DOI QR코드

DOI QR Code

Technical note: Estimation of Korean industry-average initiating event frequencies for use in probabilistic safety assessment

  • Received : 2019.03.05
  • Accepted : 2019.06.29
  • Published : 2020.01.25

Abstract

One fundamental element of probabilistic safety assessment (PSA) is the initiating event (IE) analysis. Since IE frequencies can change over time, time-trend analysis is required to obtain optimized IE frequencies. Accordingly, such time-trend analyses have been employed to estimate industry-average IE frequencies for use in the PSAs of U.S. nuclear power plants (NPPs); existing PSAs of Korean NPPs, however, neglect such analysis in the estimation of IE frequencies. This article therefore provides the method for and results of estimating Korean industry-average IE frequencies using time-trend analysis. It also examines the effects of the IE frequencies obtained from this study on risk insights by applying them to recently updated internal events Level 1 PSA models (at-power and shutdown) for an OPR-1000 plant. As a result, at-power core damage frequency decreased while shutdown core damage frequency increased, with the related contributions from each IE category changing accordingly. These results imply that the incorporation of time-trend analysis leads to different IE frequencies and resulting risk insights. The IE frequency distributions presented in this study can be used in future PSA updates for Korean NPPs, and should be further updated themselves by adding more recent data.

Keywords

References

  1. ASME/ANS, Addenda to ASME/ANS RA-S-2008, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, The American Society of Mechanical Engineers & American Nuclear Society, New York, U.S., 2013. ASME/ANS RA-Sb-2013.
  2. N. Johnson, J.A. Schroeder, Initiating Event Rates at U.S. Nuclear Power Plants: 1988-2016, Idaho National Laboratory, July 2017. INL/EXT-17-42758.
  3. U.S. Nuclear Regulatory Commission, Industry-average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants, NUREG/CR-6928, Initiating Event Data Sheets (2015 Update), February 2017.
  4. U.S. Nuclear Regulatory Commission, Rates of Initiating Events at U.S. Nuclear Power Plants: 1987-1995, 1999. NUREG/CR-5750.
  5. U.S. Nuclear Regulatory Commission, Industry-average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants, January 2012. NUREG/CR-6928, Initiating Event Data Sheets (Update 2010).
  6. Korea Hydro & Nuclear Power Co, Ltd, At-Power Internal Events Level 1 PSA Report for Hanul Units 3&4, vol. 1, Initiating Events Analysis, December 2015.
  7. U.S. Nuclear Regulatory Commission, Industry-average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants, 2007. NUREG/CR-6928.
  8. http://nrcoe.inl.gov/radscalc/.
  9. http://opis.kins.re.kr/.
  10. Korea Hydro & Nuclear Power Co, Ltd, At-Power Internal Events Level 1 PSA Report for Wolsong Units 2/3/4, vol. 1, Initiating Events Analysis, December 2015.
  11. Ministry of Trade, Industry & Energy, Korea Hydro & Nuclear Power Co, Ltd, 2013 White Paper on Nuclear Power Generation, November 2013. Administrative publication No. 11-1410000-00273-10.
  12. U.S. Nuclear Regulatory Commission, Reevaluation of Station Blackout Risk at Nuclear Power Plants - Analysis of Loss of Offsite Power Events: 1986-2004 (NUREG/CR-6890), vol. 1, 2005. Washington, D.C.
  13. Korea Hydro & Nuclear Power Co, Ltd, At-Power Internal Events Level 1 PSA Report for Hanul Units 3&4, vol. 7, Quantification, December 2015.
  14. Korea Hydro & Nuclear Power Co, Ltd, Low Power & Shutdown (LPSD) Internal Events Level 1 PSA Report for Hanul Units 3&4, December 2015.
  15. U.S. Nuclear Regulatory Commission, Handbook of Parameter Estimation for Probabilistic Risk Assessment, 2003. NUREG/CR-6823.
  16. R.E. Kass, D. Steffey, Approximate Bayesian inference in conditionally independent hierarchical models (parametric empirical Bayes models), J. Am. Stat. Assoc. 84 (1989) 717-726. https://doi.org/10.1080/01621459.1989.10478825