DOI QR코드

DOI QR Code

Development of simulation-based testing environment for safety-critical software

  • Lee, Sang Hun (Department of Mechanical Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute (RPI)) ;
  • Lee, Seung Jun (School of Mechanical, Aerospace and Nuclear Engineering, Ulsan National Institute of Science and Technology (UNIST)) ;
  • Park, Jinkyun (Integrated Safety Assessment Division, Korea Atomic Energy Research Institute (KAERI)) ;
  • Lee, Eun-chan (Korea Hydro & Nuclear Power Co., Ltd.) ;
  • Kang, Hyun Gook (Department of Mechanical Aerospace and Nuclear Engineering, Rensselaer Polytechnic Institute (RPI))
  • Received : 2018.01.30
  • Accepted : 2018.02.28
  • Published : 2018.05.25

Abstract

Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrumentation and control systems. To guarantee NPP safety, the reliability of the software used in safetycritical instrumentation and control systems must be quantified and verified with proper test cases and test environment. In this study, a software testing method using a simulation-based software test bed is proposed. The test bed is developed by emulating the microprocessor architecture of the programmable logic controller used in NPP safety-critical applications and capturing its behavior at each machine instruction. The effectiveness of the proposed method is demonstrated via a case study. To represent the possible states of software input and the internal variables that contribute to generating a dedicated safety signal, the software test cases are developed in consideration of the digital characteristics of the target system and the plant dynamics. The method provides a practical way to conduct exhaustive software testing, which can prove the software to be error free and minimize the uncertainty in software reliability quantification. Compared with existing testing methods, it can effectively reduce the software testing effort by emulating the programmable logic controller behavior at the machine level.

Keywords

References

  1. M. Hassan, W.E. Vesely, Digital I&C Systems in Nuclear Power Plants. Riskscreening of Environmental Stressors and a Comparison of Hardware Unavailability with an Existing Analog System, NUREG/CR-6579, Brookhaven National Laboratory, 1998.
  2. National Research Council, Digital Instrumentation and Control Systems in Nuclear Power Plants: Safety and Reliability Issues, National Academies Press, 1997.
  3. H.G. Kang, T. Sung, An analysis of safety-critical digital systems for riskinformed design, Reliab. Eng. Syst. Saf. 78 (2002) 307-314. https://doi.org/10.1016/S0951-8320(02)00176-X
  4. H. Ragheb, Operating and Maintenance Experience with Computer-based Systems in Nuclear Power Plants, in: International Workshop on Technical Support for Licensing Issues of Computer-based Systems Important to Safety, March 1996. Munchen, Germany.
  5. U.S. Nuclear Regulatory Commission, Guidance for Evaluation of D3 in Digital Computer-based Instrumentation and Control Systems, 2012. BTP 7-19 (Rev. 6).
  6. K. Korsah, M.D. Muhlheim, R. Wood, A Qualitative Assessment of Current CCF Guidance Based on a Review of Safety System Digital Implementation Changes with Evolving Technology, ORNL/SR-2016/148, Oak Ridge National Lab, 2016.
  7. M.R. Lyu, Handbook of Software Reliability Engineering, McGraw-Hill, New York, 1996.
  8. M.C. Kim, S.C. Jang, J. Ha, Possibilities and limitations of applying software reliability growth models to safety critical software, Nucl. Eng. Technol. 39 (2007) 145-148.
  9. N. Fenton, M. Neil, W. Marsh, P. Hearty, D. Marquez, P. Krause, R. Mishra, Predicting software defects in varying development lifecycles using Bayesian nets, Inf. Software Technol. 49 (2007) 32-43. https://doi.org/10.1016/j.infsof.2006.09.001
  10. H.S. Eom, G.Y. Park, S.C. Jang, H.S. Son, H.G. Kang, V&V-based remaining fault estimation model for safetyecritical software of a nuclear power plant, Ann. Nucl. Energy 51 (2013) 38-49. https://doi.org/10.1016/j.anucene.2012.06.030
  11. S. Brown, Overview of IEC 61508. Design of electrical/electronic/programmableelectronic safety-related systems, Comput. Contr. Eng. J 11 (2000) 6-12. https://doi.org/10.1049/cce:20000101
  12. T.L. Chu, M. Yue, M. Martinez-Guridi, J. Lehner, Review of Quantitative Software Reliability Methods, BNL-94047-2010, Brookhaven National Laboratory, 2010.
  13. J. May, G. Hughes, A.D. Lunn, Reliability estimation from appropriate testing of plant protection software, Software Eng. J. 10 (1995) 206-218. https://doi.org/10.1049/sej.1995.0026
  14. T.L. Chu, Development of Quantitative Software Reliability Models for Digital Protection Systems of Nuclear Power Plants, NUREG/CR-7044, U.S. Nuclear Regulatory Commission, 2013.
  15. S. Kuball, J.H.R. May, A discussion of statistical testing on a safety-related application, Proc. Inst. Mech. Eng. O J. Risk Reliab. 221 (2007) 121-132.
  16. H.G. Kang, H.G. Lim, H.J. Lee, M.C. Kim, S.C. Jang, Input-profile-based software failure probability quantification for safety signal generation systems, Reliab. Eng. Syst. Saf. 94 (2009) 1542-1546. https://doi.org/10.1016/j.ress.2009.02.018
  17. S.M. Shin, S.H. Lee, H.G. Kang, H.S. Son, S.J. Lee, Test based reliability quantification method for a safety critical software using finite test sets, in: Proceedings of the 9th International Topical Meeting on Nuclear Plant Instrumentation, Control & Humanemachine Interface Technologies (NPIC & HMIT 2015), Charlotte, NC, February 2015.
  18. C.V. Ramamoorthy, W.T. Tsai, Advances in software engineering, Computer 29 (1996) 47-58.
  19. K.C. Kwon, M.S. Lee, Technical review on the localized digital instrumentation and control systems, Nucl. Eng. Technol. 41 (2009) 447-454. https://doi.org/10.5516/NET.2009.41.4.447
  20. J.G. Choi, S.J. Lee, H.G. Kang, S. Hur, Y.J. Lee, S.C. Jang, Fault detection coverage quantification of automatic test functions of digital I&C system in NPPS, Nucl. Eng. Technol. 44 (2012) 421-428. https://doi.org/10.5516/NET.04.2012.515
  21. M. Lee, S. Song, D. Yun, Development and Application of POSAFE-Q PLC Platform, IAEA-CN-194, International Atomic Energy Agency (IAEA), 2012.
  22. K. Koo, B. You, T.W. Kim, S. Cho, J.S. Lee, Development of Application Programming Tool for Safety Grade PLC (POSAFE-Q), Transactions of the Korean Nuclear Society Spring Meeting, May 2006. Chuncheon, Korea.
  23. J. Palomar, R.H. Wyman, The Programmable Logic Controller and its Application in Nuclear Reactor Systems, NUREG/CR-6090, U.S. Nuclear Regulatory Commission, 1993.
  24. Texas Instruments, TMS320C3x User's Guide, 1997.
  25. D. Huizinga, A. Kolawa, Automated Defect Prevention: Best Practices in Software Management, John Wiley & Sons, 2007.
  26. C. Kaner, J. Falk, Testing Computer Software, Wiley, 1999.
  27. International Electrotechnical Commission, Programmable Controllers - Part 3: Programming Languages, IEC, 1993, pp. 61131-61133.
  28. J. Yoo, J.H. Lee, J.S. Lee, A research on seamless platform change of reactor protection system from PLC to FPGA, Nucl. Eng. Technol. 45 (2013) 477-488. https://doi.org/10.5516/NET.04.2012.078
  29. G.Y. Park, K.Y. Koh, E. Jee, P.H. Seong, K.C. Kwon, D.H. Lee, Fault tree analysis of KNICS RPS software, Nucl. Eng. Technol. 40 (2008) 397-408. https://doi.org/10.5516/NET.2008.40.5.397
  30. J.G. Choi, D.Y. Lee, Development of RPS trip logic based on PLD technology, Nucl. Eng. Technol. 44 (2012) 697-708. https://doi.org/10.5516/NET.04.2011.004
  31. Doosan Heavy Industries and Construction Co., Ltd, BP SDS for Reactor Protection System, 2008. KNICS-RPS-SDS231 (Rev. 3).
  32. J.J. Jeong, K.S. Ha, B.D. Chung, W.J. Lee, Development of a multi-dimensional thermal-hydraulic system code, MARS 1.3.1, Ann. Nucl. Energy 26 (1999) 1611-1642. https://doi.org/10.1016/S0306-4549(99)00039-0
  33. U.S. Nuclear Regulatory Commission, Report of the US Nuclear Regulatory Commission Piping Review Committee, NUREG/1061, 1984.

Cited by

  1. FBDTester 2.0: Automated test sequence generation for FBD programs with internal memory states vol.163, pp.None, 2018, https://doi.org/10.1016/j.scico.2018.04.005