Periodic Safety Review For Research Reactors

This publication provides information and guidance on the establishment of a process for periodic safety review for research reactors, including preparation, conduct of the review and reporting of results. In addition, it covers the regulatory assessment of these results. The publication also provides information on the experience of Member States in establishing and implementing periodic safety reviews of research reactors, including implementation of reasonable and practical improvements based on these reviews.

This Safety Guide provides recommendations and guidance on conducting periodic safety review (PSR) of an existing nuclear power plant. PSR is a comprehensive safety review of all important aspects of safety, carried out at regular intervals, typically every ten years. In addition, PSR may be used in support of the decision making process for licence renewal or long term operation, or for restart of a nuclear power plant following a prolonged shutdown. The review process described in this Safety Guide is valid for nuclear power plants of any age and may have a wider applicability, for example to research reactors and radioactive waste management facilities, by means of a graded approach. Although PSR may not be an appropriate means for identifying safety issues in the decommissioning phase, the documentation resulting from PSR of an operating nuclear power plant will be an important input when planning decommissioning.

Establishes requirements for all areas of the safety of research reactors, with particular emphasis on requirements for design and operation. This publication covers the lifetime of research reactor facilities, from site evaluation to design and construction, commissioning, operation, including utilization and modification, and decommissioning.

This publication presents international consensus principles useful in the operation of a research reactor. It is complemented by Safety Series No. 35-S1, Code on the Safety of Nuclear Research Reactors: Design. Both publications provide basic principles and requirements for the safety of research reactors and critical assemblies, including the essential safety requirements for siting, quality assurance and regulatory control. These codes supersede the 1984 edition of Safety Series No. 35, Safe Operation of Research Reactors and Critical Assemblies.

This Safety Guide provides recommendations on the safety assessment for research reactors in the authorization process, and on performance of safety analysis and preparation of the safety analysis report. It also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates guidance on interfaces between nuclear safety and nuclear security. The recommendations in this Safety Guide are intended for operating organizations of research reactors; it can also be used by designers performing a safety assessment for a research reactor. Furthermore, this guide provides useful guidance for regulatory bodies performing a review and assessment of submitted safety analysis reports as an important document within authorization process. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-20, which it supersedes.

This Safety Guide provides specific recommendations on the maintenance, periodic testing and inspection of research reactors to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It provides guidance on design considerations and recommends good practices in implementing the programme and establishing the organization and responsibilities for maintenance, periodic testing and inspection as well as for the selection, training and qualification of personnel. Procedures, administrative controls and maintenance facilities are also covered as well as procurement and storage of spare parts and components, and testing and inspection methods and techniques used for maintenance, periodic testing and inspection. The recommendations provided in this Safety Guide are aimed at operating organizations of research reactors, regulatory bodies and other organizations involved in a research reactor project. This Safety Guide is a revision of IAEA Safety Standards Series No. NS-G-4.2, which it supersedes.

This Safety Guide provides practical guidance and recommendations on ageing management for research reactors, to meet the relevant requirements of IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors. It is intended for use by operating organizations in establishing, implementing and improving ageing management programmes for research reactors, and by regulatory bodies in verifying that ageing of research reactors is being effectively managed. The Safety Guide focuses on managing the physical ageing of systems, structures and components important to safety, and also provides guidance on safety aspects of managing obsolescence. This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-10, which it supersedes.

Presents guidelines, approved by international consensus, for the preparation, review and assessment of the safety documentation (Safety Series No. 35-S1) and for the preparation of the Safety Analysis Report (SAR) (Safety Series No. 35-S2).