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Suggestions of HRA Method Improvement for the Practical Assessment of Human Reliability

  • Received : 2018.03.29
  • Accepted : 2018.05.10
  • Published : 2018.06.30

Abstract

Objective: In this paper, some improvements for a more practical and realistic application of HRA are suggested with an example of an HRA method recently developed. Background: Various HRA methods have been developed for quantifying human reliability of nuclear power plants. With technical bases of cognitive engineering and HRA practices, those methods aimed to reduce analysis variability and enhance traceability of the HRA process. However, several related issues needing to be resolved, were still remained. Method: With reference to recently conducted research, some measures alleviating the indicated issues are suggested. Empirical studies and several kinds of HRA methods were benchmarked for deriving improvements. Results: The four strategies including plant-specific guideline for task analysis, distinctive human error classification, grounding on empirical data, and clarification of performance shaping factor definition were suggested in this study. Conclusion: A more practical method can be generated with a foundation of human cognitive theoretic and empirical findings for a next generation of HRA method. Application: A new method is being developed for human operators in computer-based control rooms. The above suggestions will be implemented for enhanced applications of HRAs.

Keywords

References

  1. Barriere, M., Bley, D., Cooper, S., Forester, J., Kolaczkowski, A., Luckas, W., Parry, G., Ramey-Smith, A., Thompson, C. and Whitehead, D., Others, Technical Basis and Implementation Guidelines for a Technique for Human Event Analysis (ATHEANA), US NRC, NUREG-1624, 2000.
  2. Bell, J. and Holroyd, J., Review of human reliability assessment methods, Health and Safety Laboratory, HSE Books, 2009.
  3. Bladh, K., Frohm, J., Iseland, T., Karlsson, A., Becker, G., Tunturivuori, L., Porthin, M., Olsson, A., Böhm, J., Johanson, G. and Jonsson, S., Evaluation of Existing Applications and Guidance on Methods for HRA - EXAM-HRA - Phase 3a Summary Report, Nordic nuclear safety research, NKS-305, 2014.
  4. Bowie, J., Munley, G., Dang, V., Wreathall, J., Bye, A., Cooper, S., Fauchille, V., Yves, J., Haage, M., Johanson, G., Jung, W.D., Kim, J., Kubicek, J., Bot, P.L., Lee, S.J., Marble, J., Pesme, H., Peters, S., Preischl, W., Salway, A. and Xing, J., Establishing the Appropriate Attributes in Current Human Reliability Assessment Techniques for Nuclear Safety, Organisation for Economic Co-Operation and Development, NEA-CSNI-R--2015-1, 2015.
  5. Chang, Y.J., Bley, D., Criscione, L., Kirwan, B., Mosleh, A., Madary, T., Nowell, R., Richards, R., Roth, E.M., Sieben, S. and Zoulis, A., The SACADA database for human reliability and human performance, Reliability Engineering & System Safety, 125, 117-133, 2014. https://doi.org/10.1016/j.ress.2013.07.014
  6. Chang, Y.J., Xing, J. and Peters, S., "Human Reliability Analysis Method Development in the Us Nuclear Regulatory Commission", 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, Korea, 2016.
  7. Forester, J., Kelly, D., Kolaczkowski, A. and Lois, E., Evaluation of Human Reliability Analysis Methods Against Good Practices, US NRC, NUREG-1842, 2006.
  8. Forester, J., Dang, V.N., Bye, A., Lois, E., Massaiu, S., Broberg, H., Braarud, P.O., Boring, R., Mannisto, I., Liao, H., Julius, J., Parry, G. and Nelson, P., The International HRA Empirical Study: Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data, US NRC, NUREG-2127, 2014.
  9. Forester, J., Liao, H., Dang, V.N., Bye, A., Lois, E., Mary, P., Marble, J., Nowell, R., Broberg, H., Hildenbrandt, M., Hallbert, B. and Morgan, T., The US HRA Empirical Study: Assessment of HRA Method Predictions Against Operating Crew Performance on a US Nuclear Power Plant Simulator. United States Nuclear Regulatory Commission, US NRC, NUREG-2156, 2016.
  10. Gertman, D., Blackman, H., Marble, J., Byers, J. and Smith, C., The SPAR-H human reliability analysis method, US NRC, NUREG/CR-6883, 2005.
  11. Groth, K.M., Smith, C.L. and Swiler, L.P., A bayesian method for using simulator data to enhance human error probabilities assigned by existing HRA methods, Reliability Engineering & System Safety, 128, 32-40, 2014. https://doi.org/10.1016/j.ress.2014.03.010
  12. Hollnagel, E., Cognitive reliability and error analysis method (CREAM), Elsevier, 1998.
  13. Jung, W., Kang, D. and Kim, J., Development of a standard method for HRA of nuclear power plants-Level I PSA full power internal HRA, KAERI, KAERI/TR-2961/2005, 2005.
  14. Kim, J., Jung, W. and Son, Y.S., The MDTA-based method for assessing diagnosis failures and their risk impacts in nuclear power plants, Reliability Engineering & System Safety, 93(2), 337-349, 2008. https://doi.org/10.1016/j.ress.2006.10.020
  15. Kim, Y., Park, J. and Jung, W., A classification scheme of erroneous behaviors for human error probability estimations based on simulator data, Reliability Engineering & System Safety, 163, 1-13, 2017a. https://doi.org/10.1016/j.ress.2017.01.022
  16. Kim, Y., Choi, S., Kim, S. and Park, J., Identifying Considerations of the Human Reliability Analysis Method for Digitalized Control Rooms, KAERI, KAERI/TR-7163/2017, 2017b.
  17. Kim, Y., Park, J., Jung, W., Choi, S.Y. and Kim, S., Estimating the Quantitative Relation between PSFs and HEPs from Full-Scope Simulator Data, Reliability Engineering & System Safety, 173, 17-22, 2018a.
  18. Kim, Y., Choi, J., Park, J., Jung, W. and Lee, S.J., Estimating Diagnosis Time of Emergency Situations in Digitalized Control Rooms, 9th International Conference on Applied Human Factors and Ergonomics and the Affiliated Conferences, Orlando, Florida, 2018b. (To be published)
  19. Kirwan, B., Basra, G. and Taylor-Adams, S., CORE-DATA: a computerised human error database for human reliability support. In: Human Factors and Power Plants, 1997. Global Perspectives of Human Factors in Power Generation., Proceedings of the 1997 IEEE Sixth Conference on, 7-12, 1997.
  20. Kirwan, B., The development of a nuclear chemical plant human reliability management approach: HRMS and JHEDI, Reliability Engineering & System Safety, 56(2), 107-133, 1997. https://doi.org/10.1016/S0951-8320(97)00006-9
  21. Le Bot, P., Cara, F. and Bieder, C., MERMOS, a second generation HRA method: what it does and doesn't do, In Proceedings of the International Topical Meeting on Probabilistic Safety Assessment (Vol. 2), 852-880, 1999.
  22. Liao, H., Groth, K. and Stevens-Adams, S., Challenges in leveraging existing human performance data for quantifying the IDHEAS HRA method, Reliability Engineering & System Safety, 144, 159-169, 2015. https://doi.org/10.1016/j.ress.2015.07.018
  23. Liao, H., Morrow, S., Parry, G., Bley, D., Criscione, L. and Presley, M., Final Conclusions and Lessons Learned from Testing the Integrated Human Event Analysis System for Nuclear Power Plant Internal Events At-Power Application (IDHEAS AT-POWER), Probabilistic Safety Assessment and Analysis Conference (PSA 2017), Pittsburgh, PA, 2017.
  24. Nuclear Energy Agency, Use and Development of Probabilistic Safety Assessment, An Overview of the situation at the end of 2010. NEA/CSNI/R(2012)11, 2012.
  25. Parry, G., Lydell, B., Spurgin, A., Moieni, P. and Beare, A., An approach to the analysis of operator actions in PRA, Electric Power Research Institute (EPRI), EPRI TR-100259, 1992.
  26. Parry, G., Forester, J., Dang, V., Hendrickson, S., Presley, M., Lois, E. and Xing, J., IDHEAS-a new approach for human reliability analysis. In: ANS PSA 2013 international topical meeting on probabilistic safety assessment and analysis, Columbia, SC, 2013.
  27. Pasquale, V.D., Lannone, R., Miranda, S. and Riemma, S., An overview of human reliability analysis techniques in manufacturing operations, In M.M. Schiraldi (Ed), Operations Management, InTech, 2013.
  28. Preischl, W. and Hellmich, M., Human error probabilities from operational experience of German nuclear power plants. Reliability Engineering & System Safety, 109, 150-159, 2013. https://doi.org/10.1016/j.ress.2012.08.004
  29. Reece, W., Gilbert, B. and Richards, R., Nuclear Computerized Library for Assessing Reactor Reliability (NUCLARR): Data manual. Part 2: Human error probability (HEP) data, Volume 5, Revision 4, Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (United States), 1994.
  30. Swain, A.D., Accident sequence evaluation program: Human reliability analysis procedure, US NRC NUREG/CR-4772, Sandia National Labs., SAND-86-1996, 1987.
  31. Swain, A.D. and Guttmann, H.E., Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, US NRC, NUREG/CR-1278, 1983.
  32. Xing, J., Parry, G., Presley, M., Forester, J., Hendrickson, S. and Dang, V., An Integrated Human Event Analysis System (IDHEAS) for Nuclear Power Plant Internal Events At-Power Application, US NRC, NUREG-2199, Vol. 1, 2017.