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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.

List of results

• ML20116G910  + (ML20116G910)
• ML20116G915  + (ML20116G915)
• ML20116G918  + (ML20116G918)
• ML20116G927  + (ML20116G927)
• ML20116G928  + (ML20116G928)
• ML20116G930  + (ML20116G930)
• ML20116G938  + (ML20116G938)
• ML20116G943  + (ML20116G943)
• ML20116G948  + (ML20116G948)
• ML20116G960  + (ML20116G960)
• ML20116G961  + (ML20116G961)
• TXX-9252, Forwards Advance Draft FSAR to Facilitate NRC Review of Cooling Pond Hydrothermal Analysis in Support of Licensing Unit 2.Encl Matl Will Be Incorporated in FSAR Amend 87 Currently Scheduled for Dec 1992  + (ML20116G962)
• 3F1192-07, Requests NRC Approval of Temporary non-code Repair to Moderate Energy Portions of Nuclear closed-cycle Cooling Sys.Util Separately Filed Response to GL 90-05 Which Addresses Handling of Repairs.Response Awaited  + (ML20116G996)
• ET-NRC-92-3768, Forwards Detailed Schedule for AP600 Testing Program.More Detailed Description of Spes 2 & Osu Tests,Along W/Scaling Studies,Will Be Discussed at 921209-10 Meeting W/Nrc  + (ML20116H000)
• ML20116H021  + (ML20116H021)
• ML20116H028  + (ML20116H028)
• 05000458/LER-1992-021, :on 921006,discovered That Drywell Pedestal Floor Drain Sump Overflowed to Pedestal Room.On 920928, Discovered Floor Drain Pumps Inoperable.Caused by Sump Pump Malfunction.Pumps Will Be Repaired  + (ML20116H059)
• ML20116H066  + (ML20116H066)
• 05000302/LER-1992-021, :on 921004,discovered That Fluid Level in Reactor Coolant Pump Lubricating Oil Collection Tanks at 14%.Caused by Personnel Error.Plant Mod to Repair Feedwater Leak & Control Cooling Water Temp Underway  + (ML20116H077)
• ML20116H078  + (ML20116H078)
• ML20116H083  + (ML20116H083)
• RBG-37-685, Suppl 1 to Special Rept:On 920901,abnormal Traces Observed on Primary & Secondary 150-ft Wind Direction Analog Chart Recorders.Caused by Aged/Weathered Cable.All Cables Running Between Instruments & Boom Junction Boxes Replaced  + (ML20116H093)
• ML20116H097  + (ML20116H097)
• ML20116H098  + (ML20116H098)
• U-602608, Responds to RAI Re Proposed Amend of Licencse NPF-62, Requesting Changes to Eliminate Periodic Response Testing of Analog Trip Modules  + (ML20116H132)

• ML20116H133  + (ML20116H133)

• NG-92-4540, Advises That Based on Current Outage Schedules & Having Time to Review & Analyze Necessary Data,Util Intends to Complete non-seismic Portions of IPEEE by 951121.Seismic Portion of IPEEE Will Be Incorporated Into USI A-46 Program by 951121  + (ML20116H135)
• ML20116H145  + (ML20116H145)
• ML20116H146  + (ML20116H146)
• ML20116H147  + (ML20116H147)
• 05000388/LER-1985-013, :on 850327,standby Liquid Control Pump a Failed 92-day Flow Verification Surveillance Test.Caused by Faulty Suction & Discharge Valves Internal to Positive Displacement Pump.Repairs Completed  + (ML20116H155)
• ML20116H156  + (ML20116H156)
• ML20116H164  + (ML20116H164)
• 05000373/LER-1985-028-01, :on 850327,reactor Scram Occurred While Unit in Hot Shutdown.Caused by Low Reactor Vessel Level Resulting from Opening of Safety Relief Valves During Leak Test.Rhr Sys Started  + (ML20116H166)
• 05000352/LER-1985-033, :on 850321,discovered Required Hourly Fire Watch Not Performed within Allotted Times for RHR Room 102. Caused by Inadequate Communication Between Fire Watch Personnel.Training Session Conducted  + (ML20116H168)
• ML20116H172  + (ML20116H172)
• 05000362/LER-1985-011-01, :on 850401,containment Purge Isolation Sys Train B Actuated.Caused by Failed Power Supply Bridge Diode. Diode Replaced  + (ML20116H192)
• ML20116H203  + (ML20116H203)
• 05000237/LER-1985-015-02, :on 850325,three Main Steam Line Low Pressure Isolation Switches Tripped Below Tech Spec Min Trip Point. Caused by Instrument Setpoint Drift.Switches Recalibr to Meet Tech Spec Limit & Successfully Tested  + (ML20116H209)
• 05000369/LER-1985-010-01, :on 850320,keyswitch for Door on Reactor Side of Containment Personnel Airlock in Bypass Position.Caused by Procedural Deficiency.Procedures Will Be Changed to Ensure Switches Returned to Active Position  + (ML20116H212)
• ML20116H215  + (ML20116H215)
• AECM-85-0126, Forwards Application Fee for NRC Review of Test Rept on flow-induced Vibration in HPCS Svc Pump Submitted on 850228  + (ML20116H219)
• 05000364/LER-1985-008, :on 850328,reactor Trip Occurred Due to lo-lo Level in Steam Generator 2A.Caused by Personnel Error. Technician Counseled  + (ML20116H221)
• AECM-85-0131, Notifes of Intent to Eliminate Startup Testing Activities Previously Planned for Automatic Load Following Mode of Operation.Startup Test Involving Automatic Load Unnecessary, Based on GE Evaluation  + (ML20116H222)
• ML20116H228  + (ML20116H228)
• ML20116H238  + (ML20116H238)
• ML20116H240  + (ML20116H240)
• ML20116H246  + (ML20116H246)
• ML20116H248  + (ML20116H248)
• ML20116H250  + (ML20116H250)
• ML20116H252  + (ML20116H252)