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LER-1979-094, /03L-0:on 791121,while Reactor in Run Mode, Discovered B Pump Running W/O Discharge Pressure or Flow on Local Gauges.Caused by Breaking of Pump Line Bottom Shaft. Shaft & Suction Bell Replaced |
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| 3211979094R03 - NRC Website |
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33 34 Jh Jo 3J 40 44 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h Q l During disasse :bly of the pumo, it was discovered that the Iine bottom shaf t had l
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I'v. ut Desc ript ion anel Prob.ible Cen,ct;us ices (cont) not ef fe.-t o J hy t hin jncident. A previous failure of this nature on another plant service water pune occurred on ribruary 19, 1976. This failure was repc,rted un LE:t No. 50-321/19 6-13.
Cause Description and Corrective Action (cont) pump was reassembled to vendors specifications. The purp was placed back in service on ':avember 26, 1979 and it:bl-3132, Plant Service Uater Operability Test, was performad satisfactorily.
100R OREE 1579 117
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On k'ede t :.' v., hvt M e r 21, 1979, with the reactor in the run mmle at 100I FMt.snd IP41-COdlB Plant S e rvice '.'a t e r P unp, in servic e, a lew p ressure alarm in divisica II of the Plant Service 'iater system was received in the ceatrol roon.
IP41-C001D was idle in this loop and was in; mediately placed in service. This resulted in the pressure returting to normal.
Upon investi;;ation it was noted that the "B" pump was riu nine,, but had no discharge pressure or flow. The "B" pur.;p was declared inoperable and a limitir.; condition for operation was estab.ished per Tech Spec section 4.5.J.2.5.
This coadition did not trinder the continued operation of the plant.
During disansembly of the pump, it was discovered that the line hnttom shaft had twisted into. It was also noted that the suction bell bearing showed signs of galling. Itoweve r, it is not believed that this condtion caused the shaft failure.
The shaf t and suction bell bearing were replaced and the pump was reassc= bled to venders specifications. The pu=p was placed back in service on November 26, 1979 and IISP-1-3182, Plant Service Water Operability Test, was performed satisfactorily.
A section of the broken shaf t is being sent to a metallurgical lab to try to deter =ine the cause of the shaf t f ailure. A follow up report will be submitted when the cause for the shaf t failure has been determined.
Af ter revicwing the history of maintenance on Plant Service Water Pumps, the only sir ilar event found was reported on February 19, 1976 on 1.ER No. 50-321/19 76-15.
This shaft failure was due to a cetallic finw in the shaft.
P00R ORBlML 1579 118
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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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