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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

• 05000334/LER-1981-048-03, While Putting RHR Sys in Operation,One RHR Pump Suction Valve Would Not Open.Cause Unknown.Adjustment Made to Torque Switch Bypass Limit Switch & All Wiring Connections Inspected  + (While Putting RHR Sys in Operation,One RHR Pump Suction Valve Would Not Open.Cause Unknown.Adjustment Made to Torque Switch Bypass Limit Switch & All Wiring Connections Inspected)
• 05000263/LER-1981-017-03, While Removing Insulation,Cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup HX Piping,Where Connected to Hx.Caused by Poor fit-up & Welding.Slag Line Removed & Weld Repaired  + (While Removing Insulation,Cracks Discovered on 4-inch & 1-inch Reactor Water Cleanup HX Piping,Where Connected to Hx.Caused by Poor fit-up & Welding.Slag Line Removed & Weld Repaired)
• 05000316/LER-1979-026-03, While Reviewing Axial Power Distribution Monitoring Sys,Two Occasions Were Discovered in Which Only One Detector Scan Was Printed Out. Cause Undetermined.Investigation Closed  + (While Reviewing Axial Power Distribution Monitoring Sys,Two Occasions Were Discovered in Which Only One Detector Scan Was Printed Out. Cause Undetermined.Investigation Closed)
• 05000280/LER-1979-031-03, While Reviewing Liquid Waste Release Forms,Discovered That Liquid Waste Monitor Did Not Alarm High & Trip Release Valve During 791117 Isotope Activity Release.Caused by Personnel Error  + (While Reviewing Liquid Waste Release Forms,Discovered That Liquid Waste Monitor Did Not Alarm High & Trip Release Valve During 791117 Isotope Activity Release.Caused by Personnel Error)
• 05000366/LER-1980-162-03, While Reviewing Local Leak Rate Test Data on Vent Purge Outlet Isolation Valve 2T48-F318,leakage Determined to Exceed Allowable Tech Spec Limits.Caused by Worn Seat Rings.Rings Replaced  + (While Reviewing Local Leak Rate Test Data on Vent Purge Outlet Isolation Valve 2T48-F318,leakage Determined to Exceed Allowable Tech Spec Limits.Caused by Worn Seat Rings.Rings Replaced)
• 05000364/LER-1983-039-01, While Securing Steam to Turbine Bldg as Part of Normal Shutdown,Msivs Q2N11V001B, 1C & 2B Initially Failed to Close Under no-flow Conditions. Caused by Binding in Valve Packing  + (While Securing Steam to Turbine Bldg as Part of Normal Shutdown,Msivs Q2N11V001B, 1C & 2B Initially Failed to Close Under no-flow Conditions. Caused by Binding in Valve Packing)
• 05000321/LER-1982-095-03, While Shut Down for Refueling/Torus Mod Outage,Various Containment Isolation Valves Did Not Have Acceptable Results During Local Leak Rate Testing.Valves Repaired to Meet Tech Specs  + (While Shut Down for Refueling/Torus Mod Outage,Various Containment Isolation Valves Did Not Have Acceptable Results During Local Leak Rate Testing.Valves Repaired to Meet Tech Specs)
• 05000302/LER-1983-044-01, While Switching from Air Handling Fans AHF-14B & D to AHF-14A & C Due to Low flow,AHF-14A & C Would Not Start.Caused by Failed Damper Solenoid Valve & Metal Fatigue  + (While Switching from Air Handling Fans AHF-14B & D to AHF-14A & C Due to Low flow,AHF-14A & C Would Not Start.Caused by Failed Damper Solenoid Valve & Metal Fatigue)
• 05000251/LER-1980-003-03, While Testing 4C Steam Generator Feedwater Control Valve,Change in Steam Generator Level Lifted Low Setpoint Valve.Valve Did Not Fully Reseat. Caused by Binding Between Lifting Gear & Release Nut  + (While Testing 4C Steam Generator Feedwater Control Valve,Change in Steam Generator Level Lifted Low Setpoint Valve.Valve Did Not Fully Reseat. Caused by Binding Between Lifting Gear & Release Nut)
• 05000254/LER-1981-019-03, While Testing HPCI Operability,During Motor Speed Changer Control Linkage Adjustments,Torus Level Approached Tech Spec Limit.Testing Continued Until Operability Verified  + (While Testing HPCI Operability,During Motor Speed Changer Control Linkage Adjustments,Torus Level Approached Tech Spec Limit.Testing Continued Until Operability Verified)
• 05000321/LER-1981-094-03, While Testing Standby Gas Treatment Filter Train A,Train Would Not Remove Greater than or Equal to 99% of Halogenated Hydrocarbon Gas,Per Tech Specs.Caused by Defective Charcoal  + (While Testing Standby Gas Treatment Filter Train A,Train Would Not Remove Greater than or Equal to 99% of Halogenated Hydrocarbon Gas,Per Tech Specs.Caused by Defective Charcoal)
• 05000416/LER-1983-112-03, While Troubleshooting Nssss/Eccs Initiation Circuitry Re Improper Operation of E12F087B & F025B,partial LOCA Occurred.Caused by Error in Work Order.Changes Underway  + (While Troubleshooting Nssss/Eccs Initiation Circuitry Re Improper Operation of E12F087B & F025B,partial LOCA Occurred.Caused by Error in Work Order.Changes Underway)
• 05000335/LER-1980-046-03, While at 100% Power, Control Element Assembly 33 Dropped to Fully Inserted Position.Caused by Failed 15-volt Dc Power Supply in Coil Power Programmer.Power Supply Replaced  + (While at 100% Power, Control Element Assembly 33 Dropped to Fully Inserted Position.Caused by Failed 15-volt Dc Power Supply in Coil Power Programmer.Power Supply Replaced)
• 05000295/LER-1983-017-03, While at 78% Power & MSIV Partial Close Test (PT-3D) in Progress,High Steam Flow Safety Injection Occurred & MSIV 1D Found Open.Caused by MSIV Test Switch in Reset Position  + (While at 78% Power & MSIV Partial Close Test (PT-3D) in Progress,High Steam Flow Safety Injection Occurred & MSIV 1D Found Open.Caused by MSIV Test Switch in Reset Position)
• 05000416/LER-1983-068-01, While in Cold Shutdown, Discrepancy Identified Between Tech Specs & FSAR Re Secondary Containment Ventilation Isolation Damper Closure Time.Cause Unknown  + (While in Cold Shutdown, Discrepancy Identified Between Tech Specs & FSAR Re Secondary Containment Ventilation Isolation Damper Closure Time.Cause Unknown)
• 05000295/LER-1980-002-03, While in Cold Shutdown, Fire Sump Pump Radiation Monitor ORT-PR25 Was Bypassed Resulting in Failure of Fire Sump Pumps.Caused by Sand Accumulation in Sump.Sparger Sys Installed  + (While in Cold Shutdown, Fire Sump Pump Radiation Monitor ORT-PR25 Was Bypassed Resulting in Failure of Fire Sump Pumps.Caused by Sand Accumulation in Sump.Sparger Sys Installed)
• 05000416/LER-1983-062-03, While in Cold Shutdown, Limiting Condition for Operation Entered Under Tech Spec 3.8.1.2 Due to Inoperability of Diesel Generators.Caused by Binding Linkage to Fuel Injector Pump  + (While in Cold Shutdown, Limiting Condition for Operation Entered Under Tech Spec 3.8.1.2 Due to Inoperability of Diesel Generators.Caused by Binding Linkage to Fuel Injector Pump)
• 05000305/LER-1982-009-03, While in Hot Shutdown Prior to Scheduled Refueling Outage,Both Source Range Nuclear Instruments Determined Inoperable.Caused by Water Accumulation in Instrument Canisters  + (While in Hot Shutdown Prior to Scheduled Refueling Outage,Both Source Range Nuclear Instruments Determined Inoperable.Caused by Water Accumulation in Instrument Canisters)
• 05000316/LER-2076-058, While in Mode 1 at 91 Percent Power, the Wind Speed Transmitter Appeared to Be Frozen  + (While in Mode 1 at 91 Percent Power, the Wind Speed Transmitter Appeared to Be Frozen)
• 05000395/LER-1983-091-03, While in Mode 1,borated Water Vol of Accumulator a Decreased to 7,354 Gallons.Caused by Leakage Through Valves in ECCS Check Valve Leak Detection Sys  + (While in Mode 1,borated Water Vol of Accumulator a Decreased to 7,354 Gallons.Caused by Leakage Through Valves in ECCS Check Valve Leak Detection Sys)
• 05000361/LER-1982-165-03, While in Mode 1,two Snubbers Observed Damaged & Declared Inoperable.On 821222, Three Addl Snubbers Found Damaged & Declared Inoperable. Caused by Startup Testing.Snubbers Replaced  + (While in Mode 1,two Snubbers Observed Damaged & Declared Inoperable.On 821222, Three Addl Snubbers Found Damaged & Declared Inoperable. Caused by Startup Testing.Snubbers Replaced)
• 05000327/LER-1983-063-03, While in Mode 3,following Maint,Porv 1-PCV-68-340 Found Leaking.Caused by Associated Block Valve Not Closing Fully.Porvs Will Be Replaced During Refueling Outage  + (While in Mode 3,following Maint,Porv 1-PCV-68-340 Found Leaking.Caused by Associated Block Valve Not Closing Fully.Porvs Will Be Replaced During Refueling Outage)
• 05000369/LER-1983-061-03, While in Mode 3,radiation Monitor EMF-17 Was in Alarm Due to Increase in General Background Activity.Caused by Receipt of Spent Fuel from Oconee.Trip Setpoints Set Higher  + (While in Mode 3,radiation Monitor EMF-17 Was in Alarm Due to Increase in General Background Activity.Caused by Receipt of Spent Fuel from Oconee.Trip Setpoints Set Higher)
• 05000315/LER-1981-052-03, While in Mode 3,two Containment Isolation Valves on Demineralized Water Header DW-209 & DW-210 Were Opened by Personnel.Caused by Personnel Error.Retraining on Proper Procedures Conducted  + (While in Mode 3,two Containment Isolation Valves on Demineralized Water Header DW-209 & DW-210 Were Opened by Personnel.Caused by Personnel Error.Retraining on Proper Procedures Conducted)
• ML20210S442  + (Whipjet Program Final Rept)

• ML20211F244  + (Whipjet Program Rept)

• ML20237B591  + (White Book for PWR Nuclear Safety)
• ML19112A296  + (White Findings Data)
• ML090540610  + (White Paper - Inclusion of Regulatory Guide 1.177 Tier 2 Consideration in TSTF-423-A and in Technical Specifications Required Actions Email from Excel)
• ML22252A192  + (White Paper - Licensing and Regulating Fusion Energy Systems)
• ML21139A232  + (White Paper - Perspective on an Independent Shift Technical Advisor)
• ML21118A081  + (White Paper - Preliminary Options for a Regulatory Framework for Fusion Energy Systems)
• ML25114A020  + (White Paper - Risk Informed Materials Assessment Project Draft - Preparing Risk Informed Materials Engineering Submittals)
• ML18016A125  + (White Paper Addressing the Impact of CCF and Application of Qualitative R1)
• ML25246A727  + (White Paper Dated August 18, 2025 - Subcritical Systems - Energy Amplifier)
• ML063460388  + (White Paper Email from Brian Sepelak)
• ML20069H437  + (White Paper Fastner Strength Analysis Nuclear Safety Concern 93-11)
• ML16131A655  + (White Paper Prepared in Response to a Question Raised During the Audit)
• ML090540595  + (White Paper Received from Excel Corporation Inclusion of Regulatory Guide 1.177 Tier 2 Considerations in TSTF-423-A and in Technical Specifications Required Actions)
• ML072420447  + (White Paper Testing of Dynamic Soil Properties for Nuclear Power Plant COL Applications)
• ML20028F034  + (White Paper Xix, Our Marble Hill Problem)
• ML18106A080  + (White Paper from William Kerr - Development of Containment Performance Criteria for Light Water Power Reactors)
• ML22341A073  + (White Paper on - the Enduring Legacy of ACRS - Contributing to Safety-Licensing Review of Reactor Facilities)
• ML22355A073  + (White Paper on - the Enduring Legacy of ACRS - Contributing to Safety-Licensing Review of Reactor Facilities)
• NUREG-1829, White Paper on Continued Applicability of NUREG-1829  + (White Paper on Continued Applicability of NUREG-1829)
• NUREG-1903, White Paper on Continued Applicability of NUREG-1903  + (White Paper on Continued Applicability of NUREG-1903)
• ML20106F034  + (White Paper on RIPB Approach to Seismic Safety)
• ML26008A304  + (White Paper on Strategic Environmental Report Framework)
• ML19241A545  + (White Paper on Suggested Content for Pfm Submittal to the NRC)
• ML22318A241  + (White Paper on U.S. Nuclear Regulatory Commission Update on Recent Developments in Digital I&C for New Builds or Plant Upgrades)
• ML25150A388  + (White Paper on the Blue Energy Integrated Monopile System (IMS))