				Search Options
Index \| Site Map \| FAQ \| Facility Info \| Reading Rm \| New \| Help \| Glossary \| Contact Us

Good Practices for Implementing Human Reliability Analysis (HRA) (NUREG-1792)

On this page:

Publication Information
Abstract

The following links on this page are to documents in Adobe Portable Document Format (PDF). See our Plugins, Viewers, and Other Tools page for more information. For successful viewing of PDF documents on our site please be sure to use the latest version of Adobe.

NUREG-1792 (PDF - 3.92 MB)

Publication Information

Manuscript Completed: April 2005
Date Published: April 2005

Prepared by
A. Kolaczkowski/Science Applications International Corporation
J. Forester/Sandia National Laboratories
E. Lois/U.S. Nuclear Regulatory Commission
S. Cooper/U.S. Nuclear Regulatory Commission

Science Applications International Corporation
405 Urban Street, Suite 400
Lakewood, CO 80220

Sandia National Laboratories
P.O. Box 5800
Albuquerque, NM 87185

E. Lois, NRC Project Manager

Prepared for
Division of Risk Analysis and Applications
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001

Availability Notice

Abstract

The U.S. Nuclear Regulatory Commission is establishing “good practices” for performing human reliability analyses (HRAs) and reviewing HRAs to assess the quality of those analyses. The good practices were developed as part of the NRC’s activities to address quality issues related to probabilistic risk assessment (PRA) and, as such, support the implementation of Regulatory Guide (RG) 1.200, “An Approach for Determining the Technical Adequacy of Probabilistic Risk Assessment Results for Risk-Informed Activities,” dated February 2004.

The HRA good practices documented in this report are of a generic nature; that is, they are not tied to any specific methods or tools that could be employed to perform an HRA. As such, the good practices support the implementation of RG 1.200 for Level 1 and limited Level 2 internal event PRAs with the reactor at full power. Their elements are directly linked to RG 1.200, which reflects and endorses (with certain clarifications and substitutions) the “Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications” (RA-S-2002 and Addenda RA-Sa-2003) promulgated by the American Society of Mechanical Engineers, and “Probabilistic Risk Assessment (PRA) Peer Review Process Guidance” (NEI 00-02, Revision A3) promulgated by the Nuclear Energy Institute.

This report is not intended to constitute a standard and, hence, it does not provide de facto requirements; rather, this report is intended for use as a reference guide. Consequently, the authors did not write this report with the expectation that all good practices should always be met. That is, the decisions regarding which good practices are applicable — and the extent to which those practices should be met — depends on the nature of the given regulatory application. Therefore, it is important to understand that certain practices may not be applicable for a given analysis, or their applicability may be of limited scope.