Similar Documents at Hatch |
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LER-1979-125, /03L-0:on 791114,during Routine Review of Previous Radwaste Discharges,Discovered That on 791107,while at O Mwt Power,Min Required Recirculation Time Not Met on Chemical Waste Sample Tank A.Caused by Clogged Inlet Strainer |
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| 3661979125R03 - NRC Website |
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NRC FORM 366 U. S. NUCLL AH HLGUL AiUH Y COMMibblON (7 771 L4CENSEE EVENT REPORT CONTROL BLOCK: l l
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60 61 DOCKE T NUMBEH
'd WJ EVENT DATE 14 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBA0LE CONSEQUENCES h 10121 1 On 11-14-79, during a routine review of previous liquid rad'.. aste discharges, it was l
l O l 31 discovered that, on 11-7-79, while at'0 Kit power, the minimum recirculation time 1
l prior to sampling and analysis, as required by E.T.S. sectic a 2.1.2.C, was not met on 1 0 4 la ls] l Unit II Chemical Waste Sample Tank A.
5548 gallons of this tank was subsequently 10 is 1 l discharged to the Altamaha River.
A similar event occurred on this tank during power l l0 l 7 l l operation at 2399 Mit on 11-21-79 and 70 gallons was discharged to the river.
A re-l l view of the liquid radwaste radiation monitor recordin9s for these discharges (cont) 1 0
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20 SE QUENTI AL OCCURRENCE HEPORT REVISION LE R!RO EVE NT YE AR REPORT NO.
CODE TYPE NO.
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40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Ii iO I I In both events an inspection of the pump, used for both rec' rculation and discharge, I
i i i revealed that the inlet strainer had become clogged with sr.11 bits of paper which l reduced the flow capacity of the pump. The strainer was c1 cined and the pump returned; i 2 l to service.
The pump is now in full compliance with the rc uirements and no further l i
3 l reporting is required.
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% POWE R OTHER STATUS IS O F D 3COVERY DESCRIPTION 32 (G_J@ l 0 l 0 l 0 l@l NA l
B l@l Routine Inspc : tion of dischar e permits l i s ACTIVITY CONTENT RELE ASED OF RELE ASE AMOUNT OF ACTIVITY LC ATION OF RE LE ASE lZ l @ l Z l@l NA l
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8 9 10 tt 44 45 8t PERSONNEL EXPOSURES NUMB E R TYPE
DESCRIPTION
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8 9 10 69 69 80 5 NAME OF PREPARER PF m-Radiochemist
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I Georgka Power Company Plant E.
I.
Hatch Baxley, Georgia 31513 Reportable Occurrence Report No. 50-366/79-125 Event Description and Probabic Consequences continued indicate that, although the tank was not recirculated in accordance with the E.T.S.,
adequate mixing did occur prior to sampling; i.e.,
no significant increases or, decrea se's in radiation levels were observed during the discharges.
There was no significant occurrence that took place as a result of tF*s event.
There were no probable consequences as a result of thess events.
There was no cbnormal release of radioactive material as a result of these events and no effects upon the public health and safety.
These events are non-repetitive.
O O
1614 334
t
- - p f
NARRATIVE
REPORT l:
Georgia Power Company Plant E.
I.
Hatch Baxley, Georgia "1513 Reportable Occurrence Report No. 50-366/79-125 On 11-14-79 during a routine review of previous liquid radwaste discharges, it was discoverd that, on 11-7-79, while at 0 MWt power, the minimum recirculation time prior to sampling and analysis, as required by E.T.S.
section 2.1.2.C, was not met on Unit II Chemical Waste Sample Tank A.
5548 gallons of this tank was subsequently g
discharged to the Altamaha River.
A similar event occurred on this I
tank during power operation at 2399 MWt on 11-21-79 and 70 gallons was discharged to the river.
A reviaw of the liquid radwaste l
radiation monitor recordings for these discharges indicate
- that, although the tank was not recirculated in accordance with the E.T.S.,
adequate mixing did occur prior to sampling; i.e, no significant increases or decreases in radiation levels were observed during the discharges.
The tanks were recirculated for 75 and 78 minutes each.
These values are acceptable based on the normal pumping capacity of 50 gpm.
With the flow restricted, however, to 29 gpm and 20 gpm, as in these two events, the minimum recirculation times would have had to be 112 and 163 minutes, which are 37 and 85 minutes short of the Tech Spec limit.
In both events an inspection of the pump,
used for both recirculation and discharge, revealed that the inlet strainer had become clogged with small bits of paper which reduced the flow capacity of the pump.
The strainer was cleaned and the pump returned to service.
The pump is now in full compliance with the requirements and no f'arther reporting is required.
1614 335
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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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