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The Application for Renewal of Authorisation (ARA) is to be submitted by Operating Nuclear Power Stations to Atomic Energy Regulatory Board (AERB) in India to obtain the consent for operation of plant for the next authorization period. One of the most important elements of this Application for Renewal of Authorisation (ARA) is Reliability Safety Analysis of Safety & Engineered Safety Systems....
There are several equipment failure databases originating in the nuclear power plant that are successfully used in quantitative risk analysis applications Le, probabilistic safety assessment (PSA). Regulatory bodies (like AERB, India) now accept the importance and use of databases for safety and reliability studies in the nuclear industry as industry practice. Databases containing human error data...
In India, grid disturbance is a major cause of plant transients in nuclear power plants, and thus having an impact on plant safety. With better regulation and load management, the frequency of grid disturbance has come down substantially with time. Nevertheless the plant transients initiated by Class-IV power supply failure are experienced regularly. Further the incapability of emergency diesel generators'...
Probabilistic safety assessment (PSA) uses a systematic approach to estimate the reliability and risk of a nuclear power plant (NPP). The level-2 PSA provides a structured assessment of the possible accident sequences that could occur following core damage and gives insights into which of the phenomena that could arise have the greatest potential to lead to containment failure or bypass resulting...
Fire PSA is a probabilistic analysis of fire events and their potential impact on the nuclear safety of a plant. Using probabilistic models, fire PSA takes into account the possibility of a fire at various plant locations (zones); the detection and suppression of the fire; the effect of the fire on safety related cables and equipment; the possibility of damage to these cables & equipments and...
Operational Event is any event which happened at a nuclear power plant leading to an unplanned transient or significantly affecting the plant response characteristics. Such events may be caused by operator errors or equipment failures. The range of events could be from an apparently insignificant event to a transient that leads to reactor trip and subsequent actuation of designed safety systems or...
The objective of Nuclear Power Plant Safety is to ensure and demonstrate that the risk from plant to public and plant personnel is acceptably low. Probabilistic Safety Assessment (PSA) is a standard tool in safety evaluation of nuclear power plants, which provides a useful, consistent and structured framework for evaluation of safety. PSA provides an integrated model of the overall safety of the plant,...
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...
Plant Specific PSA study is the most potent tool to analyze Risk due to Nuclear Power Plant, considering design aspects, operating practices and past operating experience. It requires an optimal mixture of the critical approach of an analyst and the practical approach of an operator to develop a comprehensive and realistic Plant Specific PSA. KAPS Level-I PSA was the first comprehensive PSA carried...
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...
In nuclear power plants, both new and old, computer based instrumentation and control (I and C) systems are being used increasingly in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of engineered safety systems. The dependability of computer based systems important...
Uncertainties are integral part of Probabilistic Safety Assessment (PSA) and arising from incomplete knowledge, simplified assumptions/idealization in modeling complex process/phenomena and unpredictable variation in performance of the system under study. Uncertainties influence the decision making process and help to determine whether robust decision can be made or more information is needed first...
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