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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

• ML20111B424  + (Reactor Safety Research Programs.Quarterly Report,July- September 1984)
• ML20050A672  + (Reactor Safety Research Programs.Quarterly Report,October- December 1981)
• ML20091K136  + (Reactor Safety Research Programs.Quarterly Report,October- December 1983)
• ML20126C424  + (Reactor Safety Research Programs.Quarterly Report,October- December 1984)
• ML19345D258  + (Reactor Safety Research Programs.Quarterly Report.April-June 1980)
• ML19340C516  + (Reactor Safety Research Programs.Quarterly Report.January- March 1980)
• ML20072N904  + (Reactor Safety Research Programs.Quarterly Report.July - September 1982)
• ML20008F762  + (Reactor Safety Research Programs.Quarterly Report.October- December 1980)
• ML20097F225  + (Reactor Safety Research Quarterly REPORT.April-June 1983)
• ML20097E993  + (Reactor Safety Research Quarterly REPORT.January-March 1983)
• ML20107L876  + (Reactor Safety Research Quarterly REPORT,JULY-SEPTEMBER 1983 and OCTOBER-DECEMBER 1983.Volumes 27 and 28)
• ML20138Q653  + (Reactor Safety Research Semiannual REPORT.January-June 1985.Volume 33)
• ML20236C513  + (Reactor Safety Research Semiannual REPORT.January-June 1986. Volume 35)
• ML20150A655  + (Reactor Safety Research Semiannual REPORT.January-June 1987. Volume 37)
• ML20210L939  + (Reactor Safety Research Semiannual REPORT.July-December 1985)
• ML20133P906  + (Reactor Safety Research Summary of Activities & Results - FY84 for Nrc)
• ML20113E619  + (Reactor Safety Research.Quarterly Report,April-June 1984)
• ML20114C188  + (Reactor Safety Research.Quarterly Report,January-March 1984)
• ML20128L794  + (Reactor Safety Research.Quarterly Report,July-September 1984)
• ML20137W683  + (Reactor Safety Research.Quarterly Report,October-December 1984)
• ML20039D695  + (Reactor Safety Study Methodology Applications Program: Grand Gulf NO.1 BWR Power Plant)
• ML20054H428  + (Reactor Safety Study Methodology Applications Program: Calvert Cliffs No. 2 PWR Power Plant)
• ML19345H293  + (Reactor Safety Study Methodology Applications Program: Sequoyah 1 PWR Power Plant)
• ML20039F034  + (Reactor Safety Study Methodology Applications Program: Oconee 3 PWR Power Plant)
• ML20041A775  + (Reactor Safety Study:Assessment of Accident Risks in Us Commercial Nuclear Power Plants, Executive Summary)

• ML20004F950  + (Reactor Safety System Design Using Hardened Computers)

• ML20154K285  + (Reactor Safety in Us:Regulatory Perspective. Paper Presented on 861106 at Italian Committee on Nuclear Risk & Intl Scientific Culture & World Lab in Rome,Italy)
• ML23248A214  + (Reactor Safety: Regulatory Objectives & Framework)
• ENS 43784  + (Reactor Scram - Initiation of Ari Caused by Level 2 Signal)
• ENS 43049  + (Reactor Scram - Loss of Instrument Air Resulting in Feedwater Transient and Manual Reactor Scram)
• ENS 54855  + (Reactor Scram After Loss of Feedwater - Grand Gulf)
• ENS 46582  + (Reactor Scram After a Main Transformer Trip)
• ENS 49888  + (Reactor Scram Due to Actuation of the Alternate Rod Insertion System)
• ENS 50916  + (Reactor Scram Due to Aprm Hi Hi Signal)
• ENS 45990  + (Reactor Scram Due to Closure of Main Steam Isolation Valves)
• ENS 42986  + (Reactor Scram Due to Conductivity Excursion)
• 05000353/LER-2005-004, Reactor Scram Due to EHC Malfunction That Closed the Main Turbine Control Valves  + (Reactor Scram Due to EHC Malfunction That Closed the Main Turbine Control Valves)
• 05000354/LER-2003-007, Reactor Scram Due to Electrical Transient, Low Reactor Water Level and Loss of Reactor Feed Pumps a and C  + (Reactor Scram Due to Electrical Transient, Low Reactor Water Level and Loss of Reactor Feed Pumps a and C)
• NG-95-1893, Reactor Scram Due to FW Pump Trip Caused by Lube Oil Pump Coupling Failure.Maint Procedure, Vendor Manual & Plant Drawings for FW Pumps Being Revised to Ensure Proper Lubrication of Subj Coupling  + (Reactor Scram Due to FW Pump Trip Caused by Lube Oil Pump Coupling Failure.Maint Procedure, Vendor Manual & Plant Drawings for FW Pumps Being Revised to Ensure Proper Lubrication of Subj Coupling)
• ENS 49928  + (Reactor Scram Due to Failure to Control Main Turbine Moisture Separator Level)
• 05000237/FIN-2015002-03  + (Reactor Scram Due to Feedwater Level Control System Failure with a Reactor Recirculation Pump Runback)
• 05000416/LER-2023-002, Reactor Scram Due to Generator Stator Fault to Ground  + (Reactor Scram Due to Generator Stator Fault to Ground)
• 05000259/LER-2024-002, Reactor Scram Due to Generator Step-Up Transformer Failure  + (Reactor Scram Due to Generator Step-Up Transformer Failure)
• ENS 41741  + (Reactor Scram Due to Generator Trip/Turbine Trip Following Offsite Electical Transient)
• ENS 41252  + (Reactor Scram Due to Loss of Vital Instrument Bus)
• 05000260/LER-2025-001, Reactor Scram Due to Low Electro-Hydraulic Control Pressure  + (Reactor Scram Due to Low Electro-Hydraulic Control Pressure)
• 05000260/LER-2025-001-01, Reactor Scram Due to Low Electro-Hydraulic Control Pressure  + (Reactor Scram Due to Low Electro-Hydraulic Control Pressure)
• ENS 43159  + (Reactor Scram Due to Low Reactor Water Level)
• ENS 51112  + (Reactor Scram Due to Low Reactor Water Level)
• 05000259/LER-2025-001, Reactor Scram Due to Low Reactor Water Level  + (Reactor Scram Due to Low Reactor Water Level)
• 05000416/LER-2008-002, Reactor Scram Due to Main Generator Trip Caused by Unit Differential Lockout  + (Reactor Scram Due to Main Generator Trip Caused by Unit Differential Lockout)