| | | Reporting criterion |
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| 05000278/LER-1985-001-02, :on 850101,w/plant at 85% Power,Inverter Supplying Power to HPCI Instrumentation Failed.Caused by Three Failed Microfared Capacitors.Hpci Declared Inoperable Until Failed Inverter Replaced |
- on 850101,w/plant at 85% Power,Inverter Supplying Power to HPCI Instrumentation Failed.Caused by Three Failed Microfared Capacitors.Hpci Declared Inoperable Until Failed Inverter Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000277/LER-1985-001, :on 850108,containment Leak Test Program Identified That Total Combined Leakage of Types B & C Tests Exceeded Allowable Leak Rate Limit.Caused by Valves W/Excessive Leakage Rates.Valves Repaired |
- on 850108,containment Leak Test Program Identified That Total Combined Leakage of Types B & C Tests Exceeded Allowable Leak Rate Limit.Caused by Valves W/Excessive Leakage Rates.Valves Repaired
| 10 CFR 50.73(a)(2)(1) |
| 05000278/LER-1985-002, :on 850220,automatic Start Capability of RHR & Core Spray Sys Defeated to Permit Repairs to MSIVs W/O Reactor Mode Switch in Refuel Position.Caused by Failure of Operator to Assure Switch in Shutdown Position |
- on 850220,automatic Start Capability of RHR & Core Spray Sys Defeated to Permit Repairs to MSIVs W/O Reactor Mode Switch in Refuel Position.Caused by Failure of Operator to Assure Switch in Shutdown Position
| |
| 05000277/LER-1985-002-01, :on 850530,reactor Protection Sys Initiated Scram Signal on Reactor High Pressure During Excess Flow Check Valve Test.Caused by Personnel Response to Leak in Excess Flow Check Valve.Scram Signal Reset |
- on 850530,reactor Protection Sys Initiated Scram Signal on Reactor High Pressure During Excess Flow Check Valve Test.Caused by Personnel Response to Leak in Excess Flow Check Valve.Scram Signal Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1985-003, :on 850601 & 03,Loop a RHR Sys Outboard Injection Valve Failed.Caused by Improper Operation.Valve Thrust Assembly Rebuilt & Returned to Svc |
- on 850601 & 03,Loop a RHR Sys Outboard Injection Valve Failed.Caused by Improper Operation.Valve Thrust Assembly Rebuilt & Returned to Svc
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000278/LER-1985-003, :on 850109,during Surveillance Testing of HPCI Logic Sys,Hpci Turbine Could Not Be Tripped & Declared Inoperable.Caused by Relay Piston Binding Due to Paraffin on Piston.Piston Cleaned |
- on 850109,during Surveillance Testing of HPCI Logic Sys,Hpci Turbine Could Not Be Tripped & Declared Inoperable.Caused by Relay Piston Binding Due to Paraffin on Piston.Piston Cleaned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function |
| 05000277/LER-1985-003-02, :on 850603,loop a RHR Sys Injection Valve MO-2-10-154A Declared Inoperable.Caused by Mechanical Binding of Valve Stem in Valve Operator.Valve Operator Rebuilt & Returned to Svc |
- on 850603,loop a RHR Sys Injection Valve MO-2-10-154A Declared Inoperable.Caused by Mechanical Binding of Valve Stem in Valve Operator.Valve Operator Rebuilt & Returned to Svc
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability |
| 05000278/LER-1985-004-01, :on 850126,during Surveillance Testing,Hpci Turbine Exhaust Rupture Diaphragm Alarm Annunciated Following Startup.Caused by Failed Rupture Inner Disc PSD3-23-6.Disc Replaced |
- on 850126,during Surveillance Testing,Hpci Turbine Exhaust Rupture Diaphragm Alarm Annunciated Following Startup.Caused by Failed Rupture Inner Disc PSD3-23-6.Disc Replaced
| |
| 05000277/LER-1985-004-01, :on 850622,during Cold Shutdown,Actuation of Reactor Protection Sys & Primary Containment Isolation Sys Occurred.Caused by Reactor Level Transmitter Being Returned to Svc & Backfilled.Signals Reset |
- on 850622,during Cold Shutdown,Actuation of Reactor Protection Sys & Primary Containment Isolation Sys Occurred.Caused by Reactor Level Transmitter Being Returned to Svc & Backfilled.Signals Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1985-005, :on 850612,intermediate Range Monitors F & B Discovered Inoperable W/Reactor Protection Sys Channel B Logic Out of Tripped Condition,Violating Tech Specs.Caused by Procedural Deficiency.Procedure Revised |
- on 850612,intermediate Range Monitors F & B Discovered Inoperable W/Reactor Protection Sys Channel B Logic Out of Tripped Condition,Violating Tech Specs.Caused by Procedural Deficiency.Procedure Revised
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1985-005-02, :on 850612,w/reactor Mode Switch in Refuel Position,Intermediate Range Monitor Detectors F&B of Neutron Monitoring Sys Inoperable.Caused by Deficiency in Blocking Sequence.Sequence Will Be Revised |
- on 850612,w/reactor Mode Switch in Refuel Position,Intermediate Range Monitor Detectors F&B of Neutron Monitoring Sys Inoperable.Caused by Deficiency in Blocking Sequence.Sequence Will Be Revised
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-005-01, :on 850129,total Combined Leakage of Types B & C Tests Exceeded Allowable Leak Rate Limit.Valves W/Unacceptable Leak Rates Repaired & Retested |
- on 850129,total Combined Leakage of Types B & C Tests Exceeded Allowable Leak Rate Limit.Valves W/Unacceptable Leak Rates Repaired & Retested
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-006-01, :on 850220,RCIC Inboard Steam Isolation Valve Mo 3-13-15 Found Fitted W/Incorrect Limitorque Operator.No Addl Unsatisfactory Operators Found.Valve Fitted W/Correct Operator |
- on 850220,RCIC Inboard Steam Isolation Valve Mo 3-13-15 Found Fitted W/Incorrect Limitorque Operator.No Addl Unsatisfactory Operators Found.Valve Fitted W/Correct Operator
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1985-006-02, :on 850624,improper Limitorque Operator Found on Outboard Main Steam Line Drain Valve W/Unit in Extended Refuel Outage.Caused by Personnel Error.Proper Operator Installed & Training Session Conducted |
- on 850624,improper Limitorque Operator Found on Outboard Main Steam Line Drain Valve W/Unit in Extended Refuel Outage.Caused by Personnel Error.Proper Operator Installed & Training Session Conducted
| |
| 05000277/LER-1985-006-03, :on 850627,during Cold Shutdown for Refuel & Mod Work,Full Scram on Intermediate Range Monitor High Flux Signal Occurred.Caused by Maint Personnel Working in Subpile Room Bumping Two High Voltage Cables |
- on 850627,during Cold Shutdown for Refuel & Mod Work,Full Scram on Intermediate Range Monitor High Flux Signal Occurred.Caused by Maint Personnel Working in Subpile Room Bumping Two High Voltage Cables
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-007-01, :on 850301,during Startup from Maint Outage at 30% Power,Reactor Scrammed from Main Condenser Low Vacuum. Caused by Leak on Feedwater Heater A2 Shell Side Relief valve.Leak-off Plug Installed |
- on 850301,during Startup from Maint Outage at 30% Power,Reactor Scrammed from Main Condenser Low Vacuum. Caused by Leak on Feedwater Heater A2 Shell Side Relief valve.Leak-off Plug Installed
| |
| 05000277/LER-1985-007-02, :on 850628,reactor Protection Sys & Primary Containment Isolation Sys Initiated Due to False Reactor Low Water Level.Caused by Backfilling Instrument Sensing Lines During Maint.Backfilling Method Reviewed |
- on 850628,reactor Protection Sys & Primary Containment Isolation Sys Initiated Due to False Reactor Low Water Level.Caused by Backfilling Instrument Sensing Lines During Maint.Backfilling Method Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-008-01, :on 850313,suppression Pool Water Level Rose to 15.3 ft,0.4 Ft Above Tech Spec Limit.Caused by Operator Mistakenly Opening Torus Test Bypass Valve.Torus Pump Used to Lower Water Level & Operator Disciplined |
- on 850313,suppression Pool Water Level Rose to 15.3 ft,0.4 Ft Above Tech Spec Limit.Caused by Operator Mistakenly Opening Torus Test Bypass Valve.Torus Pump Used to Lower Water Level & Operator Disciplined
| |
| 05000277/LER-1985-008-02, :on 850725,tests Performed on Fire Barrier Penetrations W/Ceramic fiber-polyurethane Foam Showed Areas W/Polyurethane on Fire Side of Wall Failed Test.Hourly Fire Watches Established |
- on 850725,tests Performed on Fire Barrier Penetrations W/Ceramic fiber-polyurethane Foam Showed Areas W/Polyurethane on Fire Side of Wall Failed Test.Hourly Fire Watches Established
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1985-008, :on 850725,determined That Fire Barrier Penetrations Containing Ceramic fiber-polyurethane Foam Unacceptable.Caused by Incorrect Results from Tests Performed on 831103.Barriers Upgraded |
- on 850725,determined That Fire Barrier Penetrations Containing Ceramic fiber-polyurethane Foam Unacceptable.Caused by Incorrect Results from Tests Performed on 831103.Barriers Upgraded
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-009-01, :on 850328,insp Plate Discovered Missing from Standby Gas Treatment Sys Suction Plenum,Affecting Secondary Containment Capacity.Caused by Maint Personnel Removing Plate for Fan Insp.Plate Reinstalled |
- on 850328,insp Plate Discovered Missing from Standby Gas Treatment Sys Suction Plenum,Affecting Secondary Containment Capacity.Caused by Maint Personnel Removing Plate for Fan Insp.Plate Reinstalled
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1985-009-02, :on 850629,full Scram & Groups I,Ii & III Isolation Occurred W/Unit in Cold Shutdown.Caused by False Low Level Signal During Backfilling.Signal Reset & Use of Portable Backfilling Device Suspended |
- on 850629,full Scram & Groups I,Ii & III Isolation Occurred W/Unit in Cold Shutdown.Caused by False Low Level Signal During Backfilling.Signal Reset & Use of Portable Backfilling Device Suspended
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1985-010-02, :on 850629,initiation of ECCS & Diesel Generator Start Occurred W/Unit in Cold Shutdown.Caused by Inadvertent Reactor Low Level Signal.Use of Portable Backfilling Device Suspended |
- on 850629,initiation of ECCS & Diesel Generator Start Occurred W/Unit in Cold Shutdown.Caused by Inadvertent Reactor Low Level Signal.Use of Portable Backfilling Device Suspended
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-010-01, :on 850410,diesel Generators E-1 & E-3 Started & Drywell Coolers Tripped After Receiving False Reactor Low Level Signal.Caused by Defective Test Equipment Used During Surveillance Test.Generators Shut Down |
- on 850410,diesel Generators E-1 & E-3 Started & Drywell Coolers Tripped After Receiving False Reactor Low Level Signal.Caused by Defective Test Equipment Used During Surveillance Test.Generators Shut Down
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-011, :on 850621,discovered That Fire Watch Not Established for Fire Barriers Between MSIV Room & Torus Room,Per Tech Specs.Caused by Error in Design Drawings & Personnel Oversight.All Drawings Reviewed |
- on 850621,discovered That Fire Watch Not Established for Fire Barriers Between MSIV Room & Torus Room,Per Tech Specs.Caused by Error in Design Drawings & Personnel Oversight.All Drawings Reviewed
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-011-01, :on 850621,fire Watch Not Established for Degraded Fire Barrier.Caused by Design Drawing & Personnel Errors.Fire Watch Established & Penetration Seal Drawings Corrected.Penetrations Will Be Sealed |
- on 850621,fire Watch Not Established for Degraded Fire Barrier.Caused by Design Drawing & Personnel Errors.Fire Watch Established & Penetration Seal Drawings Corrected.Penetrations Will Be Sealed
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1985-011-02, :on 850805,full Scram & Groups II & III Isolations Occurred During Main Turbine Control Valve Surveillance Testing.Caused by Decrease in Relayed Emergency Trip Sys.Signals Reset & Affected Sys Restored |
- on 850805,full Scram & Groups II & III Isolations Occurred During Main Turbine Control Valve Surveillance Testing.Caused by Decrease in Relayed Emergency Trip Sys.Signals Reset & Affected Sys Restored
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1985-012-02, :on 850807,full Scram Resulted from High Neutron Flux Trip on Intermediate Range Monitors C & D. Caused by Personnel Error.General Plant Procedure GP-2 Will Be Revised |
- on 850807,full Scram Resulted from High Neutron Flux Trip on Intermediate Range Monitors C & D. Caused by Personnel Error.General Plant Procedure GP-2 Will Be Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-012-01, :on 850807,during off-loading of Reactor Fuel Core,Peripheral Fuel Bundle Isolated from Source Range Monitor.Caused by Inadequate Temporary Procedure Change & Personnel Error.Procedure Modified Further |
- on 850807,during off-loading of Reactor Fuel Core,Peripheral Fuel Bundle Isolated from Source Range Monitor.Caused by Inadequate Temporary Procedure Change & Personnel Error.Procedure Modified Further
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1985-013-01, :on 850812 & 19,Loop a RHR Sys Outboard Injection Valve Declared Inoperable.Caused by Mechanical Interference & Binding in Valve Yoke Assembly.Assembly Rebuilt Following Each Event |
- on 850812 & 19,Loop a RHR Sys Outboard Injection Valve Declared Inoperable.Caused by Mechanical Interference & Binding in Valve Yoke Assembly.Assembly Rebuilt Following Each Event
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-013, :on 850726,crack Indications Found in 40 RHR & Recirculation Piping Welds.Caused by Igscc.Eighteen Weld Overlays Repaired.Recirculation Inlet Safe Ends to Be Replaced During Next Refueling Outage |
- on 850726,crack Indications Found in 40 RHR & Recirculation Piping Welds.Caused by Igscc.Eighteen Weld Overlays Repaired.Recirculation Inlet Safe Ends to Be Replaced During Next Refueling Outage
| |
| 05000277/LER-1985-014-01, :on 850820,scram Signal & Groups II & III Isolation Occurred Due to Low Reactor Water Level.Caused by Slow Response of Controller LIC-8091 & Employee Error. Controller Tuned & Tested |
- on 850820,scram Signal & Groups II & III Isolation Occurred Due to Low Reactor Water Level.Caused by Slow Response of Controller LIC-8091 & Employee Error. Controller Tuned & Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-014-02, :on 850826,during in-vessel Inservice Insp Program,Crack Indication on 240 Degree Azimuth Core Spray Supply Junction Box Discovered.Caused by Intergranular Stress Corrosion.Brackets Installed |
- on 850826,during in-vessel Inservice Insp Program,Crack Indication on 240 Degree Azimuth Core Spray Supply Junction Box Discovered.Caused by Intergranular Stress Corrosion.Brackets Installed
| |
| 05000277/LER-1985-015-01, :on 850822,full Scram & Primary Containment Isolation Sys Groups II & III Initiated Due to Reactor Low Level Signal.Caused by Pressure Transmitter PT-53 Block Valve Leak.Block Valve Replaced |
- on 850822,full Scram & Primary Containment Isolation Sys Groups II & III Initiated Due to Reactor Low Level Signal.Caused by Pressure Transmitter PT-53 Block Valve Leak.Block Valve Replaced
| |
| 05000278/LER-1985-015, :on 850930,total Leakage of Type B & C Test Exceeded Leak Rate Limit.Caused by Several Valves Tested W/ Excessive Rates Contributing to Total.Valve Repaired & Retested Prior to Returning Unit to Operation |
- on 850930,total Leakage of Type B & C Test Exceeded Leak Rate Limit.Caused by Several Valves Tested W/ Excessive Rates Contributing to Total.Valve Repaired & Retested Prior to Returning Unit to Operation
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-015-02, :on 850930,combined Leakage of Type B & C Containment Leak Tests Exceeded Allowable Leak Rate Limit. Cause Will Be Investigated During Valve Insp.Valves to Be Repaired & Retested |
- on 850930,combined Leakage of Type B & C Containment Leak Tests Exceeded Allowable Leak Rate Limit. Cause Will Be Investigated During Valve Insp.Valves to Be Repaired & Retested
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-016, :on 841224,HPCI Turbine Exhaust Rupture Diaphragm Alarm Annunciated During Operation of HPCI Turbine.Caused by Failure of Inner Rupture Disk PSD3-23-6. Rupture Disk Replaced |
- on 841224,HPCI Turbine Exhaust Rupture Diaphragm Alarm Annunciated During Operation of HPCI Turbine.Caused by Failure of Inner Rupture Disk PSD3-23-6. Rupture Disk Replaced
| |
| 05000277/LER-1985-016-02, :on 850826,full Scram & Primary Containment Isolation Sys Groups II & III Initiated Due to Reactor Low Level Signal.Caused by Failure to Ensure That Pressure Transmitter Returned to Svc from 850822 Event |
- on 850826,full Scram & Primary Containment Isolation Sys Groups II & III Initiated Due to Reactor Low Level Signal.Caused by Failure to Ensure That Pressure Transmitter Returned to Svc from 850822 Event
| |
| 05000278/LER-1985-016-03, :on 851018,scram & Group I-III Isolations Occurred Due to Inadvertent Deenergization of Reactor Protection Sys & Primary Containment Isolation Sys Logic. Caused by Procedural Error |
- on 851018,scram & Group I-III Isolations Occurred Due to Inadvertent Deenergization of Reactor Protection Sys & Primary Containment Isolation Sys Logic. Caused by Procedural Error
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-017-02, :on 851018,reactor Protection Sys Initiated Full Scram Signal Due to False intermediate-range Monitor High Flux Signal.Caused by Personnel Bumping Cable. Technicians Made Aware of Event |
- on 851018,reactor Protection Sys Initiated Full Scram Signal Due to False intermediate-range Monitor High Flux Signal.Caused by Personnel Bumping Cable. Technicians Made Aware of Event
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1985-017-01, :on 850825,suppression Pool Vol in Torus Dropped Below Tech Spec Limit.Caused by Use of Torus Water Filter Pump to Reduce Torus Water Vol.Condensate Storage Tank Water Used to Restore Torus Vol |
- on 850825,suppression Pool Vol in Torus Dropped Below Tech Spec Limit.Caused by Use of Torus Water Filter Pump to Reduce Torus Water Vol.Condensate Storage Tank Water Used to Restore Torus Vol
| 10 CFR 50.73(a)(2)(1) |
| 05000277/LER-1985-018-01, :on 850912,reactor Water Cleanup Sys Inboard & Outboard Suction Valves Closed Due to High Flow Isolation Signal.Caused by Too Rapid Opening of Demineralizer Outlet Valve.Operator Instructed on Proper Procedures |
- on 850912,reactor Water Cleanup Sys Inboard & Outboard Suction Valves Closed Due to High Flow Isolation Signal.Caused by Too Rapid Opening of Demineralizer Outlet Valve.Operator Instructed on Proper Procedures
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-018-02, :on 840711,fault Occurred in cross-tie Between North & South Substations During Lightning Storm.Caused by Insulator Strip Flashover Due to Lightning Strike.Offsite Power Restored to Plant Startup Bus |
- on 840711,fault Occurred in cross-tie Between North & South Substations During Lightning Storm.Caused by Insulator Strip Flashover Due to Lightning Strike.Offsite Power Restored to Plant Startup Bus
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-019-02, :on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset |
- on 851116,RWCU Sys Isolated on Unexpected High Temp Signal.Caused by Instrument Technicians Troubleshooting Wrong Temp Element on RWCU sys.TE-3-12-98 Leads Reconnected & RWCU Reset
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000277/LER-1985-019, :on 850919,RHR Pump Declared Inoperable.Caused by Low Flow in Low Head Region of Pump Performance Curve. Pump Removed from Svc & Inspected.Pump Determined to Be in Compliance W/Tech Spec Requirements |
- on 850919,RHR Pump Declared Inoperable.Caused by Low Flow in Low Head Region of Pump Performance Curve. Pump Removed from Svc & Inspected.Pump Determined to Be in Compliance W/Tech Spec Requirements
| 10 CFR 50.73(a)(2)(i) |
| 05000277/LER-1985-019-01, :on 850919,RHR Pump Declared Inoperable Due to Reduced Performance of Pump in Low Head Region.Cause Undetermined.Pump Reassembled & Tested |
- on 850919,RHR Pump Declared Inoperable Due to Reduced Performance of Pump in Low Head Region.Cause Undetermined.Pump Reassembled & Tested
| 10 CFR 50.73(a)(2)(i) |
| 05000278/LER-1985-020-02, :on 851120,RHR Pump C Tripped & Caught Fire. Caused by Failed Impeller Eye Wear Ring.Fire Extinguished & New Wear Rings Installed |
- on 851120,RHR Pump C Tripped & Caught Fire. Caused by Failed Impeller Eye Wear Ring.Fire Extinguished & New Wear Rings Installed
| 10 CFR 50.73(a)(2)(vi) |
| 05000277/LER-1985-020-01, :on 850924,low Level Scram Occurred Due to Operator Error.Level Automatically Restored to Normal by Reactor Feedwater Level Control Sys.Operator Counseled |
- on 850924,low Level Scram Occurred Due to Operator Error.Level Automatically Restored to Normal by Reactor Feedwater Level Control Sys.Operator Counseled
| |
| 05000278/LER-1985-021-02, :on 850826,w/unit in Refuel Outage & No Fuel in Reactor Vessel,Reactor Protection Sys Initiated Full Logic Actuation Signals.Caused by Personnel Inadvertently Bumping intermediate-range Monitor Cables |
- on 850826,w/unit in Refuel Outage & No Fuel in Reactor Vessel,Reactor Protection Sys Initiated Full Logic Actuation Signals.Caused by Personnel Inadvertently Bumping intermediate-range Monitor Cables
| 10 CFR 50.73(a)(2)(iv), System Actuation |
| 05000278/LER-1985-021, :on 850930,determined That Motor Driven Fire Pump Left Out of Svc for More than 7 Days.Caused by Personnel Error.During Slit Removal,Steps Will Be Taken to Reduce Amount of Time Fire Pump Out of Svc |
- on 850930,determined That Motor Driven Fire Pump Left Out of Svc for More than 7 Days.Caused by Personnel Error.During Slit Removal,Steps Will Be Taken to Reduce Amount of Time Fire Pump Out of Svc
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |