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DEVELOPMENT OF THE DIGITALIZED AUTOMATIC SEISMIC TRIP SYSTEM FOR NUCLEAR POWER PLANTS USING THE SYSTEMS ENGINEERING APPROACH

  • Received : 2013.05.20
  • Accepted : 2013.11.28
  • Published : 2014.04.25

Abstract

The automatic seismic trip system (ASTS) continuously monitors PGA (peak ground acceleration) from the seismic wave, and automatically generates a trip signal. This work presents how the system can be designed by using a systems engineering approach under the given regulatory criteria. Overall design stages, from the needs analysis to design verification, have been executed under the defined processes and activities. Moreover, this work contributes two significant design areas for digitalized ASTS. These are firstly, how to categorize the ASTS if the ASTS has a backed up function of the manual reactor trip, and secondly, how to set the requirements using the given design practices either in overseas ASTS design or similar design. In addition, the methodology for determining the setpoint can be applied to the I&C design and development project which needs to justify the error sources correctly. The systematic approach that has been developed and realized in this work can be utilized in designing new I&C (instrument and control system) as well.

Keywords

References

  1. A. Kossiakoff et el., "System Engineering-Principles and Practice", Wiley
  2. IAEA meeting report, "Seismic Safety of Existing NPPs", working area 1 and 3, IAEA, 2009
  3. R. Whorton, "US utility perspectives on earthquake response and seismic instrumentation", IAEA Workshop, 1995
  4. MITI Order No. 62, "Technical Standards for Nuclear Power Plant Facilities", MITI, 1989
  5. JEAG 4601 criteria, "Technical Guidelines for Aseismic Design of Nuclear Power Plants, JEAG, 1987
  6. KINS/RG-N08.01, "Safety Classification for PWR I&C system", KINS, 2011
  7. USNRC Reg. Guide 1.29, "Seismic Design Classification", USNRC, 2007
  8. IEEE Std. 1012-1998, "IEEE standard for Software Verification and Validation", IEEE
  9. R. Whorton US utility perspectives on earthquake response and seismic instrumentation, IAEA Workshop, 1995
  10. Ting Chow and Shue, "ASTS consulting report for Korea Power Engineering Company", INER. TW, 2011
  11. ANSI/ANS 2.2, "Earthquake Instrumentation Criteria for Nuclear Power Plants", 2002.
  12. B.P. Allmann and P.M. Shearer, "Global variations of stress drop for moderate to large earthquakes", Journal of Geophysical Research, Vol. 114, 2009
  13. EPRI NP-5930s, "A Criterion for Determining Exceedance of the Operating Basis Earthquake", EPRI, 1988
  14. IAEA meeting report, "Seismic Safety of Existing NPPs", working area 1 and 3, IAEA, 2009
  15. Safety Reports Series No.66, "Earthquake Preparedness and Responses for NPPs", IAEA, 2011
  16. USNRC Reg. Guide 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants", USNRC, 1973
  17. NUREG-0800, "Standard Review Plan 3.7.1, Seismic Design Parameters", USNRC, 2007
  18. G. H Youn, et el., "Development Status of Ground-motion Criteria for Operation of NPPs Amplification", Earthquake Engineering Society of Korea workshop, 2009
  19. KR_3201, "Seismic Monitoring System-Acceptance criteria", GeoSIG Ltd.
  20. ISO/IEC 15288, "Systems and software engineering -System life cycle processes", IEC, 2008