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A list of all pages that have property "Title" with value "RO Written Examination Pass-Rates (2021)". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML20209D202  + (RO SNM Insp Rept 70-1193/73-08 on 731203-07.Noncompliance Noted:Limit of Error Associated W/Muf Exceeded 1.5 Kg Pu. Supporting Documentation Encl.Portions of Rept Details Illegible)
  • ML20039B494  + (RO SO-313/81-014 Re GE Model 12CFD12B1A Relays Used on Emergency Diesel Generators for Monitoring Proper Voltage to Current Phase Angle.Potential Problems Exist If Mechanical Agitation Precedes Circuit Energization)
  • ML20080H981  + (RO SP-N1-84-01:on 840109,I-131 Dose Equivalent Specific Activity Exceeded Tech Spec Limit.Caused by Minor Fuel Element Defects in Reactor Core.Primary Coolant Sampled & Analyzed at Accelerated Frequency)
  • ML20081B617  + (RO SPR-84-003:on 840206,following Trip from 100% Power, Specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Limit of Less than or Equal to 1.0 Uci.Caused by Fuel Element Defects in Reactor Core)
  • ML20080N339  + (RO SPR-84-1:on 840106,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level Exceeded Tech Spec Limits.Caused by Known Fuel Element Defects in Core.Tech Spec Requirements Implemented)
  • ML20087B618  + (RO SPR-84-2:on 840118,specific Activity Sample of Reactor Coolant Showed Peak Dose Equivalent I-131 Level of 1.89 Uci,Exceeding Tech Spec Limit.Caused by Fuel Element Defects in Reactor Core.Dose Level Monitored)
  • ML19316B106  + (RO SQRC-50-327/80049:on 800514,insufficient Clearance Found Between Support Guide 1-SIH-316 & 4-inch Safety Injection Pipe.Apparently Caused by Incorrect Installation Due to Misinterpretation of Specs.Guide Support Repaired)
  • ML20037C885  + (RO SQRO-327/80196:on 801211,in Mode 5,during IE Bulletin 79-14 Review,Discovered That Thermon Heat Transfer Cement Could Result in Pipe or Hanger Failure.Caused by Failure to Consider Effect of Cement on Supports.Cement Removed)
  • ML20032E637  + (RO Special Rept 81-8:on 811106,during Low Power Physics Testing,Measured Positive Moderator Temp Coefficient Exceeded Tech Specs.Control Rod Withdrawal Limits Issued. After Burnup,Unit Will Be in Compliance)
  • 3F0184-22, RO Special Rept 84-01:on 840114,leak Found in Fire Suppression Water Sys,Rendering Sys Inoperable.Caused by Compliance W/Tech Spec Limiting Condition for Operation.Sys Returned to Operable Status on 840115  + (RO Special Rept 84-01:on 840114,leak Found in Fire Suppression Water Sys,Rendering Sys Inoperable.Caused by Compliance W/Tech Spec Limiting Condition for Operation.Sys Returned to Operable Status on 840115)
  • ML20080N371  + (RO Spr 84-001:on 840110,licensee Voluntarily Entered Action Statement of Tech Spec 3.7.10, Fire-Rated Assemblies, by Opening Fire Doors to Chilled Water Pump Rooms.Further Calculations & Documentation Being Accomplished)
  • AECM-80-137, RO Status Rept 2:on 800313,electrical Cable Insulation Damaged During Pulling Process.Caused by poly-propylene Pulling Rope Damaging Cables.Cables Replaced.Training Session Initiated.Final Rept to Be Submitted by 810131  + (RO Status Rept 2:on 800313,electrical Cable Insulation Damaged During Pulling Process.Caused by poly-propylene Pulling Rope Damaging Cables.Cables Replaced.Training Session Initiated.Final Rept to Be Submitted by 810131)
  • AECM-80-133, RO Status Rept 3:on 800125,hand Switch CR-2940-US203E Supplied by GE Failed to Operate.Util Ae & Bechtel Power Corp Will Evaluate Switches.Final Rept to Be Submitted by 800918  + (RO Status Rept 3:on 800125,hand Switch CR-2940-US203E Supplied by GE Failed to Operate.Util Ae & Bechtel Power Corp Will Evaluate Switches.Final Rept to Be Submitted by 800918)
  • ML20085F500  + (RO UE-1-74:on 740514,contacts on Relays AC-1 & AC-2 Failed to Open When Deenergized.Cause Unknown.Relays Returned to Manufacturer for Further Investigation)
  • ML20085F558  + (RO UE-2-74:on 741017,startup Transformer Tripped During Quarterly Safety Injection Sys Test.Caused by Installation of Current Transformers Associated W/Differential Relays. Relays Removed from Svc Pending Investigation)
  • ML20085F481  + (RO UE-74-3:re Possible Loss of Snm.Lists Probable Route of out-of-core Fission Chamber from Cleveland,Oh to Plant)
  • ML20085E864  + (RO UE-75-010:on 751002,poison Rod Axial Growth Found in Facility Fuel.Possibly Caused by Radiation Induced Gowth. Power Level Limited to 80% & Primary Coolant Gross Gamma Radioactivity Monitored by Daily Samples)
  • ML20085F478  + (RO UE-75-2:on 750329,control Rod 30 Failed to Drop Properly During Rod Drop Timing Test.Cause Not Determined.Further Investigation to Be Conducted at Next Cold Shutdown)
  • ML20196B209  + (RO Update:On 981028,reactor Was Shutdown Upon Discovery That RB Ventilation Dampers Would Not Automatically Close.Damper Cylinder Was Repaired on 981102 & Reactor Operation Resumed on 981103)
  • ML21144A254  + (RO Written Exam)
  • ML20149K689  + (RO Written Exam (Test Answer Key))
  • ML19023A191  + (RO Written Exam Historical Performance)
  • ML20031D628  + (RO Written Examination Average Grades)
  • ML22060A195  + (RO Written Examination Average Grades)
  • ML20031D629  + (RO Written Examination Pass-Rates)
  • ML22060A197  + (RO Written Examination Pass-Rates (2021))
  • ML20031D654  + (RO Written Examination Performance Trend)
  • ML22056A519  + (RO Written Examination Performance Trend (2021))
  • ML081010310  + (RO and SRO Dresden Initial Exam - March 2008)
  • ML22143B003  + (RO and SRO Exam Reference Handouts)
  • ML19215A013  + (RO and SRO Exam with Handouts and Key Redacted)
  • ML22173A106  + (RO and SRO Reference Handouts)
  • ML24309A046  + (RO as Given Catawba 2024)
  • ML19326A050  + (RO on 720411:loss of Secondary Containment Integrity Occurred Due to Ventilation Sys Supply Dampers Failure to Close.Caused by Electrical Short in Supply Breaker.Motor Leads Disconnected & Breaker racked-in)
  • ML19290A431  + (RO on 720411:supply Dampers for Reactor Bldg Ventilation Sys Failed to Close During Performance of Routine Weekly Surveillance Test of Isolation of Reactor Bldg & Initiation of Standby Gas Treatment Sys)
  • ML19256E659  + (RO on 720728:smoke Observed Coming from Weld Joint Area During Stress Relieving Temp Increase.Caused by Melted Piece of Polyvinyl Chloride on Insulation Blanket Covering Internally Mounted Resistance Heaters.Area Cleaned)
  • ML19326A065  + (RO on 720926,two Pumps in Standby Liquid Control Sys Inoperable at Same Time.Caused by racked-out Pump Breaker. Breaker racked-in & Operations Procedures Revised)
  • ML19290A432  + (RO on 720926:A & B Liquid Control Sys Pumps Inoperable at Same Time.Caused by Interlock in Starting Circuitry Preventing Pump B from Starting When Pump a Breaker Is in Racked Out Position.Operating Procedures Changed)
  • ML19261F182  + (RO on 721108:during Prebaseline Ultrasonic Exams of Welds in Reactor Coolant Sys,Five Found W/Ultrasonic Reflectors Greater than American Matl Stds Inst B31.7 Code. Investigations & Destructive Sampling Under Way)
  • ML19261F178  + (RO on 740213:during Complete Draining of Condensate Storage Tank 1B to Condenser Hotwell,Diaphragm Punctured in Several Places.Caused by Diaphragm Being Sucked Over Suction Screen Due to Design Inadequacy.Redesigned Screen to Be Installed)
  • ML19261F272  + (RO on 740304:pump Failure During Hot Functional Testing. Caused by Shaft Fracture.Alternate Pump Activated & Motor & Pump Returned to Vendors for Insp & Repair)
  • ML20084Q039  + (RO on 740310,motor Operated Steam Inlet Valve to Turbine MO-1301-61 Found to Be Inoperable.Caused by Problem in Gear Box.Repairs in Progress)
  • ML20084Q024  + (RO on 740310,motor Operated Steam Inlet Valve to Turbine MO-1301-61 Found to Be Inoperable.Caused by Problem in Gear Box.Repairs in Progress)
  • ML19261F268  + (RO on 740402:during Check of Penetration Pressurization Sys, Leak Detected in One of Four Air Coolers in Penetration 112 for a Main Steam Line.Tubing Disconnected & Plugged)
  • ML19308A501  + (RO on 740409:during Filling of Sodium Thiosulfate Tank,Upper Section of Tank Buckled Inwards.Caused by Negative Internal Pressure.Repairs Under Way & Procedures to Prevent Recurrence in Preparation)
  • ML19261F293  + (RO on 740905-07 Re Three Inadvertent Releases of Radioactive Matl.Caused by Loss of Water from Waste Evaporator Feed Tank Loop Seal.Release Rates within Tech Spec Limits.Personnel Whole Body Counted)
  • ML19268B971  + (RO on 741008:inadvertent Release of Radioactive Matl.Caused by Leak from Feed Tank to Auxiliary Bldg Atmosphere. Personnel Monitored,Decontaminated & Nose Swabs Taken)
  • ML19308A512  + (RO on 741009 & 10:inadvertent Release of Radioactive Matl. Cause Under Investigation)
  • ML19322A442  + (RO on 741122:inadvertent Release of Radioactive Matl.Caused by Leak in Sample Line Fitting.Fitting Repaired)
  • ML19308A484  + (RO on 741125:unplanned Release of Radioactive Matl.Caused by Leaking Vent Line Valves.Gas Drawn Into Main Condenser & Discharged Through Monitor.Valves Reclosed & Procedural Revisions Under Way)
  • ML19261F329  + (RO on 770713:Tri-State Motor Transit Co Driver Observed Radwaste Leaking from Container on Truck While at Rest Area. Caused by Pinhole Leak in One Liner.Truck Returned to Station Site)
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