Add to ORKGProbabilistic risk assessments (PRA) based on internal initiators are being conducted on a number of reference plants in order to provide the Nuclear Regulatory Commission (NRC) with updated information about light water reactor risk. The results of these analyses will be used by the NRC to prepare NUREG-1150 which will examine the NRC's current perception of risk. Peach Bottom has been chosen as one of the reference plants
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
This report is a brief summary of risk science, which provides a good tool to understand quantitativ...
This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submitta...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
This paper summarizes the findings of an investigation of four probabilistic risk assessments (PRAs)...
This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for th...
During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exam...
In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe acciden...
During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exa...
The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to ...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This report describes a methodology for analyzing the safety of nuclear power plants. A historical o...
A letter report issued by the Government Accountability Office with an abstract that begins "The Nuc...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
This report is a brief summary of risk science, which provides a good tool to understand quantitativ...
This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submitta...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
This document contains the appendices for the accident sequence analysis of internally initiated eve...
In November 1988, the US Nuclear Regulatory Commission (NRC) issued Generic Letter 88-20 requesting ...
This paper summarizes the findings of an investigation of four probabilistic risk assessments (PRAs)...
This report presents the final results from the Level 1 probabilistic safety assessment (PSA) for th...
During 1989 the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exam...
In support of the Nuclear Regulatory Commission's (NRC's) assessment of the risk from severe acciden...
During 1989, the Nuclear Regulatory Commission (NRC) initiated an extensive program to carefully exa...
The U.S. Nuclear Regulatory Commission’s standardized plant analysis risk (SPAR) models are used to ...
The Nuclear Regulatory Commission`s (NRC`s) ongoing Accident Sequence Precursor (ASP) program uses p...
This report describes a methodology for analyzing the safety of nuclear power plants. A historical o...
A letter report issued by the Government Accountability Office with an abstract that begins "The Nuc...
It is sometimes the case in PRA applications that reported plant-specific failure data are, in fact,...
This report is a brief summary of risk science, which provides a good tool to understand quantitativ...
This report provides perspectives gained by reviewing 75 Individual Plant Examination (IPE) submitta...