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LER-1979-094, Forwards LER 79-094/03L-0 |
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bCilll.'I'l l\\ h\\ CT te at HmNecurrant Decer.he r 07, 1979 PM-79-1093 PLtNT E. I. HATCH Licensee Event Kcport Docket No. 50-321 United States Nuclear Regulatory Qr. mission Office of Inspection and Enforcement Region II Suite 3100 101 Marietta Street Atlanta, Georgia 30303 ATTCiTION:
Mr. James P. O'Reilly Pursuant to Section 6.9.1.9.b of Hatch Unit I Technical Specifications, please find attached Reportable Occurrence Report No. 50-321/1979-94 i
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havn any discharge pretsure or flow on local l
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o, l gauges. The "B" pump was declared inoperable and a limitirrg condition for operation l DTT71 I van established per Tech Specs section 4.5.J.2.b.
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lTTT1 I twisted into.
It was also noted that the suction bell beamig showed evidence of I
ITT'f] I galling. However it is not believed that this caused the staf t failure. A section l
, 3 l of the broken shaft is being sent to a Meta 11untcal Lab to try to determine the l
JTTT) l cause of the failure. The shaf t and suction belj ' nearing wee replaced and the (cont) J e w n
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1:ve nt th r.cript ion and Probable Con accuences (cont) not af fect ed by thi; incident. I previoas failure of this nature on another plant service water pump occurred on l'thruarj 19, 1976.
't h is failuie was reported un L13t.;o. 50-321/1976-15.
Cause Description and Corrective Action (cont) purnp was reasser. bled to vendors specifications. The pur.,p was placed back in se rvice on ';averber 26, 19 79 and 11:&l-3182, Plan t Service Uater Operability Test, was performed satisfactorily.
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'. e r 21, 19 79, with t he reactor in t':e run mmte it 1001 KJL and It'41-Cldlu, Plant Service k'ater Punp, in service,a leu pressure alar:a in divisica 11 of the Plant Survice 'Jater syste: w.m received in the control room.
IP41-C00lD was idle in this loop and uas in. mediately placed in service. This resulted in the pressure returning to normal.
Upon invca:ti;;ation it was noted that the "B" pump was running, but had no discharge pressure or flow. The "B" purap was declared inoperable and a limitin;; cot..iition for operation was established per Tech Spec section 4.5.J.2.b.
This cendi tion did not trinder the continued operatica of the plant.
During disassembly of the pump, it was discovered that the line bottom shaf t had twisted into.
It was also noted that the suction bell bearing showed signs of galling. Ilowever, it is not believed that this condtion caused the shaft failure.
The shaf t and suction bell bearing were replaced and the pump was reassembled to vendors specifications. The pump was placed back in service on November 26, 1973 and HNP-1-3182, Plant Service Water Operability Test, was perforced satisfactorily.
A section of the broken shaf t is being sent to a metallurgical lab to try to detereitic the cause of the shaf t f ailure. A follow up report will be submitted when the cause for tae shaf t failure has been determined.
Af ter reviewing the history of maintenance on Plant Service Water Pumps, the only sinilar event found was reported on February 19, 1976 on LER No. 50-321/1976-15. This shaft f ailure was due to a catallic flaw in the shaft.
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CCDfj',i!l\\)',',er r e.m i iw ".: c,, r: ant De cembe r 07, 1979 P.M-79-1093
,PLV;T E. I. HATCH
'.icensee Event Kcport Docket No. 50-321 United States Nuclear Regulatory Q: mission Office of Inspection and Enforcecent Regica Il Suite 3100 101 '.arietta St reet Atlanta, Georgia 30303 ATTENTION:
P.r. James P. O'Reilly Pursuant to Section 6.9.1.9.b of Hatch Unit I Technical Specificaticas, please find attached Reportable Occurrence Report No. 50-321/1979-94.
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Plant Manageu RT5/mla xc:
J. H. Miller, J r.
R. J. Kelly W. A. Widner C. L. Cocr.in R. D. Daker Control Room File 1579 115 S
7 93 214 0 f 2 7 5
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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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