Search by property

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

• ML20261J500  + (Wet Standpipe Fire Protection System P&I Flow Diagram. Sheet 2 of 2.No Revision Date)
• ML20261J497  + (Wet Standpipe Fire Protection System P&I Flow Diagram. Sheet 1 of 2.No Revision Date)
• ML071800137  + (Wetland Delineation for West Building Area Susquehanna Steam Electric Station)
• ML071800139  + (Wetland Delineation for the South Drainage Area at the Susquehanna Steam Electric Station)
• ML070120330  + (Wetland Digital Data - JAFNPP SEIS Web Reference)
• ML080850125  + (Wetlands Geodatabase, Wetlands Digital Data)
• ML070720615  + (Wetplants and Shrubs)
• 05000316/FIN-2016003-03  + (Wetting of Safety-Related Battery Charger)
• ML18030A533  + (Wetwell Spray Termination of Pressure Increase Results)
• ML20073R206  + (Wetwell-Drywell Vacuum Breaker Valves:Long-Term Program Structural Evaluation)
• ML18206A675  + (Weyerhaeuser N.R., Columbia Falls Mdf - Amendment 25 Corrected Copy Transmittal Letter)
• ML18206A703  + (Weyerhaeuser N.R., Columbia Falls Mdf - Amendment 25 Corrected Copy)
• ML18205A444  + (Weyerhaeuser N.R., Columbia Falls Mdf; Amendment 25; License 25-15644-01; Docket 030-09516; Control 609067)
• ML18205A442  + (Weyerhaeuser N.R., Columbia Falls Mdf; Cover Letter; Amendment 25; License 25-15644-01; Docket 030-09516; Control 609067)
• ML18205A495  + (Weyerhaeuser N.R., Columbia Falls, Mdf - Response to Notice of Violation)
• ML14155A153  + (Wg Letterhead SR-E Deman)
• ML23230B167  + (Wg Master List - Sunset August 2023)
• ML24201A146  + (Wg Master List - Sunset July 2024)
• ML24201A150  + (Wg Master List Active July 2024)
• ML22223A112  + (Wgev Presentation: Sources of Uncertainty in Probabilistic Flood Hazard Assessment)
• ML20134N685  + (Wgothic Application to AP600)
• ML22060A162  + (Wgrisk 2022 Annual Meeting - New Caps on Treatment of Uncertainties for Novel Aspects of Risk Analyses)
• ML22060A168  + (Wgrisk 2022 Annual Technical Discussion - Insights on Aggregating Risk of Hazards with Varying Levels of Uncertainties)
• ML20043F546  + (Wgrisk Annual Meeting February 24-28 2019 - NRC PRA Use and Development - Rev.1)
• ML22060A165  + (Wgrisk Annual Meeting March 2022 - NRC PRA Use and Development - Reisi Fard, Mehdi)

• ML24142A071  + (Wgrms Agenda)

• ML20127D067  + (Wh Zimmer Nuclear Power Station Schedule Analysis 781107)
• ML20127D101  + (Wh Zimmer Nuclear Power Station Schedule Analysis,781107)
• ML20070L676  + (Wh Zimmer Nuclear Power Station Seismic Qualification of Equipment,Supplemental Info. W/Three Oversize Drawings. Aperture Cards Are Available in PDR)
• ML20127D056  + (Wh Zimmer Nuclear Power Station Unit 1 Mgt Summary Analysis 810210)
• ML20071P714  + (Wh Zimmer Nuclear Power Station,Unit 1,Heavy Loads Rept)
• ML22275A007  + (What Are Health Utilities)
• ML25338A168  + (What Can the History of Function Allocation Tell Us About the Role of Automation in New Nuclear Power Plants? a Systematic Review)
• ML19274C671  + (What to Expect as Reactor Decommissioning Begins - Tony Leshinskie, VT, 2019 National State Liaison Officer Conference Presentation)
• ML18211A345  + (Wheeling Hospital, Inc.; E-mails Dated 07/19/18 and 07/18/18 Subject: Request for Additional Information)
• ML18234A506  + (Wheeling Hospital, Inc.; Telephone Conversation Record Dtd 8/20/18, Voidance of Amendment; Control No. 609142)
• ML20054M229  + (When Did Russian Health Crisis Start.Microcomputer Strategies for Answer)
• 05000324/LER-1981-097-03, When Reactor Recirculation Pump 2A Tripped,No Annunciators Received. Caused by Intermittently Sticking Contacts of Logic Channels a & C.Switch Replaced  + (When Reactor Recirculation Pump 2A Tripped,No Annunciators Received. Caused by Intermittently Sticking Contacts of Logic Channels a & C.Switch Replaced)
• 05000254/LER-1979-034-03, While Adding Nitrogen to Suppression Chamber & After Decreasing Differential Pressure,Suppression Pool Level Noted Below Limit.Caused by Slow Response by Chamber Narrow Range Instrumentation  + (While Adding Nitrogen to Suppression Chamber & After Decreasing Differential Pressure,Suppression Pool Level Noted Below Limit.Caused by Slow Response by Chamber Narrow Range Instrumentation)
• 05000237/LER-1981-060-03, While Changing Power, Daily Offgas Sample Showed Ratio of Long to short-lived Isotopes Violated Tech Spec,But Violation Not Recognized. Caused by Change in Power.Data Sheet Changed  + (While Changing Power, Daily Offgas Sample Showed Ratio of Long to short-lived Isotopes Violated Tech Spec,But Violation Not Recognized. Caused by Change in Power.Data Sheet Changed)
• ML18283B081  + (While Conducting Functional Test Which Required Interruption of RPS Power Supply Water Level on Unit 2 Decreased to 544 Inches Above Vessel Zero Due to Closure of RHR Injection Valve & Subsequent Opening of .)
• 05000293/LER-1980-058-03, While Conducting HPCI Sys Test,Hpci Sys Declared Inoperable.Possibly Caused by Dirt Which Caused Temporary Malfunction of Turbine Throttle Valve.Tests by Factory Representative Satisfactory  + (While Conducting HPCI Sys Test,Hpci Sys Declared Inoperable.Possibly Caused by Dirt Which Caused Temporary Malfunction of Turbine Throttle Valve.Tests by Factory Representative Satisfactory)
• 05000333/LER-1982-051-03, While Conducting Surveillance Testing on Reactor Low Water Scram Switch 02-3-LIS-101D,setpoint Found Less Conservative than Required.Caused by Instrument Drift.Setpoint Adjusted  + (While Conducting Surveillance Testing on Reactor Low Water Scram Switch 02-3-LIS-101D,setpoint Found Less Conservative than Required.Caused by Instrument Drift.Setpoint Adjusted)
• 05000369/LER-1983-011-01, While Core Unloaded During Fuel Assembly insp,21 of 94 Nonfuel Bearing Components Equipped W/Same Spring Design Discovered W/Broken Holddown Springs.Caused by Design Deficiency  + (While Core Unloaded During Fuel Assembly insp,21 of 94 Nonfuel Bearing Components Equipped W/Same Spring Design Discovered W/Broken Holddown Springs.Caused by Design Deficiency)
• 05000366/LER-1980-008-03, While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change  + (While Increasing Reactor Power by Rod Withdrawal,Operator Noticed Rod Select Matrix Backlighted & Rod Sequence Control Sys Not Initiating Rod Blocks Properly.Caused by Design Change)
• 05000250/LER-1981-013-03, While Making Alterations to Equipment Hatch Ramp,Small Void in Concrete Immediately Below Equipment Hatch Barrel Discovered.Probably Caused by Design Problem.Concrete Void Repaired  + (While Making Alterations to Equipment Hatch Ramp,Small Void in Concrete Immediately Below Equipment Hatch Barrel Discovered.Probably Caused by Design Problem.Concrete Void Repaired)
• 05000366/LER-1980-141-03, While Making Power Changes from 2,180 to 1,980 MWt,N004 HPCI Steam Line Dp Switch Found to Actuate at 198 Inches Water.Caused by Setpoint Drift.Switch Recalibr  + (While Making Power Changes from 2,180 to 1,980 MWt,N004 HPCI Steam Line Dp Switch Found to Actuate at 198 Inches Water.Caused by Setpoint Drift.Switch Recalibr)
• 05000321/LER-1980-096-03, While Operating at 2,389 Mwt,All Points of Drywell Temp Recorder R612 Found Reading High.Caused by Instrument Drift.Instrument Recalibr & Tested.Design Change Implemented Replacing Recorder  + (While Operating at 2,389 Mwt,All Points of Drywell Temp Recorder R612 Found Reading High.Caused by Instrument Drift.Instrument Recalibr & Tested.Design Change Implemented Replacing Recorder)
• 05000237/LER-1981-036-03, While Performing Auto Blowdown Permissive Surveillance 287-1,pressure Switch PS3-1554E Would Not Operate at Required Pressure.Caused by Plugged Instrument Snubber.Snubber Cleaned  + (While Performing Auto Blowdown Permissive Surveillance 287-1,pressure Switch PS3-1554E Would Not Operate at Required Pressure.Caused by Plugged Instrument Snubber.Snubber Cleaned)
• 05000324/LER-1982-064-03, While Performing Diesel Generator 3 Monthly Load test,PT-12.2C,diesel Tripped & Locked Out Due to Increase in Temp.Caused by Closed Diesel Jacket Water HX Inlet Valve.Valve Reopened  + (While Performing Diesel Generator 3 Monthly Load test,PT-12.2C,diesel Tripped & Locked Out Due to Increase in Temp.Caused by Closed Diesel Jacket Water HX Inlet Valve.Valve Reopened)
• 05000324/LER-1981-143-03, While Performing Diesel Generator 4 Monthly Load Test,Model F5-1316-HS6 Would Not Assure Steady Load Greater than 1,000 Kw.Cause Undetermined.Diesel Generator Returned to Svc  + (While Performing Diesel Generator 4 Monthly Load Test,Model F5-1316-HS6 Would Not Assure Steady Load Greater than 1,000 Kw.Cause Undetermined.Diesel Generator Returned to Svc)