• DocumentCode
    3313152
  • Title

    Application of PSA based operational event analysis to Indian nuclear power plants

  • Author

    Solanki, R.B. ; Gupta, S.K.

  • Author_Institution
    Atomic Energy Regul. Board, Mumbai, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    181
  • Lastpage
    187
  • Abstract
    In the aftermath of catastrophes, it is common to find prior indicators, missed signals and missed alerts that if recognized and appropriately managed well in time, the undesirable events can be averted. It has lead to the practice of identifying such indicators, also known as precursors, and carrying out accident sequence precursor analyses. The results of such analyses help significantly in design evaluation, precursor management and risk assessment. In AERB, the practice has been started of analyzing significant precursors in the Nuclear Power Plants (NPPs). Spurious opening of Instrumented relief valves (IRVs) are observed in Indian NPPs. A similar incident occurred in one of the NPP unit recently. The incident also involved the light water injection through Emergency core cooling system (ECCS). The event is analyzed both deterministically and probabilistically for assessing the safety significance of the event, identification of possible precursors. The operating event has also provided an opportunity to validate the assumptions and models used in the Probabilistic Safety Assessment (PSA) carried out for the plant.
  • Keywords
    fission reactor accidents; fission reactor cooling; fission reactor core control; fission reactor operation; nuclear power stations; Indian nuclear power plants; PSA-based operational event analysis; accident sequence precursor analyses; automatic liquid poison injection system; design evaluation; emergency core cooling system; event progression; fault tree approach; gravity addition system; heat removal systems; instrumented relief valves; poison manual injection; precursor management; probabilistic safety assessment; reactor design; rector protection system; risk assessment; shutdown cooling system; subcritical configuration; Analytical models; Accident precursor analysis; Instrumented relief valve; PSA; nuclear power plants; operational events;
  • fLanguage
    English
  • Publisher
    ieee
  • Conference_Titel
    Reliability, Safety and Hazard (ICRESH), 2010 2nd International Conference on
  • Conference_Location
    Mumbai
  • Print_ISBN
    978-1-4244-8344-0
  • Type

    conf

  • DOI
    10.1109/ICRESH.2010.5779544
  • Filename
    5779544