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 Issue dateTitleTopic
ML11348015028 November 1978LER 78-108/03L-0:on 781101,surveillance Requirements of Tech Spec 4.7.1.2 Found Not Completed.Caused by Procedural Deficiencies.Procedure Mods Written to Incorporate Tech Spec & Further Procedures Will Be Written for Remaining Testing
ML19207B11717 August 1979LER 79-084/01T-0 on 790806:containment Air Coolers Svc Outlet Valves,Automatically Regulated by Inlet Air Temp, Failed to Meet Response Time.Caused by Design Error in Actuator Air Opening Size.Valves Will Be RedesignedStroke time
ML19207C05430 August 1979LER 79-088/03L-0:on 790807,supply Breaker for Essential Unit Substation Bus F1 Tripped de-energizing Bus.Caused by Electrical Fault in Baat Room Heater,Instituting Operation of Neutral Overcurrent DeviceBoric Acid
ML19208A36827 April 1979LER 79-049/03L-1:on 790331,during Surveillance Testing Nine of 18 Main Steam Safety Valves Found Outside Design Setpoint Range.Caused by Changing Ambient Conditions,Valve Liftings from Previous Trips & Vibrations.Valves AdjustedFlow Induced Vibration
ML19209B9835 October 1979LER 79-092/03L-0:on 790908,source Range Neutron Detector NI-1 & Intermediate Range Neutron Detector NI-3 Failed Low During Reactor Shutdown.Caused by Signal Return Cable & Associated Connectors.Cables CleanedShutdown Margin
ML19209D15613 October 1979LER 79-005/03L-1:on 790106,borated Water Storage Tank Bistable Was Tripped & Decay Heat Valves DH9A Opened & DH7A Closed.Cause by Component Failure of Output Relay K51A in Safety Feature Actuation Sys Channel 4Boric Acid
ML19209D16015 March 1979LER 79-028/03L-1:on 790217,high Level Fail Alarm Received for Borated Water Storage Tank Level on Safety Features Actuation Sys Channel 1.Caused by Inadequate Insulation of Instrument Piping & Poor Location of Heat Trace Temp Sensor
ML19209D16425 April 1979LER 79-045/03L-1:on 790330,borated Water Storage Tank Low Level Trip Setpoint in Safety Feature Actuation Sys Channel 2 Was Out of Tolerance.Caused by Noisy Constant Current Test Potentiometer.Potentiometer Replaced
ML19209D17121 August 1979LER 79-086/03L-1:on 790725,train 2 of Control Room Emergency Ventilation Sys Was Inoperable.Cause by One of Three Thermistors in Compressor Motor Winding Failing to Open Circuit.Compressor Repaired & New One Will Be Installed
ML19209D2777 December 1978Supplemental Info to LER 78-114/03L-2:on 781110,borated Water Storage Tank Low Level Trip Setpoint Out of Tolerance. Caused by Noisy Constant Current Test Potentiometer within Safety Features Actuation Sys Cabinet
ML19210C4791 November 1979LER 79-099/03L-0:on 791008,during Boron Injection Heat Trace Test,Unit Failed to Achieve 105 F Temp at One Point on Sys Heat Trace Line.Caused by Sys Design Deficiencies.Test ST 5011.01 Performed Successfully on 791009Boric Acid
ML19210D62821 November 1979LER 79-104/03L-0:on 791025,reactor Coolant Pump 2-2 Tripped While Pump 1-1 Shut Down.Caused by Blown Fuse in Pump Interlock Circuit Due to Double Grounding on Dc Buses.Maint Work Orders & Facility Change Requests Completed
ML19210D64121 November 1979LER 79-105/01T-0:on 791109,steam Generator Low Level Trip Setpoints to Steam & Feedwater Rupture Control Sys Channels 1 & 2 Found Less Conservative than Tech Specs.Caused by Error in Analysis to Determine Low Level Bistable Setpoints
ML19210D65220 November 1979LER 79-102/03L-0:on 791022,during Feedwater Sys Monthly Surveillance Test,No Oil Level Visible in Oil Sight Glass on Inboard Bearing of Auxiliary Feedpump Turbine 1-1.Caused by Loose Sight Glass.Glass Tightened & Oil Replaced
ML19210D67120 November 1979LER 79-103/03L-0:on 791023,first & Third Seals in Reactor Coolant Pump 1-1-1 Were Not Staging.Caused by Thermal Shocking Which Occurred During Loss of Offsite Power on 791015.Seal Package Refurbished & Reinstalled
ML19210E09923 November 1979LER 79-106/01T-0:on 791112,design of 11 Seismic Hangers Not as Conservative as Required.Caused by Design Error.Hangers Modified Before Unit Returned to OperationEarthquake
ML19211A27111 December 1979LER 79-111/03L-0:on 791114,during Surveillance Testing, Accelerometer Tracer Could Not Be Discerned Due to Excessive Noise.Caused by Component Failure.Source of Noise Being Investigated,Possibly Caused by Battery Charger
ML19211A27511 December 1979LER 79-109/03L-0:on 791113,discovered Couch (Deutsch) Relay Contacts Were Driving High Inductive Loads in 26 Nuclear safety-related Circuits.Caused by Inductive Surge When Contacts Open.Arc Suppression Diodes Added to Circuits
ML19211A28211 December 1979LER 79-110/03L-0:on 791112,while Testing HPI Pump 1-1 in Mode 5,pump Failed to Start.Caused by Improperly Terminated Lug in Breaker Control Wiring.Lead Properly Terminated & Reinstalled
ML19211C7288 January 1980LER 79-130/03L-0:on 791227,insufficient Clearance Discovered Between RCS Hot Leg & Pipe Whip Restraint Shims.Caused by Bechtel Design Error.Pipe Whip Restraints Modified
ML19211C7458 January 1980LER 79-129/03L-0:on 791211,during Control Room Emergency Ventilation Sys 18-month Test,Charcoal Filter Bank in Unit 1-2 Failed to Meet Efficiency Required Per Tech Specs. Caused by Leakage Between Filter Plate & Assembly
ML19211C7584 December 1979Updated LER 79-107/03L:on 791105,w/unit in Mode 5,loss of Essential Instrumentation Distribution Panel Y2 Occurred. Caused by Open Resistor in Logic Voltage Supply to silicon- Controlled Rectifiers.Inverter Repaired
ML19211C7668 January 1980LER 79-128/03L-0:on 791210,during Emergency Ventilation Sys Test,Charcoal Filter Bank in Unit 1-1 Failed to Meet Efficiency Limit in Modes 1-4.Caused by Leakage Between Filter Plate & Assembly Due to Insufficient Gasket Pressure
ML19211D27111 January 1980LER 79-132/01T-0:on 791231,during Review of Effects of Changing RCS Cold Leg Temp on Accuracy of Power Range Nuclear Instrumentation,Calibr Procedures Found Inconsistent W/Accident Analysis.Caused by Procedure Error
ML19224C9973 July 1979LER 79-064/01T-0 on 790621:impact Points of Eight Main Steam Line Seismic Restraint Locations May Deform If Sufficient Seismic Event Occurs.Caused by Design Deficiency.Web Reinforcing Plates Installed at Impact PointsDesign basis earthquake
ML19224D0055 July 1979LER 79-065/03L-0 on 790609:contact Data Logger Failed, Rendering Fire & Radiation Remote Monitoring Sys Inoperable. Caused by Intermittent Equipment Problem of Undetermined Nature.Computer Program Reloaded;Equipment to Be Phased Out
ML19224D0125 July 1979LER 79-066/03L-0 on 790609:fire Alarm Point Alarmed, Although Investigation Revealed No Fire.Cause Suspected to Be Dust or Dirt on Detector.Detector Removed,Tested & ReinstalledFire Watch
ML19224D78210 July 1979LER 79-067/01T-0 on 790628:short Circuit Caused Loss of Essential Bus Y4 Sypplying Power to Safety Feature Actuation Sys.Blown Inverter Fuse Was Replaced & Y4 Bus Returned to Normal Supply
ML19242A14419 July 1979LER 79-068/03L-0 on 790623:during Performance of Svc Water Sys Monthly Test ST 5075.01,component Cooling Water Heat Exchanger 1-3 Outlet Valve Failed to Close Fully.Caused by Vibrational Loosening of Retaining Nut
ML19242A18319 July 1979LER 79-069/03L-0 on 790623:during Performance of Surveillance Testing,Containment post-accident Radiation Monitor Re 5029 Had Low Flow Alarm & Was Declared Inoperable.Caused by Loose Sheave Set Screws
ML19242A8282 August 1979LER 79-075/03L-0 on 790708:no Visible Oil Level in Outboard Bearing Oil Reservoir Sight Glass on Containment Spray Pump 1-2.Caused by Component Failure.Oil Added to Reservoir & Fittings TightenedLoctite
ML19242A8412 August 1979LER 79-072/03L-0 on 790708:position Indication on Rod Two of Group Eight Was Inoperable.Caused by Component Failure of Reed Switch within Position Indicator Tube.Part Was Replaced & Returned to Svc
ML19242A8462 August 1979LER 79-073/03L-0 on 790708:during Checkout of Valve Relay, Main Steam Inlet to Auxiliary Feed Pipe Turbine 1-1 Isolation Valve Torqued While Opening.Caused by Normal Valve Wear.Valve Was Readjusted & Returned to Svc
ML19242B0941 August 1979LER 79-070/03L-0 on 790705:1/2 Trip Occurred on Channels 1 & 3 of Steam & Feedwater Rupture Control Sys. Caused by Failure of +24 Volt Dc Power Supply PS02 in Steam Generator Level Instrumentation Cabinet Channel 1
ML19242B2191 August 1979LER 79-071/03L-0 on 790704:while Performing Valve Lineup for Auxiliary Feedwater Sys Test ST 5071.04,valve AF 3870 Was Discovered to Lack Position Indication at Control Room Switch.Caused by Short in Motor Winding or Single Phasing
ML19242B9486 August 1979LER 79-078/03L-0 on 790710:indication of Source Range Neutron Detector NI-1 Failed Low Twice.Cause Due to Undetermined Component Failure in Both Cases.Unit Tested to Verify Operability
ML19242C4373 August 1979LER 79-077/03L-0 on 790705:auxiliary Feedwater Pump Turbine I-1 Steam Inlet Valve M5-106 Would Not Close on Simulated Low Turbine Inlet Pressure Signal.Caused by Component Failure Components Replaced
ML19242C4803 August 1979LER 79-076/03L-0 on 790708:reading of Core Flood Tank Level Indicator Li-CF3B2 Did Not Appear to Read Same as Indicator LI-CF3B1.Caused by Faulty Amplifier in Level Transmitter LT-CF3B2.Amplifier Replaced & Transmitter Recalibr
ML19242C5082 August 1979LER 79-074/03L-0 on 790707:auxiliary Feedwater Pump 1-2 suction-before-strainer Pressure Switch PSL-4929B Actuated at Pressure Input Outside Allowable Tolerance.Caused by Component Failure Due to Misapplication.Switch ReplacedOvertravel
ML19242D3009 August 1979LER 79-079/03L-0 on 790712:while Repositioning Group 8, Absolute Position Indication for Rod 4 Shifted from 25% to 0% Position.Caused by Oxide Film Buildup on Reed Switch Contacts.Corrective Maint Performed
ML19242D60710 August 1979LER 79-080/03L-0 on 790716:safety Features Actuation Sys Containment Radiation Detector Re 2005 Spiked & Tripped Channel 2 Containment Radiation Bistable.Caused by Component Failure.Detector Will Be Relocated Outside Containment
ML19246A78216 May 1979LER 79-054/03L-1 on 790409:control Room Damper Stuck Open. Apparently Caused by Corrosion of Damper Shaft Leading to Binding in One Bushing.Damper Removed,Reconditioned & Returned to Svc
ML19249A24216 August 1979LER 79-082/03L-0 on 790720:discovered That Containment post-accident Radiation Monitor Re 5030 Had Tripped.Caused by Sufficient Pump Wear Resulting in Low Flow Setpoint Being Reached.Pump Bypass Valve Adjusted
ML19249A24616 August 1979LER 79-083/03L-0 on 790720:while Verifying Relative Position Indication for Group 5,Rod 4,discovered That Rod 6 of Group 5 Showed 50% Withdrawn on Absolute Position Indication.Caused by Oxide Buildup on Tube Reed Switches
ML19249A24913 August 1979LER 79-081/03L-0 on 790717:post-accident Containment Radiation Monitor Re 5029 Out of Svc Due to Pump Failure. Caused by Loss of Lubrication to Pump Bearings.Improved Pump Bearings Will Be Installed
ML19249A52917 August 1979LER 79-085/03L-0 on 790722:containment post-accident Radiation Monitor Declared Inoperable.Caused by Component Failure.Pump Replaced W/Rebuilt Pump,Surveillance Tested & Declared Operable
ML19249B39227 August 1979LER 79-087/03L-0:on 790731,operators Twice Received Control Rod Sequence Fault Alarm.Caused by Faulty Integrated Circuit in Auxiliary Power Supply of Command Logic String.Circuit Replaced & Proper Operation Verified
ML19249E80026 September 1979LER 79-091/03L-0:on 790901,steam Generator 2 Low Level Trip Occurred on Steam & Feedwater Rupture Control Sys Channel 3.Caused by Inoperable Optical Isolator in Faulty Input Buffer Card.Board Was Replaced & New Buffer Card Installed
ML19250C00030 October 1979LER 79-097/03L-0:on 791004,steam & Feedwater Rupture Control Sys Channel Supply Failed,Resulting in Half Trip.Caused by Failure of Sorenson Power Supply Which Provides Volt in Channel 4.Power Supply Replaced
ML19250C02130 October 1979LER 79-098/03L-0:on 791004,during Component Cooling Water Monthly Test,Decay Hear Cooler 1 Component Cooling Outlet Valve CC 1467 Would Not Operate.Caused by Slippage of Valve Linkage.Linkage Realigned & Calibr