IEC TR 63192
Nuclear power plants – Instrumentation and control systems important to safety – Hazard analysis: a review of current approaches
|Publication Date:||1 January 2019|
|ICS Code (Solar energy engineering):||27.160|
This document provides the comparison of the hazard analysis requirements between IAEA framework and NRC-IEEE framework of standards and guidance. The hazard analysis requirements in the different standards were compared with a set of comparison criteria, including the safety principle, the safety process, the definitions, the hazard analysis process, etc. This document includes the comparison results of the HA requirements of the safety control systems of other safety industries in Annex C.
For a nuclear power plant, the design safety and operation safety shall be analyzed, for example, to meet the IAEA Safety Requirements for Design (SSR-2/1) and Operation (SSR-2/2). The scope of this document is to survey the state of the art in the hazard analysis for the design of I&C system of NPPs.
Figure 1 illustrates the scope of I&C systems important to safety which have hazard analysis requirements, in the form of a three by three matrix which is in IEEE 603-2009. This document covers the hazard analysis for the sense and command features of digital systems. This document also considers the requirements for hazard analysis of the system of systems(SoS), including the software, hardware and human for the digital systems.