This publication gives the general roadmap on how to perform the design and evaluation of the protection of nuclear power plants against human induced external hazards, consistent with IAEA Safety Standards. The publication concentrates on an overall view of the methodology and on the important considerations for its application to existing and new nuclear power plants. Topics covered include elements of the design/evaluation approach, developed in five phases: event identification; load characterization; design and assessment approaches; plant performance assessment and acceptance criteria; and operator response. The publication provides an approach to the assessment of extreme human induced external events which is fully consistent with the methods used for evaluation of nuclear facilities subjected to extreme natural events, such as earthquakes and floods.

This publication provides detailed guidelines for the safety assessment of nuclear power structures against mechanical impact, explosion and fire caused by human induced external events. It covers the characterization of loading, the assessment of structural integrity using both simplified methods and more elaborated methodologies, and the assessment of induced vibration. The acceptance criteria provided in the publication are for different failure modes: overall stability, overall bending and shear, local failure modes and induced vibrations. The process of analysing fire consequences is also included.

This publication describes the procedures for calculating the margins of nuclear power plants in relation to human induced external hazards. It focuses on plant and systems performance evaluations. A two level approach for margin assessment is provided. The first level consists of a deterministic procedure in which, for each scenario, the existence of at least one undamaged success path to comply with the fundamental safety function is investigated. This procedure can be subsequently extended to calculate probability measures such as conditional core damage probability and the conditional probability of spent fuel damage. In the most elaborated stage, probabilistic safety assessment (PSA) techniques are introduced, giving consideration to the probabilistic aspects of the hazards and of the capacity of structures, systems and components (fragility). Event tree and fault tree models are used to compute PSA metrics, such as core damage frequency, large-early release frequency and frequency of spent fuel damage.

Recommends actions, conditions and procedures in relation to external human induced events and provides guidance for fulfilling the requirements of Safety Standards Series No. NS-R-3, Site Evaluation for Nuclear Installations, when conducting a site evaluation for a nuclear power plant.

This guide advises on the protection of nuclear power plants against the effects of external man-induced events which originate outside the site and which have been identified and selected as design basis external man-induced events (DBEMIEs) according to Safety Guide No. 50-SG-S5, to which this guide is complementary.

This guide discusses the hazardous phenomena associated with external man-induced events, such as aircraft crashes, explosions, release of hazardous fluids using screening distances and probabilities. Their potential effects on the nuclear power plant and methods used to develop adequate design bases for the plant to prevent such effects are also included.