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IEEE 1082-2017

IEEE Guide for Incorporating Human Reliability Analysis into Probabilistic Risk Assessments for Nuclear Power Generating Stations and Other Nuclear Facilities

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IEEE 1082-2017

IEEE Guide for Incorporating Human Reliability Analysis into Probabilistic Risk Assessments for Nuclear Power Generating Stations and Other Nuclear Facilities

PUBLISH DATE 2018

PAGES 34

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Revision Standard - Active. A structured framework for the incorporation of human reliability analysis (HRA) into probabilistic risk assessments (PRAs) is provided in this guide. To enhance the analysis of human/system interactions in PRAs, to help ensure reproducible conclusions, and to standardize the documentation of such assessments are the purposes of this guide. To do this, a specific HRA framework is developed from standard practices. The HRA framework is neutral with respect to specific HRA methods.

This guide provides a structured framework for the incorporation of human reliability analysis (HRA) into probabilistic risk assessments (PRAs).

The purpose of this guide is to enhance the analysis of human-system interactions in PRAs, to help ensure reproducible conclusions, and to standardize the documentation of such assessments. To do this, a specific HRA framework is developed from standard practices to serve as a benchmark to assess alternative ways of incorporating HRA into PRA.


SDO	IEEE: Institute of Electrical and Electronics Engineers
Document Number	1082
Publication Date	April 9, 2018
Language	en - English
Page Count	34
Revision Level
Supercedes
Committee	Nuclear Power Engineering Committee

Publish Date	Document Id	Type	View
April 9, 2018	1082-2017	Revision
Nov. 30, 1996	1082-1997	Revision

SDO	Document	Title
BSI	BS IEC 63260	Guide for incorporating human reliability analysis into probabilistic risk assessments for nuclear power generating stations and other nuclear facilities
IEC	IEC 63260	Guide for incorporating human reliability analysis into probabilistic risk assessments for nuclear power generating stations and other nuclear facilities
IEEE	IEEE 352	IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
IEEE	IEEE 1792	IEEE Recommended Practice for Nuclear Power Generating Station Preferred Power Supply Reliability
IEEE	IEEE 352/N41.4	Draft American National Standard - IEEE Trial-Use Guide: General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems
IEEE	IEEE 1786	IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities
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IEEE 1082-2017

IEEE Guide for Incorporating Human Reliability Analysis into Probabilistic Risk Assessments for Nuclear Power Generating Stations and Other Nuclear Facilities

IEEE 1082-2017

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