Pages that link to "NRC Form 3eSA"

The following pages link to NRC Form 3eSA:

Displayed 22 items.

• 05000301/LER-1998-003-01, :on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement ‎ (← 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)
• 05000413/LER-1986-042, :on 860808,reactor Tripped During Breaker Testing.Caused by Personnel Error.Supervisors & Technicians Will Be Cautioned Re Importance of Attention to Detail Concerning Testing ‎ (← links)
• 05000369/LER-1986-020-03, :on 861028,charging Line Outside Containment Isolation Valves Declared Inoperable Due to Incorrect Torque Settings on Rotork Motor Operators.Caused by Mfg Deficiency. Procedures Revised & Operators Evaluated ‎ (← links)
• 05000237/LER-1986-024-04, :on 861117,main Chimney Separate Particulate Iodine & Noble Gas Sampler (Sping) Experienced Loss of Flow Condition.Caused by Water in Filters of Sping.Work Request D59639 Initiated ‎ (← links)
• 05000237/LER-1986-013-05, :on 860524,reactor Operator Observed That Reactor Vessel Not Vented at Less than 149 F,Violating Tech Spec 3.6.B.1.Caused by Personnel Error.Tech Spec Change Initiated to Change Min Temp to 100 F ‎ (← links)
• 05000237/LER-1986-011-05, :on 860520 Full Scram Occurred Twice Due to Low Reactor Water Level.Caused by Reactor Feedwater Regulating Valve B Booster Relay Failure & Personnel Error.Relay Replaced & Violation Rept Completed ‎ (← links)
• 05000289/LER-1999-002, :on 990212,potential Failure of Multiple Containment Monitoring Sys CIV (CM-V-1,2,3 & 4) Was Noted. Caused by Inappropriate Use of Vendor Info.Personnel Will Be Trained on Mgt Expectations.With ‎ (← links)
• 05000260/LER-1986-005-02, :on 860403,primary Containment Isolation Occurred.Caused by Insecure Jumper Connections Across Relay & Hampered Relay Access During Surveillance Instruction. Interim Measure Eliminates Jumper Placement ‎ (← links)
• 05000324/LER-1986-001, :on 860107,discovered That 10 of 11 Safety Relief Valves Tested Exhibited Symptoms of higher-than- Allowed Setpoint Drift.Caused by Pilot disc-to-seat Sticking & High Friction.Maint Program Revised ‎ (← links)
• 05000219/LER-1986-027, :on 860930,containment Isolated & Standby Gas Treatment Sys Initiated When Radiation Monitor Power Supply Inadvertently Grounded During Surveillance.Caused by Personnel Error.Power Supply Replaced ‎ (← links)
• 05000423/LER-1999-007-01, :on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With ‎ (← links)
• 05000369/LER-1986-006-01, :on 860311,failure to Fully Test Nuclear Svc Water Sys Until 860130 Noted.Caused by Mgt Deficiency. Periodic Flow Balance Test Procedures Written ‎ (← links)
• 05000528/LER-1985-016, :from 850323-0415,hourly Fire Patrols Not Conducted Per Tech Spec 3.7.12.Caused by Personnel Disregard for Responsibilities.Personnel Fired &/Or Replaced W/Station Staff & Logs & Monitoring Improved ‎ (← links)
• 05000260/LER-1984-007-02, :on 840922,excessive Leakage Occurred on Main Steam Line Isolation Valves B & C.Cause Not Stated.Valve Poppet Will Be Machined & Valve Seat Lapped to Ensure Proper Seating & Acceptable Leakage ‎ (← links)
• 05000413/LER-1984-024-02, :on 841124,auxiliary Feedwater Pumps 1A & 1B Started Due to lo-lo Level in Steam Generator 1C.Caused by Personnel Deviating from Procedure.Steam Generator Level Restored & Alarm Cleared ‎ (← links)
• 05000446/LER-1996-002, :on 960126,noted That TS Surveillance for Turbine Overspeed Missed Due to Oversight in Rescheduling Required Surveillance by Cognizant Personnel.Test Completed on 960126 & Event Reviewed as Lesson Learned ‎ (← links)
• 05000219/LER-1985-006, :on 850224,during Startup,Automatic Scram Occurred Due to Low Reactor Water Level.Caused by Operator Error.Drywell Access Procedure Will Be Revised to Caution Operators on Sensitivity of Level & Pressure ‎ (← links)
• 05000456/LER-1995-013-04, :on 951012,fire Protection App R Design Discrepancies Occurred Due to Inadequate Evaluations During Preparation of Original Analysis.Maintained Hourly Fire Watches for All Fire Zones ‎ (← links)
• 05000293/LER-1984-008, :on 840521,HFA Relay in Reactor Protection Sys Found Hot & Smoking.Caused by Generic Hfa Relay Problem. Relay de-energized & Replaced W/Ge Century Series Relay ‎ (← links)
• 05000250/LER-1984-007, :on 840216,while at Steady Operation,Dual Unit Trip Occurred from 100% Power,Resulting in Loss of 4,160- Volt Buses 3C & 4C.Caused by Bolt in Breaker 4AC01 Cubicle Door Travel.Doors Checked for Proper Clearance ‎ (← links)
• 05000321/LER-2016-003, Regarding Reactor Coolant System Piping Has Unacceptable Weld Indication Discovered During Refueling Outage ‎ (← links)