Safety Assessment Of Emergency Power Systems For Nuclear Power Plants

Presents the questions which must be posed by the safety assessor when reviewing the safety of an emergency power system in the design of a nuclear power plant. An extensive reference list of relevant international and national technical standards provides further guidance on acceptable design solutions.

This publication contains guidance and recommendations on the requirements for ensuring the reliability of all types of emergency powers systems (EPSs) for both new and operating nuclear power plants. It is intended for the use of those involved in the design, operation, assessment and licensing of EPSs, including designers, safety assessors, regulators and operators. It revises the previous safety guide (Safety standards series no. 50-SG-D7 (Rev. 1) (ISBN 9201232918) issued in 1991.

Presents the safety objective, and detailed requirements for the fulfilment of safety function for the various types of emergency power systems. AC, DC, non-interruptible AC, standby diesel generators and non-electric systems such as steam turbines for individual pumps and instrument air, and the necessary distribution systems are dealt with.

This Safety Guide provides recommendations on the structure and content of the safety analysis report to be submitted by the operating organization to the regulatory body for authorization of the siting, construction, commissioning, operation and decommissioning of a nuclear power plant. It is intended to facilitate both the development of the safety analysis report by the operating organization and the checking of its completeness and adequacy by the regulatory body. The publication is a revision of IAEA Safety Standards Series No. GS-G-4.1, Format and Content of the Safety Analysis Report for Nuclear Power Plants, which it supersedes. The revision reflects feedback experience from the Fukushima Daiichi accident and the subsequent stress tests performed. It also describes good practices and experience from the use of safety analysis reports for newly built nuclear power plants in different States and informs on recent progress made in approaches to safety assessment.

This guide deals primarily with design requirements for instrumentation and control systems important to safety but not part of the protection system (Safety Series No. 50-SG-D3). It gives recommendations on instrumentation and control systems for the prevention or termination of plant transients to avoid, if possible, the actuation of safety systems.

Provides a detailed list of the issues, and some of the limitations, to be considered when evaluating the adequacy and effectiveness of the fire hazard analysis of a nuclear power plant. It further gives a broad description of the methodology to be used by operators in preparing a fire hazard analysis for their own plant.