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ADVANCED MMIS TOWARD SUBSTANTIAL REDUCTION IN HUMAN ERRORS IN NPPS

  • 투고 : 2013.03.15
  • 발행 : 2013.04.25

초록

This paper aims to give an overview of the methods to inherently prevent human errors and to effectively mitigate the consequences of such errors by securing defense-in-depth during plant management through the advanced man-machine interface system (MMIS). It is needless to stress the significance of human error reduction during an accident in nuclear power plants (NPPs). Unexpected shutdowns caused by human errors not only threaten nuclear safety but also make public acceptance of nuclear power extremely lower. We have to recognize there must be the possibility of human errors occurring since humans are not essentially perfect particularly under stressful conditions. However, we have the opportunity to improve such a situation through advanced information and communication technologies on the basis of lessons learned from our experiences. As important lessons, authors explained key issues associated with automation, man-machine interface, operator support systems, and procedures. Upon this investigation, we outlined the concept and technical factors to develop advanced automation, operation and maintenance support systems, and computer-based procedures using wired/wireless technology. It should be noted that the ultimate responsibility of nuclear safety obviously belongs to humans not to machines. Therefore, safety culture including education and training, which is a kind of organizational factor, should be emphasized as well. In regard to safety culture for human error reduction, several issues that we are facing these days were described. We expect the ideas of the advanced MMIS proposed in this paper to lead in the future direction of related researches and finally supplement the safety of NPPs.

키워드

참고문헌

  1. KONIS (KOrea hydro & nuclear power company Nuclear Information System).
  2. Operational Performance Information System for Nuclear Power Plants (http://opis.kins.re.kr).
  3. S. D. Swain and H. E. Guttmann, Handbook of Human- Reliability Analysis with Emphasis on Nuclear Power Plant Application, NUREG/CR-1278, US NRC (1983).
  4. International Atomic Energy Agency, The Chernobyl Accident: Updating of INSAG-7, INSAG-7, IAEA (1992).
  5. R. L. Brune and M. Weinstein, Development of a checklist for evaluating maintenance, test, and calibration procedures used in nuclear power plants, NUREG/CR- 1368, US NRC (1980).
  6. J. H. Hong, M. S. Lee, and D. H. Hwang, "Computerized procedure system for the APR1400 simulator," Nucl. Eng. Des., vol. 239, pp. 3092-3104 (2009). https://doi.org/10.1016/j.nucengdes.2009.09.024
  7. Electric Power Research Institute, Guidance for the Design and Use of Automation in Nuclear Power Plants, EPRI-1011851 (2005).
  8. K. Thornburg, Automation and HSI Complexity in Advanced Reactors, NRC-04-09-151, US Nuclear Regulatory Commission (2009).
  9. M. Endsley and D. Kaber, "Level of Automation Effects on Performance, Situation Awareness and Workload in a Dynamic Control Task," Ergonomics, vol. 42, no. 3, pp. 462-492 (1999). https://doi.org/10.1080/001401399185595
  10. T. Sheridan, Humans and Automation: System Design and Research Issues, New York: Wiley & Sons (2002).
  11. H. Basher and J. S. Neal, Autonomous Control of Nuclear Power Plants, ORNL/TM-2003/252, Oak Ridge National Laboratory (2003).
  12. P. H. Seong, Reliability and Risk Issues in Large Scale Safety-critical Digital Control Systems, Springer (2008).
  13. C. D. Wickens, J. Lee, Y. Liu, S. G. Becker, An Introduction to Human Factors Engineering, Prentice-Hall (2004).
  14. J. R. Lamarsh, Introduction to Nuclear Engineering, Addison Wesley (1983).
  15. F. Owre, "Role of the Man-Machine Interface in Accident Management Strategies," Nucl. Eng. Des., vol. 209, no. 1- 3, pp. 201-210 (2001). https://doi.org/10.1016/S0029-5493(01)00403-4
  16. M. A. S. A. Harbi, A. R. Kim, I. Jang, P. H. Seong, S. Shirouzu, S. Katayama, and H. G. Kang, "Effects of Soft Control in the Nuclear Power Plants Emergency Operation Condition," Ann. Nucl. Ene., vol. 54, pp. 184-191 (2013). https://doi.org/10.1016/j.anucene.2012.11.014
  17. C. D. Wickens, Engineering Psychology and Human Performance, 3rd ed., Prentice Hall (1999).
  18. International Atomic Energy Agency, Good practice with respect to the development and use of nuclear power plant procedures, IAEA-TECDOC-1058, IAEA (1998).
  19. US Nuclear Regulatory Commission, 10 CFR Part 50, Appendix B-Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, US NRC (2013).
  20. US Nuclear Regulatory Commission, Human Factors Engineering Program Review Model, NUREG-0711, Rev. 3, US NRC (2012).
  21. US Nuclear Regulatory Commission, Standard Review Plan, NUREG-0800, Chapter 13, US NRC (1987).
  22. US Nuclear Regulatory Commission, Guidelines for the preparation of emergency operating procedures, NUREG- 0899, US NRC (1982).
  23. US Nuclear Regulatory Commission, Computer-based procedure systems: technical basis and human factors review guidance, NUREG/CR-6634, US NRC (2000).
  24. Electric Power Research Institute, Computerized Procedure Systems, TR-1015313 (2010).
  25. The American Nuclear Society Special Committee on Fukushima, Fukushima Daiichi: ANS Committee Report, ANS (2012).
  26. The ASME Presidential Task Force on Response to Japan Nuclear Power Plant Events, Forging a New Nuclear Safety Construct, ASME (2012).
  27. International Atomic Energy Agency, Managing Human Resources in the Field of Nuclear Energy, NG-G-2.1, IAEA (2009).
  28. International Atomic Energy Agency, Knowledge Management for Nuclear Industry Operating Organizations, TECDOC-1510, IAEA (2006).
  29. International Atomic Energy Agency, Human Resource Issues Related to an Expanding Nuclear Power Programme, TECDOC-1501, IAEA (2006).
  30. Electric Power Research Institute, Effective Engineering Technical Training at Nuclear Power Plants, TR-107436, EPRI (1998).
  31. M.T. Crichton, R. Flin, "Identifying and Training Non- Technical Skills of Nuclear Emergency Response Teams," Ann. Nucl. Ene., vol. 31, no. 12, pp. 1317-1330 (2004). https://doi.org/10.1016/j.anucene.2004.03.011
  32. S. K. Kim, S. N. Byun, D. H. Lee, and C. H. Jeong, "Development of a Crew Resource Management Training Program for Reduction of Human Errors in APR-1400 Nuclear Power Plant," J. Erg. Soc. Korea, vol. 28, no. 1, pp. 37-51 (2009). https://doi.org/10.5143/JESK.2009.28.1.037
  33. International Atomic Energy Agency, Safety Culture, INSAG-4, IAEA (1991).
  34. E. H. Schein, Organizational Culture and Leadership, San Francisco: Jossey-Bass (1992).
  35. Organization for Economic Cooperation and Development Nuclear Energy Institute, Fostering a Strong Nuclear Safety Culture, NEI-09-07 (2009).
  36. Institute of Nuclear Power Operations, Principles for a strong nuclear safety culture, INPO (2004).
  37. Institute of Nuclear Power Operations, Traits of a Healthy Nuclear Safety Culture, INPO (2012).
  38. Y. S. Choi, J. D. Ko, K. S. Choi, and Y. H. Chung, Safety Culture Indicators for NPP: International Trends and Development Status in Korea, Proc. Korean Nucl. Soci., Gyeongju, Korea, May 2004.
  39. J. T. Kim, K. C. Kwon, I. K. Hwang, D. Y. Lee, W. M. Park, J. S. Kim, and S. J. Lee, "Development of advanced I&C in nuclear power plants: ADIOS and ASICS," Nucl. Eng. Des., vol. 207. no. 1, pp. 105-119 (2001). https://doi.org/10.1016/S0029-5493(00)00430-1
  40. Y. Inazumi and M. Takashima, Automatic Control System for Plant Heatup and Cooldown Operations in Japanese PWR Plants, Int. Sym. Nucl. Power Plant. Inst. Cont., Tokyo, Japan, May 1992.
  41. R. C. Berkan, B. R. Upadhyaya, L. H. Tsoukalas, R. A. Kisner, and R. L. Bywater, "Advanced Automation Concepts for Large-Scale Systems," IEEE Control Systems Magazine, vol. 11, no. 6, pp. 4-12 (1991).
  42. Takashi Iijima, Yoshiaki Nakajima, and Yasushi Nishiwaki, "Application of Fuzzy Logic Control System for Reactor Feed-water Control," Fuzzy Sets and Systems, vol. 74, no. 1, pp. 61-72 (1995). https://doi.org/10.1016/0165-0114(95)00036-K
  43. Y. J. Lee and M. G. Na, "Robust Controller Design of Nuclear Reactor Power by Parametric Method," Nucl. Eng. Tech., vol. 34, no. 5, pp. 436-444 (2002).
  44. M. Boroushaki, M. B. Ghofrani, C. Lucas, and M. J. Yazdanpanah, "Identification and Control of a Nuclear Reactor Core (VVER) Using Recurrent Neural Networks and Fuzzy Systems," IEEE Trans. Nucl. Sci., vol. 50, no. 1, pp. 159-174 (2003). https://doi.org/10.1109/TNS.2002.807856
  45. M. G. Na and Y. J. Lee, "A Receding Horizon Controller for the Steam Generator Water Level," Nucl. Tech., vol. 143, no. 2, pp. 180-196 (2003). https://doi.org/10.13182/NT03-A3408
  46. D. Ruan and J. S. Ben_tez-Read, "Fuzzy Control for Nuclear Reactor Operation - Strengths, Weaknesses, Opportunities and Threats," J. Intelligent and Fuzzy Systems, vol. 16, no. 4, pp. 289-295 (2005).
  47. R. A. Shaffer, R. M. Edwards, and K. Y. Lee, "Design and Validation of Robust and Autonomous Control for Nuclear Reactors," Nucl. Eng. Tech., vol. 37, no. 2, pp. 139-150 (2002).
  48. M. G. Na, I. J. Hwang, and Y. J. Lee, "Design of a Fuzzy Model Predictive Power Controller for Pressurized Water Reactors," IEEE Trans. Nucl. Sci., vol. 53, no. 3, pp. 1504-1514 (2006). https://doi.org/10.1109/TNS.2006.871085
  49. S. W. Lee, J. H. Kim, D. S. Kim, M. G. Na, K. J. Yu, and H. G. Kim, "Design of a Load Following Controller for APR+ Nuclear Plants," Nucl. Eng. Tech., vol. 44, no. 4, pp. 369-378 (2012). https://doi.org/10.5516/NET.04.2012.509
  50. H. G. Kang and S. C. Jang, "Application of Conditionbased HRA Method for a Manual Actuation of the Safety Features in a Nuclear Power Plant," Rel. Eng. & Sys. Safety, vol. 91, no. 6, pp. 627-633 (2006). https://doi.org/10.1016/j.ress.2005.04.007
  51. H. M. Hashemian, C. J. Kiger, G. W. Morton, B. D. Shumaker, "Wireless Sensor Applications in Nuclear Power Plants," Nucl. Tech., vol. 173, no. 1, pp. 8-16 (2011). https://doi.org/10.13182/NT11-1