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.
- Sponsor Committee
- PE/NPE - Nuclear Power Engineering
Learn More - Status
- Active Standard
- PAR Approval
- 2012-03-29
- Board Approval
- 2015-10-26
- History
-
- ANSI Approved:
- 2017-03-16
- Published:
- 2015-12-30
Working Group Details
- Society
- IEEE Power and Energy Society
Learn More - Sponsor Committee
- PE/NPE - Nuclear Power Engineering
Learn More - Working Group
-
WG_5.3 - Human Performance and Reliability
Learn More - IEEE Program Manager
- Christian Orlando
Contact - Working Group Chair
- Ron Boring
No Active Projects
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.
No Superseded Standards
No Inactive-Withdrawn Standards
No Inactive-Reserved Standards