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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
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- 05000336/LER-1987-003, :on 870129,reanalysis of Steam Generator Tube Exam Data Identified That One Tube Which Contained Repairable Defect,Not Been Repaired,As Required by Tech Spec 4.4.5.1.4.b.Defective Tubes Plugged +
- 05000336/LER-1987-007, :on 870416,reactor Tripped Automatically Due to Turbine Trip Caused by Generator Exciter Field Breaker Opening.Caused by Generator Volts/Hertz Relay Actuation. Emergency Operating Procedure 2525 & 2526 Done +
- 05000368/LER-1987-010, :on 870522,plant Protection Sys Panels Seismic Qualification Compromised Due to Loose Fasteners.Caused by Personnel Error When Personnel Elected Not to Tighten All Screws.Personnel Counseled +
- 05000336/LER-1987-010-01, :on 870730,inadequacies Identified in Fire Protection Coating on Raceway Support Structures in Main Cable Vault & Hallway Leading to Charging Pumps.Hourly Fire Watch Started & Automatic Sprinkler Installed +
- 05000277/LER-1987-008, :on 870529,control Room Ventilation Radiation Monitoring Sys Found Inoperable.Caused by Piping Error Made During Initial Installation.Piping Errors Corrected & Sys Returned to Svc +
- 05000414/LER-1987-013, :on 870325,auxiliary Feedwater Automatically Started Due to Loss of Two Main Feedwater Pumps.Caused by Calibr Error of Barton 273A Differential Pressure Transmitters.Calibr Procedure Changed +
- 05000414/LER-1987-021-01, :on 870727,condensate Transient Occurred Resulting in Reactor Trip.Cause of Event Unknown.Control Room Personnel Stabilized Unit in Mode 3,hot Standby & Condensate Flow Reestablished Manually +
- 05000366/LER-1987-006, :on 870726,inadequate Design for Inverter Cooling Caused Power Failure Resulting in Reactor Scram. Caused by Equipment Failure Due to Inadequate HVAC Design. Inverter Refurbished +
- 05000321/LER-1987-011, :on 870723,reactor Water Level Decreased to Reactor Protection Sys Actuation Setpoint & Reactor Scram Occurred.Caused by Equipment Failure Due to Inadequate Ventilation Design.Inverter Refurbished +
- 05000302/LER-1987-017, :on 870808,problems During CRD Mechanism Repairs Delayed Plant Heatup Preventing Pump Restoration. Caused by Securing of Steam Supply to Emergency Feedwater Pump.Tech Spec Rev Submitted +
- 05000456/LER-1987-057, :on 871009,as Throttle Valve 2 Being Cycled, MW Output Became Erratic Resulting in Reactor Trip.Root Cause Indeterminate.Temporary Instrumentation Installed on Sensing Line of Turbine Impulse Transmitter +
- 05000416/LER-1987-009, :on 870629,reactor Scram Occurred.Caused by Agastat Relay N62-R33 Intermittently Failing Which Caused Main Steam Inlet Valve to Steam Jet Air Ejector B to Close. Caused by Break in Relay Wire Crimp +
- 05000482/LER-1987-043, :on 870929,discovered That Testing of Power Range Neutron Flux Low Setpoint & Reactor Trip Sys Interlocks P-8,P-9 & P-10 Not Performed,Per Tech Spec Requirements.Caused by Procedural Deficiencies +
- 05000440/LER-1987-038, :on 870529,discovered That Div III Fuel Oil Out of Spec for Approx 48 H,Beginning on 870527,w/o Required Control Room Notification.Caused by Personnel Error. Personnel Counseled +
- 05000395/LER-1987-013, :on 870526,RCS Pressure Boundary Leakage Occurred.Caused by Crack in Reactor Coolant Pump C Thermal Barrier Flange in Area of Seal Injection Inlet Nozzle Weld. Weld Ground Out & Repaired +
- 05000245/LER-1987-013-01, :on 870527,standby Gas Treatment Sys Automatically Initiated & Reactor Bldg Ventilation Sys Isolated.Caused by Underwater Vacuum Canisters Floating to Surface of Fuel Pool.Procedures Revised +
- 05000440/LER-1987-037, :on 870527,reactor Scrammed on Steam Flow/ Feedwater Flow Mismatch.Caused by Failed Resistor within Motor Driven Feedwater Pump Controller.Card Containing Resistor Replaced & Control Circuit Calibr +
- 05000440/LER-1987-039, :on 870530,main Steam Line Inboard Isolation Valve Closed Unexpectedly.Caused by Suspected Bad Connection in Channel C NSSS Isolation Logic.Valve Closure Could Not Be Duplicated Through Troubleshooting & No Addl Action Planned +
- 05000309/LER-1987-005, :on 870526,workers Found Cable Was Unexpected Brand Which Did Not Have Documentation of Environ Qualification.Cable Containing Terminal Block Replaced in Entirety W/Environ Qualified Cable +
- 05000254/LER-1987-006-02, :on 870403,HPCI Inoperable Due to Loose Solenoid Soldered Connection.Caused by Excessive Tension on Leads of Coil & Normal Equipment Vibration.Failed Solenoid Valve Replaced & Wire Leads of Coil Lengthened +
- 05000424/LER-1987-081, :on 870505,discovered That Excessive Anchor Darling (AD) Valve Weight Could Have Prevented Fulfillment of Safety Sys Function.Caused by Failure of AD to Notify Bechtel of Change in Weights.Valves Reviewed +
- 05000368/LER-1987-012, :on 870511,discovered Low Temp Overpressure Sys Relief Valves Deviated from Configurations Shown on Piping Isometric Drawings.Caused by Lack of Programmatic Mod Controls.Snubber Clamp Replaced +
- 05000368/LER-1987-011, :on 870727,discovered That Instrumentation for Shutdown Cooling Sys Flow Rate Did Not Meet Requirements of Tech Spec 3.3.3.5.Caused by Personnel Error.Plant Mod Developed & Installed +
- 05000483/LER-1987-018, :on 870815,essential Svc Water Train B Declared Inoperable Due to Partially Shut UHS Isolation Valve EF-V-0117.Caused by Personnel Error.Valve Actuator Caution Tagged & Will Be Repaired During Refuel II +
- 05000328/LER-1987-008-03, :on 871127,electromagnetic Interference Spike Occurred Initiating Containment Ventilation Isolation.Caused by Electromagnetic Pulse Due to Inadequate Detector Cable Ground.Ground Wire Secured +
- 05000482/LER-1987-033, :on 870813,tests of All Types B & C Valves Indicated Leakage in Excess of Tech Spec Limit.Caused by Cognitive Personnel Error.Ltr Issued Outlining Testing Requirements & Maint Activities +
- 05000341/LER-1987-038, :on 870815,automatic Initiation of Div I Emergency Equipment Cooling Water (EECW) Occurred.Caused by Inadequate Sys Design for Pressure compensation.Motor- Operated Valves Installed to EECW Makeup Tanks +
- 05000412/LER-1987-016, :on 870816,motor Driven Auxiliary Feedwater Pump 2FWE-P22 Started Inadvertently.Caused by Isolation of Pressure Switch 2FWE-PS158B,which Provided Erroneous Low Signal.Ltr Issued Detailing Lessons Learned +
- 05000322/LER-1987-028, :on 870827,meteorological Air Temp Monitoring Instrumentation Inoperable for More than 7 Days.Caused by Faulty Temp Sensors Located at 33 Ft & 150 Ft Elevations of Tower.Temp Sensors to Be Replaced by 870921 +
- 05000271/LER-1987-004, :on 870729,discovered That Surveillance of Inside Fire Hose Stations Had Not Been Completed.Caused by Personnel Errors.Surveillance Procedure Revised to Include 18-month Inside Fire Hose Surveillance Insp +
- 05000313/LER-1987-003-01, :on 870808,emergency Feedwater Sys Actuation Occurred During Power Reduction.Caused by Main Feedwater Valve Fulcrum Pin Out of Position Due to Personnel Error.New Set Screws & Pin Installed +
- 05000338/LER-1987-016-01, :on 870814,determined That Redundant Butterfly Valves in Turbine Overspeed Protection Sys Would Not Have Properly Isolated Steam Between 870629-870710.Caused by Inadequate Maint Procedures.Procedures Revised +
- 05000309/LER-1987-006, :on 870627,manual Reactor Trip Initiated Due to Uncontrollable Increase in Steam Generator 3.Caused by Personnel Error.Drawing Revised to Reflect Actual Termination Points for Time Lag Unit wires.W/870909 1tr +
- 05000259/LER-1987-022-01, :on 870811,ESF Actuation Occurred Due to Two Emergency Equipment Cooling Water Pumps Inadvertently Starting.Caused by Personnel Error in Calibr of Pressure Switch.Wire Moved & Terminated & Switch Reset +
- 05000454/LER-1987-018-03, :on 870811,reactor Trip Occurred.Caused by Trip of Main Feedwater Pump Due to Broken Wire on Proximity Probe.Feedwater Supervisory Instrumentation Repaired & Calibr & Automatic Trips on Pumps Disabled +
- 05000458/LER-1987-017, :on 870811,discovered RCIC Leak Detection Sys Isolation Logic Inoperative Due to Mispositioned Valve.Cause Undetermined.Valve Lineup Check Revealed No Other Mispositioned Valves +
- 05000301/LER-1987-002-01, :on 870816,reactor Trip Occurred.Caused by Lightning Strike to Transmission Line Associated w/2X01 Transformers or Ground Near Transformers.Damaged Corona Ring of 2X01 Phase B Transformer Repaired +
- 05000322/LER-1987-027, :on 870821,procedure Used for Weekly,Monthly & Quarterly Composite Samples of Continuous Liquid Releases Determined Not Adequate Per Tech Specs.Procedure Revised to Meet Requirements of Tech Specs +
- 05000454/LER-1987-019-03, :on 870812,safety Injection & Reactor Trip from Low Steam Line Pressure Occurred Due to Failed Main Turbine Throttle.Caused by Failed Moog Servo Valve.Valve Replaced & Procedures Revised +
- 05000412/LER-1987-015-01, :on 870815,automatic Reactor Trip Occurred Due to lo-lo Steam Generator Level.Caused by Personnel Error. Administrative Guidance Provided to Operations Personnel +
- 05000271/LER-1987-005, :on 870807,while Shutting Down for Scheduled Refueling Outage,Reactor Scram Occurred.Caused by Inability of Mechanical Pressure Regulator Sys to Take Control from Electrical Pressure Regulator Sys +
- 05000245/LER-1987-033, :on 870812,LPCI Subsystem a Inadvertently Initiated.Caused by Technician Error When Test Plug Connected to Wrong Jack During Surveillance on Automatic Pressure Relief Sys.Procedure Reviewed +
- 05000414/LER-1987-022-01, :on 870728,main Feedwater Isolation Occurred Due to hi-hi Steam Generator Water Level.Caused by Debris in Feedwater Control Valve Positioner.Valve Positioner Replaced & Calibr Check Completed +
- 05000413/LER-1987-030, :on 870726,failure to Perform Type C Leak Rate Test on Valve 1NI-120B Following Replacement of Torque Switch Occurred.Caused by Inadequate Retest Policy.Retest Performed.Memo Re Leak Rate Tests to Be Issued +
- 05000440/LER-1987-058, :on 870815,control Rods Withdrawn Prior to Performing Source Range Monitors Signal to Noise Ratio Verification.Caused by Operator Error.Operators Involved Counseled.Tech Specs Rounds Will Be Revised +
- 05000412/LER-1987-014-01, :on 870815,reactor Trip on lo-lo Level in Steam Generator 21A Occurred.Caused by Operator Inexperience in Rod Motion W/Rods of High Differential Value.Administrative Guidance provided.W/870909 1tr +
- 05000245/LER-1987-032-01, :on 870811,first Stage Bypass Switches Failed to Meet Tech Spec Requirements.Caused by Setpoint Drift from Extended Periods of Depressurization.Switches Recalibrated to Conform to Tech Specs +
- 05000413/LER-1987-031, :on 870729,vent Gas Radiation Monitor Found Inoperable.Caused by non-conservative High Radiation Alarm Setpoint.Setpoint Returned to Original Setting & Policy Will Be Clarified +
- 05000369/LER-1987-015-02, :on 870727,fire/flood Barrier Between Diesel Generator & Diesel Lube Oil Holding Tanks Room Breached. Caused by Personnel Error.Personnel Counseled +
- 05000414/LER-1987-023-01, :on 870807,unusual Event Declared Due to Inoperable Containment Valve.Caused by Improper Setting of Air Actuator Following Maint Activity.Valve Repaired & Successfully Retested +