366/1979-129 t
Cause Description and Corrective Actions (cont) overloads reset.
Procedure llSP-2-3303 was then perforiaed correctly and' found l
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Procedure llNP-2-3303 ull1.be reviewed to con fitta that sufficient precautions i
are p,1ven to insure that the llPCL Turbine will not be run below 2l00 RPM; also, the 11PCi ~a xiliary oil pump cont rol circuit will be reviewed to determine if a timer should be added to the pressure switch ci rcuit.
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NARRATIVE
REPORT f
Georgia Power Company Plant E. 1. Ilatch j
Baxley, Georgia 31513 l
Reportable Occurrence Report No. 50-366/1979-129 With the reactor at 100% power, on November 29, 1979, the thermal overloads of the llPC1 Auxiliary 011 Pump tripped while performing procedure llNP-2-3303.
The llPCI turbine was secured and the system declared inoperable per Technical Spe ci fi ca t ion 3. 5.1.
Operablility of Reactor Core Isolation Cooling, Automatic Depressurization, Core Spray and Low Pressure Coolant Injection was then ascertained by veri fying t. hat the survel))ances were complete and satisf actory.
Although there have been other failures of the llPCI system, re f e ren ce Reportable Occurrence Eeport No. 50-366/1979-116, this occurrence was not repetitive because a corrponent did not f all but personnel were in error.
Instead of tripping the turbine at 2l00 RPM, af ter running it at rated flow as required by procedure and allowing it to.const down, i t was b rough t.down gradually by manual control to approximately 1000 RP:1. This allowed the auxiliary oil pump, which is controlled by a pressure swi tch in the oil system, t o be aided by the shaf t driven oil pu ip and cycle on and off which caused the breaker thernal overloads to t rip.
The auxt]Iary oil pump and motor were checked for damage and the thermal overloads reset.
P roce dure llNP-2-3303 uns then performed correctly and found satisf actorily on Novembe r 30, 1979.
P rocedu re llNP-2-3303 uill be reviewed to confi rm that suf ficient precautions are given to lusure that the llPCI Turbine will not be run below 2100 RPM; also, the llPCI auxiliary oil pump cont rol circuit will be reviewed to determine if l
anything can be added that w1]l help prevent a re-occurrence of this incidtut.
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| 05000366/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000366/LER-1979-001-03, /03L-0 on 781229:in Cold Shutdown While Performing HNP-2-3154,reactor Water Level Instrument Switch 1 Was Found Inoperative Due to Broken Foot, & Switch 3 Actuated at 122.2 in H2O Input | /03L-0 on 781229:in Cold Shutdown While Performing HNP-2-3154,reactor Water Level Instrument Switch 1 Was Found Inoperative Due to Broken Foot, & Switch 3 Actuated at 122.2 in H2O Input | | | 05000321/LER-1979-001, Forwards LER 79-001/03L-0 | Forwards LER 79-001/03L-0 | | | 05000321/LER-1979-001-03, /03L-0 on 790109:during Steady State Power at 2400 Mwt,Plant Personnel Inadvertently Opened Both Doors of Reactor Bldg 130-ft Airlock R106.For Reasons Unknown,Switch Which Allows Defeat of Interlock Was Operated | /03L-0 on 790109:during Steady State Power at 2400 Mwt,Plant Personnel Inadvertently Opened Both Doors of Reactor Bldg 130-ft Airlock R106.For Reasons Unknown,Switch Which Allows Defeat of Interlock Was Operated | | | 05000321/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000321/LER-1979-002-03, /03L-0 on 790111:during Normal Operation,Hpci Steam Supply valves,E41-F002 & E41-F003,automatically Isolated Due to Equipment Room High Differential Temp & Cold Outside Air Flowing Across Inlet Air Temp Elements | /03L-0 on 790111:during Normal Operation,Hpci Steam Supply valves,E41-F002 & E41-F003,automatically Isolated Due to Equipment Room High Differential Temp & Cold Outside Air Flowing Across Inlet Air Temp Elements | | | 05000366/LER-1979-002, Forwards LER 79-002/03L-0 | Forwards LER 79-002/03L-0 | | | 05000366/LER-1979-002-03, /03L-0 on 791231:in Cold Shutdown While Performing HNP-2-3456,overvoltage Trip Setpoint for Reactor Protection Sys Motor Generator Set B Was Found at 133.5 Volts Alternating Current.Caused by Setpoint Drift | /03L-0 on 791231:in Cold Shutdown While Performing HNP-2-3456,overvoltage Trip Setpoint for Reactor Protection Sys Motor Generator Set B Was Found at 133.5 Volts Alternating Current.Caused by Setpoint Drift | | | 05000321/LER-1979-003-03, /03L-0 on 790114:during Normal operation,hi-flow Alarm Occurred on Stack Effluent Radiation Monitor.Sample Pump Was Found Not Running.Restart Failed,As Did Spare Pump. Caused by Failure of Operating Pump Carbon Valves | /03L-0 on 790114:during Normal operation,hi-flow Alarm Occurred on Stack Effluent Radiation Monitor.Sample Pump Was Found Not Running.Restart Failed,As Did Spare Pump. Caused by Failure of Operating Pump Carbon Valves | | | 05000321/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000366/LER-1979-003, Forwards LER 79-003/03L-0 | Forwards LER 79-003/03L-0 | | | 05000366/LER-1979-003-03, /03L-0 on 790102:in Cold Shutdown While Performing HNP-2-3173 on Reactor Pressure Switch 2B21-N021C,setpoint Found Above 600 Psig for Switch No 2.Caused by Switch Setpoint Drift | /03L-0 on 790102:in Cold Shutdown While Performing HNP-2-3173 on Reactor Pressure Switch 2B21-N021C,setpoint Found Above 600 Psig for Switch No 2.Caused by Switch Setpoint Drift | | | 05000321/LER-1979-004-03, /03L-0 on 790119:during Performance of Procedure HNP-1-3302,armature Winding of HPCI Injecting Valve Motor (E41-F006) Burned When Valve Was Opening.Minor Internal Disorder Probably Led to Overheat | /03L-0 on 790119:during Performance of Procedure HNP-1-3302,armature Winding of HPCI Injecting Valve Motor (E41-F006) Burned When Valve Was Opening.Minor Internal Disorder Probably Led to Overheat | | | 05000366/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000366/LER-1979-004-03, /03L-0 on 790104:review of HNP-2-3610-0 (RHR Pump Operability) Data Sheet Revealed Pump Delta Requirements Not Met.Caused by Personnel Error Resulting from New Procedures | /03L-0 on 790104:review of HNP-2-3610-0 (RHR Pump Operability) Data Sheet Revealed Pump Delta Requirements Not Met.Caused by Personnel Error Resulting from New Procedures | | | 05000321/LER-1979-004, Forwards LER 79-004/03L-0 | Forwards LER 79-004/03L-0 | | | 05000366/LER-1979-005-03, /03L-0 on 790103:under Frequency Trip Setpoint Found at 54.1HZ for Motor Generator Set A.Caused by pre-op Test on Sys.Surveillance Test HNP-2-3456 Contains Setpoint More Conservative than Tech Specs | /03L-0 on 790103:under Frequency Trip Setpoint Found at 54.1HZ for Motor Generator Set A.Caused by pre-op Test on Sys.Surveillance Test HNP-2-3456 Contains Setpoint More Conservative than Tech Specs | | | 05000366/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000321/LER-1979-005, Forwards LER 79-005/03L-0 | Forwards LER 79-005/03L-0 | | | 05000321/LER-1979-005-03, /03L-0 on 790118:while Performing HNP-1-350-M,TDR G31-R616D Failed to Actuate at Its Setting of 15-s.Two-h Time Limit Exceeded W/Sys Down for Repair.Caused by Loose Screw on Diaphragm,Resulting in Component Failure | /03L-0 on 790118:while Performing HNP-1-350-M,TDR G31-R616D Failed to Actuate at Its Setting of 15-s.Two-h Time Limit Exceeded W/Sys Down for Repair.Caused by Loose Screw on Diaphragm,Resulting in Component Failure | | | 05000366/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000366/LER-1979-006-03, /03L-0 on 790102:reactor Pressure Instrument Ft&C, Relay 2B21-K34A Failed to Operate W/Actuation of 2B21-N021A. Caused by Open Coil | /03L-0 on 790102:reactor Pressure Instrument Ft&C, Relay 2B21-K34A Failed to Operate W/Actuation of 2B21-N021A. Caused by Open Coil | | | 05000321/LER-1979-006, Forwards LER 79-006/03L-0 | Forwards LER 79-006/03L-0 | | | 05000321/LER-1979-006-03, /03L-0 on 790122:during Normal Startup,Reactor Operated Above 1% for Over 24-h W/O Critical Mass Peaking Factor Being Calculated.Caused by Computer Limitations for Low Power Operation | /03L-0 on 790122:during Normal Startup,Reactor Operated Above 1% for Over 24-h W/O Critical Mass Peaking Factor Being Calculated.Caused by Computer Limitations for Low Power Operation | | | 05000321/LER-1979-007, Forwards LER 79-007/03L-0 | Forwards LER 79-007/03L-0 | | | 05000321/LER-1979-007-03, /03L-0 on 790120:reactor Core Isolation Cooling Min Flow Valve (E51-F019) Failed to Close Automatically. Caused by Failure of Open Limit Switch,Resulting in Damage to Valve Operator & Torque Switch | /03L-0 on 790120:reactor Core Isolation Cooling Min Flow Valve (E51-F019) Failed to Close Automatically. Caused by Failure of Open Limit Switch,Resulting in Damage to Valve Operator & Torque Switch | | | 05000321/LER-1979-008-03, /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure | /03L-0 on 790121:reactor Max Cooling Rate Exceeded Due to Injection of Condensate Feedwater Into Reactor Vessel During Slowdown.Caused by Pressure Decreasing Below Condensate Booster Pump Discharge Pressure | | | 05000366/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000366/LER-1979-008-03, /03L-0 on 790110:reactor Core Isolation Cooling Steam Line Differential Pressure Low Switch Found to Actuate at 119 in H2O & High Switch at +122 in H2O.Caused by Switch Setpoint Drift | /03L-0 on 790110:reactor Core Isolation Cooling Steam Line Differential Pressure Low Switch Found to Actuate at 119 in H2O & High Switch at +122 in H2O.Caused by Switch Setpoint Drift | | | 05000321/LER-1979-008, Forwards LER 79-008/03L-0 | Forwards LER 79-008/03L-0 | | | 05000366/LER-1979-009-03, /03L-0 on 790111:low Switch & High Switch of 2E51-NO18 Operated Contrary to Tech Specs.Caused by Switch Setpoint Drift.Corrected by Performance of HNP-2-5202 Procedure | /03L-0 on 790111:low Switch & High Switch of 2E51-NO18 Operated Contrary to Tech Specs.Caused by Switch Setpoint Drift.Corrected by Performance of HNP-2-5202 Procedure | | | 05000366/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000321/LER-1979-009, Forwards LER 79-009/03L-0 | Forwards LER 79-009/03L-0 | | | 05000321/LER-1979-009-03, /03L-0 on 790123:during Normal Operation,While Performing Maint on Reactor Water Cleanup Pumps,Personnel Unable to Sample Primary Coolant Every 4-h.Caused by Stopped Up Redundant Sample Line | /03L-0 on 790123:during Normal Operation,While Performing Maint on Reactor Water Cleanup Pumps,Personnel Unable to Sample Primary Coolant Every 4-h.Caused by Stopped Up Redundant Sample Line | | | 05000321/LER-1979-010-03, /03L-0 on 790124:during Normal pre-conditional Ramp,Determined That a Reactor Coolant Chemistry Sample Could Not Be Obtained.Caused by Both Reactor Water Cleanup Pumps Being Inoperable & Primary Sample Line Clogged | /03L-0 on 790124:during Normal pre-conditional Ramp,Determined That a Reactor Coolant Chemistry Sample Could Not Be Obtained.Caused by Both Reactor Water Cleanup Pumps Being Inoperable & Primary Sample Line Clogged | | | 05000321/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000366/LER-1979-010, Forwards LER 79-010/03L-0 | Forwards LER 79-010/03L-0 | | | 05000366/LER-1979-010-03, /03L-0 on 790117:in Cold Shutdown,While Performing HNP-2-3820,switches 2B21-N301 F,H & L Did Not Actuate.Caused by Switch Diaphragm Failure | /03L-0 on 790117:in Cold Shutdown,While Performing HNP-2-3820,switches 2B21-N301 F,H & L Did Not Actuate.Caused by Switch Diaphragm Failure | | | 05000321/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000366/LER-1979-011, Forwards LER 79-011/03L-0 | Forwards LER 79-011/03L-0 | | | 05000366/LER-1979-011-03, /03L-0 on 790117:during Normal Startup Test & Reactor in Cold Shutdown,Review of HNP-2-3160 (RHR Pump Operability) Revealed Required Flow Not Being Met.Caused by Procedural Error by Personnel | /03L-0 on 790117:during Normal Startup Test & Reactor in Cold Shutdown,Review of HNP-2-3160 (RHR Pump Operability) Revealed Required Flow Not Being Met.Caused by Procedural Error by Personnel | | | 05000321/LER-1979-011-03, /03L-0 on 790124:while in Cold Shutdown,Both Doors of Reactor Bldg Were Opened,Violating Secondary Containment. Bracket Into Which Dead Bolt Projects Was Bent,Preventing Interlock from Functioning.Bracket Was Repaired | /03L-0 on 790124:while in Cold Shutdown,Both Doors of Reactor Bldg Were Opened,Violating Secondary Containment. Bracket Into Which Dead Bolt Projects Was Bent,Preventing Interlock from Functioning.Bracket Was Repaired | | | 05000366/LER-1979-012, Has Been Voided | Has Been Voided | | | 05000321/LER-1979-012-03, /03L-0 on 790124:during Shutdown,High Pressure of 200 to 300 Psig Existed in RHR Heat Exchangers.Caused by Slow Leak Past E11-F015A Valve | /03L-0 on 790124:during Shutdown,High Pressure of 200 to 300 Psig Existed in RHR Heat Exchangers.Caused by Slow Leak Past E11-F015A Valve | | | 05000321/LER-1979-012, Forwards LER 79-012/03L-0 | Forwards LER 79-012/03L-0 | | | 05000366/LER-1979-013, Forwards LER 79-013/03L-0 | Forwards LER 79-013/03L-0 | | | 05000321/LER-1979-013-01, /01X-1 on 790131:scram Received on Intermediate Range Monitor Hi-Hi Trip at Notch 26 of Rod 42-15.Caused by Notches Being Withdrawn Past Point Required to Achieve Criticality.Procedures Revised | /01X-1 on 790131:scram Received on Intermediate Range Monitor Hi-Hi Trip at Notch 26 of Rod 42-15.Caused by Notches Being Withdrawn Past Point Required to Achieve Criticality.Procedures Revised | | | 05000366/LER-1979-013-03, /03L-0 on 790125:while in Refuel Mode,Control Rod & Control Rod Drive Removal Was Begun Before Performing one- Rod Out Refueling Interlock Operability Test.Caused by Omission of This Step in Procedure.Procedure to Be Revised | /03L-0 on 790125:while in Refuel Mode,Control Rod & Control Rod Drive Removal Was Begun Before Performing one- Rod Out Refueling Interlock Operability Test.Caused by Omission of This Step in Procedure.Procedure to Be Revised | | | 05000321/LER-1979-013, Foward LER 79-013/01X-1 | Foward LER 79-013/01X-1 | | | 05000321/LER-1979-014, Forwards LER 79-014/03L-0 | Forwards LER 79-014/03L-0 | |
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