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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

• 05000423/LER-1996-004-02, :on 960316,auxiliary Feedwater Isolation Valves Noncompliance W/Ts Occurred.Caused by Misinterpretation of Ts.Event Reviewed W/Station Personnel to Caution Others on TS Surveillance Requirements  + (ML20107J201)
• ML20107J202  + (ML20107J202)
• ML20107J207  + (ML20107J207)
• PY-CEI-NRR-0157, Responds to Sser 4 Confirmatory Issue 56 Re Containment Purge Sys.Commitment to Three Programs to Assess Need for Use of Containment Purge Sys & to Minimize Use Consistent W/Alara Guidelines Verified.Programs Encl  + (ML20107J208)
• ML20107J218  + (ML20107J218)
• ML20107J224  + (ML20107J224)
• ML20107J226  + (ML20107J226)
• ML20107J229  + (ML20107J229)
• ML20107J234  + (ML20107J234)
• ML20107J236  + (ML20107J236)
• ML20107J246  + (ML20107J246)
• ML20107J253  + (ML20107J253)
• ML20107J256  + (ML20107J256)
• ML20107J259  + (ML20107J259)
• 05000388/LER-1984-020-01, :on 840929,unplanned ESF Actuation Occurred During Calibr of Differential Pressure Instrument Resulting in Isolation of Reactor Water Cleanup Sys.Caused by Closure of Containment Isolation Valve  + (ML20107J260)
• ML20107J261  + (ML20107J261)
• DCL-85-050, Provides Final Responses to IE Bulletins 79-02, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts & 79-14, Seismic Analysis for As-Built Safety- Related Piping Sys  + (ML20107J264)
• ML20107J266  + (ML20107J266)
• ML20107J268  + (ML20107J268)
• ML20107J271  + (ML20107J271)
• ML20107J273  + (ML20107J273)
• ML20107J274  + (ML20107J274)
• ML20107J281  + (ML20107J281)
• ML20107J282  + (ML20107J282)
• ML20107J284  + (ML20107J284)

• ML20107J287  + (ML20107J287)

• ML20107J313  + (ML20107J313)
• ML20107J317  + (ML20107J317)
• 05000286/LER-1985-002-01, :on 850123,high Level Generator Triggered Turbine & Reactor Trips.Caused by Feedwater Sys Perturbation Due to Starting Second Condensate Pump & Recirculation Valve.Valve Repaired & Calibr  + (ML20107J337)
• ML20107J339  + (ML20107J339)
• IR 05000219/1974008  + (ML20107J343)
• 05000286/LER-1985-001-01, :on 850121,unit Trip & Safety Injection Actuation Occurred.Caused by Operators Switching Bus 31 to Backup Power Due to Low Voltage on Two Buses.Solenoid Coil Replaced & Surveillance Test Peformed  + (ML20107J347)
• ML20107J348  + (ML20107J348)
• ML20107J357  + (ML20107J357)
• RBG-20-165, Forwards 20 Oversize Drawings Requested by Instrumentation & Control Sys Branch Re Automatic Depressurization Sys. Drawings Will Close Out SER Confirmatory Item 28,Table 1.4. Aperture Cards Available in PDR  + (ML20107J360)
• LIC-96-0053, Responds to Generic Ltr 96-01, Testing of SR Logic Circuits  + (ML20107J364)
• ML20107J374  + (ML20107J374)
• ML20107J378  + (ML20107J378)
• ML20107J397  + (ML20107J397)
• 05000324/LER-1984-001-02, :on 840330,local Leak Rate Testing of Primary Containment Isolation Valves Revealed Nonquantifiable Leak Rate for Reactor Feedwater Line B Penetration X-9B.Caused by Problems W/Seat discs,O-rings & Bellows  + (ML20107J404)
• ML20107J409  + (ML20107J409)
• 05000339/LER-1984-007-02, :on 840916,discovered Smoke Detector in Control Room Emergency Air Supply Failed to Operate as Required. Caused Not Stated.Fire Watch Placed in Effect During Inoperability.Detector Replaced  + (ML20107J411)
• ML20107J415  + (ML20107J415)
• 05000325/LER-1984-027, :on 840930,RCIC Automatically Isolated Due to Actuation of Sys a Isolation Logic RCIC Equipment Room Temp Instrument 1-E51-N602A.Caused by Deflected Steam from Leak at RCIC Sys Valve 1-E51-V20  + (ML20107J419)
• 05000361/LER-1984-070, :on 841105,during Preparations to Lift Reactor Vessel Head from Pressure Vessel,Horizontal Inflatable Seal Failed & Completely Depressurized.Instrument Air & Nitrogen Backup Pressurization Supplies Isolated  + (ML20107J420)
• STC-20-032, Seminar with Medical Licensees to Request Temporary Regulatory Relief During the COVID-19 Public Health Emergency  + (ML20107J425)
• ML20107J430  + (ML20107J430)
• 05000250/LER-1984-029, :on 841127,turbine Runback to 50 MW & Approx 65% Reactor Power Occurred.Caused by Personnel Error.Load Decrease Stopped by Raising Governor Oil Pressure Which Increased Generator Load to Approx 225 MW  + (ML20107J432)
• 05000413/LER-1985-006, :on 850120,hot Standby Initiated After Reactor Coolant Average Temp Could Not Be Increased to Greater than 541 F 15 Minutes After Temp Decrease During Performance of Natural Circulation Verification Test  + (ML20107J433)
• ML20107J434  + (ML20107J434)
• 05000373/LER-1985-009-01, :on 850122,investigation Determined That No Assigned Calibr or Functional Test Procedure for Suction Pressure Switch Existed as Required by Tech Specs.Caused by Improper Setpoint Info.Switches Calibr  + (ML20107J435)