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/NPEC - Nuclear Power Engineering Committee
Learn More About PE/NPEC - Nuclear Power Engineering Committee - 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
Learn More About IEEE Power and Energy Society - Sponsor Committee
- PE/NPEC - Nuclear Power Engineering Committee
Learn More About PE/NPEC - Nuclear Power Engineering Committee - Working Group
-
WG_5.3 - Human Performance and Reliability
- IEEE Program Manager
- Christian Orlando
Contact Christian Orlando - Working Group Chair
- Jeffrey JOE
Other Activities From This Working Group
Current projects that have been authorized by the IEEE SA Standards Board to develop a standard.
P1707
Recommended Practice for the Investigation of Events at Nuclear Facilities
This document provides common terminology and recommended practices for initiating and conducting event investigations related to personnel, processes, equipment, and systems at nuclear facilities, including: analyzing data, producing results, and identifying corrective actions.
Standards approved by the IEEE SA Standards Board that are within the 10-year lifecycle.
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.
These standards have been replaced with a revised version of the standard, or by a compilation of the original active standard and all its existing amendments, corrigenda, and errata.
No Superseded Standards
These standards have been removed from active status through a ballot where the standard is made inactive as a consensus decision of a balloting group.
No Inactive-Withdrawn Standards
These standards are removed from active status through an administrative process for standards that have not undergone a revision process within 10 years.
No Inactive-Reserved Standards