Pages that link to "NRC Form 396A"
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The following pages link to NRC Form 396A:
Displayed 22 items.
- ML22305A692 (← links)
- ML23075A331 (← links)
- 05000424/LER-1989-016, :on 890708,manual Reactor Trip Occurred Due to Failure of Main Feedwater Isolation Valve.On 890803,loop 4 Main Feedwater Isolation Valve Spuriously Closed Resulting in Reactor Trip.Caused by Reduced Flow (← links)
- 05000412/LER-1989-017, :on 890517,abnormal Reactor Vessel Level Indication Sys Indications Experienced on wide-range Channels.Caused by Inadequate Procedures,Unit Differences & Personnel Error.Qc Coverage Increased (← links)
- 05000338/LER-1999-006-01, :on 990904,potential for Safegurads Exhaust Flow to Bypass Charcoal Filter,Was Discovered.Caused by Degraded Damper.Plant Issue Rept Submitted for B Train of Savs Flow Rate.With (← links)
- 05000346/LER-1987-004, :on 870112,auxiliary Feedwater Train 1 Declared Inoperable.Caused by Failure to Evaluate Effects of Main Steam Sys Chemistry on Installed Diaphragms.Three Layer Pressure Switch Diaphragm Matl Replaced (← links)
- 05000245/LER-1996-035, :on 960506,discovered Leaking gamma-radiography Access Port Plug in LPCI Sys Piping.Caused by Access Port Plug Not Being Included in Insp Program.Two Degraded Gamma Plugs Will Be Repaired by Weld Overlay (← links)
- 05000461/LER-1998-037, :on 981215,identified That SR 3.3.3.1.2,which Requires Channel Calibr of Drywell & Primary Containment Hydrogen & Oxygen Analyzers Not Properly Implemented.Caused by Lack of Info Validation & Verification.Procedure Revised (← links)
- 05000289/LER-1997-008, :on 970621,power to Control Rod Drive Mechanisms Was Lost & Reactor Tripped.Caused by Long Trip Insertion Times at Tmi.Rods Were Trip Tested Per Surveillance Procedure 1303.11.1 (← links)
- 05000259/LER-1986-009, :on 860226,inadvertent Secondary Containment Occurred Due to Instrument Mechanics Placing Jumper Across Terminal Points CC-38 & CC-40 to Bypass Relay 16A-K61A. Caused by Personnel Error.Personnel Cautioned (← links)
- 05000213/LER-1996-024, :on 960901,B RHR Pump Was Found Inoperable in Mode 5.Caused by Original Mfg Defects Along W/Marginal Pump Design.Replaced Pump Rotating Element (← links)
- 05000382/LER-1997-005, :on 890715,failure to Perform Coolant Low Flow Trip Operating Bypass Surveillance Occurred.Caused by Failure to Implement Procedural Controls to Test Reactor Coolant Low Flow Bypass.Event Will Be Reviewed (← links)
- 05000369/LER-1996-004, :on 961010,incorrectly Calibrated Rcl Loss of Flow Reactor Trip Bistables Identified.Caused by Procedural/ Technical Inaccuracy.All Affected Procedures Were Changed & Instruments Calibrated within TS Limits (← links)
- 05000285/LER-1996-013, :on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted (← links)
- 05000302/LER-1996-020, :on 960910,identified Unreviewed Safety Question Re Diesel Generator Loading.Caused by Personnel Error in Interpreting Regulatory Requirements.Imposed Startup Restraint (← links)
- 05000325/LER-1995-015, :on 950713,automatic Reactor Shutdown Occurred Due to electro-hydraulic Control Pressure Regulator Malfunction.Replaced Four Electronic Circuit Boards Comprising a EHC Pressure Regulator (← links)
- ML20077H463 (← links)
- 05000298/LER-1993-034, :on 931028,identified That Fire Brigade Members from Support Groups Had Not Received Quarterly Fire Brigade Training Due to Misunderstanding.Quarterly Fire Brigade Training Provided to Appropriate Personnel (← links)
- 05000412/LER-1993-002, :on 930130,bistaples for Loop a Channel II Ms Pressure in Tripped Condition for Transmitter Replacement. Caused by Comparator Card Power Supply Failure.Associated Valves Actuated to Design Positions (← links)
- 05000281/LER-1988-010-02, :on 880516,reactor Trip Occurred as Result of Steam Generator lo-lo Level.Caused by Rapid Closure of Turbine Governor Valves.Recorder Will Be Used to Monitor Electrohydraulic Control Sys During Startup (← links)
- 05000529/LER-2012-002, Regarding Condition Prohibited by Technical Specification Due to Low Pressure Safety Injection System Drain Pipe Leak (← links)
- NUREG-1478, DFC, Rev. 3, Operator Licensing Examiner Standards for Research and Test Reactors Draft Report for Comment (← links)