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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

• ML20261C074  + (Assy BOP Process Instrument Panel. Sheet 1)
• ML20261B780  + (Assy Control Rod Test Instrument Panel)
• ML20261C003  + (Assy Div 1 Low Pressure Core Spray & Residual Heat Removal Relay Vb)
• ML20261C107  + (Assy Div 1 MSIV Leakage Control Cabinet. Sheet 1)
• ML20261C102  + (Assy Div 3 ESF Logic Vb. Sheet 1)
• ML20261C082  + (Assy Division 1 Engineered Safeguard Features Relay Vb. Sheet 1)
• ML20261C088  + (Assy Division 1 Engineered Safeguard Features Relay Vb. Sheet 2)
• ML20261C093  + (Assy Division 2 Engineered Safeguard Features Relay Vb. Sheet 1)
• ML20261C097  + (Assy Division 2 Engineered Safeguard Features Relay Vb. Sheet 2)
• ML20261C000  + (Assy Division 2 RHR Relay Vb. Sheet 1)
• ML20261B932  + (Assy Division 4 ESF Logic Vb)
• ML20261B990  + (Assy Division I Leak Detection Vb. Sheet 1)
• ML20261B819  + (Assy ESF Transformer No 11 Protection Vb)
• ML20261B823  + (Assy Efs Transformer No 21 Protection Vb)
• ML20261C034  + (Assy Feedwater & Recirculation Instrument Panel)
• ML20261C044  + (Assy Gen & Trans Protection Vb. Sheet 1)
• ML20261C049  + (Assy Gen & Trans Protection Vb. Sheet 2)
• ML20261C054  + (Assy Gen & Trans Protection Vb. Sheet 3)
• ML20261C039  + (Assy High Pressure Core Spray Relay Vb)
• ML20261B795  + (Assy Inboard Valve Relay Vb. Sheet 1)
• ML20261B799  + (Assy Inboard Valve Relay Vb. Sheet 2)
• ML20266D830  + (Assy Insert P680-09C. Sheet 1)
• ML20261B784  + (Assy Nuclear Steam Supply Shutoff Process Instr Panel. Sheet 1)
• ML20261B996  + (Assy Nuclear Steam Supply Shutoff Temperature Recorder Vb)
• ML20261B811  + (Assy Outboard Valve Relay Vb. Sheet 2)

• ML20261B815  + (Assy Process Radiation Monitoring Instrument Panel)

• ML20261B789  + (Assy Reactor Core Isolation Cooling Relay Vb)
• ML20261C024  + (Assy Rps/Nsss Logic Vb)
• ML20261C014  + (Assy Rps/Nsss Logic Vb)
• ML20261C058  + (Assy Service Transformer No 11 & 12 Bop. Sheet 1)
• ML20261C063  + (Assy Service Transformer No 11 & 12 Bop. Sheet 2)
• ML20266D841  + (Assy Standby Information Vb. Sheet 1.Rev Date Illegible)
• ML20261B772  + (Assy Traversing in Core Probe Control Monitoring Instrument Panel)
• ML20261C069  + (Assy Turbine Supervisory Recorder Vb)
• ML17214A313  + (Assy of Nuclear Class Butterfly Valve)
• ML18298A354  + (Astro 2018: Handout, the NRC Is Seeking Input on Its Evaluation of Training and Experience for Authorized Users)
• ML18298A352  + (Astro Annual Meeting 2018: Poster, USNRC Evaluation of Training and Experience for Radiopharmaceutical Use)
• ML20038C030  + (Asvises ASLB of Util Demand for Commission to Return All Copies of Fault Trees Comprising Part of Plant Probabilistic Risk Assessment.Certificate of Svc Encl.Related Correspondence)
• ML19325F159  + (Asvises That Rept Q-6-85-CI-1000 49-1-1-RD Was Shredded on 860512)
• ML19341A975  + (Asymmetric Blowdown Loads on PWR Primary Systems. Resolution of Generic Task Action Plan A-2)
• ML19317F735  + (Asymmetric LOCA Loads Evaluation Program)
• ML19093B010  + (At 08/24/1977 Meeting, Agreed to Perform Additional Analytical Work & Provide with Additional Information Concerning Justification for Continued Operation of Surry Units 1 & 2 with Concern Relating to Net .)
• 05000366/LER-1981-121-03, At 2,402 MWt,N004 HPCI Steam Line Dp Switch Actuated at 207.5 Inches Below Tech Spec Limit of Plus/Minus 300% Rated Flow.Caused by Setpoint Drift.Switch Recalibr,Tested & Returned to Svc  + (At 2,402 MWt,N004 HPCI Steam Line Dp Switch Actuated at 207.5 Inches Below Tech Spec Limit of Plus/Minus 300% Rated Flow.Caused by Setpoint Drift.Switch Recalibr,Tested & Returned to Svc)
• ML19273B020  + (At 781201 Meeting Two Documents Were Distributed & Discussed.Copies of Documents, Shoreham Outstanding Issues & Shoreham Open-Item Analysis Will Be Provided W/Meeting Summary)
• 05000366/LER-1979-048-03, At 86% Power,Average Drywell Temp Discovered at 135.3 F.High Temp Caused by Control Rod Drive Access to Underside of Vessel Through Biological Shield Left Off During Drywell Closeout  + (At 86% Power,Average Drywell Temp Discovered at 135.3 F.High Temp Caused by Control Rod Drive Access to Underside of Vessel Through Biological Shield Left Off During Drywell Closeout)
• 05000366/LER-1980-103-01, At 97% Power,High Drywell Pressure Switches N010A - D Actuated at 2.21,2.34,2.27 & 2.47 Psig,Respectively;Above Tech Spec Limit of Plus/Minus 2 Psig.Caused by Setpoint Drift.Switches Recalibr & Tested  + (At 97% Power,High Drywell Pressure Switches N010A - D Actuated at 2.21,2.34,2.27 & 2.47 Psig,Respectively;Above Tech Spec Limit of Plus/Minus 2 Psig.Caused by Setpoint Drift.Switches Recalibr & Tested)
• ML19093B011  + (At Meeting with NRC Staff on 08/19/1977, Discussed the Operation of the Recirculation Spray Pumps Under Postulated Loss of Coolant Conditions Based on Results of Most Recent Analysis Using Conservative Assumptions)
• ML19220A252  + (At Present Time,Nrc Has Not Required Operators of Other Nuclear Power Plants to Take Any New Actions.Nrc Is Not Contemplating Recommending Any New Reactor Shutdowns)
• ML101830272  + (At a Glance)
• ML20117J049  + (At&T Round Cell Nuclear Util Users Council Charter)
• ML23219A025  + (At-Risk Construction Final)