Mesures préventives concernant les matières nucléaires et autres matières radioactives non soumises à un contrôle réglementaire

Guide d’application

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• Éditeur: International Atomic Energy Agency
• Année: 2021
• ISBN de l'eBook: 9789202433212
• Sujet: Technologie et ingénierie
• Sujet: Génie mécanique

La présente publication décrit plus en détail les recommandations relatives aux mesures préventives figurant dans la publication no 15 de la collection Sécurité nucléaire de l'AIEA, intitulée « Recommandations de sécurité nucléaire sur les matières nucléaires et autres matières radioactives non soumises à un contrôle réglementaire ». Elle sert de document d'orientation aux États Membres qui souhaitent renforcer leur régime de sécurité nucléaire en ce qui concerne les matières nucléaires et autres matières radioactives non soumises à un contrôle réglementaire et améliorer leurs capacités. Elle couvre les éléments indicatifs suivants: considérations générales concernant les mesures préventives; mesures de dissuasion, à la fois par la sanction et par le découragement; sécurité de l'information; promotion d'une culture de sécurité nucléaire; et mesures visant à faire face à la menace interne, notamment à promouvoir la loyauté du personnel. La dernière section donne des orientations sur la coopération et l'assistance internationales en vue du renforcement des mesures préventives.

1. INTRODUCTION

Background

1.1. IAEA Safety Standards Series No. SSR-2/1 (Rev. 1), Safety of Nuclear Power Plants: Design [1], establishes design requirements for the structures, systems and components (SSCs) of a nuclear power plant. Requirements for the design of research reactors and of nuclear fuel cycle facilities are established in IAEA Safety Standards Series No. SSR-3, Safety of Research Reactors [2], and IAEA Safety Standards Series No. SSR-4, Safety of Nuclear Fuel Cycle Facilities [3], respectively. These publications include requirements for the design to take into account external events, including earthquakes. This Safety Guide provides specific recommendations on the design of nuclear installations to cope with the effects generated by earthquakes.

1.2. This Safety Guide incorporates the following:

(a) Progress in the design of nuclear installations and in related research, as well as regulatory practices in States, considering the lessons identified from recent strong earthquakes that have affected nuclear installations;

(b) Recent developments in regulatory practices on application of risk informed and performance based approaches for assessing the safety of nuclear installations;

(c) The experience and results from seismic design for new nuclear installations in States;

(d) A more coordinated treatment of the design of nuclear installations against seismically induced geological and geotechnical hazards and concomitant events.

1.3. This Safety Guide provides a clear distinction between (a) the process for assessing the seismic hazards at a specific site and (b) the process for defining the related basis for design and evaluation of the nuclear installations. These processes correspond to (and are performed at) different stages in the lifetime of a nuclear installation. This Safety Guide addresses the interface between these processes so as to bridge any gaps between them and avoid undue overlapping of recommendations.

1.4. Recommendations on the process for assessing the seismic hazards at a specific site, including the definition of the parameters resulting from such an assessment, are provided in IAEA Safety Standards Series No. SSG-9 (Rev. 1), Seismic Hazards in Site Evaluation for Nuclear Installations [4].

1.5. There is an important difference between the seismic design and the seismic safety evaluation of nuclear installations. Seismic design and qualification of SSCs is most often performed at the design stage of the installation, prior to its construction. Seismic safety evaluation can be conducted at the design stage (using data corresponding to the detailed design) and after the installation has been constructed (using as-built and as-operating conditions). There are some exceptions, such as the seismic design of new or replacement components after construction of the installation. Recommendations on the evaluation of existing nuclear installations are provided in IAEA Safety Standards Series No. NS-G-2.13, Evaluation of Seismic Safety for Existing Nuclear Installations [5].

1.6. In several States, designs of new nuclear reactors are being developed generically to meet the needs of many sites across a large geographical area. The intent is that each generic design uses design bases that envelop the potential seismic hazard challenges at all the candidate sites. Confirmation of this is needed when a generic design is nominated for a particular site. At this point, the site specific seismic hazards need to be assessed and compared with the generic seismic hazard design bases to ensure there is an acceptable enveloping margin between them.

1.7. This Safety Guide supersedes IAEA Safety Standards Series No. NS-G-1.6, Seismic Design and Qualification for Nuclear Power Plants1.

Objective

1.8. The objective of this Safety Guide is to provide recommendations on how to meet the safety requirements established in SSR-2/1 (Rev. 1) [1], SSR-3 [2...

Table des matières

• 1. INTRODUCTION
• REFERENCES
• DEFINITIONS
• CONTRIBUTORS TO DRAFTING AND REVIEW