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 Issue dateTitleTopic
05000458/LER-1986-009, Corrected LER 86-009-00:on 860114,radwaste Liquid Effluent Monitor Sample Pump Not Started During Radioactive Liquid Discharge.Caused by Miscommunication & Procedure Ambiguities.Procedures Revised13 February 1986Corrected LER 86-009-00:on 860114,radwaste Liquid Effluent Monitor Sample Pump Not Started During Radioactive Liquid Discharge.Caused by Miscommunication & Procedure Ambiguities.Procedures Revised
05000458/LER-1987-001, Corrected LER 87-001-00:on 870108,discovered That Main Plant & Fuel Bldg Exhaust Radiation Monitor Particulate & Iodine Samplers Isolated Since 870107.Caused by Operator Error. Operator Aid Issued9 February 1987Corrected LER 87-001-00:on 870108,discovered That Main Plant & Fuel Bldg Exhaust Radiation Monitor Particulate & Iodine Samplers Isolated Since 870107.Caused by Operator Error. Operator Aid Issued
05000458/LER-1990-02218 June 1990LER 90-022-00:on 900518,HPCS Sys Declared Inoperable & 14-day Shutdown Limiting Condition for Operation Entered Due to Inoperative Suppression Pool Level Transmitter.Caused by Personnel Error.Reactor Operators trained.W/900618 LtrTime of Discovery
Fuel cladding
05000458/LER-1993-01016 August 1993LER 93-010-01:on 930514,SDC Loss for Three Minutes When SDC Suction Valves Closed.Caused by Failure to Identify Need for Compensatory Measures.Revised Procedural Guidance Clarifying Valve isolation.W/930816 Ltr
05000458/LER-1993-01226 August 1993LER 93-012-01:on 930603,deficiency in Plant Surveillance Test Procedures Identified.Caused by Inattention to Detail During Initial Procedure.Surveillance Test Procedures revised.W/930826 LtrTime of Discovery
05000458/LER-1993-01523 August 1993LER 93-015-00:on 930723,discovered Time Response Testing of Isolation Instrumentation for RWCU & RCIC Sys Not Performed at Intervals Required by Tss.Caused by Scheduling Error & Misinterpretation of Ts.Schedule revised.W/930824 Ltr
05000458/LER-1993-01627 August 1993LER 93-016-00:on 930727,HPCS Sys Actuation Occurred Due to Improperly Prepared Rev to Surveillance Test Procedure. Changed Surveillance Procedure STP-051-4811.W/930827 LtrReactor Vessel Water Level
ML17279A1917 April 1987Comparision of Electrical Design of Wye Pattern Globe Valve Actuator W/Ball Valve,Hanford 2 & River Bend Design. Five Oversize Drawings Encl
ML18010A95230 November 1992NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.Nondestructive Examination
Liquid penetrant
ML18010B0845 May 1993NRC Licensing Submittal Review of Licensing Conditions Imposed by NUREG-1216.Safe Shutdown
Boric Acid
Shutdown Margin
Loop seal
Stroke time
Temporary Modification
Stress corrosion cracking
Liquid penetrant
Overspeed trip
ML19208B56312 July 1979Statement of Safety Implication Re Discontinuities in K-bevel Area of T Weld Which May Lead to Unacceptable Stresses & Deformations During Plant Operation
ML19210E60630 November 1979Alternatives Studied to Minimize Impact on Port Hudson Battlefield Historic Natl Landmark. One Oversize Map Encl & Available in Central Files Only
ML19225C26327 June 1979Deficiency Re Cadsleeve Welds Mfg by Graver Energy Sys & Produced by Semiautomatic Welding Procedure.All Defective Cadsleeves Will Be Replaced Using Manual Welding Process W/Increased Inprocess Controls
ML19282B36428 February 1979Alligator Bayou Flood Study,Present Bayou Hydrology.
ML19290D6583 December 1979Deficiency Rept Re Acceptance Testing of Concrete Matls. on 790925-26,Southwestern Labs QA Audits Revealed That QA Requirements Re Calibr & Shop Practices Had Not Been Met. Caused by Noncompliance W/Manual.Rept by 791230
ML19296A8343 December 1979Advises That Rept on Protential Deficiency Reported 791105 Re NDT for Fabrication of Primary Shield Wall Will Be Provided by 800105Non-Destructive Examination
ML19296B99831 December 1979Final Deficiency Rept:On 791203,informed NRC of Deficiency in QC of Concrete Testing Svcs by Southwestern Labs.Caused by Errors in Testing Program.Concrete Placed Prior to 791102 Retested by Pittsburgh Testing Labs
ML19296C16212 November 1979Interim Deficiency Rept Re T Weld Cracking.S&W Performing Metallurgical Analysis of Test Specimens & Graver Engineering Reviewing Voltage Variation & Bead Shape.Rework & Repair or Replacement Planned
ML19316B06122 May 1980Deficiency Rept Re Diesel Generator Bldg Concrete Matl Cold Joint.Equipment Failure Did Not Represent Breakdown in QA Program.Structural Analysis Indicated Unplanned Const Joint Did Not Impair Structural Integrity or Performance of Matl
ML19323A40414 April 1980Annual Financial Rept 1979
ML19323G73322 April 1980Advises That Potential Deficiency Re Concrete Cold Joint Does Not Appear to Represent Significant Deficiency Reportable Under 10CFR50.55(e).Results of Final Analysis Will Be Forwarded within 30 Days
ML19324B62227 October 1989LER 89-034-00:on 890930,determined That 10 H Run of Standby Gas Treatment Sys Train B Not Performed within Allowable Surveillance Tolerance Which Had Ended on 890904.Caused by Human Error.Operations Personnel trained.W/891027 Ltr
ML19325D13230 September 1989Monthly Operating Rept for Sept 1989 for River Bend Station Unit 1.W/891013 Ltr
ML19325D49316 October 1989LER 89-033-00:on 890916,electrical Power Lost to Div II 120 Volt Ac Distribution Panel,Resulting in auto-start of Div II Standby Gas Treatment & Annulus Mixing Sys.Caused by Failure of Elgar Power Line Conditioning transformer.W/891016 Ltr
ML19325E66127 October 1989LER 89-035-00:on 890930,reactor Automatically Scrammed During Performance of Routine Reactor Protection Sys.Caused by Defective Test Switch in Reactor Protection Sys.Test Switch Replaced Via Prompt Maint Work order.W/891027 LtrSafe Shutdown
Half scram
ML19325E72720 October 1989Part 21 Rept Re Defect in Eight GE Type CR 2940 Control Switches at Plant.Initial Condition Found on 890930.Contacts 3 & 4 for All Switches in Plant Sys Verified to Be in Correct Position for Intended Application
ML19327B10016 October 1989Special Rept:On 890620 & 26,temp in Diesel Generator 1A & 1B Control Room Found Above Tech Spec Limit of 104 F Greater than 8 H.Caused by Heat Generated Inside Bldg,High Outside Ambient Temp & Insufficient Ventilation
ML19330C4887 July 1980Final Deficiency Rept Re Use of Improperly Qualified 67 & 8 Concrete Aggregate in Category 1 Structures.Investigation Complete.No Reportable Deficiency Exists
ML19332B93814 November 1989Special Rept:On 891017,invalid Failure of Div 1 Diesel Generator Occurred Due to Trip.Trip Caused by High Vibration Signal from Turbocharger Vibration Switch.Switch Reset Per Maint Work Order R056445
ML19332B99114 November 1989Special Rept:On 890620,temp in Diesel Generator Control Room Identified as Above Tech Spec 3/4.7.8 Limit for Greater than 8 H.Similar Event Noted on 890626.Caused by Heat,High Outside Ambient Temps & Insufficient Ventilation
ML19332C53616 November 1989LER 89-036-00:on 891017,reported That Various motor-operated Valves Energized Contrary to Plant Fire Hazard Analyses. Caused by Failure to Implement Design Documents.Valves Reanalyzed & Procedures revised.W/891116 LtrSafe Shutdown
Fire Barrier
ML19332C78931 October 1989Monthly Operating Rept for Oct 1989 for River Bend Station, Unit 1.W/891114 Ltr
ML19332E86528 November 1989LER 88-018-03:on 880825,reactor Automatically Scrammed Due to Turbine Control Valve Fast Closure.Casued by Loss of Main Generator Field Excitation Resulting in Generator & Turbine Trips.Preventive Maint Procedure revised.W/891128 LtrSafe Shutdown
Slow transfer
ML19341D7043 April 1981Annual Financial Rept 1980
ML19343B5018 December 1980Part 21 Rept Re Reactor Protection Sys Flexible Conduit Defect Causing Hot Shorts If Improperly Grounded.Caused by Paint on Panel Surfaces or High Resistance Connection to Panel Survaces Where Termination Modules Are MountedHot Short
ML19347B50812 September 1980Interim Deficiency Rept Re Incorrect Input in Calculations Used to Generate Amplified Response Spectra of Reactor Bldg Structures.Detailed Review Initiated & Rept to Be Submitted Pending Review Findings
ML19347F82031 December 1980Interim Deficiency Rept Re Incorrect Input to Calculations to Generate Amplified Response Spectra for Reactor Bldg Structures.Error Has Been Corrected.Final Analysis Will Be Sent by 810401
ML19351A4648 December 1989LER 89-037-00:on 891108,Div II Control Bldg Ventilation Sys Isolated & Filtration Unit Automatically Initiated.Caused by Spurious Signal from Control Bldg Intake Radiation Monitor. Voltage Suppressors Installed on monitors.W/891208 Ltr
ML19351A65814 December 1989Special Rept:On 891114,trip Occurred on Div I Diesel Generator 1EGS*EG1A.Caused by Defective High Bearing Temp Detector & Water in Plastic Tubing Used to Connect Test Gauge.Shutdown Logic Board & Defective Connector Replaced
ML19351A67130 November 1989Monthly Operating Rept for Nov 1989 for River Bend Station Unit 1.W/891213 Ltr
ML19351A67613 December 1989LER 89-038-00:on 891113,unplanned Loss of Div I 125 Volt Dc Bus Occurred.Caused by Failure to Adequately Verify Clearance Boundaries.Power Restored to Bus & Isolations reset.W/891213 Ltr
ML19354D40027 October 1989Informational Rept:On 890928,field Engineer Made Emergency Exit from High Radiation Area Through High Radiation Door AB78-01.Total Exposure Received by Engineer Was 10 Mr.Door Not Required to Be Locked & Therefore Lock on Door DefeatedHigh Radiation Area
ML20003C84524 February 1981Interim Deficiency Rept Re Overturning of Primary Containment Shield Wall,Initially Reported on 810126. Nonconformance Rept Has Been Initiated to Address Damage to Shield Wall.Next Rept Will Be Forwarded within 60 Days
ML20003H7325 May 1981Annual Financial Rept 1979
ML20005A43423 June 1981Final Deficiency Rept Re Overturning of Primary Shield Wall During Const Movement.Base Plate Is Being Reworked to Restore to Original Design Conditions.Attachments to Base Plate Will Be Replaced
ML20005E13826 December 1989LER 89-041-00:on 891125,unplanned ESF Actuation Occurred as Result of Two Leads Shorted Together During Testing of Control Circuitry,Causing Valve Isolation from Suppression Pool.Sys Lineup Restored to Normal position.W/891226 Ltr
ML20005E8512 January 1990LER 89-042-01:on 891201,main Turbine Generator Tripped, Resulting in Reactor Scram.Caused by Sensing Fault on Offsite 230 Kv Line.Sys Maint Procedure Being Revised to Include Test of Failed Portion of relay.W/900102 LtrSafe Shutdown
Slow transfer
ML20005E8522 January 1990LER 89-043-00:on 891201.two Outboard MSIVs Inoperable Due to Failure of Corresponding Fast Closure solenoid-operated Valve.Caused by Incomplete Removal of Silicone Lubricant. Lubricant Removed by Application of Acetone.W/900102 Ltr
ML20005F8568 January 1990Special Rept:On 891211,invalid Failure of Div II Diesel Generator Occurred During Monthly Surveillance Test Procedure STP-309-0202.Caused by Failed GE Breaker in Exhaust Fan.Breaker Replaced & Generator Returned to Svc
ML20005G16410 January 1990LER 89-044-00:on 891211,unplanned ESF Actuation Occurred, Resulting in Isolation of Rcic.Caused by Technician Failing to Perform Steps of Surveillance Test Procedure in Sequence.Div II Isolation Signal reset.W/900110 Ltr