05000260/LER-1998-004-03, :on 981202,SR Intent Was Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Procedures to Provide Proper SR Implementation.With
RC-98-0133, Responds to Violations Noted in Insp Rept 50-395/98-04. Corrective Actions:Need for Adding Applicable Action Statement for Tt & Feedwater Isolation Automatic Actuation Logic as Part of Conversion to Improved TS Will Be Assessed
05000370/LER-1989-008-04, :on 890828,discovered That Sample Obtained for Chemical & Vol Control Sys Letdown HX Outlet Found to Be Invalid.Caused by Chemistry Technician Failure to Follow Procedure.Event Reviewed W/All Technicians
05000327/LER-1989-013, :on 890503,train B Control Room Isolation Signal Received in Main Control Room.Caused by Operator Bumping Radiation Monitor Pump Motor Breaker While Changing Recorder Chart Paper.Chart Paper Replaced
05000339/LER-1989-004-02, :on 890502,unexpected Automatic Reactor Trip Signal Generated During Performance of ICP-FW-2-F-2486. Caused by Procedure Inadequacy.Instrument Dept Procedures Will Be Reviewed & Revised
05000327/LER-1989-025, :on 890815,all Four Emergency Diesel Generators Declared Inoperable Because Fuel Oil Not Sampled.Caused by Inadequate Procedure Due to Chemistry Personnel Omission. Samples Obtained & Analyzed
05000461/LER-1989-013, :on 890302,all intermediate-range Channels Declared Inoperable Because Weekly Channel Functional Surveillance Could Not Be Performed Due to Plant Conditions. Caused by Personnel Error.Personnel Counseled
05000298/LER-1989-024, :on 890731,crack in Diesel Generator Injection Pump Pedestal Found During Surveillance Testing.Caused by Unusual Hydraulic Forces Created by Lube Oil Trapped in Pedestal.Tubing Inserted in Bearing Oil Port
05000298/LER-1989-021, :on 890602,undocumented Wiring Configurations Associated w/safety-related Equipment Discovered During Implementation of Design Change 87-190.Caused by Existence of Unexpected GE Supplied Subj Configurations
05000425/LER-1989-024, :on 890726,failure of Pressure Channel Circuit Card Caused Reactor Trip.Caused by Failure of Operational Amplifier in non-isolated Section of Process Card.Defective NLP2 Card Replaced
05000312/LER-1989-004, :on 890328,plant Main Feedwater Pumps (MFP) Experienced Speed Control Problems.Because of MFP Controller Problems,Integrated Control Sys Response Caused post-trip. Test Program Established to Monitor Pump
05000382/LER-1998-011, :on 980603,TS 3.0.3 Entry Was Noted.Caused by Component Cooling Water Makeup Check Valve Failing Ist. Operability of a Train of CCW Was Restored Immediately & Check Valve Internals Were Replaced
05000368/LER-1989-002, :on 890109,discovered That Tech Spec Required 14-day Periodic Surveillance Test for Svc Water Flow Rate to Containment Cooling Units Not Performed.Caused by Personnel Error.Personnel Counseled
05000413/LER-1987-019, :on 870501,two Work Requests Were Discovered Failing to Specify Retest Requirements.Caused by Personnel Failure to Specify Retest Requirements on Implementation Plan.Incident Reviewed W/Appropriate Personnel
05000315/LER-1986-018-01, :on 860802,reactor Trip Occurred from Steam Generator Flow Mismatch Coinciding W/Low Steam Generator Level.Caused by Increased Turbine Load.Personnel Counseled
05000317/LER-1987-003, :on 870127,reactor Tripped Due to Decreasing Steam Generator Levels.Caused by Loss of Instrument Air Pressure.Pressure Restored.Engineering Analysis to Increase Reliability of Air Sys Performed
05000338/LER-1987-001-01, :on 870127,7-day Period Allowed for Fire Pump to Be Out of Svc Exceeded.Caused by Inclement Weather & Further Repair Efforts.Pump Returned to Svc on 870213.W/
05000289/LER-1999-001-01, :on 990122,short Sections of Piping Caused by Misplacement of Sensing Elements & Insulation.Caused by Failure to Adhere to Vendor instruction.Re-installed Heat Trace Sys
05000409/LER-1986-021, :on 860716,reactor Scram Occurred.Caused by Static Inverter 1A Transferring Alternate Source & Momentarily Deengergizing Scram Trains.Inverter Will Be Replaced Prior to Plant Startup
05000414/LER-1986-028-01, :on 860627,safety Injection Actuated on Low Pressurizer & Main Steam Line Pressure.Pressure Decreased Due to Inadvertent Opening of Porvs.Caused by Procedure Deficiency.Procedure Revised
05000259/LER-1985-057, :on 851009,determined That wide-range Torus Water Level Transmitters Not Qualified.Cause Unstated. Replacement of Existing wide-range Monitors Planned for Current Unit Outages
05000302/LER-1997-017, :on 970621,inadequate Electrical Separation of High Pressure Flow Indicators Was Noted.Caused by Personnel Error.Insp of Immediately Accessible Areas in Main Control Board Conducted
05000395/LER-1997-002, :on 970426,turbine Trip & Feedwater Isolation Occurred.Caused by Hi-Hi Level in Steam Generator C Signal. Verified Sys Integrity & Proper Plant Response & Initiated Plant Restart
05000382/LER-1997-015, :on 970418,ultimate Heat Sink Did Not Incorporate Conservative Assumptions.Caused by Design Errors Associated W/Original Design of Ultimate Heat Sink. Operability Evaluation Completed on 970404
05000269/LER-1986-004-02, :on 860312,Nuclear Instrumentation Channel NI-1 Discovered Not Operating While Eight Fuel Assemblies Inserted Into Core.Caused by Failure to Maintain Full Requirements of Refueling Procedure
05000213/LER-1985-028, :on 851110 & 21,during Coastdown,High Steam Flow (Hsf) Reactor Trips Occurred Due to Automatic Reactor Protection Sys Initiation.Caused by Communication Between Hsf Channels 1,2 & 4.Loop 3 Solenoids Replaced
05000327/LER-1985-041-01, :on 851014,inadvertent Start of Diesel Generator Occurred.Caused by Dislodged Fuse.Diesel Generator Shut Down.Caution Placed in Standby Power Checklist
05000323/LER-1985-021-01, :on 851204,spurious Safety Injection Occurred. Caused by Safety Injection Signal Received on Train a of Solid State Protection Sys While Preparing to Investigate 851202 Event.No Corrective Action Required
05000416/LER-1996-004, :on 960606,manual Reactor Scram Occurred Due to Spurious Multiple SRV Lifts.Trip Unit 1C11N655B Was Shipped to Manufacturer for Failure Analysis
05000213/LER-1985-020, :on 850803,ladder Left Unattended W/O Restricting Access During Permanent Ladder Installation to High Radiation Area.Caused by Miscommunication to Maint Staff.Locked Gate Installed at Ladder Base
05000409/LER-1985-014, :on 850725,partial Reactor Scram Occurred,Hpcs Pumps & Emergency Diesel Generators Started & Containment Bldg Isolated.Caused by Ground in Gas Pressure Scram Circuit.Ground Located & Wire Repaired
05000213/LER-1985-009-01, :on 850910,one Auxiliary Feedwater solenoid- Operated Valve Failed to Change State Upon Deenergization. Caused by Stuck Valve NP-8320A-185E.Periodic Cycling Will Be Performed Until Problem Resolved
05000318/LER-1996-006, :on 961210,discovered EDG Had Been Inoperable for Six Days.Caused by Personnel Error.Checked Fuse Holder Covers,Conducted Tailgate Training & Revised Procedure Re Installation of Fuse Holder Covers
05000382/LER-1985-030, :on 850630,ESF Portion of Control Room Ventilation Sys Actuated Due to Electrical Spike in Control Room Air Intake Radiation Monitors.Caused by Portable Radio Transmitters Used Near Radiation Monitors
05000409/LER-1985-010, :on 850424,degraded Fire Barrier Penetration Discovered.Caused by Improper Installation.Barriers Repaired.Caution Sign Posted Near Electrical Penetrations in Fire Barriers Protecting safety-related Areas
05000445/LER-1996-007, :on 960809,automatic Reactor Trip Occurred Due to Lightning Strike.Bypass Mod to RPS ESF Channels Initiated
05000277/LER-1996-004-01, :on 960417,HPCI Sys Declared Inoperable Due to Leak in Cooling Water Relief Valve.Caused by Igscc.Hpci Cooling Water Relief Valve Was Replaced.W/Undated Ltr
05000327/LER-1985-015, :on 850404,hourly Fire Watch for Auxiliary Bldg Supply Air Fan Room Not Conducted.Caused by Inoperable Door. Door repaired,post-maint Check Made & Fire Watch Reestablished
05000416/LER-1985-015, :on 850404,RCIC Sys Inadvertently Isolated When Bypass Switch Mistakenly Returned to Normal During Testing.Caused by Misunderstanding Between Personnel.Sys Restored.Need for Clear Communication Stressed
05000352/LER-1996-016, :on 960725,core Thermal Power Exceeded Licensed Power Limit During Power Transient.Caused by Defective EHC Sys Component & Reactor Scram.Defective Primary Frequency/ Voltage Converter Replaced & Calibration Performed
05000277/LER-1992-018, :on 920915,security Personnel Discovered That TS Required 1 H Firewatch Performed in Excess of 1 H Interval.Caused by Personnel Error.Security Supervisor Counselled
05000352/LER-1996-013, :on 960521,Unit 1 Reactor Scram Occurred.Caused by Inadequate Procedural Guidance & Undetermined Equipment Malfunction.Procedure Will Be Revised to Ensure Appropriate Barriers,In Place to Minimize Risk of Scram
05000413/LER-1985-019, :on 850307,during Performance of Analog Channel Operational Test,Steam Generator C Level Channel 4 Found Inoperable.Caused by Personnel Error.Circuit Card Replaced
05000293/LER-1992-005, :on 920403,actuation of CSCS Logic Circuitry Occurred While Shut Down.Caused by Procedure Deficiency. Procedure Tp 92-020,Rev 0 Retired & Replaced by Procedure Tp 92-022,Rev 0
05000352/LER-1995-008-01, :on 950911,unusual Event Declared & RPS Actuated When Reactor Manually Shutdown Due to Inadvertent Opening of Ms SRV M.Caused by Pilot Valve Seat Leakage.Srv M & Four Other SRVs Removed & Replaced
05000331/LER-1984-019, :on 840521,0603,05 & 06,unplanned Partial Group V Isolation Experienced.Caused by Random Noise in Circuit.Further Study to Reduce Susceptibility of Sys to Spurious Isolation Pursued
05000352/LER-1995-003-01, :on 950719,Unit Maximum Power Level of 100% Was Exceeded by 3.4% Due to Unanticipated Response of 1B Reactor Recirculation Pump Following Decrease Speed Signal. Established Administrative Limit of 100% Core Flow
05000278/LER-1991-017-02, :on 910924,Automatic Depressurization Sys Discovered Inoperable Due to Components Being Unqualified. Caused by MSRV Thermal Insulation Being Improperly Installed.Subj Insulation Properly Reinstalled
05000352/LER-1995-002, :on 950221,reactor Protection Systems Actuated as Result of Trips of Main Turbines.Caused by Breaker Failure & Voltage Spike.Ground Fault Detection Relay Settings Being Evaluated
05000293/LER-1994-003, :on 940427,false Low Rector Vessel Water Level Signal Occurred While Shut Down.Caused by Deficiency in Procedure Being Used for Venting & Filling.Corrective Action Included Filling & Venting Water Header
05000285/LER-1994-002, :on 940308,boric Acid Pump Declared Inoperable Due to Inability to Ensure Reliable Starting of CH-4B Motor. Breaker Replaced W/Appropriate Model Breaker & Breaker for Boric Acid Pump Verified Appropriate
05000301/LER-1993-005-01, :on 931119,molded Case Circuit Breakers Failed Test Due to Grease Solidification.Caused by age-related Grease Solidification in MCCB Tripping Mechanism.Mccb Tested & Schedule for Replacement
05000443/LER-1994-002, :on 940210,determined Method for Performing Slave Relay Test Valve Did Not Satisfy Ts.Caused by Omission of Relevent Information from Surveillance Procedures. Procedures Revised
05000293/LER-1993-019, :on 930722,automatic Actuation of RHR Sys Portion of PCIS Occurred.Caused by Momentary Pressure Transient That Actuated Protective High Pressure Switches. Calibr Performed
05000331/LER-1993-004, :on 930611,while Performing EDG Operability Surveillance,Edg a Tripped Approx 3 After Initial Start Signal.Possibly Caused by Partially Latched Condition of Trip Mechanism.Latch Will Be Reset
05000423/LER-1993-007-01, :on 930611,plant Mgt Discovered Reduction in EDG Fuel Oil Storage Capacity Per SER & Fsar,Constituting Event Outside Design Basis of Plant.Caused by Inadequate Design Interface.Temporary Tanker Utilized
05000282/LER-1993-006, :on 930325,cooling Water Pump 121 auto-started on Low Header Pressure While Aligned for Safeguards Operation.Caused by Operator Failing to Open Header Valves a & B.Surveillance Procedures Will Be Revised
05000263/LER-1989-040, :on 891219,secondary Containment Failed to Meet Operability Requirements for Secondary Containment Capability.Caused by Design Deficiencies.On 930317,addl Design Deficiency Noted Re Damper Controls
05000482/LER-1993-004-01, :on 930316,broken Fuel rod,11-12 Inches in Length,Protruded Out of Fuel Assembly F67 at Core Position FH-6.Caused by Grid to Rod Fretting Failures.Util Evaluating Fluid Elastic Instability
05000282/LER-1993-003-01, :on 930204,discovered That Lower Detector Flux Signal from All Four Nis power-range Channels Outside Acceptance Criterion.Caused by Miscalibration of power-range Channels.Procedures Revised & Test Labeling Improved
05000280/LER-1993-006-01, :on 930513,SW Flow Path to Main CR Chillers Declared Inoperable Due to Pipe Leak.Two Inch Backwash Supply Line & Strainer 1-VS-S-1A & Associated Isolation Valves Replaced
05000281/LER-1992-008-03, :on 921215,RCS Leak Identified Near Low Pressure Letdown Flow Transmitter.Caused by Failure of Swagelock Fitting on Flow Transmitter.Root Cause Evaluation in Progress & Fitting & Tube Replaced
05000280/LER-1991-011-01, :on 910406,simulated Design Basis Accident Conditions Resulted in Failure of Pumps to Develop Design Flow & Discharge Pressure.Caused by Inadequate Design. Permanent Mod of Radiation Sys Evaluated
05000281/LER-1989-003-02, :on 890813,charging Pump B Automatically Started After Control Switch Disengaged from pull-to-lock Position.Caused by Operator Not Adequately Engaging Pumps Switch in Position Prior to Event
05000281/LER-1993-006-03, :on 931115,Unit 2 Experienced Automatic Reactor Trip.Caused by Electrical Circuit Failure.Electrical Failure Traced to Defective Circuit Breaker & Replaced
05000281/LER-1993-003-03, :on 930803,automatic Reactor Trip Occurred Due to Low Steam Generator Water Level Coincident W/Steam/ Feedwater Flow Mismatch Resulting from Spurious Closure of Main Feedwater Regulating Valve a
05000280/LER-1994-006, :on 940511,manual Reactor Trip Occurred During Safeguards Actuation Logic Testing.Caused by Inadvertent Actuation of Relay in Safety Injection Actuation Circuitry. Reactor Placed in Safe,Hot Shutdown Condition
05000280/LER-1994-003-01, :on 940204,hole in Recirculating Spray HX Svc Water Outlet Piping Identified.Caused by Failure of Coal Tar Epoxy Coating.Piping Inspected & Will Be Pressure Tested Per Station Procedures
05000281/LER-1993-004-02, :on 930823,reactor Tripped Due to Turbine - Generator Trip.Caused by Loss of Field Relay.Reactor Trip Breakers Verified Open & Control Rods Verified Inserted Into Core
05000280/LER-1988-005-01, :on 880219,heat Tracing Proper Control Setpoints Could Not Be Verified.Caused by Inadequate Surveillance & Maint Procedures.Verification of Correct Setpoints Initiated
05000280/LER-1987-027, :on 871027,electrical Short in Train a Turbine Bldg Flood Control Panel Caused Spurious Completion of Flood Protection Circuit.Caused by Leak on Access Manway of Moisture Separator Reheater 1-MS-E-1B
05000373/LER-2018-003, Regarding Two Main Steam Safety Relief Valves Failed Inservice Lift Inspection Pressure Test
05000296/LER-1993-001-03, :on 930228,unplanned Actuation of ESF Occurred When 3 DGs Automatically Fast Started.Caused by Inappropriate Personnel Action.Licensee Will Replace Damaged CAS Logic Cable & Will Submit Followup Rept
05000400/LER-1992-007-02, :on 920712,automatic Turbine Trip & Reactor Trip Occurred Due to Failure of Low Pressure Turbine Exhaust Boot Seal.Repairs to Low Pressure Turbine Exhaust Boot Seal Completed on 920713
05000400/LER-1990-010, :on 900405,control of Reactor Auxiliary Bldg Emergency Exhaust Pressure Boundary Not Implemented.Caused by Lack of Administrative Controls for Doors & Hatches. Administrative Controls Implemented
05000400/LER-1987-030, :on 870512,Maint Surveillance Tests I0140, I0141 & I0142 for P-12 Interlock Missed Thus Violating Tech Specs Requirements.Caused by Personnel Error.Procedures Revised
05000251/LER-1987-007-01, :on 870310,air Leakage During Leak Rate Testing of Personnel Hatch Exceeded Tech Spec Requirements.Caused by Malfunctioning Equilizing Valve Not Being Able to Fully Close.Valve Replaced
05000315/LER-1994-001, :on 940203,04 & 05,13 of 20 MSSVs Lift Settings Found Out of Tolerance.Caused by Mild Galling Between Disk & Nozzle Components.Valve Mfg Recommended That Nozzle & Disc Seatingsurfaces Have Grey Matt Finish
05000315/LER-1990-010, :on 900824,discovered That Routing Cable Associated W/Unit 1 Low Shutdown Indication Panels Not in Compliance w/10CFR50,App R.Minor Plant Mod Initiated to Provide Encl (Wrapped) Around Subj Conduit
05000316/LER-1993-002, :on 930219,determined That Condenser Air Ejector TS Sample Had Not Been Taken.Caused by Personnel Error.Appropriate Administrative Action Taken in Regards to Individuals Lack of Attention to Detail
05000316/LER-1993-008, :on 930827,reactor Trip Occurred from Steam Flow/Feed Flow Mismatch Coincident W/Low Level in SG 4. Defective current-to-current Repeater Replaced
05000315/LER-1991-009, :on 910927,discovered That CO2 pop-off Chain for Fire Damper Not Wired to CO2 Piping,Rendering Fire Damper Inoperable.Caused by Personnel Error.Wire Removed & Approved Clip Reattached to Chain
05000315/LER-1991-005, :on 910718,emergency Diesels Declared Inoperable When Design Documents Could Not Be Located to Demonstrate Capability of EDG to Withstand Effects of Tornado.Edg Room Fans Will Be Run
05000315/LER-1991-006, :on 901129,facility Outside Design Basis for Separation of Safety Related & Nonsafety Related Circuits. Caused by Personnel Error.Design Procedures Revised
05000315/LER-1991-003, :on 910308,liquid Release to Unrestricted Area in Violation of Tech Spec.Caused by Failure of Hi Fail Status of RRS-1000 to Produce Trip.Operations Procedure 12 Ohp Revised
05000315/LER-1990-008, :on 900619,discovered That Isolation Relay Circuitry for Low Header Pressure Auto Start Switch for Essential Svc Water Pumps Installed Incorrectly.Caused by Design Errors.Plant Mod Packet Initiated
05000315/LER-1989-002-01, :on 890303,failure of MSIVs to Meet Tech Spec Lift Setpoint Requirements Occurred.Safety Valve Setpoints Reset within Specified Ranges
05000316/LER-1992-002-01, :on 890124,containment Isolation Valves Not Repaired When ASME Section XI Leakrate Acceptance Criteria Exceeded.Caused by Procedure Requirements Not Being Included in Test Procedure.Packing Replaced
05000315/LER-1987-005, :on 870408,during Cooldown & Depressurization, Pressure/Temp Limits of Tech Spec 3.4.9.1 Exceeded.Caused by Personnel Error.Administrative Controls & Procedural Enhancements Incorporated
05000316/LER-1987-001-01, :on 870303,spurious Signal from Source Range Instrument Channel N-31 Resulted in ESF Actuation.Caused by Malfunction of Detector.Source Range Instrument Detector Removed,Replaced & Declared Operable on 870314
05000529/LER-1990-010-01, :on 901110,EDG Jacket Cooling Water Line Inadequately Supported
05000529/LER-1990-011, :on 901113,inadvertent Control Room Essential Filtration ESF Actuation Occurred
05000528/LER-1990-009, :on 900620,identified That License Holders Had Not Received Biennial Medical re-exams,per 10CFR55.21.Caused by Inadequate Tracking Sys & Medical Personnel Failure to Follow Procedures.Procedures Developed
05000397/LER-1997-003, :on 970320,notification of Noncompliance W/Ts as TS SRs for Response Time Testing Were Not Being Met for Specified Instrumentation in Rps,Pcis & Eccs.Requested Enforcement Discretion for One Time Exemption
05000397/LER-1991-024, :on 910909,unanalyzed Condition Associated W/ Postulated Main Steam Line Failure Outside Containment Discovered by Ge.Caused by Failure to Consider Iodine Source Term.Procedure Re Cold Startup Changed
05000397/LER-1991-013, :on 910507,non-compliances W/Tech Specs Identified as Part of Program of Surveillance Procedure Verification.Further Evaluation Performed.Quality Action Team to Be Chartered to Evaluate Program
05000397/LER-1991-015, :on 910602,high HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred.Caused by Personnel Error.Operator Involved Ack & Reset Alarm
05000397/LER-1990-013, :on 900610,ESF Isolations & Actuations Occurred Due to Breaker Trip.Cause of Event Not Determined.Power Restored to E-MC-7A & Isolations Restored
05000397/LER-1989-033, :on 890811,RWCU Isolation Occurred When Fuse in Power Supply to Leak Detection Monitor Blew,Giving False High Alarm Signal to Isolation Logic.Cause Unknown.Fuse Replaced & RWCU Sys Restored to Operation
05000397/LER-1990-014, :on 900703,HPCS Sys Pump Suction Switchover from Condensate Storage Tanks to Suppression Pool Occurred Due to Suppression Pool High Water Level Condition.Caused by Procedural Inadequacy.Procedures Modified
05000397/LER-1989-011, :on 890502,determined That Eight Valve Motors Did Not Meet Plant Commitment Made in Response to IE Circular 81-13.Caused by Less than Adequate Design Basis Documentation.Plant Mod Request Revised
05000244/LER-1995-009, :on 950817,surveillance Was Not Performed Due to Improper Application of TS Requirements Resulting in TS Violation.Testing of MOV-515 Was Performed on 951115.W/
05000244/LER-1992-006, :on 920518,main FW Isolations Occurred on SG a Due to Overfeeding SG a While in Manual Control.Caused by Heater Drain Tank Level Control Sys Problem.Administrative Controls Instituted to Ensure Valve Not Open
05000389/LER-1999-003, :on 990406,ECCS Suction Header Leak Resulted in Both ECCS Trains Being Inoperable & Entry Into TS 3.0.3. Caused by Chloride Induced OD Stress Corrosion Cracking of Piping.Made Code Repairs & Coated Piping.With
05000335/LER-1996-002-01, :on 960222,control Element Assembly Dropped on Unit 1 During Periodic Testing.Caused by Failed Silicon Control Rectifier in Upper Gripper Power Switch Module.Power Switch Modules Replaced
05000389/LER-1992-004-03, :on 920708,reactor Manually Tripped Due to Low SG Water Level.Caused by Failed Lead/Lag Circuit in Feedwater Regulating Valve Sys.Design Change Will Delete Circuits from SG Water Level Circuitry
05000335/LER-1990-010-02, :on 900720,erroneous Low Temp Overprotection (LTOP) Setpoint Put in Place & Unit Entered Mode 3 on 900805.Caused by Personnel Error & Failure to Utilize Design Control Process.Setpoints Changed
05000461/LER-1917-004, For Clinton Power Station, Unit 1 Main Steam Isolation Valve Local Leak Rate Test Limit Exceeded During Refueling Outage
05000219/LER-2015-003, Regarding Failure of the No. 1 Emergency Diesel Generator to Start During Surveillance Testing
05000390/LER-2015-002, Regarding Unanalyzed Condition Related to Spurious Opening of a Pressurizer Power Operated Relief Valve During a Postulated Appendix R Fire
05000280/LER-2012-001, Regarding Oil Foaming in Speed Increaser Results in Inoperable Charging Pump
05000272/LER-2006-001, Re Plant Turbine Trip - Reactor Trip with Reactor Power Above P-9
05000440/LER-2006-001, Re Incorrect Wiring in the Remote Shutdown Panel Results in a Fire Protection Program Violation
05000454/LER-2005-004, Regarding Technical Specification Required Action Not Satisfied Due to Ambiguous Implementing Procedure
05000397/LER-2004-004, Regarding Items of Reportability and Corrective Actions Taken
05000321/LER-2003-001, Edwin I.Hatch Nuclear Plant - Unit 1 Regarding Broken Reactor Protection System Neutral Bolt Results in RPS Bus Trip
05000390/LER-2003-002, Failure in Power Distribution Panel in Reactor Protection Panel 1-R-9
05000313/LER-2002-003, For Arkansas Unit 1 Reactor Coolant System Pressure Boundary Leakage from a Crack in a Control Rod Drive Mechanism Nozzle Reactor Vessel Head Penetration Weld Due to Previous Weld Repair Method
05000483/LER-2002-011, For Callaway Plant Unit 1 Regarding a Steam Generator Tube Inspection Results Classified as C-3
05000335/LER-2002-001, As-Found Cycle 17 Main Steam Safety Value Setpoints Outside Technical Specification Limits
05000316/LER-2002-001, Containment Isolation Valve Alignment Error During Local Leak Rate Testing
05000346/LER-1998-003, :on 980519,Mode 3 Entry Without Completion of Surveillance Requirement Occurred.Caused by Failure of I&C Technicians to Perform Each Sp as Written or Adherence. Revised Procedure
05000424/LER-1999-003-02, :on 990922,CR Door Painting Resulted in Loss of Positive Pressure Boundary.Caused by Inadequate pre-job Briefing.Doors Were Closed Upon Discovery by CR Personnel. with
05000443/LER-1987-003, :on 870202,failure to Perform Surveillance Test on Source Range Nuclear Instrumentation within Specified Interval Discovered.Caused by Personnel Error.Procedure for Surveillance Test Scheduling Being Revised
05000416/LER-1987-001, :on 870108,chemistry Section Personnel Determined Hydrogen Samples Taken from Condenser Offgas Pretreatment Sample Station Not Representative of Main Condenser Offgas Due to Failed Solenoid Valve
05000382/LER-1999-006-01, :on 990614,plant Experienced Automatic Reactor Trip Following Loss of 7kV Bus.Caused by Spurious Actuation of Relay on Either RCP 1A or 2A.Personnel Performed Final Switchgear Walkdown with Indications Normal.With
05000454/LER-1997-013-03, :on 970522,valve Mistakenly Opened & Caused post-LOCA Leakage to Exceed Limit.Cause Unknown.Licensee Identified Affected Sys & Procedures That Vent or Open Affected Sys
05000395/LER-1996-007, :on 960730,determined That Itt Barton Model 763 Pressure Transmitters Safety Hazard After Previous Failures. Caused by Loose Strain Gauge Lead.Devices Returned for Analytical Testing.Also Reportable Per Part 21
05000414/LER-1994-007-01, :on 941018,reactor Trip Occurred & TS Violated. Caused by Document Use Practices & Less than Adequate Mgt Directions.Cr Operators Entered Appropriate Emergency Procedures & Stabilized Plant