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

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List of results

  • ML19319B785  + (RO NP-33-77-55:on 770815,main Steam Line 2 Isolation Valve MS100 Closed Due to Control Air Leak.Caused by Instrument Air Moisture Trap Failure at Plastic Bowl Threads.Valve Closure Investigated & Moisture Traps Removed by 770817)
  • ML19319B802  + (RO NP-33-77-56:on 770816,diesel Generator 1 Found Inoperable.Caused by Speed Switch Component Failure.Burned Resistors & Shorted Diodes Found in Switch ESSB-4AT.Switch Replaced,Returned to Vendor & Generator Returned to Svc)
  • ML19319B804  + (RO NP-33-77-57:on 770818,decay Heat Pump 1-2 Inoperable Due to Closed Injection Valve DH1A.Caused by Personnel Closing Valve During Surveillance Test.Valve Immediately Opened.Event Will Be Discussed W/All Operators)
  • ML19319B799  + (RO NP-33-77-58:on 770817,Control Rod 3,Group 5,indicator Found Misaligned to More than 6.5%.Caused by Loose Control Room Panel Indicator Connection.Connection Tightened & Indicator Returned to Correct Position)
  • ML19319B815  + (RO NP-33-77-59:on 770826,intermediate Range Nuclear Instrument NI-3 Disconnected from Reactor Protection Sys & Connected to Reactimeter to Perform Reactivity Measurements. NI-4 Operable During Test.Power Level Maintained at 5%)
  • ML19319B801  + (RO NP-33-77-60:on 770816,electrolte Level Found Too Low for Station Battery Cell 2N-41.Caused by Personnel Covering Vent Cap Opening.Maint Work Order 77-1698 Initiated to Bypass Cell 2N-4L.Cell 2N-41 Checked for Cracked & Leaks)
  • ML19319B794  + (RO NP-33-77-61:on 770823,auxiliary Feed Pump 2 Rendered Inoperable During Planned Adjustment to Governor Valve. Governor Hung Up at Certain Speeds Necessitating Maint Action.Auxiliary Feed Pump Tested & Returned to Svc)
  • ML19319B822  + (RO NP-33-77-62:on 770825,auxiliary Feed Pump 1-1 Rendered Inoperable During Permanent Pressure Relief Valve Psv 4980 Installation.Relief Valve Installation Completed,Auxiliary Feed Pump Cooling Water Restored & Pump Declared Operable)
  • ML19319B788  + (RO NP-33-77-63:on 770812,absolute Position Indicator for Control Rod 4 Showed Fluctuation Reading.Caused by Defective Relay in Position Indicator Panel.Relay Replaced Returning Absolute Position Indicator to Svc)
  • ML20027A375  + (RO NP-33-77-64 on 770827:reactor Coolant Pump 1-1-2 Tripped Removing One of Two Reactor Coolant Pumps of Loop from Operation.B&C Phase Surge Capacitors Were Discovered to Be Damaged Due to Design Deficiency)
  • ML19319B809  + (RO NP-33-77-64:on 770827,reactor Coolant Pump Motor 1-1-2 Tripped W/Instantaneous Ground & Differential Current Relay Indicating Fault.Caused by Damaged B&C Phase Surge Capacitors.Capacitors Repaired & Setpoints Reset)
  • ML19319B793  + (RO NP-33-77-65:on 770708,wind Speed & Direction Monitoring Channels Found Inoperable While Computer Out of Svc.Mod to Surveillance Test 5099.02 Included Provision for Recording Weather Data from Emergency Control Ctr Instrumentation)
  • ML19319B790  + (RO NP-33-77-66:on 770824,decay Heat Pump 1-2 Taken Out of Svc While Installing Union on Cooling Water Line.Planned Maint Activity Allowed Seismic Support Tightening.Maint Completed & Heat Pump Returned to Svc)
  • ML19319B812  + (RO NP-33-77-67:on 770819,reactor Protection Sys Channel 3 Coolant Flow Meter Found at Zero.Caused by Improper Contact Between Flow Transmitter Ft RC01B3 Power Supply Fuse & Fuse Holder.Holder Cleaned & Fuse Realigned in Fuse Holder)
  • ML19319B810  + (RO NP-33-77-68:on 770812,intermediate Range Nuclear Instrument NI-3 Indicated Constant Neutron Level.Caused by Min Voltage in Compensating Power Supply.Setpoint Reset & Indication Returned to Normal)
  • ML19319B786  + (RO NP-33-77-69:on 770823,hydraulic Snubber EBD-19-H 144 Discovered Upside Down.Caused by Loose Lock Nut on Snubber Extension Piece Allowing Rotation & Placing Fluid Reservoir Below Cylinder.Snubber Purged & Tested.Lock Nut Tightened)
  • ML19319B820  + (RO NP-33-77-70:on 770822,hydraulic Snubbers SR17 & SR11 Found Close to End of Piston Travel.Caused by Oversight in Design.Piston Design Temp Settings Not Changed When Support Position changed.1.5 Inch Shim Added to Support)
  • ML19319B782  + (RO NP-33-77-71:on 770819,auxiliary Feed Pump Rendered Inoperable Enabling Maint Personnel to Stroke Isolation Valve MS106.Valve Repacked Stopping Packing Leak.Isolation Valve MS106 Cycled to Verify Proper Operation)
  • ML19329A782  + (RO NP-33-77-73:on 770917,makeup Pump 1-2 Removed from Svc to Allow Repair of Oil Leak on Outboard Bearing Plate. Caused by Design Deficiency in End Plate Seal.New O-ring Installed)
  • ML19329A796  + (RO NP-33-77-74:on 770907,decay Heat Suction Valve DH-12 Closed During Switching from Normal to Alternate Power Supply for Valve.Caused by Design Deficiency in Interlock/Control Circuit.Wiring Change in Process)
  • ML19329A807  + (RO NP-33-77-75:on 770829,RCS Have Less than 525 F in Mode 2,startup.Caused by Procedure Error in Shutdown Procedure & Fact That Only Three Reactor Coolant Pumps Were in Operation.Reactor Shut Down)
  • ML19329A812  + (RO NP-33-77-76:on 770901,reactor Coolant Pump 1-2-1 Tripped.Caused by Low Seal Injection & Component Cooling Water Flow,Due to Personnel Error.Instrument Air Valves Relabeled)
  • ML19326A557  + (RO NP-33-77-78:on 770727,power Indication Light for Containment Vacuum Relief Valve Cv 5074 Found Off.Caused by Local Remote Switch Found in Local Position.Valve Returned to Svc)
  • ML19329B901  + (RO NP-9-77-1:on 770609,computer Point T565,intake Canal from Lake in Temp Failed to Function,Causing No Computer Point Calculations & No Manual Temp Readings.Caused by Blown Fuse. Work Rept Issues & Computer Point Restored)
  • ML20085F480  + (RO NRE-75-10:on 750214,leak Became Apparent in One Component Cooling Water Hx.Hx B Isolated.Event Nonreportable)
  • ML22060A198  + (RO Operating Test Pass-Rates (2021))
  • ML20031D626  + (RO Overall Pass-Rates)
  • ML22060A194  + (RO Overall Pass-Rates)
  • ML22060A193  + (RO Overall Pass-Rates (2021))
  • ML20151C190  + (RO P-1-76:on 760119,inadequate Design Pressure Ratings Found on Relief Switches DPS-9051 & 9052,transmitter PT-173 & Reactor Protection Containment Pressure Switches PS-664,665, 666 & 667.Caused by Inadequate Design Specs)
  • ML20052J076  + (RO P-RO-82-7:on 820501,rod Control Sys Component Failed Causing Loss of Drive Motion for Some Rods.Caused by Failed Bridge Thyristor in Power Cabinet 1BD.Unit Brought to Hot Shutdown & Rod Control Sys Repaired on 820502)
  • ML20081B328  + (RO Re 1983 Land Use Census,Enumerating Changes in Land Use within 5-mile Radius of Site Ref Point Which Have Resulted in Calculated Dose Commitments Greater than Values Currently Calculated,Per Tech Spec 4.11.2.3)
  • ML20042A885  + (RO Re 3-h Fire Barriers.Continuous Fire Watch Stationed Prior to Breaching Fire Barrier for Installation of Conduit Associated W/Deluge Sys.Barrier Will Be Functional by 820331)
  • ML20084U481  + (RO Re Bending of Nut Capture Devices & Continuous Outward Driving of Control Rod Drive Mechanism Motor Package.Caused by Control Blade Interference & Cable Termination Degradation,Respectively.Nuts Straightened & Wires Modified)
  • ML20050L676  + (RO Re Cable Spreading Room Deluge Sys,Per 810526 Special Rept & 811231 Suppl.Installation & Checkout of Automatic Initiation Equipment Will Be Delayed Until June 1982 Due to Electrical Equipment Maint)
  • ML20084B191  + (RO Re Condenser Pump Room Mods.Condenser Pit Will Be Sealed Off from Condensate Pump Room to Preclude Flooding & RHR Svc Water Pumps Will Be Enclosed in Watertight Vaults)
  • ML20050M387  + (RO Re Deficiency in Establishment of Sufficient Fire Watches,Per Tech Spec Section 3.7.9,App a Limiting Conditions for Operation.Continuous Fire Watches Established.Impact Evaluation Will Be Submitted in 14 Days)
  • ML20084E421  + (RO Re Excessive Leakage of LPCI Valve 2-1501-25B.LIS-263-73B Setpoint Found Out of Limits.Core Spray Sys Stop Check Valve 1402-8B Stuck Open During Depressurizing of Core Spray Header on 750123)
  • ML20054D275  + (RO Re Failure of Control Room Area Monitor (Channel R-1) of Radiation Monitoring Sys & Immediate & long-term Corrective Actions.Portable Radiation Monitor Placed in Control Room. Monthly Testing Performed)
  • PLA-1735, RO Re Failure of Startup Transformer T10.Cause Under Investigation.Transformer Will Be Disassembled for Repair at Which Time Evaluation of Failure Will Be Conducted. Transformer W/Automatic Tap Changer Will Be Installed  + (RO Re Failure of Startup Transformer T10.Cause Under Investigation.Transformer Will Be Disassembled for Repair at Which Time Evaluation of Failure Will Be Conducted. Transformer W/Automatic Tap Changer Will Be Installed)
  • ML20080G288  + (RO Re Fire Protection Cable Separation Criteria.Intent of License Condition 2.G Discussed W/Nrr & Util Submitted Request for License Amend to Revise Reporting Requirements)
  • BSEP-83-3248, RO Re HPCI Sys,Reported on 830909.Condition Determined Not Reportable  + (RO Re HPCI Sys,Reported on 830909.Condition Determined Not Reportable)
  • ML20084Q230  + (RO Re Increased Surveillance Being Performed on Differential Pressure Switches Which Monitor Recirculation Pump Operation & Provide Input to RHR Sys Loop Select Logic.Quarterly Calibr & Functional Testing Program Will Continue)
  • ML20154J251  + (RO Re Jan 1988 Event in Which Procedures Consistent W/New NRC Policy Used Rather than Exact Written Procedures.Reactor Operations Committee Meeting on 880513 Preceeded Info for Review.Staff Instructed to Use Exact Procedures)
  • ML20197A797  + (RO Re Malfunction of Fuel Temp Readout.Caused by Low Battery Voltage in Thermocouple Circuit.Battery Replacement Procedure,Using 6-month Replacement Interval,Implemented)
  • ML20084B435  + (RO Re Mods to Condenser Pump Room as Result of Flooding.All Equipment & Procedures Will Be Available & Enforced on & After 720711 Until Const of RHR Diesel Cooling Water Pump Vaults Completed)
  • ML20084S483  + (RO Re Notification by GE of Oversight in Reload 2 Licensing Submittal Leading to Possible Nonconservative Operation During Cycle 3.Work Request to Lower Rod Block Monitor Line to 10% at Full Flow Initiated)
  • ML20086F418  + (RO Re Plant Iodine & Particulate Release Rate Exceeding 4% of Tech Spec 3.8.C.2 Averaged Over Fourth Calendar Quarter 1976.Caused by Leaks in Reactor Water Cleanup Sys.Leaks Repaired & Equipment Modified to Reduce Leakage)
  • ML19249A513  + (RO Re Possible Failure of Containment Air Cooler Svc Water Outlet Valves to Meet Response Time Requirements of Tech Specs.Discovered During Review of Facility Change Request 79-259.Setpoints Modified)
  • B13840, RO Re Potential Failure of LPSI Sys Piping.Evaluation Involving Estimate of LPSI Piping Stress Upstream of LPSI Injection MOVs Performed.Reverse Flow Testing of LPSI Injection Check Valves Will Be Conducted by 1992 Outage  + (RO Re Potential Failure of LPSI Sys Piping.Evaluation Involving Estimate of LPSI Piping Stress Upstream of LPSI Injection MOVs Performed.Reverse Flow Testing of LPSI Injection Check Valves Will Be Conducted by 1992 Outage)
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