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Core Management and Fuel Handling for Nuclear Power Plants

Aimed primarily at operating organizations of nuclear power plants and regulatory bodies, this Safety Guide covers the safety objective of core management and the basic tasks of the core management programme. The receipt of fresh fuel, storage and handling of fuel assemblies and core components, the loading and unloading of fuel assemblies and core components, and the insertion and removal of other reactor materials are within the scope of this Safety Guide. The publication also covers the preparations for the dispatch of irradiated fuel from the site.

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2022
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No.

Operational Limits and Conditions and Operating Procedures for Nuclear Power Plants

The recommendations provided in this Safety Guide are aimed primarily at operating organizations of nuclear power plants and regulatory bodies. It covers the concept of operational limits and conditions (OLCs), their content as applicable to nuclear power plants, and the responsibilities of the operating organization for their establishment, modification, compliance and documentation. Operating procedures (including emergency operating procedures and severe accident management guidelines) to support the implementation of the OLCs and to ensure their observance are also within the scope of this Safety Guide.

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No.

Modifications to Nuclear Power Plants

Aimed primarily at regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide provides recommendations on controlling activities relating to modifications to nuclear power plants. It covers modifications relating to plant configuration and to the operating organization, as well as temporary modifications. The responsibilities of the operating organization for the design, safety assessment and review, control, implementation and testing of these modifications are also within the scope of this Safety Guide as are the repair and replacement of equipment and components as part of the maintenance of the plant leading to new components.

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2022
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No.

The Operating Organization for Nuclear Power Plants

Written for use by regulatory bodies and the operating organizations of nuclear power plants, this Safety Guide addresses the commissioning, operation and preparation for decommissioning stages for a nuclear power plant. The role of the operating organization in the siting, design, manufacturing and construction of a nuclear power plant is outside the scope. In most States, the operating organization is the legal entity responsible for safety, financial and commercial obligations, as well as other obligations that are connected with the operation of a nuclear power plant. This Safety Guide is solely concerned with those responsibilities and obligations that are necessary to ensure the safe operation of the nuclear power plant(s) under the control of the operating organization.

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2022
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No.

Criticality Safety in the Handling of Fissile Material

The objectives of nuclear criticality safety are to prevent a self-sustained nuclear chain reaction. This Safety Guide provides guidance and recommendations on how to meet the relevant requirements for ensuring subcriticality when dealing with fissile material and for planning the response to criticality accidents. The recommendations address how to ensure subcriticality in systems involving fissile materials during normal operation and during credible abnormal conditions, from initial design through commissioning, operation and decommissioning. This publication also provides recommendations on identification of credible abnormal conditions; performance of criticality safety assessments; verification, benchmarking and validation of calculation methods; safety measures to ensure subcriticality; and management of criticality safety. The guidance and recommendations are applicable to both regulatory bodies and operating organizations.

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SSG-27 (Rev. 1)
Specific Safety Guide
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2022
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No.

Safety in the Utilization and Modification of Research Reactors

This Safety Guide is a revision of IAEA Safety Standards Series No. SSG-24, which it supersedes. The current publication provides recommendations on how to meet the applicable safety requirements relating to the utilization and modification of research reactors. The recommendations focus on the categorization, safety assessment and approval of research reactor experiments and modification projects. The publication also incorporates the relevant lessons learned from the accident at the Fukushima Daiichi nuclear power plant and elaborates on interfaces between nuclear safety and nuclear security. Specific safety considerations in different phases of utilization and modification projects are covered, including pre­implementation, implementation, and post implementation phases. Guidance is given on operational safety of experiments, including the handling, dismantling, post-irradiation examination and disposal of experimental devices. The publication is intended to be of use to individuals within the operating organizations of research reactors, regulatory bodies, as well as the experimenters, technical support organizations and other persons involved in utilization and modification projects.

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SSG-24 (Rev. 1)
24
Specific Safety Guide
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No.

Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report

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.

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SSG-20 (Rev. 1)
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Format and Content of the Package Design Safety Report for the Transport of Radioactive Material

Requirements for the safe transport of radioactive material are established in IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material, 2018 Edition. Packages intended for the transport of radioactive material have to be designed to meet applicable national and international regulations. For package designs that require approval by a competent authority, the documentary evidence of compliance with the applicable regulations is commonly known as package design safety report (PDSR). For package designs that do not require competent authority approval, a PDSR would also be an appropriate form of documentary evidence of compliance with the Transport Regulations. This Safety Guide provides recommendations on the preparation of a PDSR to demonstrate compliance of a package design for the transport of radioactive material with the Transport Regulations. This Safety Guide is intended for use by applicants for approval of package designs (when package designs are subject to competent authority approval) as well as by package designers and/or consignors (when package designs do not require competent authority approval). Regulators will benefit from the common structure for the competent authority assessment process, and designers and consignors will find a consistent approach to justify the compliance of a package design with the regulatory requirements.

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SSG-66
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No.

Advisory Material for the IAEA Regulations for the Safe Transport of Radioactive Material (2018 Edition)

This Safety Guide provides recommendations and guidance on achieving and demonstrating compliance with IAEA Safety Standards Series No. SSR-6 (Rev. 1), Regulations for the Safe Transport of Radioactive Material (2018 Edition), which establishes the requirements to be applied to the national and international transport of radioactive material. Transport is deemed to comprise all operations and conditions associated with and involved in the movement of radioactive material, including the design, fabrication and maintenance of packaging, and the preparation, consigning, handling, carriage, storage in transit, shipment after storage and receipt at the final destination of packages. The Advisory Material is not a stand-alone text. It is to be used concurrently as a companion to the IAEA Safety Standards Series No. SSR-6 (Rev. 1) and each paragraph of this guide is numbered correspondingly to the paragraph of the Regulations to which it most directly relates.

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SSG-26 (Rev. 1)
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No.

Protection Against Internal and External Hazards in the Operation of Nuclear Power Plants

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.

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No.

Seismic Hazards in Site Evaluation for Nuclear Installations

This Safety Guide supersedes the 2010 edition of IAEA Safety Standards Series No. SSG-9. It takes account of recently gained knowledge and practices developed by Member States related to seismic hazards, especially lessons from the Fukushima Daiichi accident. It also addresses concomitant events associated with earthquakes, such as tsunamis. The revision provides a clearer separation between the process for assessing the seismic hazards at a specific nuclear installation site and the process for defining the related basis for design and safety assessment of the nuclear installation. Thus, it bridges gaps and avoids undue overlap of the two processes, which correspond to and are performed at different stages of siting of the nuclear installation.

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Preparedness and Response for a Nuclear or Radiological Emergency Involving the Transport of Radioactive Material

This publication provides guidance and recommendations on arrangements to be made at the preparedness stage, as part of overall emergency preparedness, for emergencies involving the transport of radioactive material. The guidance and recommendations in this Safety Guide are aimed at any State and its government, and at regulatory bodies and other response organizations, including consignors, carriers and consignees. It supports the implementation of the requirements established in IAEA Safety Standards Series No. GSR Part 7 for such emergencies, irrespective of their cause, and the IAEA Transport Regulations, IAEA Safety Standards Series No. SSR-6 (Rev. 1).

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