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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
- ML20100A659 + (ML20100A659)
- B11379, Forwards Amend 11 to FSAR & Responses to Selected Requests for Addl Info + (ML20100A670)
- W3P84-3337, Forwards Addl Info on Soil Spring Distributions & north- South Bending Capacities in Positive & Negative Directions Re Foundation Basemat Cracks,Per Js Ma 841116,20 & 26 Requests + (ML20100A680)
- ML20100A686 + (ML20100A686)
- ML20100A687 + (ML20100A687)
- ML20100A689 + (ML20100A689)
- 05000249/LER-1985-004-06, :on 850215,level Indicating Switch 3-263-58B Found to Trip at 116.5 Inches Water & Switch 3-263-57B Found to Trip at 127 Inches Water (Differential Pressure).Caused by Setpoint Drift.Switches Adjusted & Recalibr + (ML20100A709)
- 05000397/LER-1985-018, :on 850224,containment Monitoring Sys Temp Indicator Exceeded 150 F for Greater than 8 H.Caused by Circulating Water Sys Cooling Towers Alternately Being Taken Out of Svc for Electrical Repairs + (ML20100A715)
- HL-5089, Responds to NRC Re Violations Noted in Insp Rept 50-321/95-23.Corrective Actions:Peo Disciplined,Operations Personnel Reviewed Applicable Fuel Oil Transfer Procedures. Procedure Rev W/Appropriate Enhancements Implemented + (ML20100A722)
- 05000397/LER-1985-019, :on 850216,temp Monitoring of RHR Pump Room Areas Not Accomplished in Accordance W/Tech Specs.Caused by Incorrect Transference of Instructions from Plant Procedure Deviation to Actual Procedure Used on 850216 + (ML20100A723)
- 05000397/LER-1985-015, :on 850213,fire Detection Instrument Discovered to Have Been Removed from RHR Valve Room During Plant Mod. from 840909-850213 No Fire Detection or Fire Watch Patrol Monitored RHR Valve Room + (ML20100A737)
- ML20100A744 + (ML20100A744)
- 05000397/LER-1985-014, :on 850214,high Pressure Reactor Scram Initiated Due to Actuation of Turbine Bypass Valve 7 Inches Mercury Low Condenser Vacuum Interlock.Normal Scram Recovery Procedures Followed + (ML20100A750)
- ML20100A751 + (ML20100A751)
- ML20100A761 + (ML20100A761)
- ML20100A762 + (ML20100A762)
- ML20100A768 + (ML20100A768)
- ML20100A771 + (ML20100A771)
- ML20100A780 + (ML20100A780)
- ML20100A782 + (ML20100A782)
- 05000333/LER-1985-007, :on 850220,actuation of Reactor Protection Sys Occurred.Caused by Erroneous Low Level Signal Resulting from Protective Tagging Evolution to Remove Reactor Pressure Vessel Transmitter from Svc + (ML20100A784)
- ML20100A799 + (ML20100A799)
- ML20100A801 + (ML20100A801)
- ML20100A806 + (ML20100A806)
- ML20100A811 + (ML20100A811)
- ML20100A812 + (ML20100A812)
- ML20100A829 + (ML20100A829)
- ML20100A834 + (ML20100A834)
- ML20100A856 + (ML20100A856)
- ML20100A860 + (ML20100A860)
- ML20100A863 + (ML20100A863)
- ML20100A875 + (ML20100A875)
- ML20100A877 + (ML20100A877)
- W3P84-3340, Informs That SPDS Integrated Sys Validation Testing Will Involve Use of Trained Operators to Validate That SPDS Coordinates W/Training & Procedures & Allows Rapid Assessment of Plant Safety Status + (ML20100A881)
- ML20100A883 + (ML20100A883)
- DCL-84-364, Advises That Util Response to Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing Interval, Contained Entirely in Westinghouse WCAP-10271 Re Reactor Protection Instrumentation Sys,Currently Under NRC Review + (ML20100A891)
- ML20100A894 + (ML20100A894)
- ML20100A899 + (ML20100A899)
- ML20100A901 + (ML20100A901)
- ML20100A904 + (ML20100A904)
- ML20100A905 + (ML20100A905)
- ML20100A908 + (ML20100A908)
- ML20100A911 + (ML20100A911)
- ML20100A914 + (ML20100A914)
- ML20100A917 + (ML20100A917)
- ML20100A922 + (ML20100A922)
- ML20100A928 + (ML20100A928)
- SNRC-1118, Forwards Responses to Concerns Discussed in R Caruso 841126 Telcon.Responses Include Concerns Associated W/Arithmetic Discrepancies W/Loss of Offsite Power Load for Tdi Diesel Generator 101 + (ML20100A932)
- ML20100A933 + (ML20100A933)
- ML20100A942 + (ML20100A942)
- ML20100A949 + (ML20100A949)