This Safety Guide provides recommendations on the design of nuclear installations for protection against the effects of external events (excluding earthquakes), meeting the applicable safety requirements established in relation to the design aspects of nuclear installations subjected to external events. It provides methods and procedures for defining an appropriate design for a nuclear installation, based on the site hazard evaluation and the layout of the installation. The aim is to provide design guidance, in particular for the protection of structures, systems and components important to safety against design basis external events. The guide also provides recommendations on the selection of beyond design basis external events, in order to check and verify safety margins.

This Safety Guide provides recommendations on the design of nuclear installations for protection against the effects of external events (excluding earthquakes), meeting the applicable safety requirements established in relation to the design aspects of nuclear installations subjected to external events. It provides methods and procedures for defining an appropriate design for a nuclear installation, based on the site hazard evaluation and the layout of the installation. The aim is to provide design guidance, in particular for the protection of structures, systems and components important to safety against design basis external events. The guide also provides recommendations on the selection of beyond design basis external events, in order to check and verify safety margins.

This Safety Guide provides recommendations for ensuring radiation protection in the design of new nuclear power plants, design modifications to operating plants, and checking the adequacy of the radiation protection aspects of design at different stages in the lifetime of operating plants. It also provides recommendations for measures to be taken in the design for the protection of site personnel, the public and the environment, and outlines the methodologies used to calculate on-site and off-site radiological conditions and to verify that the design provides an adequate level of radiation protection during operating lifetime and decommissioning. The guide is intended primarily for land-based, stationary nuclear power plants with water cooled reactors designed for electricity generation or for other heat generating applications. This publication is intended for organizations responsible for designing, manufacturing, and constructing nuclear power plants, operating organizations and contractors, including plant operators who are involved in planning, managing and implementing the design and design modification of nuclear power plants, and regulatory bodies and technical support organizations.

This Safety Guide provides specific recommendations on protection against internal and external hazards in the operation of nuclear power plants. It provides new or updated recommendations derived from enhanced understanding of operational aspects of hazards and combinations of hazards. Operating experience gained from incidents and accidents in nuclear power plants around the world has demonstrated that fire can be an important risk contributor in many Member States. However, there are other internal and external hazards that have also to be considered in the design and operation of nuclear power plants. This Safety Guide supersedes and expands the scope of lAEA Safety Standards Series No. NS- G-2. 1, Fire Safety in the Operation of Nuclear Power Plants, to include recommendations on these other hazards.

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.

The objective of this Safety Guide is to provide recommendations for meeting the requirements of GSR Part 4 (Rev. 1) in the development and application of Level 1 Probabilistic Safety Assessments (PSAs) for nuclear power plants (NPPs). The recommendations provided in this publication promoting technical consistency among Level 1 PSA studies, in order to provide reliable support for applications of PSAs and risk informed decision making, particularly to support the design of NPPs and decision making during plant commissioning and operation. The revised Safety Guide's scope encompasses the main methodological aspects of PSA and in particular has been updated to reflect developments in specific areas, such as passive systems reliability, computer based systems reliability, combinations of hazards, human reliability analysis and to expand the scope of PSA to include site level risk considerations such as multi-unit and spent fuel pool PSA.

This Safety Guide provides recommendations on how to meet the requirements of IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design, in relation to fuel handling and storage systems. The publication addresses the design aspects of handling and storage systems for fuel that remain part of the operational activities of a nuclear reactor. It covers the following stages of fuel handling and storage in a nuclear power plant: receipt, storage and inspection of fresh fuel before use and transfer of fresh fuel into the reactor; removal of irradiated fuel from the reactor and transfer of the irradiated fuel to the spent fuel pool; and reinsertion of irradiated fuel from the spent fuel pool into the reactor. Recommendations are also provided on the storage, inspection and repair of irradiated or spent fuel in the spent fuel pool, and the preparation for the removal of this fuel from the spent fuel pool and on the handling of fuel casks in the spent fuel pool and on their transfer.

In response to an increase in global activities related to non-water-cooled reactors and small modular reactors, this new Safety Report documenting areas of novelty of these technologies when compared to the current fleet of reactors has been developed. The impact of these areas of novelty on the applicability and completeness of the IAEA safety standards is assessed in the publication. Gaps and areas for additional consideration are identified. The review undertaken to develop this report encompassed the safety standards related to the lifetime of these reactor technologies. The publication also considers the interface between safety, security, and safeguards in the design of these technologies.

This publication explains how a reactor technology assessment is performed and how the process and its results enable decision making for nuclear power planning and implementation at each of its phases. The methodology has been revised to incorporate developments since the first edition in 2013 and includes feedback from comprehensive training workshops offered for the last six years to Member States introducing nuclear power programmes. The aim of this publication is to help newcomer Member States to understand the complexity involved in the selection of the most suitable reactor technology as well as obligations and responsibilities integral to an unbiased assessment. The publication can also be used by countries that already have nuclear power programmes, to assist in their selection of the next nuclear power plant.

This Safety Guide provides recommendations on how to meet the requirements established in IAEA Safety Standards Series No. SSR-2/1 (Rev. 1) in relation to the reactor coolant system and associated systems for nuclear power plants. It is a revision of IAEA Safety Standards Series No. NS-G-1.9, which it supersedes. The publication takes into account developments, experience and practices in the design of nuclear power plants throughout their lifetime. It references and considers other IAEA safety standards that are relevant and related to the design of the reactor coolant system and associated systems for nuclear power plants. Recommendations to achieve the required reliability of the capabilities designed to transfer residual heat to the ultimate heat sink in the different plant states are also included. As those systems are dependent on specific reactor technologies, more appropriate recommendations have been developed respectively for pressurized light water reactors, boiling water reactors and pressurized heavy water reactors.