• DocumentCode
    3313282
  • Title

    NAPS PSA application allowed outage time optimisation

  • Author

    Phukan, Nipu ; Singh, Bhim ; Jain, L.K. ; Vijaya, A.K. ; Guptan, Rajee

  • Author_Institution
    NAPS Oper., Narora Atomic Power Station (NAPS), Narora, India
  • fYear
    2010
  • fDate
    14-16 Dec. 2010
  • Firstpage
    222
  • Lastpage
    225
  • Abstract
    PSA provides an integrated model of the overall safety of the plant, which puts the safety issues in perspective, and helps in safety decisions related to both design and operations. NAPS Level-l PSA has been completed with the objective of presenting an integrated picture of safety of the NAPS which encompasses design, operational practices, component reliability, dependencies and human reliability. This has helped in understanding the weak links and plant vulnerabilities and the strengths in design and operational practices. There is always a desire to optimize the technical competency, resources and to operate the plant in most efficient practicable manner. In recent years, the operation of Indian Nuclear Power Plants has been characterized by improved availability/capacity factors and reduced forced outages. NAPS Technical Specification for operation has been revised in the year 2009. NAPS PSA level-1 was extensively used as an engineering tool for Risk Informed Decision making for optimization of Station Technical Specifications with regard to Allowed Outage Time (AOT) and Surveillance Test Intervals (STIs). The approach outlined in USNRC RG-1.174 [5] andRG-1.177 [6] has been used as a guideline for optimization of Allowed Outage Time taking into consideration Instantaneous (conditional) risk, Cumulative Risk over the allowed outage time period, and the average risk over a long period. This paper outlines the approaches followed for the revision of AOTs in station technical specification. The paper also covers the acceptance criteria for the assessment of the submittals on technical specification change proposals. The illustrative clauses, where application of this methodology for technical specification optimization are presented.
  • Keywords
    fission reactor safety; nuclear power stations; nuclear reactor maintenance; risk management; Indian Nuclear Power Plants; NAPS PSA application; RG-1.177; Risk Informed Decision making; USNRC RG-1.174; allowed outage time optimisation; cumulative Risk; instantaneous risk; integrated model; nuclear power plants; plant vulnerabilities; probabilistic safety assessment; safety decisions; station technical specification; station technical specifications; surveillance test intervals; technical competency; Analytical models; Atomic measurements; Frequency conversion; Frequency estimation; Allowed Outage Time; Probabilistic Safety Assessment; Surveillance Test Interval; Technical Specification;
  • 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.2010.5779550
  • Filename
    5779550