ASN Report 2018

PROVENCE-ALPES-CÔTE D’AZUR REGIONAL OVERVIEWOF NUCLEAR SAFETY AND RADIATION PROTECTION ÉOLE and Minerve research reactors – CEA Centre The experimental ÉOLE and Minerve reactors are very low- power (less than 1 kWe) critical mock-ups, used for neutron studies, in particular to evaluate the absorption of gamma rays or neutrons by materials. The ÉOLE reactor (BNI 42), whose construction was authorised by the Decree of 23 June 1965, was mainly intended for neutron studies of moderated arrays, in particular those of Pressurised Water Reactors (PWR) and BoilingWater Reactors (BWR). The Minerve reactor (BNI 95), whose transfer from the Fontenay‑aux‑Roses studies centre to the Cadarache studies centre was authorised by Decree of 21 September 1977, is situated in the same hall as the ÉOLE reactor. Teaching and research activities were carried out on these mock-ups until their final shutdown on 31 December 2017. The CEA submitted the decommissioning file for these installations in July 2018, and ASN is currently examining it. Pending decommissioning, operations in preparation for decommissioning, such as the removal of radioactive and hazardous substances, took place in 2018. ASN considers that the level of nuclear safety and radiation protection of the ÉOLE and Minerve in 2018 is on the whole satisfactory. In September 2018, the licensee reported a significant event that occurred during the transport of radioactive substances between the two installations, rated level 1 on the INES scale due to noncompliance with two on-site transport rules. The enriched Uranium Processing Facilities (ATUe) – CEA Centre From 1963 to 1995, the ATUe (BNI 52) converted uranium hexafluoride from the enrichment plants into sinterable oxide, and ensured the chemical reprocessing of waste from the manufacture of fuel elements. Decommissioning of this facility was authorised by Decree in February 2006. The licensee is seriously behind schedule in these decommissioning operations, mainly due to the poor assessment of the radiological condition of the installation prior to the first decommissioning operations. On this account, in 2010 the licensee requested a modification to its decree to take account of the true radiological condition of the installation; ASN has made several requests for additional information in this respect, and the modification request is still being examined. In 2018, ASN authorised the CEA to proceed with the treatment of the radiologically marked soils situated within the perimeter of the installation. ASN considers that the decommissioning of the ATUe is conducted in a relatively satisfactory manner. Central Fissile Material Warehouse (MCMF) – CEA Centre Created in 1968, the MCMF (BNI 53) was a warehouse for storing enriched uranium and plutonium until its final shutdown and the removal of all its nuclear materials on 31 December 2017. The licensee submitted its decommissioning file in November 2018, and ASN is currently examining it. High-activity laboratory LECA-STAR – CEA Centre The Active Fuel Examination Laboratory (LECA) and the Treatment, Clean-out and Reconditioning Station (STAR) – an extension of LECA, constitute expert assessment tools used by the CEA for the analysis of spent fuels. Commissioned in 1964, the LECA laboratory enables CEA to carry out destructive and non-destructive examinations of spent fuel from the nuclear power, research and naval propulsion sectors. As the facility is old, it was partially reinforced in the early 2010’s to ensure its earthquake resistance. Nevertheless, its resistance to an earthquake of the «Safe Shutdown Earthquake» (SSE) level is not guaranteed today, and the CEA must propose ASN an acceptable strategy for the future of this facility. Commissioned in 1999, the STAR facility is an extension of the LECA laboratory, designed for the stabilisation and reconditioning of spent fuel. The CEA gave ASN the periodic safety review reports for the LECA facility in June 2014 and for STAR in February 2018, and it is currently examining them. ASN considers that the safety of BNI 55 was maintained at a satisfactory level in 2018. ASN notes a good level of involvement of senior management in the safety issues. Nonetheless, ASN remains attentive to ensuring that social, organisational and human factors are properly taken into account in the operation of the facility. The licensee reported a significant event rated level 1 on the INES scale, for under- estimation of the mass of fissile material contained in two fuel cladding samples transferred from CEA Cadarache to CEA Saclay. Solid Radioactive Waste Storage Area – CEA Centre BNI 56, declared in January 1968 for the disposal of waste, is used for interim storage of legacy solid radioactive waste from the Cadarache centre. It comprises 3 pools, 6 pits, 5 trenches and hangars, which contain in particular Intermediate-Level Long-Lived Waste (ILW-LL) from the operation or decommissioning of CEA installations Major legacy waste retrieval and packaging work has been in progress for several years, and the CEA submitted the decommissioning file for the installation to ASN in June 2018. ASN notes the lateness in the projects for retrieval and packaging of the waste stored in this facility. On account ASN report on the state of nuclear safety and radiation protection in France in 2018  83