Pages that link to "NRC Form 3e6A"
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The following pages link to NRC Form 3e6A:
Displayed 50 items.
- 05000413/LER-1998-002-04, :on 980507,incorrectly Set Valve Leads to Elevated Condensate Storage Sys Temperature,Causing Condition Outside Design Basis of Plant,Was Noted.Caused by Inadequate Training.Alarm Response Guideline Revised (← links)
- 05000461/LER-1989-027, :on 890628,identified That Between 890411 & 0518,plant Operated in Condition Prohibited by Tech Specs. on 890403,screw Securing Control Room HVAC Sys Time Delay Relays Found to Be Missing (← links)
- 05000259/LER-1989-023-02, :on 890824,determined That Disabling auto-start Feature of Emergency Equipment Cooling Water (EECW) Sys Pump Rendered EECW Inoperable.Caused by Deficient Surveillance Instruction.Instruction Revised (← links)
- 05000259/LER-1989-024-02, :on 890826 & 0920,reactor Protection Sys Bus 1B Deenergized Resulting in Actuation of Plant Esfs.Caused by Inadequate Design of Protector Setpoints.Degraded Voltage Adjustment Potentiometer Replaced (← links)
- 05000293/LER-1988-006, :on 880203,trip Signal Generated Unexpectedly from ATWS Div 2 Circuitry Resulting in Automatic Trip of Recirculation Sys Pumps & Subsequent Reactor Protection Sys Scram Signal.Cause Not Conclusively Determined (← links)
- 05000425/LER-1989-004-01, :on 890309,during Check Valve Testing, Discovered That RCS Leakage Exceeded Tech Spec Limit.Caused by Excessive Wear on Internal Check Valve Components.Valve Repaired & Internal Components Replaced (← links)
- 05000338/LER-1989-016-01, :on 890826,recirculation Spray HX Svc Water a Supply Header Isolation Motor Operated Valves Deenergized in Closed Position.Caused by Miscommunication Between Shift Supervisor & Other Personnel.Power Reinstated (← links)
- 05000318/LER-1989-006, :on 890417 & 19,discovered Tech Spec Requirement for Containment Closure During Core Alterations Not Satisfied.Caused by Inadequate Administrative Control. Corrective Actions Listed (← links)
- 05000298/LER-1989-008, :Insufficient Operator Guidance to Assure Adequate Svc Water Flow During Design Basis LOCA Identified During NRC Insp on 870511-0619.Caused by Procedural Deficiency.Procedures Revised (← links)
- 05000328/LER-1989-005-01, :on 890415,16 & 19,three Unit 2 Reactor Trips Occurred Due to Lo Lo Steam Generator Level During Startup. Cause for 890419 Trip Was Operating Loops Bypass Valves in Manual (← links)
- 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 (← links)
- 05000382/LER-1989-013, :on 890719,rapidly Decreasing Level Observed in Steam Generator 1 Resulting in Manual Reactor Trip.Caused by Circuit Failure in Position Control Circuitry.Circuit Card W/Failed Component Replaced & Sys Restored (← links)
- 05000369/LER-1989-013-02, :on 890630,flow Indication for Steam Generator C Failed High & on 890705,alarm for 3% Deviation Received During Power Escalation.Caused by Inappropriate Action & Procedure Deficiency.Training Implemented (← links)
- 05000412/LER-1989-004, :on 890320,seat Leakage Prompted Closure of Block Valve for PORV Resulting in No Overpressure Protection Sys Operation.Caused by Compound Acceptance Criteria in Surveillance Test.Test Revised (← links)
- 05000424/LER-1987-068, :on 871117,control Room Ventilation Isolation Occurred.Caused by Faulty Monitor Sensing Tube & Faulty Computer Software Design.Tube Replaced & Software Will Be Changed (← links)
- 05000321/LER-1989-002-01, :on 890205,4 H Grab Sampling & Analyses Not Performed,Per Tech Spec 3.6.G.2.A When Particulate Fission Product Monitor Inoperable.Caused by Personnel Error. Procedures Upgraded & Personnel Counseled (← links)
- 05000412/LER-1997-004-01, :on 970911,discovered That Four Containment Isolation Valves Were Not Tested IAW Ts.Caused by Inadequate Mgt Change.Will Revise Licensing Requirements Manual Table 5.1-1 & UFSAR Table 6.2-60 (← links)
- 05000321/LER-1986-038, :on 860913,RCIC Inboard Primary Containment Isolation Sys Valve Failed to Close During Reactor Cooldown. Caused by Thermally Induced Binding.Valve Verified Operable When Manually Assisted from Backseat (← links)
- 05000328/LER-1986-004-04, :on 860922,incorrect Data Used in Executing Incore Computer Program.Caused by Personnel Error.Incore Corrected & Verified.Previous Informal Written Procedure for Installing Data & Software Formalized (← links)
- 05000280/LER-1986-030, :on 861029,number of Inoperable Control Room Chillers Exceeded Requirements of Tech Spec 3.14.Caused by Reduced Water Flow Due to Marine Growth in Svc Water Line. Growth Removed & Chillers Returned to Svc (← links)
- 05000483/LER-1987-006, :on 870413,util Received Ltr from Westinghouse Re Inaccuracy in Tech Specs for Response Times Associated W/ Safety Injection Signal.Tech Spec Change Requested & Granted on 870504 (← links)
- 05000370/LER-1987-005-03, :on 870318,both Channels of Control Rod Indication Sys Became Inoperable During Maint Activity. Cause Attributed to Electronics Failure of Unknown Nature. Addl Info Needed Before Conclusion Reached (← links)
- 05000245/LER-1997-037-01, :on 970930,house Heating Boiler Ash Was Found to Be Slightly Contaminated.Caused by Unmonitored Release Path for Airborne Effluents IAW Requirements of TS 4.8.D.4. Restricted Boiler Use Until SE Was Performed (← links)
- 05000302/LER-1986-009, :on 860629,reactor Containment Isolation Design Basis Violated.Caused by Failure to Update Procedure OP-417 W/Necessary Administrative controls.Short-term Instruction 86-35 Issued on 860630 (← links)
- 05000334/LER-1997-031, :on 970919,identified That Routine Testing of Surveillance Procedures for ESF Were Inadequate.Caused by Inadequate Development of Procedures.Will Develop Addl Routine Surveillance Testing (← links)
- 05000213/LER-1986-021, :on 860524,one of Four ex-core Channels Failed to Meet Acceptance Criteria for Dropped Rod Load Runback Setpoint.Caused by Setpoint Drift.Setpoint Recalibr & Weekly Surveillances Established (← links)
- 05000413/LER-1987-002, :on 870111,unit Shutdown Commenced When Unidentified Reactor Coolant Leakage Greater than 1 Gpm Determined.Caused by Leak in Loop C RTD Manifold Tubing. Leak Repaired & Unit Returned to Power (← links)
- 05000327/LER-1986-043, :on 860910,Surveillance Instruction (SI)-156 for Surveillance Requirement 4.6.1.2 Did Not Provide for Venting of Three Containment Isolation Valves During Testing.Caused by Inadequate Review (← links)
- 05000269/LER-1986-012-04, :on 861015,water Supply Available to Standby Shutdown Facility (Ssf) Insufficient to Enable Ssf to Accomplish Function.Caused by Failure to Define Design Bases of Ssf.Listed Plant Mods Completed (← links)
- 05000483/LER-1987-002, :on 870403,plant Shut Down Due to Inoperability of Diesel Generator a on 870401 & Fuel Oil Leak on Injector Pump Housing on 870402.Caused by Faulty Control Card plug-in Connections & Crack in Valve (← links)
- 05000336/LER-1986-008, :on 860920,6 of 16 Valves Failed Main Steam Safety Valves Simmer Test Used to Verify Pressure Setpoint. Cause of Setpoint Drift Unknown.Increased Accuracy Pressure Gauges Used to Reduce Test Error (← links)
- 05000327/LER-1986-054, :on 861201,discovered That Discrepancy Existed Between Data Contained on Drawings for 125-volt Dc Vital Battery Sys & Data Used in Surveillance Instruction (SI)- 105.Instruction Will Be Revised (← links)
- 05000269/LER-1986-015-04, :on 861120,Keowee Hydro Relay 94 T/K Actuated During Mod Work,Causing Lockout of Transformer,Trip of Circuit Breakers & Loss of Overhead Emergency Power.Caused by Mechanical Vibration Due to Drilling (← links)
- 05000387/LER-1986-039, :on 861202,Limiting Condition for Operation 3.0.3 Entered During Suppression Pool Nitrogen Addition & Purging.Caused by Leakage in Containment Radiation Monitoring Sys.Sys Isolated (← links)
- 05000370/LER-1986-010-03, :on 860623,refueling Water Storage Tank Declared Inoperable Per Tech Spec 3.5.3.d Due to High Temp. Caused by Mgt Deficiency.Procedure Will Be Written for Calibr of Operator Aid Computer Point for Temp (← links)
- 05000249/LER-1986-006-08, :on 860529,Group II & III Primary Containment Isolation Occurred While Work Performed on Analog Trip Sys. Caused by Personnel Inadvertently Grounding Live Wire. Personnel Reminded to Pay Attention to Details (← links)
- 05000423/LER-1986-040, :on 860721,Train B Control Bldg Isolation Signals Generated Due to Failures of Control Bldg Inlet Ventilation Chlorine Detectors.Caused by Presence of Contaminants on Probes.Detectors Relocated (← links)
- 05000414/LER-1986-032, :on 860709,main Feedwater Isolation Occurred Due to hi-hi Level in Steam Generator C.Caused by Leaking Control Valves.Procedures Revised to Isolate Control Valves When Providing Flow W/Control Bypass Valves (← links)
- 05000364/LER-1987-001-01, :on 870228,reactor Tripped.Caused by Spike on Channel 1 of Over temp-delta-t While Channel 3 in Test. Investigation Into Cause of 7300 Series lead-lag Cards Continuing (← links)
- 05000354/LER-1986-002-01, :on 860413,inadvertent Channel B LOCA Signal Occurred During Performance of Channel Functional Test Procedure IC-FT.BB-004(Q).Caused by Procedural Inadequacy. Technician Instructed to Check Battery During Testing (← links)
- 05000440/LER-1986-054, :on 860902,07,11,13,15 & 19,RCIC Isolations Occurred.Caused by Instrument Isolation Valve Failure & Impulse Line Slope Problems,Leak Detection Response Time & Personnel Error.Valves Repaired or Replaced (← links)
- 05000331/LER-1986-017, :on 860613,at Approx 5% Power,Manual Scram Initiated When Reactor Water Level Approached Low Level Scram Setpoint.Caused by Faulty Position Controllers. Positioners Replaced & Cleaned (← links)
- 05000344/LER-1986-004, :on 860411,merchant Ship Lost Steering & Ran Aground Outside Intake Structure of Facility.Grounding Damaged Plant Outfall Pipe.Replacement Section of Outfall Pipe Being Mfg (← links)
- 05000423/LER-1986-017, :on 860213,while Operating at 15% Power,W/Main Turbine Generator off-line,plant Received Reactor Trip. Caused by General Warning Alarm Present in Both Trains of Solid State Protection Sys (← links)
- 05000334/LER-1997-018, :on 970705,potential for Spurious Seismically Induced FPS Sys Activation Affecting EDG Was Noted.Caused by Deficiency in Original Design.Established Fire Watch (← links)
- 05000219/LER-1996-011, :on 961026,discovered Primary Leak Rate Above TS Limit.Caused by Improper Valve Reassembly on V-26-5 During 16R Outage.Replaced Valve V-26-5 O Rings,Reassembled Subject Valve & Revised Procedures (← links)
- 05000302/LER-1996-001, :on 960110,personnel Error Results in Operation Outside 10CFR50,App R Design Basis.Brought Affected Circuits Back Into Compliance W/App R & Completed Field Validation of Selected App R Drawings (← links)
- 05000370/LER-1986-002-02, :on 860123,reactor Trip Occurred as Result of intermediate-range (IR) high-flux Reactor Trip Signal.Caused by Defective Procedure.Ir Detectors Recalibr & Trip Reset Point Changed to 15% Power.Procedures Revised (← links)
- 05000334/LER-1997-006, :on 970322,failure to Test Solid State Protection Sys Logic IAW TS Caused by Procedural Deficiencies.Performed Surveillance Testing on 970324 (← links)
- 05000529/LER-1985-004-01, :on 851218,spurious Automatic ESF Actuation Initiated Due to Noise Spiking on Control Room Ventilation Intake Noble Gas Radiation Monitor.Caused by Noise from Unused Pair of Contacts on Radiation Monitor (← links)