Pages that link to "NRC Form 38SA"

The following pages link to NRC Form 38SA:

Displayed 24 items.

• 05000409/LER-1986-001, :on 860106,during Performance of Type C Leakage Test on Reactor Bldg MSIV & Bypass,Leakage Measured Above Acceptance Criteria.Caused by Valve Plug Hitting One Side of Seat More than Other.New Seat Installed ‎ (← links)
• 05000461/LER-1997-001, :on 970103,nuclear Fuel Supplier Failed to Analyze Turbine Pressure Regulator Downscale Failure Event in off-rated Condition Per 10CFR21.21.Caused by Error in Nuclear Fuel Supplier.Mcpr Will Be Implemented ‎ (← links)
• 05000354/LER-1995-028, :on 951030,failed to Exert Best Efforts to Restore Liquid Effluent Radiation Monitoring Sys to Operable Status.Caused by Low Mgt Priority Given.Improved Related Processes ‎ (← links)
• 05000370/LER-1984-008, :on 840223,technician Removed Thermometer from Speed Changer on Centrifugal Charging Pump 2B for Calibr, Resulting in Loss of Speed Changer Lubrication.Caused by Thermometer Installed in Wrong Location ‎ (← links)
• 05000331/LER-1994-001-01, :on 940107,determined That Test of Average Power Range Monitor High Flux Scram Trip Setpoint Inadequate.Caused by Unawareness of Test Requirement.Test Verified Clamping Function Set Properly ‎ (← links)
• 05000272/LER-1996-002, :on 960110,evaluation Determined That Motor Operated Gate Valves Susceptible to Pressure Locking & Thermal Binding.Caused by Inability to Meet GL 95-07 Criteria.Test Procedure Changed ‎ (← links)
• 05000255/LER-1995-005-01, :on 950721,received Two Inadvertent SISs While Performing TS Test RO-12.Caused by Two Wires Taped Together After Being Removed from Terminal in Attempt to Isolate Sis. Procedure RO-12 Revised ‎ (← links)
• 05000255/LER-1992-038, :on 920825,reactor Tripped,Resulting from Loss of Preferred Ac Bus Y-20,coincident W/Blown Fuse in Second Channel of Rps.Caused by Failure of Inverter ED-07.All Fuses Checked & Plant Drawings/Vendor Manuals Updated ‎ (← links)
• 05000410/LER-1988-014, :on 880313,reactor Scram & ESF Actuations Occurred.Caused by Equipment Failure Due to Design Deficiency.Transmitter Replaced W/Upgraded Model & Temporary Mod Performed to Bypass Logic for Valves ‎ (← 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)
• 05000316/LER-1994-001-01, :on 940221,reactor Tripped on low-low Level in Steam Generator 4 as Result of Inadequate Valve Actuator/ Stroke Adjustment Procedure.Procedures Revised ‎ (← links)
• 05000315/LER-1987-010, :on 870605,inadvertent Opening of Reactor Trip Breakers Occurred Due to High Turbine Exhaust Pressure. Caused by Excessive Leakage of Low Pressure Steam Supply Isolation Valve AMO-12.Procedures Implemented ‎ (← links)
• 05000529/LER-1988-002, :on 880118,ASME Section XI Surveillance Test Interval Exceeded.Caused by Inadequate Administrative Controls Established for Tracking of Partially Completed Surveillance Tests.Controls Established ‎ (← links)
• 05000528/LER-1987-011, :on 870331,while in Mode 1,fire Watch Round Not Performed Per Tech Spec 3.7.12.Caused by Cognitive Personnel Error.Fire Watch Patrolman Counseled on Safety Warnings & Scheduled for Addl Training ‎ (← links)
• 05000397/LER-1989-025, :on 890617 & 18,three Separate But Related Events Occurred Which Caused ESF Isolations & Actuations During Excess Flow Check Valve Testing.Caused by Inadequate Procedure.Procedure Modified ‎ (← 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-1989-023, :on 890531,ESF Isolations & Actuations Occurred Due to Loss of Reactor Protection Sys Bus During Testing. Caused by Personnel Error.Logic Sys Functional Test Procedure Revised.Test Engineer Counseled ‎ (← links)
• 05000397/LER-1989-021, :on 890527,electrical Protection Assembly Breaker Tripped Causing Loss of Power to Reactor Protection Sys Bus B.Cause Unknown.Upgraded Breaker Equipment Will Be Installed ‎ (← links)
• 05000397/LER-1989-003, :on 890209,control Room Emergency Filtration Sys Adsorber Charcoal Sample Not Taken After 720 H of Operation.Caused by Misinterpretation of Tech Specs.Charcoal Sample Analyzed & Procedure Revised ‎ (← links)
• 05000397/LER-1988-017, :on 880615,problems W/Limitorque Models SMB-000 & SMB-00 Discovered W/Potential Defective Switches.Caused by Design Problem.Investigation & Evaluation of Switch Problems Immediately Initiated.Part 21 Related ‎ (← links)
• 05000397/LER-1987-030, :on 871106,upgraded Plant Tech Spec Fire Wall Not Constructed to Qualify as 3 H Fire Barrier & Wall Penetration Not Sealed.Cause Unknown.Engineering Evaluation of Wall & Penetration Will Be Conducted ‎ (← links)
• 05000244/LER-1992-005, :on 920420,determined That 242 Tubes in a SG & 216 Tubes in B SG Required Corrective Action Due to Tube Degradation.Affected Tubes Either Sleeved or Plugged.W/ ‎ (← links)
• 05000335/LER-1996-016, :on 961122,insufficient Testing & Maint Were Noted on 125 Vdc Bus cross-tie Breakers.Caused by Lack of Effective Maint & Testing.All Four 125 Vdc cross-tie Breakers Will Be Refurbished ‎ (← links)
• 05000335/LER-1996-008-01, :on 960608,inadvertent Actuation of Safety Injection Actuation Signal & Containment Isolation Actuation Signal Occurred.Caused by Loss of Power Supply.Reviewed Power Supply Design & Conducted Visual Insp ‎ (← links)