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Human Reliability Analysis (HRA) Good Practices

  • Alan Kolaczkowski
  • John Forester
  • Erasmia Lois
  • Gareth Parry
  • Dennis Bley
Conference paper

Abstract

With the expectation that PRA will continue to be used in the commercial nuclear industry in assessing current operating risks, in estimating changes in risk as a result of temporary and permanent plant changes, and as an adjunct to the design process of newer generation plants, it is important that practitioners perform human reliability analysis (HRA) in accordance with good practices and that reviewers recognize the implementation of good practices (or failure to do so) in these analyses. Documents such as the American Society of Mechanical Engineers (ASME) Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications provide requirements for performing a good HRA. However, the requirements do not provide implementation guidance, i.e., they are not as “tutorial” as is necessary to support HRA analysts. This paper provides examples of “good practices” for a HRA as they should be implemented within a broader probabilistic risk assessment (PRA). It also discusses the consideration of “errors of commission” (EOCs) that is not explicitly addressed in the ASME Standard. The good HRA practice guidance focuses on identifying the attributes of a good HRA regardless of the specific methods or tools that are used and does not endorse the use of any particular method.

Keywords

Good Practice Human Event Nuclear Regulatory Commission Probabilistic Risk Assessment Capability Category 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

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References

  1. 1.
    Technical Basis and Implementation Guidelines for A Technique for Human Event Analysis (ATHEANA), NUREG-1624, Rev. 1, US Nuclear Regulatory Commission, May 2000.Google Scholar
  2. 2.
    Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-S-2002, American Society of Mechanical Engineers, April 5, 2002.Google Scholar
  3. 3.
    Use of Probabilistic Risk Assessment in Plant-Specific, Risk-Informed Decisionmaking: General Guidance, NUREG-0800, Chapter 19, Rev. 1, US Nuclear Regulatory Commission, November, 2002.Google Scholar

Copyright information

© Springer-Verlag London 2004

Authors and Affiliations

  • Alan Kolaczkowski
    • 1
  • John Forester
    • 2
  • Erasmia Lois
    • 3
  • Gareth Parry
    • 3
  • Dennis Bley
    • 4
  1. 1.Science Applications International Corp.EugeneUSA
  2. 2.Sandia National LaboratoriesAlbuquerqueUSA
  3. 3.U.S. Nuclear Regulatory CommissionUSA
  4. 4.Buttonwood Consulting Inc.OaktonUSA

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