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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.

Search by property

A list of all pages that have property "Title" with value "Site Property". Since there have been only a few results, also nearby values are displayed.

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List of results

  • ML19256B824  + (Site Problem Rept 193:Loop a Hot Leg Resistance Temp detector,RC-4A-TE2 Used in Reactor Protection Sys Had Drifting Temp Indications Vs Stable Readings of Remaining Resistance Temp Detector in Loop A.Detector Replaced)
  • ML20136C065  + (Site Problem Rept 198 Re Inability to Adjust Delta Flux Difference Amplifiers to Obtain K Factors Greater than Five Per Results of Tp 800/18,power Imbalance Detector Correlation Test.Old & New Wiring Diagrams Encl)
  • ML19322A354  + (Site Problem Rept 241 Re 820 inter-communication Sys Component Failures on 761108.Supporting Matl Encl)
  • ML19322D194  + (Site Problem Rept 254:on 740227,util Lost Nuclear Svc River Water Pump,Loosing Flow to IC Coolers.Sys Temp at Inlet of IC Pumps Rose Above Facility Limits.Ao to Be Written by General Public Utils)
  • ML19322D201  + (Site Problem Rept 289:on 740720,turbine Tripped.Caused by GE Work.Recommends Addition of Feed Forward from Turbine Header Pressure to Feed Pump Speed Control Raising Speed Demand When Header Pressure Jumps on Turbine Trip)
  • ML19322A360  + (Site Problem Rept 322 Re Low Pressurizer Level Following Reactor Trip on 741004.Caused by Slow Decay of Trapped Steam Pressure in Turbine Header Resulting in Turbine Bypass Remaining Open Excessively.Supporting Matl Encl)
  • ML19322C572  + (Site Problem Rept 322 Re Low Pressurizer Level Following Reactor Trip.Revisions 0 & 1,B&W 750416 Memo & B&W to Util Encl)
  • ML19322C196  + (Site Problem Rept 369:on 770924,following Steam & Feedwater Rupture Control Sys Actuation,Steam & Feedwater Was Isolated to Both Steam Generators & RCS Pressure Increased Above 2255 Psig.Probably Caused by Missing Relay)
  • ML19290A084  + (Site Problem Rept 386 Re Failure of Pilot Valve to Close on 771013 During Seventh Test Cycle.Electromagnetic Relief Valve Isolated & Cooled Down.Caused by Blinding Condition Between Stem & Pilot Valve Nozzle)
  • ML19322C574  + (Site Problem Rept 386:on 771013,electromagnetic Relief Valve Failed to Close on Seventh Test.Caused by Pilot Valve Stem Sticking Open Due to Close Tolerance Causing Binding & Metal Particle in Stem/Nozzle Area.Clearance Increased)
  • ML19308C935  + (Site Problem Rept 386:on 771013,electromatic Relief Valve Tested After Completion of Repairs Outlined in Site Problem Rept 369.Pilot Valve Failed to Close on Seventh Test Cycle. Caused by Close Tolerance of Pilot Valve Stem & Nozzle)
  • ML19322D225  + (Site Problem Rept 41:on 721010,RS Rand Contacted Bailey Meter Co Re Inability of Pressurizer Level Compensation Circuit to Be Calibr to Match Revised Pressurizer Compensation Data Transmitted Apr 1972 by Siegel)
  • ML19322A364  + (Site Problem Rept 444,on 730122:reactor Coolant Valve Steam Leak.Valve Had Excessive Travel & Yoke Bushing Threads Were Cut by Stem.During Replacement of Yoke Bushing,Steam Leaked Past Reactor Coolant Valve 3.Supporting Matl Encl)
  • ML19322A353  + (Site Problem Rept 445 Re once-through Steam Generator Boiled Dry on Three Occasions on 770422-3.Post Trip Reviews & Relevant Strip Chart Recordings Encl)
  • ML19322A355  + (Site Problem Rept 446 Re Upgrading of Core Flood Valves Documentation on 780815.Supporting Matl Including Ja Lauer 780109 Memos to CA Armontrout & Fr Faist & Manufacturers Data Rept for Nuclear Pumps & Valves Encl)
  • ML19322A356  + (Site Problem Rept 456 Re Confusing 855 Pressurizer Level Indication on 730901.Recommends Output for Pressurizer Inputs Be Temp & Pressure Compensated Pressurizer Level. Supporting Matl Including Ha Baker 740114 Memo Encl)
  • ML19322A365  + (Site Problem Rept 533 on 730518 Re Loss of Feedwater.Caused by Failure of Emergency Feedwater Pump to Start & Main Turbine to Trip Upon Loss of Feedwater Pumps.Supporting Matl Encl)
  • ML19322A357  + (Site Problem Rept 546 Re Erratic Operation of Reactor coolant-valve 1 on 730706.Caused by Galled Shaft.Shaft Dressed W/Emery Cloth & Valve Repacked on 730707.Sheared Key Found During 730708 Checkout.Supporting Matl Encl)
  • ML19322A362  + (Site Problem Rept 560 Re Reactor Coolant Valve (RC-V2) Motor Burnout on 731005.Caused by Failure of Valve to Open During Dropped Rod Incident & Operator Error.Valve Actuator Replaced on 731007 & Returned to Svc W/Overloads Bypassed)
  • ML19322A358  + (Site Problem Rept 571 Re Loss of Feedwater to once-through Steam Generators on 741011.Supporting Matl Including Ja Bailey 741112 & 13 Ltrs to Util Encl)
  • ML19322D197  + (Site Problem Rept 679:on 770403,facility Started Following once-through Steam Generator Tube Leak Repairs.High Pressure Rx Tripped Due to Bad Summer Module in Ics.Recommenced Startup Following Module Repair)
  • ML20024C726  + (Site Problem Rept Resolution transmittal,13-6-183-0)
  • ML20024C814  + (Site Problem Rept SPR-108:on 750613,during Shutdown to Replace Reactor Coolant Pump Seals,Rcs Rapid Depressurization Transient Experienced.Caused by Pressure Spike)
  • ML19322A366  + (Site Problem Rept on 790320 Re Rapid Cooldown Transient. Caused by Loss of Power to non-nuclear Instrumentation Sys & Subsequent Loss of Input Signals to Control Room,Computer & Intercommunicatin Sys Due to Short.Supporting Matl Encl)
  • ML19308B766  + (Site Problem on 771129,reactor Tripped on Reactor Protection Sys Channel 2 & 4 High Flux.Caused by Not Removing Jumpers in Startup Reactimeter Patch Board.B&W Will Evaluate Transient Data & Recommend follow-up Action)
  • ML20262A835  + (Site Radiation Zones Normal Operation Shutdown)
  • ML20262A851  + (Site Radiation Zones Post Accident)
  • ML20262A727  + (Site Radiological Access Controls Normal Operation Shutdown)
  • ML20086T469  + (Site Redress Plan)
  • ML032721611  + (Site Redress Plan for the Exelon Generation Company, LLC Early Site Permit)
  • ML19350C339  + (Site Regulatory Compliance Manual for Nuclear Fuel Div,At AL Nuclear Fuel Fabrication Plant)
  • ML20262A166  + (Site Related Main Control Board RL013 and RL014)
  • ML20262A055  + (Site Related Main Control Board RL013 and RL014)
  • ML21272A001  + (Site Response SSHAC Level 2 Workshop Presentations - January 28-29, 2020)
  • ML20265E627  + (Site Rough Grading & Drainage Plan)
  • ML20261A284  + (Site Rough Grading Area Plan. Sheet 1)
  • ML20261A221  + (Site Rough Grading Area Plan. Sheet 10)
  • ML20261A147  + (Site Rough Grading Area Plan. Sheet 11)
  • ML20261A149  + (Site Rough Grading Area Plan. Sheet 12)
  • ML20261A160  + (Site Rough Grading Area Plan. Sheet 13)
  • ML20261A166  + (Site Rough Grading Area Plan. Sheet 14)
  • ML20261A069  + (Site Rough Grading Area Plan. Sheet 15)
  • ML20261A288  + (Site Rough Grading Area Plan. Sheet 2)
  • ML20261A233  + (Site Rough Grading Area Plan. Sheet 3)
  • ML20261A179  + (Site Rough Grading Area Plan. Sheet 4)
  • ML20261A190  + (Site Rough Grading Area Plan. Sheet 5)
  • ML20261A194  + (Site Rough Grading Area Plan. Sheet 6)
  • ML20261A203  + (Site Rough Grading Area Plan. Sheet 7)
  • ML20261A207  + (Site Rough Grading Area Plan. Sheet 8)
  • ML20261A211  + (Site Rough Grading Area Plan. Sheet 9)
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