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This page provides a simple browsing interface for finding entities described by a property and a named value. Other available search interfaces include the page property search, and the ask query builder.
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- AECM-84-0460, RO 84-035/0:on 840912,during Routine Calibr Check of Portable instrument,152 Uci Calibr Source Found Leaking. Caused by Breached Mylar Coating on Sealed Calibr Source. Source Disposed of as Radwaste & Lockers Inspected + (RO 84-035/0:on 840912,during Routine Calibr Check of Portable instrument,152 Uci Calibr Source Found Leaking. Caused by Breached Mylar Coating on Sealed Calibr Source. Source Disposed of as Radwaste & Lockers Inspected)
- ML20151M743 + (RO 84-21:on 841218,boric Acid Tank Selector Switch Misaligned.Complete Issuance of Improved Surveillance Procedures Delayed Until 860601)
- ML20090E514 + (RO 84-2:on 840528,erratic Performance of Reactor Servo Control Not Noted in Log.Caused by Personnel Error.Operator Cautioned to Be More Observant While Taking Log Readings)
- ML20090E124 + (RO 84-3:on 840604,reactor Operator Observed That Safety Power Measuring Channel 2 Not Responding as Reactor Power Level Increased Beyond 30 Kw.Caused by Loose Safety Channel 2 Signal Cable.Connector Replaced)
- ML20133H637 + (RO 85-09:on 850702,Cardox (CO2) Fire Suppression Sys Reported Inoperable for 14 Days.Sys Deenergized Due to Failure of Fire Doors to Withstand Sys Discharge Pressure W/O Opening.Latching Mechanism Changed)
- ML20134P739 + (RO 85-1:on 850108,fuel Temp Recorder Indicated 600 F Instead of 720 F.Caused by Failure of Reactor Safety Sys Channel. Faulty Slide Wire & Contact Arm Replaced)
- ML20113D568 + (RO 85-2;on 850111,safety Channel 1 Detector Failed During Reactor Operation.Caused by Loose Connector Pin Making Intermittent Contact.New Connector Installed & Detector Verified Operable Prior to Reinstallation)
- ML20203L266 + (RO 86-002:on 860627,loose Parts Monitoring Sys Inoperable in Excess of Tech Spec Action Statement 3.3.7.9.a 30-day Limit. Caused by Inadequate Calibr.New Amplifier Cards Installed & Channels Recalibr)
- ML20205J931 + (RO 86-01:on 860204,temp Recorder Providing LSSS Signal to Scram on High Fuel Temp Malfunctioned.Caused by Defective Motor Bearing.Bearing Replaced & Recorder Calibr)
- ML20203G787 + (RO 86-03:on 860508,no Down Signal Received from Transient Rod During Manual Scram.Caused by Fine Grit in Air Cylinder Causing Friction & Preventing Full Insertion.Cylinder Cleaned & Lubricated & Air Filter Replaced)
- L-86-334, RO 86-05:on 860817,during Repair of Control Rod in Position J-5,technician Caught Foot in IAEA Seal String.String Broke. Four Remaining Seals Intact.Seal & String Will Be Turned Over to IAEA During Insp on 860821 & 22 + (RO 86-05:on 860817,during Repair of Control Rod in Position J-5,technician Caught Foot in IAEA Seal String.String Broke. Four Remaining Seals Intact.Seal & String Will Be Turned Over to IAEA During Insp on 860821 & 22)
- L-86-346, RO 86-06:on 860821,IAEA Safeguards Inspectors View of Reactor Head Revealed Second Missing Seal in Addition to Missing Seal Reported in RO 86-05.Remaining Seals Provided Indication That Reactor Head Not Removed Since Installation + (RO 86-06:on 860821,IAEA Safeguards Inspectors View of Reactor Head Revealed Second Missing Seal in Addition to Missing Seal Reported in RO 86-05.Remaining Seals Provided Indication That Reactor Head Not Removed Since Installation)
- ML20215L115 + (RO 86-20:provides Updated List of Nonfunctional Fire Barriers Not Restored to Functional Status within 7 Days,Per Tech Spec Sections 3.14.6.2 & 6.9.5.E.Fire Watches Posted. Total of 71 Breaches Open & Past Forecasted Close Date)
- L-86-283, RO 86-3:on 860708 & 10,loss of Lighting in Spent Fuel Pool Occurred.Caused by Deenergization of 4-kV Bus 4C.Bus Realigned to Normal Power Supply.Work Plans Discussed in 860708 Telcon + (RO 86-3:on 860708 & 10,loss of Lighting in Spent Fuel Pool Occurred.Caused by Deenergization of 4-kV Bus 4C.Bus Realigned to Normal Power Supply.Work Plans Discussed in 860708 Telcon)
- AECM-87-0249, RO 87-006/0:on 871126,emergency Diesel Generator 12 Tripped on High Vibration Signal During Surveillance.Cause Undetermined.Calibr Procedure & Vibration Sensor Trip Settings Reviewed & Determined to Be Correct + (RO 87-006/0:on 871126,emergency Diesel Generator 12 Tripped on High Vibration Signal During Surveillance.Cause Undetermined.Calibr Procedure & Vibration Sensor Trip Settings Reviewed & Determined to Be Correct)
- ML20210D179 + (RO 87-01:on 870127,area Lights in Spent Fuel Pool Burnt Out. Caused by Low Wattage Bulbs.Bulbs Replaced W/Longer Life Bulbs.Area Lights Will Be Verified Once Per Day)
- L-87-141, RO 87-03:on 870315,NRC Notified of Intention to Remove IAEA Seals on Equipment Hatch & Reactor Missile Shields.Caused by Performance of Maint & Insps on Reactor Head.Addl Work Will Be Performed When Reactor Head Removed + (RO 87-03:on 870315,NRC Notified of Intention to Remove IAEA Seals on Equipment Hatch & Reactor Missile Shields.Caused by Performance of Maint & Insps on Reactor Head.Addl Work Will Be Performed When Reactor Head Removed)
- ML20150B183 + (RO 88-002-00:on 880226,pieces of Wire Lodged in Reactor Vessel Feedwater Sparger Nozzles.Caused by Potential Loose Parts Leftover as Const Debris.Wire Pieces Removed & Examined & Vessel Annulus Deck Area Inspected)
- ML20154C830 + (RO 88-003-00:on 880416,one Air Receiver Failed to Discharge & One Barring Device Interlock Pistons in Flowpath of Control to Air Start Valve Solenoid Stuck in Closed Position.Caused by Failure of Barring Gear Interlock Piston)
- ML20207K924 + (RO 88-01:on 880725,during Inventory of Snm,Discrepancy Noted for Intermediate Range Monitor Detector Removed from Core Location C.Caused by Inadequage SNM Control & Accountability Practices Existing at Time of Installation & Shipment)
- ML20031C147 + (RO 9-74:on 740423,during Pressure Test of Offgas Sys,Valve CV-4015 Failed to Seat Properly.Caused by Improper Leverage Action Through Linkage to Valve Operator.Curved Linkage Assembly Replaced to Provide Increased Closing Torque)
- ML20012E066 + (RO 90-01:on 900228,reactor Operator Received Servo Fault Alarm.After Directed Shutdown,Complete Loss of Linear Power Channel Noted.Caused by Corroded Connector at Detector Leads.Connector Replaced.Part 21 Related)
- ML20106D740 + (RO 92-19:on 920804,discovered That Drive Shaft on Pump 1MNVPU0046 Was Rotating in Opposite Direction than Specified on Pump Casing.Caused by Mgt Deficiency.Motor Leads of Subj Pump Reconfigured to Provide Correct Pump Shaft Rotation)
- ML20086E139 + (RO 95-002:on 950605,invalid Failure of Division 13,HPCS EDG Occurred.Surveillance Procedures Used for ECCS Testing Will Be Evaluated to Provide Alternate Method for Initiating Trip Signals,Thereby Eliminating Need for Finger Relays)
- ML19305C363 + (RO 9:on 800303,during Hot Cave Preparation of Bromine Motor Oil Sample,Approx 45 Mci Br-82 Was Released Through Stack 2. Caused by Operator Bumping Solution Beaker.Small Amount Spilled & Released as Free Bromine)
- ML14225A515 + (RO Admin 1)
- ML14225A523 + (RO Admin 2)
- ML14225A526 + (RO Admin 3)
- ML14225A547 + (RO Admin 4)
- ML20149K687 + (RO Admin JPM)
- ML21144A250 + (RO Admin JPM)
- ML21005A080 + (RO Admin JPM)
- ML22153A488 + (RO Admin JPM)
- ML23038A139 + (RO Admin JPM)
- ML23160A088 + (RO Admin JPM)
- ML20153A795 + (RO Admin JPMs)
- ML20079G646 + (RO Admin JPMs)
- ML20078L058 + (RO Admin JPMs)
- ML21361A323 + (RO Admin Job Performance Measure, Rev. 2)
- ML20055B518 + (RO Advising That Triaxial Accelerometer Devices in Reactor Core Isolation Cooling Sys Pump Room Inoperable for More than 30 Days.Replacement Detector to Be Installed by 820831)
- ML20024B430 + (RO B-350:on 750613,during Maint Shutdown,Rcs Pressure Spike Occurred,Opening Power Actuated Pressure Relief Valve 3RC66.Valve Stuck in Open Position.Caused by Heat Expansion & Boron Buildup.Valve Will Be Removed,Repaired & Replaced)
- ML17054D136 + (RO Bulletin 73-06, Inadvertent Criticality in Bwr)
- ML17249A962 + (RO Bulletin 74-10, Failures in 4-Inch Bypass Piping at Dresden-2)
- ML17054D115 + (RO Bulletin 74-10A, Failures in 4-inch Bypass Piping at Dresden-2)
- ML20235D957 + (RO Bulletin 74-14, BWR Relief Valve Discharge to Suppression Pool)
- ML20054L562 + (RO Correcting Reporting RO 82-20 Re Missed Surveillance Requirement on Personnel Hatch.Time at Which Surveillance Due Should Have Been 1100-h Instead of 1300-h)
- ML19345G120 + (RO DPR-7/74-1:on 740327,while Collecting Semiannual Liquid Poison Sample,Sample Did Not Flow Properly Until Poison Injection Equalizing Valve Tapped.Caused by Valves Failure to Close W/Proper Seating Due to Foreign Particle on Seat)
- ML19345G119 + (RO DPR-7/74-2:on 740617,while Performing Picoammeter Trip Setting Test,No Trip Observed Upon Reaching 123% on Picoammeter 2.Caused by Trip Circuit & 150 Volt Internal Power Supply Components Degradation.Components Replaced)
- ML19345G117 + (RO DPR-7/74-3:on 741105-06,during Test of High Pressure Trip Sensors,Two Trip Settings Found Out of Tolerance on High Side.Caused by Setpoint Drifts.Switch Settings to Be Left Near Tolerance Band Ctr)
- ML19345G110 + (RO DPR-7/74-5:on 741224,feedwater Control Valve Air Supply Closed Rendering Feedwater Control Valve Unavailable for Remote Operation.Caused by Maint Personnel Leaving Control Air Supply Valve in Closed Position)
- ML19345G113 + (RO DPR-7/74-7:on 741117,five of Eight Feedwater Sparger Holddown U-bolts Failed,Allowing Sparger to Shift 1.7 Inches from Initial Location.Broken Bolts Being Tested to Identify Failure Mechanism.Redesigned Holddown Clamps Installed)