Nuclear Technology / Volume 201 / Number 2 / February 2018 / Pages 180-189
Technical Note / dx.doi.org/10.1080/00295450.2017.1407594
Dependability management practices in nuclear power plants in India are conventionally governed by a set of rules known as “safety criteria.” Probabilistic assessments of safety systems are used in a modern plant to complement such rules. In this technical note, various design provisions provided in the instrumentation and control (I&C) of prototype fast breeder reactor (PFBR) (a reactor under commission in India) are detailed. As a precursor, the relationship between safety criteria and the average probability of failure on demand (PFDAvg) of safety systems is established. Subsequently, various design provisions provided in the I&C of PFBR to reduce PFDAvg are discussed. Such a review, with a dependability viewpoint, has resulted in identifying areas for further design improvement in future reactors. Research work carried out in areas of relays toward reducing PFDAvg of safety systems is highlighted.