An internal Fire Probabilistic Safety Assessment (FPSA) study was conducted in the control room of the TRIGA PUSPATI (RTP) research reactor. This study aims to determine the likelihood of a fire occurring in the control room of RTP and the probability of fire occurring after an accident loss of instrumentation and control (LOIC) to the core damage frequency (CDF) value. The quantification results of the CDF are compared between LOIC with fire-induced (LOIC-F) and without fire-induced (LOIC). A methodical strategy to identify potential fire hazards that includes the precise identification of the design area, the size of any opening compartments, the location of electrical cabinets and fire suppression systems, as well as the placement of any safety-related equipment was applied. Included is Failure Mode and Effect Analysis (FMEA), which determines failure modes and designates repercussions for each scenario. This research will contribute on providing essential information on status of fire in RTP’s control room as an insight of identifying any risk of fire scenario that may occur including investigation of current fire protection system sufficiency. In addition, a core damage end state of consequences of fire after an LOIC is also presented. The result of this research can be beneficial and creating awareness to the management as well as reactor operators in case of fire in the control room of RTP.
An internal fire analysis Level-I probabilistic safety assessment (PSA) for TRIGA PUSPATI (RTP) nuclear research reactor was initiated. Previous study on half-scope mode Level-I PSA, focusing only on internal initiating event, were developed for both full power and shutdown operational mode. Hence, in ensuring PSA remains relevant, a subsequent study to kept PSA up to date is a compulsory. The aim of this study is to present the step-by-step work done and the insights gained in identifying and screening significant compartments that are potential to had the worst consequences as an ignition sources. This preliminary study will only focus on RTP’s basement which consist of 3 compartments: switch room, battery room and basement hall. Procedure in data collection were based on IAEA document, Specific Safety Guide No. 3: Development and Application of Level 1 Probabilistic Safety Assessment for Nuclear Power Plants (SSG-3). Microsoft Excel was used as data collection media and internal fire hazard database development. A brief qualitative analysis using failure mode and effect analysis is also presented.
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