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국내 원자력발전소의 화재사건 확률론적안전성평가에서 다중오동작 분석 연구

A Study on the Multiple Spurious Operation Analysis in Fire Events Probabilistic Safety Assessment of Domestic Nuclear Power Plant

  • 강대일 (한국원자력연구원 리스크.환경안전연구부) ;
  • 정용훈 (한국원자력연구원 리스크.환경안전연구부) ;
  • 최선영 (한국원자력연구원 리스크.환경안전연구부) ;
  • 황미정 (한국원자력연구원 리스크.환경안전연구부)
  • 투고 : 2018.10.01
  • 심사 : 2018.12.11
  • 발행 : 2018.12.31

초록

In this study, we conducted a pilot study on the multiple spurious operations (MSO) analysis in the fire probabilistic safety assessment (PSA) of domestic nuclear power plant (NPP) to identify the degree of influence of the operator actions used in the MSO mitigation strategies. The MSO scenario of the domestic reference NPP selected for this study is refueling water tank (RWT) drain down event. It could be caused by spurious operations of the containment spray system (CSS) of the reference NPP. The RWT drain down event can be stopped by the main control room (MCR) operator actions for stopping the operation of CSS pump or closing the CSS motor operated valve if the containment spray actuation signal (CSAS) is spuriously actuated. Outside the MCR, it can be stopped by operator actions for closing the CSS manual valves or motor operated valve or stopping the operation of CSS pump. The quantification result of a fire PSA model that takes into account all recovery actions for the RWT drain down event lead to risk reduction by about 95%, compared with quantification result of fire PSA model without considering them. Among the various operator actions, the recovery action for the spurious CSAS operations and the operator action for the manual valve are identified as the most important operator actions. This study quantitatively showed the extent to which the operator actions used as MSO countermeasures have affected the fire PSA quantification results. In addition, we can see the rank of importance among the operator recovery actions in quantitative terms.

키워드

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Fig. 1. Simplified diagram of containment spray system for the reference NPP.

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Fig. 2. Event tree of small LOCA for the reference NPP.

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Fig. 3. Fault tree of HPSIS injection for the reference NPP.

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Fig. 4. Fault tree of MSO scenario for fire-induced RWT drain down.

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Fig. 5. Fault Tree of MSO scenario for Fire-Induced RWT drain down (recovery)(1/2).

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Fig. 6. Fault Tree of MSO scenario for Fire-Induced RWT drain down (recovery)(2/2).

Table 1. Recovery actions for MSO scenarios for RWT drain down

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Table 2. Quantification results of fire-induced RWT drain down MSO scenario

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참고문헌

  1. H. J. Jeon, "A Risk Impact Assessment according to the Reliability Improvement of the Emergency Power Supply System of a Nuclear Power Plant", J. Korean Soc. Saf., Vol. 27, No. 5, pp. 224-228, 2012. https://doi.org/10.14346/JKOSOS.2012.27.5.224
  2. D. I. Kang and K. Kim, "A Study on the Constructions of Fire Events Probabilistic Safety Assessment Model for Nuclear Power Plants", J. Korean Soc. Saf., Vol. 31, No. 5, pp. 187-194, 2016. https://doi.org/10.14346/JKOSOS.2016.31.5.187
  3. Nuclear Safety and Security Commission, "Technical Standards of Fire Hazard Analysis", NSSC Notice No. 2015-11, 2015.
  4. B. Najafi, S. P. Nowlen, F. Joglar, D. Funk, R. C. Anoba, M. Kazarians, F. Wyant, A. Kolaczkowski, G. Hannaman and J. Forester, "Fire PRA methodology for Nuclear Power Facilities", NUREG/CR-6850, USNRC, 2005.
  5. USNRC, "Enforcement Guidance Memorandum-Enforcement Discretion for Fire Induced Circuit Faults," EGM 09-002, 2009.
  6. NEI, "Guidance for Post Fire Safe Shutdown Circuit Analysis", NEI 00-01, Revision 3, Nuclear Energy Institute, 2011.
  7. Richard C. Anoba, "Mapping of Fire Events to Multiple Internal Events PRA Initiating Events", International Topical Meeting on Probabilistic Safety Assessment and Analysis PSA 2011, March 13-17, 2011.
  8. N. Lovelace et al., "Approach for Integration of Initiating Events into External Event Models", Probabilistic Safety Assessment and Management PSAM 12, June 2014.
  9. D. I.Kang and Y. H. Jung, "Comparative Study on the Construction of Support System Initiating Event Fault Trees for a Fire Probabilistic Safety Assessment", Nuclear Engineering and Design 332, pp 345-356, 2018. https://doi.org/10.1016/j.nucengdes.2018.03.038
  10. H. Yuehua, L. Lin, Y. Zhen and S. Lei, "The Application of Fault Tree Method in Systematic Multiple Spurious Operation Analysis in Fire PSA", 25th International Conference on Nuclear Engineering, Shanghai, China, July 2-6, 2017.
  11. J. Lee and J. H. Kim, "Study on Post-Fire Safe Shutdown Analysis using an Imaginary Plant for Training", Fire Science & Engineering, Vol. 32, No. 1, pp. 57-65, 2018.
  12. H. Yim, S. Oh and W. Kim, "A Study on the Verification Scheme for Electrical Circuit Analysis of Fire Hazard Analysis in Nuclear Power Plant", J. Korean Soc. Saf., Vol. 30, No. 3, pp. 114-122, 2015. https://doi.org/10.14346/JKOSOS.2015.30.3.114
  13. I. H. Kim, H. S. Lim and Y. K. Bae, "Study of Post-Fire Safe-Shutdown Analysis of a CANDU Main Control Room based on NEI 00-01 Methodology", Fire Science & Engineering, Vol. 30, No. 4, pp. 20-26, 2016. https://doi.org/10.7731/KIFSE.2016.30.4.020
  14. Y. Lee, Y. K. Bae and M. Kim, "Analysis of Multiple Spurious Operation Scenarios for Decay Heat Removal Function of CANDU Reactors", Transactions of the Korean Nuclear Society Autumn Meeting Gyeongju, Korea, October 27-28, 2016.
  15. D. I. Kang et al., "A Pilot Study on the Multiple Spurious Operation Scenario Analyses for the Construction of Fire Events PSA Model", KAERI/TR-7359/2018, KAERI, 2018.
  16. S. Lewis et al., "EPRI/NRC-RES Fire Human Reliability Analysis Guidelines", NUREG1-1921, USNRC, 2012.
  17. A. D. Swain and H.E. Guttmann, "Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications", USNRC, NUREG/CR-1278, 1983.