Pages that link to "NRCOC"

The following pages link to NRCOC:

Displayed 49 items.

• 05000251/LER-1985-007, :on 850218,containment Spray Pump Power 4A Supply Breaker Inoperable.Caused by Closing Spring Charging Motor Being Off During Test,Resulting in Closing Springs Discharging.Charging Power Restored ‎ (← links)
• 05000251/LER-1984-023-01, :on 841016,reactor Trip Occurred.Caused by Detector on Nis N-32 Channel Failing & Generating High Level Signal.Nis Channel N-32 Taken Out of Svc & Detector Replaced ‎ (← links)
• 05000251/LER-1984-022-01, :on 841009,during Heat Up from Cold to Hot Shutdown,Reactor Trip Occurred.Caused by Blown Fuse Supplying Instrument Power to Panel 4P07,which Caused Instrumentation Bistables to Deenergize ‎ (← links)
• 05000250/LER-1984-026, :on 841009,turbine Runback to 70% Reactor Power Occurred.Possibly Caused by Inadvertent Transfer of Power for Panel 3P07 from Normal Inverter 3A Spare Inverter As. Personnel Trained ‎ (← links)
• 05000250/LER-1984-023, :on 840822,while at 100% Power,Turbine Runback to 45% Power Occurred.Caused by Dropped Control Rod in Shutdown Bank a & Blown Stationary Gripper Fuse.Loose Cable Connector Replaced ‎ (← links)
• 05000251/LER-1984-016-01, :on 840624,auxiliary Feedwater Sys Manually Actuated.Caused by Incorrect Hotwell Reject Regulator LCV-1500 Setup.Regulator Setup Corrected ‎ (← links)
• 05000250/LER-1984-021, :on 840714,reactor Tripped from Subcritical Condition.Caused by Power Interruption of Source Range Nuclear Instrumentation Control Power.Personnel Counseled.W/ ‎ (← links)
• 05000251/LER-1984-009-01, :on 840527,28 & 30,low Discharge Flow Observed from Reactor Coolant Drain Tank Pumps.Caused by Damaged O-rings in Stem Guide to Valve Actuator.Damaged Diaphragms Replaced & Valve Stroke Adjusted ‎ (← links)
• 05000250/LER-1984-017, :on 840607,primary Water Valve (3-220) Discovered Leaking.Leak Repair Required Isolation of Primary Storage Water Tank,Resulting in Unit Not in Compliance W/Tech Specs.Valve Stem & Diaphragm Replaced ‎ (← links)
• 05000251/LER-1984-010-01, :on 840604,steam Generator Feedwater Pump 4A Tripped Due to Low Suction Pressure.Caused by Opening of Reactor Trip Breaker A.Reactor Trip Breaker a Replaced ‎ (← links)
• 05000250/LER-1984-009, :on 840306,turbine Runback Experienced During Operating Procedure 1004.2.Caused by Spurious Signal to Rod Drop Logic.Rack Will Be Monitored While Performing Reactor Protection Test to Prevent Recurrence ‎ (← links)
• 05000251/LER-1984-004-02, :on 840307,while Purging,Spurious Signal to Process Radiation Monitor R-11 Actuated Containment & Control Room Ventilation Sys Logic,Closing Purge Valve & Placing Ventilation Sys in Recirculation Mode ‎ (← 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)
• 05000250/LER-1984-011, :on 840323,turbine Runback Experienced, Resulting in Automatic Load Reduction.Caused by Detector B Reading Low on Nis Power Range Channel 42,producing Overpower & Overtemp & Rod Drop Signal ‎ (← links)
• 05000445/LER-1990-027, :on 900907,manual Reactor Trip Due to Shearing of Feedwater Flow Control Valve Feedback Linkage Arm.W/ ‎ (← links)
• ML20044D514 ‎ (← links)
• IR 05000250/1990038 ‎ (← links)
• L-99-173, Informs That on 990722,util Determined Blind Specimen Submitted to Smithkline Beecham Clinical Labs on 990721,was Reported Back with Unsatisfactory Results.Attachment 1 Is Summary of Investigation of Unsatisfactory Performance ‎ (← links)
• 05000250/LER-1998-001-02, :on 980216,manual Reactor Trip Occurred Due to Loss of Turbine Control Oil Pressure W/Steam Leak in Auxiliary Feedwater Steam Supply Piping.Auxiliary Governor Maint Instructions Will Be Revised ‎ (← links)
• 05000250/LER-1997-006-02, :on 970722,manual Reactor Trip Occurred Due to Failed Rod Control Power Supplies.Replaced Twelve Power Supplies in Rod Control Logic & Power Cabinets ‎ (← links)
• 05000250/LER-1996-011-01, :on 961009,potential for Overpressurizing Post Accident Containment Vent Filter Housings Occurred.Caused by Improper Change Mgt.Monitoring Sys Operating Procedures Revised ‎ (← links)
• 05000250/LER-1994-005, :on 941103,both Units Outside Design Basis Due to Design Defect in Safeguards Bus Sequencer Test Logic. Resumed Monthly Manual Testing of Sequencer ‎ (← links)
• 05000250/LER-1995-004, :on 950407,unit Being Shutdown to Investigate Recurring non-urgent Failure Alarms from Redundant Rod Control Power Supplies.Reactor Manually Tripped.All Four PS-3 Power Supplies Replaced ‎ (← links)
• 05000251/LER-1994-006-02, :on 941130,Unit 4 Tripped Automatically.Caused by Failure of Flexible Link Connection Between Main Generator B Phase Bus & Associated Isolated Phase Bus Bar. All Bolts on Flexible Link Checked ‎ (← links)
• 05000250/LER-1994-005-03, :on 941103,design Defect in Safeguards Bus Sequencer Test Logic Places Both Units Outside Design Basis. Caused by 3A Sequencer Failed to Respond as Expected to Opposite Unit SI Signal ‎ (← links)
• 05000250/LER-1994-004-03, :on 941103,Unit 3 Outside Design Basis Due to Two of Three Required Safety Injection Pumps Inoperable. Control Switches for 3A & 3B Safety Injection Pumps Immediately Returned to Automatic ‎ (← links)
• 05000251/LER-1994-005-02, :on 940924,Unit 4 Manually Tripped.Caused by Manual Actuation.Light Bulb & Socket Replaced ‎ (← links)
• 05000251/LER-1994-004-02, :on 940923,Unit 4 Tripped Automatically from Rated Power.Caused by Faulty Regulator Transistor.Faulty Backup Power Supply Replaced & Maint History for Power Supplies Reviewed ‎ (← links)
• 05000251/LER-1994-003, :on 940318,ARPI Indicated Greater than Twelve Steps Deviation from Associated Group Counter.Caused by Rod Position Indication Varying W/Temp.Apris Adjusted.W/ ‎ (← links)
• 05000251/LER-1993-003-03, :on 930816,Turbine Trip/Rt Occurred Due to Personnel Error in Which High Pressure Feedwater Heaters Were Not Returned to Svc Correctly.Counseled Involved Operators & Revised Procedure ‎ (← links)
• L-93-150, Special Rept:On 930525,nonsafety-grade Standby Feedwater Pumps Isolated for 18 H & 15 Minutes to Establish Boundary to Repair Valve 4-20-130.Standby Feedwater Sys Supply Returned to svc.Marked-up Administrative Procedure Encl ‎ (← links)
• 05000250/LER-1993-002-01, :on 930115,small Steam Leak Discovered on Abandoned Pressurizer Spray Valve Bypass Line.Caused by Welders Failing to Ensure Adequate Pullback of Pipe Cap.New Pipe Cap Welded on & Faulted Line Removed ‎ (← links)
• 05000250/LER-1992-014, :on 921125,small Steam Leak Discovered on Abandoned Bellows Rupture Telltale Line on Pressurizer Spray Valve.Caused by Inappropriate Application of Matl from Which Cap Fabricated.Pipe Cap Replaced ‎ (← links)
• ML17349A392 ‎ (← links)
• 05000250/LER-1991-004-03, :on 910822,inadvertent Start of 3A Diesel Generator Occurred.Caused by Inadequate Communication Between Startup Personnel & Licensed Operators.Procedures Revised & Personnel Trained ‎ (← links)
• L-91-239, Forwards Emergency Plan Implementing Procedure 20101, Duties of Emergency Coordinator & Rev 22 to Turkey Point Radiological Emergency Plan ‎ (← links)
• 05000250/LER-1991-003-03, :on 910724,main Generator Lockout Signal Tripped Generator Output Breaker,Losing Power to Vital Busses.Caused by Inadequate Contact Between Potential Transformer Drawer Stabs & Wipes ‎ (← links)
• L-90-314, Forwards Objectives for 901108 Emergency Plan Exercise. Exercise Will Involve Participation by Local Emergency Response Agencies & State Emergency Response Personnel & Will Not Be Evaluated by FEMA ‎ (← links)
• L-86-516, Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency... ‎ (← links)
• L-88-425, Forwards mgt-on-shift Weekly Rept,Per NRC Order Dtd 871019. Plant Supervisor Nuclear Shift Repts Also Encl ‎ (← links)
• ML17296A420 ‎ (← links)
• ML17229B298 ‎ (← links)
• ML16341C928 ‎ (← links)
• 05000414/LER-2004-001, Re Reactor Coolant System Pressure Boundary Leakage Due to Small Cracks Found in Steam Generator Channel Head Bowl Drain Line on 2C & 2D Steam Generators ‎ (← links)
• NLS2003132, To EPIP 5.7ENS, ENS Communicator ‎ (← links)
• L-2003-242, 0 to EPIP-05, Activation and Operation of the Operational Support Center, and Revision 7 to EPIP-06, Activation and Operation of the Emergency Operations Facility ‎ (← links)
• ML030970196 ‎ (← links)
• NLS2003035, To EPIP 5.7ENS to ENS Communicator ‎ (← links)
• HL-6387, Emergency Implementing Procedure Revision ‎ (← links)