05000412/LER-2009-001, Equipment Operability for Steam Generator Tube Rupture Safety Analysis Not Met
05000266/LER-1989-005, :on 890503,inoperability of Low Temp Overpressure Protection Sys Using Nitrogen Gas Discovered. Caused by Inadequate post-mod Testing.Nitrogen Regulators Moved to Location Near PORVs
05000339/LER-1989-003, Advises of Change in Reportability for LER 89-003-00 Re 10 Containment Isolation Valves W/Excessive Leak Rates
05000312/LER-1986-023, :on 861111,inadequate Voltage Supplies Sent to Control Room/Technical Support Center HVAC Under Certain Worst Case Conditions.Caused by Inadequate Engineering Review.Ecn R-0911 Written
05000267/LER-1987-012, :on 870416,functional Test Procedures for Gaseous & Liquid Effluent Radiation Monitors Discovered Deficient.Caused by Personnel Oversight.Procedures Changed
05000352/LER-1987-005, :on 870130,two Temporary Cables,Used to Collect Data During Startup,Incorrectly Routed & Not Connected to Proper Channelized Multiplexers.Caused by Improper Evaluation During Cable Installation
05000255/LER-1987-001, :on 870114,plant Engineering Personnel Discovered Four Containment Penetrations Did Not Employ Redundant Isolation Logic.Caused by Architect/Engineer Error.Mod Being Performed
05000336/LER-1986-015-01, :on 861114,diesel Generator Differential Relays Not Seismically Qualified for Class IE Svc.Caused by Installation of Nonqualified Relays.Relays Removed from Svc & Replaced
05000255/LER-1987-001-01, :on 870114,containment Penetrations Associated W/Containment Hydrogen Monitoring Sys Did Not Employ Redundant Isolation Logic.Caused by Sys Design Description Not Being Implemented as Prescribed
05000336/LER-1987-015, :on 861114,util Informed That GE Model 12 Cfd Relays Installed Above 30-ft Elevation Not Seismically Qualified for Class 1E Svc.Caused by Design Error.Relay Replaced
05000456/LER-1986-003-09, :on 861121,hard Rubber Fire Hoses Declared Inoperable Due to Lack of Valid,Current Hydrostatic Test. Caused by Hose Failure Due to Improper Coupling for Intended Use.Hoses Replaced.Personnel Counseled
05000423/LER-1986-023, :on 860311,inappropriate Calibr Method Used & on 860312,monitors Calibr Nonconservatively.Caused by Defective Procedure.Calibr Methods for Radiation Monitors Reviewed & Four Monitors Recalibr
05000338/LER-1985-003-02, :on 850319,discovered Previous Studies Did Not Identify Units 3 & 4 Const Area as Potential Flood Path. Caused by Only Partial Flooding Addressed in Updated Fsar. Corrective Actions Being Evaluated
05000397/LER-1986-019, :on 860415,deficiencies Identified in RHR Valve 9 in Limitorque motor-operated Valve During Insp.Similar Environ Qualification Deficiencies Found in 27 Valves.All Deficiencies Corrected
05000295/LER-1986-008, :on 860221,negative Flux Rate Trip Discovered to Be Calibr to Nonconservative Value.Caused by Input Changes to Accident Analysis for Dropped Rods.Safety Analysis Procedures Reviewed
05000245/LER-1988-004, :on 880318,determined Potential Fouling of ECCS Suction Strainers.Caused by Insufficient Area of Existing Strainers.Project Assignment Initiated to Replace ECCS Suction Strainers
05000277/LER-1987-028, :on 871217,design Deficiency That Could Permit Diesel Generator Trips During Seismic Event Discovered. Caused by Deficiency in Original Design.Two Possible Design Mods to Resolve Problem Being Evaluated
05000245/LER-1988-004-02, :on 880318,discovered Potential for ECCS Pump Suction Strainers to Foul W/Fibrous Insulation Debris.Caused by Insufficient Area of Existing Strainers.Strainers Replaced
05000277/LER-1987-028-01, :on 871217,design Deficiency Discovered Which Could Result in Diesel Generator Trips During Loss of Offsite Power Event.Caused by Deficiency in Original Design. Design Review of Cardox Sys Initiated
05000413/LER-1988-011, :on 880126,nuts Received W/O Proper Charpy Impact Testing Documentation.Caused by Mfg Deficiency & Personnel Error.Incident Reviewed W/General Ofc QA Personnel.Nuts Tested Per NRC Bulletin 87-002
05000295/LER-1986-008-01, :on 860221,negative Flux Rate Trip Discovered Calibr to Nonconservative Value.Caused by Discrepant Westinghouse Owners Group Procedure Restrictions.Tech Spec Approved by NRC
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
05000369/LER-1985-029-01, :on 851001,Westinghouse Notified Util That Reanalysis of Peak Containment Pressure Calculation Resulted in Greater Value than Internal Pressure of 15 Psig.Emergency Procedure for Nd Spray Initiation Revised
05000219/LER-1985-023, :on 851211 Re Emergency Svc Water Sys Seismic Concerns.Caused by Original Design Error.Procedures Used to Determine Pump Operability Revised to Change Min Acceptable Flow Rate & Engineering Evaluation Performed
05000346/LER-1985-013, :on 850609,main Feedwater Pump 1 Tripped on Overspeed Due to Control Problem.Reactor Also Tripped on High RCS Pressure Because of Inadequate Feedwater.Corrective Actions Not Yet Determined
05000321/LER-1985-021, :on 850612,plant Personnel Determined That Fire Protection Valve Cycling Procedures Could Make Valves Inaccessible During Operations to Be Cycled Once Every 18 Months Rather than Every 12 Months
05000366/LER-1985-011, :on 850401,main Steam Line Monitor B High Trip Setpoint Set at 3.2 Times Full Power Background.Caused by Personnel Communication Error.Setpoint Data Will Be Retrieved in Person Rather than Via Telephone
05000321/LER-1985-020, :on 850415,special Purpose Procedure Directing Implementation of Direct Conversion Reactor on Plant Standby Gas Treatment Sys in Violation of Tech Specs.Caused by Inadequate Technical Review of Procedures
05000338/LER-1985-004, :on 850328,depth of Compacted Backfill Over Svc Water Sys Supply & Return Piping Between Svc Water Pumphouse & Safeguards Area Determined Less than 6 Ft Required for Tornado Missile Protection
05000338/LER-1985-004-02, :on 850328,determined That Compacted Backfill Depth Over Svc Water Sys Supply & Return Piping Did Not Meet 6-ft Min Limit Required for Tornado Missile Protection. Cause Not Stated.Depth Corrected on 850329
05000219/LER-1984-009-01, :on 840922,secondary Containment Integrity Degraded While Contractor Personnel Opened Both Doors of Reactor Bldg Personnel Access Airlock to Transport Pipe. Caused by Personnel Error.Personnel Counseled
05000237/LER-1985-009-04, :on 850221,standby Liquid Control Pump Taken Out of Svc & Required Operability Test for Redundant Pump 2B Not Performed Until 850223.Caused by Inadvertent Dept Oversight.Event Discussed W/Shift Personnel
05000333/LER-1992-012, :on 920224,determined That Normal Closed Position of Rhr/Lpci Pump Min Flow Valves Could Result in Failure of Pump.Caused by Improper Positioning of RHR Valves.Valve Position Changed to Open
05000237/LER-1984-007-06, :on 840628,during Hot Standby,Fuse 2330-702 Removed,Causing Loss of Automatic Control for Lpci/Component Cooling Water Sys HX Delta P.Caused by Wiring Sys Using Same Fuse Circuits
05000336/LER-1995-021, :on 950517,design Error Confirmed to Be Present in Esas.Caused by ESAS Design Deficiency.Delay Circuit Installed on SIAS Actuation Module Relay Output
05000387/LER-1984-001, :on 840103,hydrogen Dioxide Analyzers in Containment Atmosphere Monitoring Sys Inoperable.Caused by Design Deficiency.Catalyst Will Be Replaced on 840201 for Unit 1 & on 840215 for Unit 2
05000327/LER-1994-017, :on 941222,B-train Abi & Start of B-train Abgst Occurred as Result of High Radiation in Spent Fuel Area.Personnel Involved W/Spent Fuel Pool Rack Replacement Briefed on Event
05000336/LER-1994-018-01, :on 940602,filter Fans Crac Appeared to Be Feeding Opposite Supply Train.Caused by Incorrect Installation of Crac Sys.Plant Design Change 2 Was Implemented on 940605
05000266/LER-1990-007, :on 900712,error Indicating Potential for Failure to Comply W/Peak Cladding Temp Acceptance Limit Noted.Caused by Human Error.Util Committed to Reduced Height Dependent Heat Flux Hot Channel Factor Limit
05000336/LER-1990-005-02, :on 900503,identified Potential for High Energy Line Break in Auxiliary Steam Sys That Could Degrade Plant Areas Determined as Mild Environs.Probably Caused by Incorrect Conclusions from Analysis in 1973
05000266/LER-1990-003, :on 900409,determined That Piping & Supports in Fuel Oil Pumphouse Could Not Be Demonstrated to Perform Support Functions.Caused by Design Base Not Sufficiently Documented.Mod Performed to Support Fuel Oil Piping
05000155/LER-1991-010-01, Forwards LER 91-010-01,reactor Protection Sys Pressure Switches Experiencing Setpoint Drift.Util Considered Event Reportable to NRC Per 10CFR50.73(a)(2)(vi) as Potential Generic Problem
05000155/LER-1991-010, :on 911215,two Out of Four Reactor Pressure Switches Were Found to Be out-of-tolerance High.Caused by Aging & Corrosion Experienced by Instrumentation.Switches Were Recalibrated in Accordance W/Plant Procedure
05000301/LER-1989-009-01, :on 891115,unexpected Steam Generator a lo-lo Level & Steam Generator B lo-lo Level Reactor Trip Signals Experienced.Caused by Installation of Analog Signal Generator.Procedures Revised
05000311/LER-1987-009, :on 871125,util Task Force Examining Compliance w/10CFR50,App R Found Inadequacies Re RHR Room Coolers & Control Cablings.Caused by Inadequate Design Review.Design Change Mods Being Made
05000311/LER-1987-009-01, :on 870619,svc Water Sys Cabling Deficiency Discoverd.On 870625,nonseismically Qualified Marinite Walls Discovered.Caused by Inadequate Design Review & Documentation.Walls Reinforced
05000255/LER-1989-019, :on 890731,determined That Boron Dilution Incident Not Bounding for Recently Hypothesized Event.Caused by Vendor & Plant Personnel Preparing Analyses Unaware of Flow Path.Operating Procedures Being Revised
05000255/LER-1988-013, :on 880822,control Room HVAC Sys Declared Inoperable for Failing to Meet Tech Spec Criteria.Caused by Open Electrical Penetrations in Control Room Floor.Tech Spec Test RO-28 Revised to Correct Fan line-up
05000296/LER-1997-005-02, :on 970824,LCO Was Not Entered When Valve Was Malfunctioning.Caused by Lack of Questioning Attitude by Operations Crew.Involved SROs Were Counseled & Problem Evaluation Rept Will Be Discussed
05000296/LER-1992-003-04, :on 921027,discovered Failure of Reactor Zone Isolation Dampers to Close.Caused by Failed Solenoid Operated Valve.Outboard Damper Manually Closed by Isolating Air Supply & Bleeding Air Off Damper
05000400/LER-1990-015, :on 900524,concluded from Evaluation That Failure of Microswitch Contacts Could Prohibit Proper Sequencer Response to Safety Injection & Loss of Offsite Power Signals.Caused by Design Deficiency
05000250/LER-1993-003, :on 930116,discovered That Manual Discharge Valves of Both Trains of Containment Spray Sys Isolated While in Mode 4.Caused by Communication Errors.Night Order Issued Re Proper Procedure Use
05000315/LER-1988-013, :on 881123,spurious ESF Actuation (Reactor Trip) from Loss or Reactor Flow Logic Circuit Concurrent W/ Tripping of All Four Reactor Coolant Pump Breakers Occurred. Cause Not Determined.Logic Card Replaced
05000315/LER-1989-015-01, :on 891128,pyralarm Fire Detection Zone 3 Made Inoperable When Welding in Laundry Room Caused Standing Alarm.Fire Watch Patrol Not Assigned within 1 H.Caused by Personnel Error.Event Reviewed W/Operators
05000293/LER-2015-010, Regarding Motor-Operated Valve Control Circuit Vulnerability to Information Notice 92-18 Concern
05000280/LER-2015-001, Regarding Inadequate Missile Protection Due to Failure to Procedurally Control Sliding Missile Shields
05000455/LER-2011-001, Regarding Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications Due to Inadequate Work
05000482/LER-2010-001, For Wolf Creek, Regarding Automatic Start of Motor Driven Auxiliary Feedwater Pumps Inoperable During Startup in Mode 1
05000286/LER-2008-002, Regarding Loss of Single Train 31 Pressurizer Backup Heater Bank Required to Function to Shutdown and Maintain the Reactor in a Safe Condition Remote from Control Room
05000305/LER-2007-008, Inadequate Emergency Diesel Generator Testing When Redundant Emergency Diesel Generator Was Inoperable
05000305/LER-2005-014-01, Re Technical Specification LCO Not Entered for Diesel Generators Inoperable While in Refueling Shutdown
05000305/LER-2005-011, Re the Setting of a Permissive (P-10) in the Power Range Channels of the Nuclear Instrumentation System Was Outside of Plant Technical Specification Requirements
05000301/LER-2005-001, Regarding Main Steam Safety Valve 2MS-02008 Lift Set Point Exceeds Acceptance Criteria
05000285/LER-2005-001, Re Unplanned Reactor Trip Due to a Feedwater Transient at Low Power During Plant Shutdown
05000289/LER-2004-001, High Pressure Injection Pump Seismic Qualification Impacted Due to an Oversight in the Design Process When Power Supplies for the Auxiliary Oil Pumps Were Relocated
05000389/LER-2003-004, Regarding Condensate Pump Motor Bearing Failure That Resulted in Manual Reactor Trip
05000301/LER-2003-005, Re Manual Reactor Trip and Manual Safety Injection Due to Pressurizer Low Level
05000331/LER-2003-001, Manual Reactor Scram and Reactor Coolant Chemistry Excursion Due to Punctured Main Condenser Tube Caused by Failed Condenser Deflector Plate
05000272/LER-1988-006, :on 880318,10CFR50 App R Cable Design Deficiency Identified.Caused by Design Error.Cable Will Be re-routed During Next Refueling Outage.Roving Fire Watch Will Be Continued Until Completion of Repair
05000255/LER-1989-023, :on 891010,identified That U-bolt Connection Assembly for Main Steam Line Support Structure Exceeded Stress Allowed by FSAR by Approx 14%.Caused by Inadequate Review of Analyses by Vendor
05000336/LER-1994-022-01, :on 940620,second Analyzer Failed Surveillance Test.Caused by Timer Switch Left in Off Position in Accordance W/Operating Procedure.I&C Repaired Defective Unit & Surveillance Sp 2403C Performed