Pages that link to "NRC Form 3BSA"
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The following pages link to NRC Form 3BSA:
Displayed 43 items.
- 05000483/LER-1989-011-01, :on 890905,ESF Containment Purge,Control Room Ventilation & Fuel Bldg Ventilation Isolations Received. Caused by Failed 15-volt Dc Power Supply in Train B ESF Cabinet.Power Supply Replaced & Tested (← links)
- 05000369/LER-1989-021-01, :on 890623,discovered That Design of Sys Did Not Take Into Account temp-induced Difference in Pressure Gradients Inside & Outside Annulus.Caused by Design Deficiency.Sys Setpoint Mods Implemented (← links)
- 05000325/LER-1989-017, :on 890624,HPCI Sys,Steam Line Break Delta Pressure High Signal,Channel A,Isolation Occurred.Probably Caused by Spurious Trip of Redundant Div 1 ECCS Trip Unit. Unit Replacd & Original Unit Bench Tested (← links)
- 05000413/LER-1989-015-01, :on 890616,emergency Low Level Signal for Nuclear Svc Water Sys Pit a Initiated Automatic Swap to Standby Nuclear Svc Water Pond.Caused by Blown Fuse AA-2. Fuse Replaced W/Littelfuse Type Flq Fuse (← links)
- 05000346/LER-1989-006, :on 890614,determined That Tech Spec Surveillance Requirement 4.7.8.1.2.c Had Not Been Completed for Two Gamma Metrics Fission Detectors.Precautionary Step Added to Procedure DB-PF-00100 (← links)
- 05000369/LER-1989-016-01, :on 890714,loss of Flow Alarm for Unit Vent Radiation Monitor Received in Control Room & Radioactive Gas Sample Not Taken Every 12 H.Caused by Failure to Follow Procedures.Personnel Instructed (← links)
- 05000338/LER-1989-009-01, :on 890515,main Steam Line Code Safety Valves as Found Set Pressures Found to Be Outside Lift Set Pressure Tolerance.Cause of Event Not Determined.Valves Refurbished & Retested by Wyle Labs (← links)
- 05000425/LER-1989-008-01, :on 890319,improper Control of Steam Generator Water Level Led to Feedwater Isolation.Caused by Operator Not Requesting Relief.Operator Counseled Re Importance of Maintaining Watch on Operations in Progress (← links)
- 05000364/LER-1987-004-01, :on 871113,steam Generator Tube Degradation Observed.Investigations & Evaluations Performed Identified Four Areas Where Tube Degradation Observed.Tubes Have Been Plugged as Required & Listed Actions Taken (← links)
- 05000483/LER-1987-017-01, :on 870629 & 0715,safety Injection Pumps to Refueling Water Storage Sys Hand Control Valve Momentarily Shut.Caused by Personnel Error.Procedure Revised (← links)
- 05000440/LER-1987-063, :on 870906,RCIC Sys Isolation Occurred.Cause Undetermined.Engineering Design Change Initiated to Provide Indication of RCIC Trip Delay Status When Taking RCIC Ld Isolation Channels from Bypass to Normal (← links)
- 05000482/LER-1989-003, :on 890131,discovered That Several Lugs Improperly Crimped Per Current Stds,Resulting in Degradation of Fire Protection Sys.Caused by No Specific Unique Util Imposed Crimping Stds for Panels (← links)
- 05000366/LER-1986-031-02, :on 860927,full Reactor Protection Sys Actuations Occurred.Caused by Spurious Electrical Noise Signals During Outage Maint/Mod Activities.Logic Actuation Signals Reset (← links)
- 05000366/LER-1986-026-01, :on 860919,reactor Protection Sys Actuation Occurred Initiating one-half Primary Containment Isolation Sys Valve Group 2 & RHR Shutdown Cooling Sys Isolation. Caused by False Signals (← links)
- 05000366/LER-1986-025-01, :on 861023,personnel Determined That Certain Instruments Listed in Tech Specs Not Tested Periodically to Assure Appropriate Sys Actuation.Caused by Personnel Error. Personnel Counseled (← links)
- 05000213/LER-1986-033, :on 860715,w/plant in Mode 4,RCS Low Temp Overpressurization Protection (Ltod) Sys Interlock Would Not Permit Opening One Train of LTOP Isolation Valves.Tech Spec Temp Limits Reduced (← links)
- 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 (← links)
- 05000482/LER-1987-005, :on 870117,ESF Actuations Occurred During Turbine Testing.Caused by High Vibrations Which Required Rapid Reduction in Speed of Main Turbine.Precaution Added to Sys Procedure (← links)
- 05000413/LER-1986-046, :on 860816,steam Generators Reactor Trip Alarm Occurred & motor-driven Auxiliary Feedwater Pump B Started Automatically.Caused by lo-lo Level in Steam Generator D. Pump B auto-start Logic Secured (← links)
- 05000331/LER-1987-002, :on 870214,automatic Isolation of Control Bldg Ventilation Sys & Initiation of Standby Filter B Occurred. Caused by Incorrect Setting of Downscale Trip Point of Radiation Monitor.Trip Point Lowered (← links)
- 05000341/LER-1987-008, :on 870301,power to Portions of Turbine Control Circuitry Lost Resulting in ESF Valve Isolation,Reactor Protection Sys Actuation & Reactor Scram.Caused by Personnel Error.Alarm Response Procedures Revised (← links)
- 05000369/LER-1986-001, :on 860105,during Mode 1,chemical & Vol Control Sys Pump 1B Inoperable More than 72 H.Caused by Delay in Pump Repair.Repairs Completed.Memo to Maint Personnel Re Matl Handling Will Be Written (← links)
- 05000237/LER-1985-024-02, :on 850505,APRM Channel 1 Inoperable During Gain Change.Caused by Personnel Error.Mode Switch Placed in Run Position to Make APRM Channel Operable (← links)
- 05000271/LER-1984-019, :on 840615,indication Lost from Rosemount Level Transmitter 1152T0280.Caused by Loose Circuit Board Mounting Screws.All Other Transmitters Checked & Loose Screws Retightened.Proper Calibr Verified (← links)
- 05000338/LER-1984-022, :on 841127,fire Protection Sys Main Header Ruptured,Causing Sys to Be Inoperable.Caused by Pipe Crack Probably Occurring During Installation.Ruptured Section of Pipe Replaced (← links)
- 05000237/LER-1984-025, :on 841220,main Feed Breaker 152-2430 on Bus 24-1 Failed to Trip Open.Caused by Dirty Auxiliary Breaker Contacts.Contact Cleaned,Tested & Returned to Svc (← links)
- 05000387/LER-1984-015, :on 840121,background Radiation Surrounding Svc Water Radiation Monitor Reached Levels That Exceeded Tech Spec Limits.Cause Not Stated.Calibr Procedure Revised (← links)
- 05000369/LER-1984-003-01, :on 840220,during Normal Rotation of Equipment, Centrifugal Charging Pump 1A Would Not Start.Pump Breaker Not in Fully Connect Position Due to Personnel Error in Restoring Breaker After Routine Oil Sample (← links)
- 05000413/LER-1990-016, :on 900305,Tech Spec Sample of Refueling Water Storage Tank Missed.Caused by Inappropriate Action Due to Failure to Recognize Need to Ensure Operable Borated Water Source.Chemistry Mgt Procedure Revised (← links)
- 05000327/LER-1989-026-01, :on 891107,Limiting Condition for Operation 3.0.3 Entered as Result of More than One Rod Position Indicator (RPI) Per Bank Being Inoperable.Caused by Lack of Preventive Maint.Rpis Adjusted (← links)
- 05000412/LER-1989-027, :on 891106,Train a Svc Water Pump Seal Water Supply Automatically Transferred to Backup Supply Due to Low Pressure.Caused by Seal Water Normal Supply Inadvertently Isolating While de-energizing.Manual Revised (← links)
- 05000296/LER-1996-006-03, :on 961106,loss of ECCS Div 1 Instrumentation Rendered ECCS Equipment Inoperable.Caused by Cleared Fuse in ECCS Div.Fuse Replaced & Addl Testing to Challenge Replacement Fuse Performed (← links)
- 05000250/LER-1988-032, :on 881202,personnel Error Resulted in Loss of Power to Vital Instrument Bus & Isolation of Stated Ventilation Sys.Operator Counseled.Spare Inverter Relabeled as Spare & Procedures Revised (← links)
- 05000250/LER-1988-014, :on 880714,RCS Leakage Surveillance Not Performed within Required Interval Due to Personnel Error. Note Placed in Night Book Stressing Need to Meet 18-30 H Tech Specs Requirements (← links)
- 05000316/LER-1990-006, :on 900625,failure of Facility Main Steam Safety Valves to Meet Tech Spec Lift Setpoint Requirements. Caused by Incompatibility of Required Setpoint Tolerance & Repeatability.Tech Spec Change Requested (← links)
- 05000315/LER-1988-007-01, :on 880908,flow Passage Insp of Ice Condenser Revealed Frost & Ice Buildup.Caused by Sublimation of Ice or High Humidity in Containment Air.Flow Passages Manually Cleaned to Remove Accessible Frost (← links)
- 05000316/LER-1987-007-01, :on 870714,ESF Reactor Trip Occurred Due to Undervoltage of Reactor Coolant Buses.Caused by Failure of Main Generator Voltage Control Sys.Failed & Suspected Components of Sys Replaced (← links)
- 05000528/LER-1990-001-01, :on 900209,fuel Bldg Exhaust Ventilation high- Range Radiation Monitor Energized,Causing low-range Radiation Monitor to Spike & ESF Actuation.Caused by Noise in Circuit of Monitors.Channel B Bypassed (← links)
- 05000397/LER-1989-024, :on 890614,secondary Containment Bypass Leakage Found Greater than Allowed by Design Basis.Caused by Equipment Design Deficiency.Check Valves in Common Discharge Line of CRD Pump Installed to Prevent Leakage (← links)
- 05000397/LER-1989-015, :on 890512,three-quarter-inch High Point Vent Line Failed During Performance of HPCS Sys Operability Procedure.Caused by Reverse Bending Fatigue Caused by Vibration.Design Change Implemented (← links)
- 05000389/LER-1997-004-02, :on 970611,discovered Incorrect Original Cable Tray Fire Stop Assembly Installation Was Outside App R Design Basis.Caused by Personnel Error.Hourly Fire Watch Patrols Will Be Posted (← links)
- 05000335/LER-1988-008-02, :on 880920,power Supply Wire Lead Inadvertently Lifted When Personnel Removed Another Lead on Same Terminal Lug Connection Causing Reactor Trip.Caused by Personnel Error.Unit Stabilized in Hot Standby (← links)
- 05000389/LER-1988-001-02, :on 880201,safety Injection Tank 2B2 Declared Out of Svc & Relief Valve on Fill & Drain Line to Safety Injection Tank 2A2 Lifted & Failed to Reseat.Caused by Failure of Valves.Work Repair Orders Issued (← links)