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SACADA and HuREX: Part 1. the use of SACADA and HuREX systems to collect human reliability data

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초록

As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), theprimary role of human reliability analysis (HRA) is to provide credible estimations of the human errorprobabilities (HEPs) of safety-critical tasks. Accordingly, HRA community has emphasized the accumulation of HRA data to support HRA practitioners for many decades. To this end, it is critical to resolvepractical problems including (but not limited to): (1) how to collect HRA data from available informationsources, and (2) how to inform HRA practitioners with the collected HRA data. In this regard, the U.S. Nuclear Regulatory Commission (NRC) and Korea Atomic Energy Research Institute (KAERI) independently initiated two large projects to accumulate HRA data by using full-scale simulators (i.e., simulatordata). In terms of resolving the first practical problem, the NRC and KAERI developed two dedicated HRAdata collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) andHuREX (Human Reliability data EXtraction), respectively. In addition, to inform HRA practitioners, theNRC and KAERI proposed several ideas to extract useful information from simulator data. This paper isthe first of two papers to discuss the technical underpinnings of the development of the SACADA andHuREX systems

Abstract

As a part of probabilistic risk (or safety) assessment (PRA or PSA) of nuclear power plants (NPPs), theprimary role of human reliability analysis (HRA) is to provide credible estimations of the human errorprobabilities (HEPs) of safety-critical tasks. Accordingly, HRA community has emphasized the accumulation of HRA data to support HRA practitioners for many decades. To this end, it is critical to resolvepractical problems including (but not limited to): (1) how to collect HRA data from available informationsources, and (2) how to inform HRA practitioners with the collected HRA data. In this regard, the U.S. Nuclear Regulatory Commission (NRC) and Korea Atomic Energy Research Institute (KAERI) independently initiated two large projects to accumulate HRA data by using full-scale simulators (i.e., simulatordata). In terms of resolving the first practical problem, the NRC and KAERI developed two dedicated HRAdata collection systems, SACADA (Scenario Authoring, Characterization, And Debriefing Application) andHuREX (Human Reliability data EXtraction), respectively. In addition, to inform HRA practitioners, theNRC and KAERI proposed several ideas to extract useful information from simulator data. This paper isthe first of two papers to discuss the technical underpinnings of the development of the SACADA andHuREX systems

참고문헌 (44)

  1. EPRI NP-6937, Operator Reliability Experiments Using Power Plant Simulators Volume 1: Executive Summary, vol. 1, "A. J. Spurgin", Electric Power Research Institute, ~ (1990)
  2. Appende\\ixes, Operator Reliability Experiments Using Power Plant Simulators Volume 3, vol. 3, "A. J. Spurgin", Electric Power Research Institute, ~, pp.EPRI NP-6937 (1990)
  3. Technical Report, Operator Reliability Experiments Using Power Plant Simulators Volume 2, vol. 2, "A. J. Spurgin", Electric Power Research Institute, ~, pp.EPRI NP-6937 (1990)
  4. A Human Reliability Analysis Approach Using Measurements for Individual Plant Examination, "A.J. Spurgin", Electric Power Research Institute, ~, pp.NP-6560-L (1989)
  5. C. Bieder, "MERMOS : EDF's new advanced HRA method", IAPSAM, 4, pp.129~134 (1998), Springer
  6. "MERMOS: an extended second generation HRA method" (2007)[URL]
  7. W. Jung, "HuREX e a framework of HRA data collection from simulators in nuclear power plants", Reliab. Eng. Syst. Saf, 194, pp.106235~ (2020)[DOI]
  8. J. Park, "OPERAda human performance database under simulated emergencies of nuclear power plants", Reliab. Eng. Syst. Saf, 92(4), pp.503~519 (2007)[DOI]
  9. Analysis of Human Performance Observed under Simulated Emergencies of Nuclear Power Plants, "J. Park", Korea Atomic Energy Research Institute, ~, pp.KAERI (2005), TR-2895[DOI]
  10. An HRA Method for Digital Main Control Rooms d Part I: Estimating the Failure Probability of Timely Performance, "Y. Kim", Korea Atomic Energy Research Institute, ~, pp.KAERI (2019), TR-7607[DOI]
  11. J. Kim, "HuRECA: human reliability evaluator for computer-based control room Actions", The Joint WGRISK, 2012, ~[DOI]
  12. HuRECA: the Human Reliability Analysis Method for Computer-Based Advanced Control Rooms, "J. Kim", Korea Atomic Energy Research Institute, ~, pp.KAERI (2011), TR-4385
  13. Y. J. Chang, "The SACADA database for human reliability and human performance", Reliab. Eng. Syst. Saf, 125, pp.117~133 (2014)[DOI]
  14. "Human reliability analysis data -SACADA data" (2019)[URL]
  15. Integrated human event analysis system for event and condition assessment (IDHEAS-ECA), RIL-2020-02, "J. Xing", Nuclear Regulatory Commission, ~ (2020)
  16. The General Methodology of an Integrated Human Event Analysis System (IDHEAS-G), "J. Xing", Nuclear Regulatory Commission, ~, pp.NUREG-2198 U.S (2021)
  17. K. Jan, "HRA data collection projects in Czech Republic", HRA Data Workshop, U.S. Nuclear Regulatory Commission (2020)
  18. The U.S. HRA empirical study e assessment of HRA method predictions against operating crew performance on a U.S. Nuclear power plant simulator, "J. Forester", U.S. Nuclear Regulatory Commission, ~, pp.NUREG-2156 (2016)
  19. The International HRA Empirical Study - Phase 2 Report Results from Comparing HRA Methods Predictions to HAMMLAB Simulator on SGTR Scenarios - Appendix A, OECD Halden Reactor Project, "A. Bye", APP A, ~, pp.HWR-915 (2010)
  20. NUREG, "IA-0216, International HRA Empirical Study - Phase 3 Report: Results from Comparing HRA Methods Predictions to HAMMLAB Simulator Data on LOFW Scenarios, vol. 3", V. N. Dang, 2014
  21. The International HRA Empirical Study eFinal Report e Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data, "J. Forester", ~, pp.HPR-373 (2012)
  22. The International HRA Empirical Study: Lessons Learned from Comparing HRA Methods Predictions to HAMMLAB Simulator Data, "J. Forester", U.S. Nuclear Regulatory Commission, ~, pp.NUREG-2127 (2014)
  23. NUREG, "IA-0216, International HRA Empirical Study - Phase 1 Report: Description of Overall Approach and Pilot Phase Results from Comparing HRA Methods to Simulator Performance Data, vol. 1", E. Lois, 2009
  24. Human Factors Reliability Benchmark Exercise (HF-RBE) Synthesis Report, "A. Poucet", Commission of the European Communities, ~ (1989)
  25. Simulator Studies for HRA Purposes - Workshop Proceedings, "Nuclear Energy Agency", NEA, R, pp.2012, ~
  26. W. Jung, "HuREXeHuman reliability data extraction - a framework for simulator data collection and analysis to generate human error probability", HRA Data Workshop, U.S. Nuclear Regulatory Commission (2018)
  27. K. Jan, "Roundtable discussion - UJV", HRA Data Workshop, U.S. Nuclear Regulatory Commission (2020)
  28. NUREG, "IA-0216, International HRA Empirical Study - Phase 2 Report: Results from Comparing HRA Method Predictions to Simulator Data from SGTR Scenarios, vol. 2", A. Bye, 2011
  29. Human Reliability Data for Central Control of Modern Power Stations, CRA-IFE-ENGL, "A. Wright", EDF Energy Generation Limited, ~ (2019)
  30. "Collecting HRA Data Workshop, Probabilistic Safety Assessment and Management (PSAM 14)" (2018)[URL]
  31. U. S. Nuclear Regulatory Commission, "HRA Data Workshop", ~ (2018)
  32. U. S. Nuclear Regulatory Commission, "HRA Data Workshop", March 14-15, ~ (2019)
  33. U. S. Nuclear Regulatory Commission, "HRA Data Workshop", ~ (2020)
  34. "Wednesday, February 4, 2009 U.S. Nuclear Regulatory Commission, Staffrequirements e briefing on risk-informed, performance-based regulation, 1:30p.m., SRM M090204B, in: Commissioners' Conference Room, One White Flint North" (2009)[URL]
  35. Application of the HuREX Framework for Calculating Empirical Human Error Probabilities from the Operation Experience of Domestic Nuclear Power Plants e Preliminary Results, "J. Park", Korea Atomic Energy Research Institute, ~, pp.KAERI (2016), TR-6474
  36. J. Reason, "Human Error" (1990), Cambridge University Press
  37. A Framework to Estimate HEPs from the Full-Scope Simulators of NPPs: Unsafe Act Definition, Identification and Quantification, "J. K. Park", Korea Atomic Energy Research Institute, ~, pp.KAERI (2016), TR-6401[DOI]
  38. Review on the Applicability and Appropriateness of HRA Data Extraction Based on the HuREX Framework, "J. Park", Korea Atomic Energy Research Institute, ~, pp.KAERI (2020), TR-8038
  39. Y. Kim, "Incorporating prior knowledge with simulation data to estimate PSF multipliers using Bayesian logistic regression", Reliab. Eng. Syst. Saf, 189, pp.210~217 (2019)
  40. Seunghwan Kim, "Design and Implementation of HuREX Analysis Supporting Interface for HRA Data Extraction", Nuclear Technology, 202(2-3), pp.259~277 (2018), Informa UK Limited[DOI]
  41. 김요찬, "Considerations for generating meaningful HRA data: Lessons learned from HuREX data collection", Nuclear Engineering and Technology, 52(8), pp.1697~1705 (2020), 한국원자력학회[DOI]
  42. M. A. Azarm, "Proposed methods for using SACADA DATA for empirical HRA estimation", HRA Data Workshop, the NRC Headquarters (2018), U.S. Nuclear Regulatory Commission
  43. S. Fitch, "A method to use SACADA data for estimating human error probabilities of human failure events", HRA Data Workshop, the NRC Headquarters (2018)
  44. K. M. Groth, "Transforming HRA using SACADA data, Bayesian methods, and DBNs", HRA Data Workshop, the NRC Headquarters (2018)

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