Pages that link to "NRC-90-0008, LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr"
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The following pages link to NRC-90-0008, LER 89-037-00:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed.Caused by Personnel Error. Critique of Event Being developed.W/900119 Ltr:
Displayed 41 items.
- NRC-89-0194, LER 89-027-00:on 891015,reactor Bldg Hvac,Control Ctr HVAC & Drywell Floor & Equipment Drain Sumps Isolated & Standby Gas Treatment Sys & Noninterrruptalbe Control Air Compressors Started.Caused by Personnel error.W/891114 Ltr (← links)
- NRC-89-0185, LER 89-021-00:on 890906,local Leak Rate Testing of Containment Isolation Valves & Penetrations Exceeded Tech Spec Limit.Caused by Excessive Containment Isolation Valve Leakage Due to Degradation of valve.W/891006 Ltr (← links)
- NRC-89-0186, LER 89-016-01:on 890711,Div 1 of RHR Svc Water Sys Declared Inoperable Due to Low Nitrogen Pressure for Cooling Tower Fan Brake.Caused by Leak in One Hose.Leaking Hose Replaced & Nitrogen Pressure restored.W/891006 Ltr (← links)
- NRC-89-0193, LER 89-026-00:on 891010,control Ctr HVAC Shifted to Recirculation Mode of Operaton Due to Short Circuit.Caused by Failure of Lamp Filament When Being Tightened.Fuse & Lamp Replaced & Sys Returned to Normal operation.W/891109 Ltr (← links)
- NRC-89-0192, LER 87-045-01:on 870908,fuse Removed Which Deenergized Dc Control Power to Bus 72C & Resulted in Loss of Power Supply to Swing Bus & LPCI Loop Selection Valves.Caused by Design Error.Undervoltage Relay Added & Training held.W/891106 Ltr (← links)
- NRC-89-0190, LER 89-023-00:on 890924,personnel Inadvertently Caused Trip of Essential Safety Sys Buses 64B & 64C.Caused by Failure of Personnel Involved to Review Applicable Prints Prior to Performing Test.Event Reviewed w/personnel.W/891024 Ltr (← links)
- NRC-89-0255, LER 89-031-00:on 891120,both Div II Emergency Equipment Cooling Water (EECW) & Emergency Equipment Svc Water Sys Pumps Tripped Immediately.Caused by Inadequacies in Stated Procedures.Procedures revised.W/891220 Ltr (← links)
- NRC-89-0256, LER 89-022-01:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse C71A-F15B Blew.On 890928, Reactor Bldg HVAC Isolated.Caused by Personnel Error. Procedures Will Be revised.W/891215 Ltr (← links)
- NRC-89-0258, LER 89-025-00:on 891115,low Level 2 Signal Unintentionally Induced During Reactor Pressure Vessel Hydrostatic Pressure Test.Caused by Personnel Error.Personnel Counseled on Notifying & Coordinating Instrument lineups.W/891215 Ltr (← links)
- NRC-89-0259, LER 89-017-01:on 890810,new Analysis of Feedwater Line Break Scenario Assumes Failure of Feedwater Startup Control Valve in Open Position.Review of Pipe Break Documentation Conducted.Updated FSAR Change to Be submitted.W/891215 Ltr (← links)
- NRC-89-0251, LER 89-019-01:on 890819,discovered That Div I Recirculation Fan Not Rotating Which Resulted in Decrease in Control Room Air Pressure.Caused by Lack of Lubrication in Bearings. Lubrication Program Improvements evaluated.W/891130 Ltr (← links)
- NRC-89-0249, LER 89-029-00:on 891023,half Scram Signal Received When Power Was Lost on Reactor Protection Sys Bus B,Resulting in Several ESFs Actuation.Caused by Location of Breaker Operating Switch in High Traffic area.W/891122 Ltr (← links)
- NRC-89-0244, LER 89-024-00:on 891019,recognized That Secondary Containment Dampers Not Tested as Required by Tech Spec 3.6.5.2.Caused by Operations Personnel Error.Event Critique to Be Included in Required Reading program.W/891120 Ltr (← links)
- NRC-89-0246, LER 89-028-00:on 891020,eight safety-related Valves Failed Set Pressure Test.Cause Under Review.All Valves Removed for Testing Being Refurbished,Cleaned,Retested & Recertified to Be within Plant Accepted tolerances.W/891120 Ltr (← links)
- NRC-89-0189, LER 89-022-00:on 890923 & 24,reactor Protection Sys Logic Actuations Occurred When Fuse Blew.On 890928,reactor Bldg HVAC Isolated When Jumper Lifted Per Incorrect Work Plan Instruction.Caused by Personnel error.W/891023 Ltr (← links)
- NRC-90-0018, LER 89-039-00:on 891226,Div I Emergency Equipment Cooling Water & Svc Water Sys Automatically Started Due to Partial Load Shed of Bus 72E.Caused by Personnel Error. Accountability Meeting Held on 900117.W/900125 Ltr (← links)
- NRC-90-0007, LER 89-036-00:on 891218,control Room Operator Inadvertently Depressed Closed Push Buttons on Inboard MSIVs A,B & C & Reactor Scram Resulted.Caused by Operator Error.Operator Involved Was Removed from Licensed duties.W/900117 Ltr (← links)
- NRC-90-0003, LER 89-034-00:on 891208,review of Key Card Transactions Showed That Fire Watch Personnel Missed Assigned Hourly Fire Watch from 891020-1207.Fire Watch Person Discharged.Plan Re Improvement of Fire Watches developed.W/900108 Ltr (← links)
- NRC-90-0004, LER 89-030-00:on 891026,Channel C Level 1 & 2 Replacement Transmitter Found to Be Installed Incorrectly & Condition Recognized on 891210,when Level 2 Trip Unit Was Reading Upscale.Caused by Personnel error.W/900109 Ltr (← links)
- NRC-90-0005, LER 89-035-00:on 891210,steam Jet Air Ejectors Placed in Svc W/O Required Surveillance Completed & Required Grab Sample Not Started Until 891213.Caused by Personnel Error.Off Gas Sys Operating Procedure Will Be revised.W/900111 Ltr (← links)
- NRC-90-0002, LER 89-033-00:on 891207,volt-ohm Meter Connected to Incorrect Terminal,Causing Div II of Emergency Equipment Cooling Water Sys to Actuate.Caused by Personnel Error.Sys Secured & Channel Test Successfully completed.W/900108 Ltr (← links)
- NRC-89-0261, LER 89-028-00:on 891129,ESF Actuations Occurred During Set Up for Surveillance.Caused by Blown Fuse.Blown Fuse Replaced & Affected Sys Returned to Normal Operation Following Completion of surveillance.W/891228 Ltr (← links)
- NRC-90-0008 (redirect page) (← links)
- ML19354E102 (redirect page) (← links)
- ML19354E097 (← links)
- NRC-91-0058, LER 91-008-00:on 910424,reactor Bldg HVAC Tripped,Div I SGTS Auto Started & Div I Control Ctr HVAC Shifted to Recirculation Mode Due to Mispositioned Trip Output Logic switch.W/910524 Ltr (← links)
- NRC-91-0055, LER 91-006-00:on 910410,balance of Plant Breaker Opened Causing Reactor Bldg HVAC Isolation.Caused by Component Failures.Nprds Search Conducted for Similiar Problems. W/910510 Ltr (← links)
- NRC-90-0048, LER 89-037-01:on 891220,determined That Tech Spec Stroke Time Testing for Outboard Reactor Water Sample Line Isolation Valve Not Performed Prior to Expiration on 891125. Caused by Personnel Error.Procedure revised.W/900322 Ltr (← links)
- NRC-90-0027, LER 89-034-01:on 891208,two Members of Fire Watch Did Not Complete Assigned Hourly Rounds from 891002-1207 in Reactor & Auxiliary Bldgs.Both Individuals Terminated & Fire Stations Equipped W/Unique Bar code.W/900221 Ltr (← links)
- NRC-90-0021, LER 90-001-00:on 900108,annunciator 2D5 Alarmed for Div II ECCS Testability Logic/Power Failure.Caused by Blown Fuse. Fuse Installed During Course of Troubleshooting W/No Subsequent Problems noted.W/900207 Ltr (← links)
- NRC-90-0019, LER 89-028-01:on 891028,eight Safety Relief Valves Failed Set Pressure Tolerance Test.Cause Under Review by Util & Generically by BWR Owners Group Safety Relief Valve Set Point Drift Committee.Valves Removed & cleaned.W/900131 Ltr (← links)
- NRC-89-0260, LER 89-021-01:on 890906,35 of 237 Containment Isolation Valves Exceeded Administrative Allowable Leakage Rate When Tested.Caused by Normal Wear & Degradation During Specified Time Interval.Valves Cleaned & repaired.W/891221 Ltr (← links)
- NRC-94-0025, LER 93-014-01:on 931225,turbine Generator Tripped When Mechanical Overspeed Device Was Activated.Caused by Severe Vibration.Corrective Action:Assessment of Structural Integrity of Pedestal Was conducted.W/940425 Ltr (← links)
- NRC-91-0004, LER 90-013-00:on 901228,determined That Inadequate Control Could Occur During Air Grab Sampling Process.Caused by Lack of Proper Administrative Controls in Sampling Procedure. Sample Suction added.W/910128 Ltr (← links)
- NRC-90-0144, LER 90-007-00:on 900829,control Ctr Ventilation Shifted to Recirculation Due to Blown Fuse.Caused by Design Deficiency in Div 1 & 2 Radiation Monitor Trip Circuitry.Design Change Implemented to Eliminate Trip Relay logic.W/900928 Ltr (← links)
- NRC-93-0058, LER 93-008-00:on 930518,discovered That Recorder T50-R802A Could Not Be Considered Operable Per TS 3.3.7.5.Caused by Personnel Error.Lessons Learned Will Be Incorporated Into Training Programs & Plant procedures.W/930618 Ltr (← links)
- NRC-93-0055, LER 93-007-00:on 930420,reactor Tripped on Intermediate Range Monitor Upscale During Reactor Pressure & Feedwater Transient.Caused by Personnel Error.Affected Pressure Transmitters replaced.W/930520 Ltr (← links)
- NRC-90-0107, LER 88-034-01:on 880831,RWCU Outboard Isolation Valve Closed,Causing RWCU Pumps to Trip.Caused by Loss of Continuity to Relay Due to Deposits Built Up on Surface of Contacts.Relay in Isolation Circuits replaced.W/900622 Ltr (← links)
- NRC-90-0087, LER 90-002-01:on 900202,determined That Area Radiation Surveillance Procedure 44.080.301 Listed Incorrect Values for Alarm Setpoints.Caused by Unavailable Setpoint Calculations.Procedure revised.W/900608 Ltr (← links)
- NRC-90-0075, LER 87-045-02:on 870908,operator Removed Fuse Which Deenergized Dc Control Power to Bus 72C,resulting in Loss of Power Supply to Swing Bus & to LPCI Loop Selection Valves. Caused by Design Flaw.Design Change initiated.W/900518 Ltr (← links)
- NRC-90-0073, LER 90-003-00:on 900410,Div I Reactor Protection Sys Power Supply Failure & Subsequent MSIV Closure.Caused by Coil Burn Up.Relays Replaced & MG Sets Returned to svc.W/900508 Ltr (← links)