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Title: Human Reliability Implementation Guide

Authors:
 [1];  [1]
  1. ORNL
Publication Date:
Research Org.:
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Sponsoring Org.:
Work for Others (WFO)
OSTI Identifier:
1154850
Report Number(s):
ORNL/TM-2014/292
400809000
DOE Contract Number:
DE-AC05-00OR22725
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English

Citation Formats

Coates, Cameron W, and Eisele, Gerhard R. Human Reliability Implementation Guide. United States: N. p., 2014. Web. doi:10.2172/1154850.
Coates, Cameron W, & Eisele, Gerhard R. Human Reliability Implementation Guide. United States. doi:10.2172/1154850.
Coates, Cameron W, and Eisele, Gerhard R. Fri . "Human Reliability Implementation Guide". United States. doi:10.2172/1154850. https://www.osti.gov/servlets/purl/1154850.
@article{osti_1154850,
title = {Human Reliability Implementation Guide},
author = {Coates, Cameron W and Eisele, Gerhard R},
abstractNote = {},
doi = {10.2172/1154850},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Aug 01 00:00:00 EDT 2014},
month = {Fri Aug 01 00:00:00 EDT 2014}
}

Technical Report:

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  • The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability (HEP) and hardware component failure data (HCFD). The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. Users can perform data base searches to furnish HEP estimates and HCFD rates. In this manner, the NUCLARR system can be used to support a variety of risk assessment activities. This volume, Volume 3 of a 5-volume series, presents the procedures used to process HEP and HCFD for entry in NUCLARR and describes how to modify the existingmore » NUCLARR taxonomy in order to add either equipment types or action verbs. Volume 3 also specifies the various roles of the administrative staff on assignment to the NUCLARR Clearinghouse who are tasked with maintaining the data base, dealing with user requests, and processing NUCLARR data. 5 refs., 34 figs., 3 tabs.« less
  • Martin Marietta Energy Systems, Inc., (MMES) is engaged in a phased program to update the MMES safety documentation for the existing DOE facilities it manages. This guidance for Human Reliability Analysis (HRA) is intended for use in probabilistic safety analysis of DOE facilities. It is intended to supplement the Facility Safety Evaluation Application Guide, CSET-10, (July 1991), and subsequent revisions. The primary intended use of the guidance is to support accident analysis in Phase II of the Energy Systems Safety Analysis Report Update Program (SARUP). However, the guidance can be used for any safety analysis that needs human reliability analysis.more » The human reliability analysis methods covered by how-to'' sections of the guide are direct application of or adaptations of methods developed for Probabilistic Risk Assessments (PRA) of nuclear power plants. The adaptations of these methods were designed to make the methods more suitable to DOE non-reactor applications. The methods have been adapted for use by the personnel who will perform the accident analysis task. This has been done by furnishing guidance intended for accident analysts who are experienced in human reliability analysis and by providing various methods of several levels of complexity and sophistication that lend themselves to a graded approach. The methods also lend themselves to progressive, iterative refinement so that the more burdensome versions of the methods may be reserved for use only when the importance to safety of the human reliability issues clearly warrants the time and effort. The recommended techniques build upon logic models of the human interactions with the facility that contribute to accident sequences. The recommended techniques employ assessments of a catalog of Performance Shaping Factors (PSFs) that influence the reliability of operating crews in carrying out their activities.« less
  • Martin Marietta Energy Systems, Inc., (MMES) is engaged in a phased program to update the MMES safety documentation for the existing DOE facilities it manages. This guidance for Human Reliability Analysis (HRA) is intended for use in probabilistic safety analysis of DOE facilities. It is intended to supplement the Facility Safety Evaluation Application Guide, CSET-10, (July 1991), and subsequent revisions. The primary intended use of the guidance is to support accident analysis in Phase II of the Energy Systems Safety Analysis Report Update Program (SARUP). However, the guidance can be used for any safety analysis that needs human reliability analysis.more » The human reliability analysis methods covered by ``how-to`` sections of the guide are direct application of or adaptations of methods developed for Probabilistic Risk Assessments (PRA) of nuclear power plants. The adaptations of these methods were designed to make the methods more suitable to DOE non-reactor applications. The methods have been adapted for use by the personnel who will perform the accident analysis task. This has been done by furnishing guidance intended for accident analysts who are experienced in human reliability analysis and by providing various methods of several levels of complexity and sophistication that lend themselves to a graded approach. The methods also lend themselves to progressive, iterative refinement so that the more burdensome versions of the methods may be reserved for use only when the importance to safety of the human reliability issues clearly warrants the time and effort. The recommended techniques build upon logic models of the human interactions with the facility that contribute to accident sequences. The recommended techniques employ assessments of a catalog of Performance Shaping Factors (PSFs) that influence the reliability of operating crews in carrying out their activities.« less
  • To assess adequately the impact of human performance on nuclear power plant reliability using probabilistic risk assessment (PRA) techniques, the US Nuclear Regulatory Commission determined that a human reliability data bank should be developed. Sandia National Laboratories contracted with General Physics Corporation to (1) determine the applicability of existing human reliability data banks to nuclear power plant PRAs, and (2) develop a concept for a human reliability data bank and a program for its implementation. The results of the first task are given in Volume 1 of NUREG/CR-2744, while Volume 2 of the same NUREG contains the results of themore » data bank concept development task. This report describes a survey and comparative analysis of previous and current attempts to quantify and predict human operator and maintainer performance as a function of design, training, procedural, or situational factors. An assessment was made of these methods and techniques as to their potential applicability to PRA and as a supplement to the data and procedures in NUREG/CR-1278. Five previously established human reliability data banks were reviewed along with five current systems, all of which inlcude estimates of human error related events. The data banks were evaluated against a set of criteria intended to serve as guidelines for an idealized human reliability data reporting, storage, and retrieval system. It was concluded that insufficient data currently exist in these systems to adequately support nuclear PRA activities, and it was therefore recommended that a human reliability data bank specific to nuclear power plant PRA applications be developed. The appendices to Volume 1 reproduce the previously established data banks in their entirety and selected tables from currently existing data banks.« less
  • The Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR) is an automated data base management system for processing and storing human error probability and hardware component failure data. The NUCLARR system software resides on an IBM (or compatible) personal micro-computer. NUCLARR can be used by the end user to furnish data inputs for both human and hardware reliability analysis in support of a variety of risk assessment activities. The NUCLARR system is documented in a five-volume series of reports. Volume IV of this series is the User's Guide for operating the NUCLARR software and is presented in three parts. Thismore » volume, Part 2: Guide to Operations, contains the instructions and basic procedures for using the NUCLARR software. Part 2 provides guidance and information for getting started, performing the desired functions, and making the most efficient use of the system's features.« less