• DocumentCode
    3313316
  • Title

    “Level-1 PSA of RAPS-2: Review of the safety of the first Indian PHWR by probabilistic method”

  • Author

    Jha, K.K. ; Budhiraja, Y.K. ; Vijaya, A.K. ; Guptan, Rajee

  • Author_Institution
    Nucl. Power Corp. of India Ltd., Mumbai, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    230
  • Lastpage
    233
  • Abstract
    This paper presents the tasks and insights of Level-1 PSA of Rajasthan Atomic Power Station, RAPS-2 viz. Initiating Events, Event Tree Analysis, Data Analysis and Quality Assurance program. This also brings out the strengths in design and operating experiences of the oldest IPHWR. The PSA has been carried out with plant specific data to gain insights to the overall safety of the plant. In the present analysis, the entire spectrum of fuel damage accidents has been considered with four major classes. These were further sub-divided depending on the severity of core damage. Common Cause Failures and Human reliability have also been considered. The calculated CDF indicate good operational health and adequacy of maintenance program & surveillance requirements.
  • Keywords
    data analysis; fission reactor accidents; fission reactor containment; fission reactor core control; heavy water reactors; nuclear reactor maintenance; CDF; Indian PHWR; RAPS-2; Rajasthan Atomic Power Station; common cause failures; core damage; data analysis; event tree analysis; fission reactor containment; fuel damage accidents; human reliability; level-1 PSA; maintenance program; probabilistic method; Biomedical monitoring; Inductors; Instruments; Monitoring; Reliability; Valves; CDF; PSA; Quality Assurance;
  • 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.2010.5779552
  • Filename
    5779552