LES ACTIVITÉS NUCLÉAIRES : RAYONNEMENTS IONISANTS ET RISQUES POUR LA SANTÉ ET L’ENVIRONNEMENT 2.6.2 – Prevention and control of the non-radiological risks Prevention of non-radiological risks with airborne effects The accidents with effects said to be “non-radiological” are those which can arise from the release of hazard potentials which do not concern radioactive substances. These hazard potentials, which can also be present in other industries covered by the system for Installations Classified for Protection of the Environment (ICPEs), are associated with storage facilities and processes using gaseous or liquid chemical substances. The consideration of these non-radiological accidents is included in the nuclear safety case in accordance with the provisions of Title III of the Order of 7 February 2012, through a specific study. This study is drawn up using the methodology applicable to ICPEs. The purpose of this study is to justify the thermal and toxic effects, projectiles or over-pressure effects generated by release of the hazard potentials present on the site and leading to no effects beyond the perimeter of the site. This justification is based, on the one hand, on identification of the hazard potentials (storage facilities or processes) and their potential hazard sources and, on the other, on characterisation of the possible dangerous phenomena and the specific prevention measures for reducing both probability and effects. Each NPP thus has a study of non-radiological risks which analyses and as necessary characterises the possible dangerous phenomena, as well as the specific material and organisational provisions for preventing these phenomena or limiting their effects. Prevention of liquid pollution resulting from accidental spillage of dangerous substances As with numerous industrial activities, the operation of an NPP involves the handling and storage of dangerous liquid chemical substances. The management of these substances and the prevention of pollution, which are the responsibility of the licensee, are regulated by the Order of 7 February 2012 and ASN resolution 2013-DC-0360 of 16 July 2013 and must also comply with the requirements of the European texts. The licensee has obligations regarding the operational management of these substances and the GRAPH 3 Liquid radioactive discharges for the NPPs in 2025 (per reactor) GRAPH 4 Gaseous radioactive discharges for the NPPs in 2025 (per reactor) 0 5 10 15 20 25 35 30 Blayais/4 Bugey/4 Chinon/4 Cruas-Meysse/4 Dampierre-en-Burly/4 Gravelines/6 Saint-Laurent-des-Eaux/2 Tricastin/4 Belleville-sur-Loire/2 Cattenom/4 Flamanville/3 Golfech/2 Nogent-sur-Seine/2 Paluel/4 Penly/2 Saint-Alban/2 Chooz/2 Civaux/2 Rejected activity Tritium (TBq) per reactor Discharges other than tritium (TBq) per reactor 0.0 0.2 0.4 0.6 0.8 1.0 1.4 1.2 1.6 1.8 2.0 0 5 10 15 20 25 35 30 40 45 50 Rejected activity Gas (TBq) Halogens and aerosols (TBq) Blayais/4 Bugey/4 Chinon/4 Cruas-Meysse/4 Dampierre-en-Burly/4 Gravelines/6 Saint-Laurent-des-Eaux/2 Tricastin/4 Belleville-sur-Loire/2 Cattenom/4 Flamanville/3 Golfech/2 Nogent-sur-Seine/2 Paluel/4 Penly/2 Saint-Alban/2 Chooz/2 Civaux/2 Total gases (TBq) per reactor Total halogens and aerosols (TBq) per reactor As there can be a different number of reactors on each site, the results are given per reactor, to enable a comparison to be made from one site to another. This therefore amounts to dividing the site's discharges by the number of reactors. For example, for the Golfech site, which has two reactors, the discharges are divided by two; for the Chinon site, which has four reactors, the discharges are divided by four. For the Gravelines site, which has six reactors, the discharges are divided by six. 300 ASNR Report on the state of nuclear safety and radiation protection in France in 2025
RkJQdWJsaXNoZXIy NjQ0NzU=