Active Standard

IEEE 1082-2017

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

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.

Sponsor Committee
PE/NPE - Nuclear Power Engineering
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Status
Active Standard
PAR Approval
2012-03-29
Superseding
1082-1997
Board Approval
2017-12-06
History
Published:
2018-04-09

Working Group Details

Society
IEEE Power and Energy Society
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Sponsor Committee
PE/NPE - Nuclear Power Engineering
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Working Group
WG_5.3 - Human Performance and Reliability
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IEEE Program Manager
Christian Orlando
Contact
Working Group Chair
Ron Boring
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1707-2015

IEEE Recommended Practice for the Investigation of Events at Nuclear Facilities

Common terminology and recommended practices for initiating and conducting event investigations, analyzing data, producing results, and identifying corrective actions associated with facility personnel, processes, equipment, and systems at nuclear facilities are provided in this document. The scope of event investigation activities addressed includes, but is not limited to, root cause analysis, which is an in depth investigation process used to identify primary causes of an event based on the systematic and consistent use of analysis tools. This recommended practice can be used for the investigation of all events and allows the use of a graduated approach to the depth of the investigation based upon the event significance.

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No Superseded Standards
No Inactive-Withdrawn Standards
No Inactive-Reserved Standards
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