ASN Report 2020

that at the end of this phase, the residual activity contained in the waste will have reached a residual level such that human and environmental exposure levels are acceptable, even in the event of a significant loss of the containment properties of the facility. There are two facilities of this type in France, the Manche repository (CSM – BNI 66), commissioned in 1969 and closed since 1994, and the Aube repository (CSA – BNI 149) in operation (see Regional Overview in the introduction to this report). The quantity of LL/ILW-SL waste emplaced in the CSA repository totalled 353,147 m 3 at the end of 2020, which represents 35% of the facility’s maximum authorised capacity. Added to this quantity is the waste emplaced in the Manche repository, which represents 527,214 m 3 . The total quantity of LL/ILW-SL waste emplaced in the Andra facilities is therefore 880,361 m 3 , to be compared with the quantity of 917,000 m 3 produced at the end of 2018. According to the data of the national inventory drawn up by Andra, this waste will represent a maximum volume of 2,000,000 m 3 , on completion of decommissioning of the existing facilities. According to the estimates made by Andra in 2016 at the time of the periodic safety review of the CSA, this facility could reach its maximum filling capacity by 2060 instead of 2042 as initially forecast, this new estimate being based on better knowledge of the future waste and the waste delivery schedules. 1.3.3 Management of low-level long-lived waste The low-level long-lived waste (LLW-LL) initially comprised two main categories: graphite waste resulting from operation of the Gas-Cooled Reactors (GCRs) and radium-bearing waste from the radium industry and its offshoots. Other types of waste have been added to this category such as certain bituminised effluents, substances containing radium, uranium and thorium with low specific activity, as well as certain disused sealed radioactive sources. Furthermore, a fraction of the waste from the Orano Malvesi plant (Aude département ) produced as from 1 January 2019 is now included in this waste category. The solid waste produced until 31 December 2018, on account of the large volumes it represents, is placed in a specific category of the national inventory called RTCU (French acronym standing for “Uranium Fuel Reprocessing Residues”). Putting in place a definitive management solution for this type of waste is one of the objectives defined by the Act of 28 June 2006. Finding such a management solution necessitates firstly having greater knowledge of LLW-LL waste and secondly conducting safety studies on the associated disposal solution. The successive editions of the PNGMDR have set out this objective. ASN also drafted a notice in 2008 giving general safety guidelines concerning the search for a site capable of accommodating LLW-LL. The PNGMDR 2010-2012 opened up the possibility of separate disposal of graphite waste and radium-containing waste, and asked Andra to work on the two design options: ∙ reworked cover disposal in an outcropping geological layer by excavation followed by backfilling; ∙ intact cover disposal dug in underground layer of clay at a greater depth. The PNGMDR 2013-2015 required the various actors involved to carry out studies (characterisation and waste treatment possibilities, geological investigations on a site identified by Andra, design studies and preliminary safety analyses) so that in 2016 the State can specify guidelines for the management of LLW-LL waste. Thus, the holders of LLW-LL waste have progressed in the characterisation of their waste and in the processing possibilities, particularly with regard to graphite waste and some bituminised waste packages. More specifically, the radiological inventory for chlorine-36 and iodine-129 has undergone a significant downward reassessment. As part of the PNGMDR, Andra submitted a report in July 2015 containing: ∙ proposals of choices of management scenarios for graphite waste and bituminous waste; ∙ preliminary design studies covering the disposal options referred to as “intact cover disposal” and “reworked cover disposal”; ∙ the inventory of the waste to be emplaced in it and the implementation schedule. ASN issued an opinion 2016-AV-264 on Andra’s interim report on the disposal project for LLW-LL waste on 29 March 2016. At the same time, ASN has started revising the general safety guidelines notice of 2008. A working group bringing together ASN the the French Institute for Radiation Protection and Nuclear Safety (IRSN), Andra, the LLW-LL waste producers and representatives of civil society was thus set up in Autumn 2018. A synthesis of the work carried out will be provided in an IRSN report in 2021. The recommendations of this report will be taken into account in the revision of the general safety guidelines for LLW-LL of 2008, which will be replaced by an ASN guide. Lastly, in accordance with Article 7 of the Decree of 27 December 2013, Orano has submitted a study on the long-term management of the Malvési site waste already produced, stored in BNI 175 – Écrin. Various envisaged disposal concepts are presented. ∙ above-ground disposal; ∙ near-surface (40m), reworked cover disposal, in the former open-cast mine pit; ∙ near-surface (40 m) reworked cover disposal, in a new pit as yet to be built. Given the nature of the waste and the configuration of the site, ASN indicated in its opinion 2012-AV-0166 of 4 October 2012 that it is not in favour of continuing the development of this type of disposal as it considers that it does not meet the long-term safety requirements. The other two disposal options presented in the Areva study of December 2014 on the long-term management of legacy waste from the conversion process, are based on an identical concept, namely near-surface reworked cover disposal at a depth of about 40 m. On 2 September 2019, ASN issued its opinion on the studies required by Article 7 of the Decree of 27 December 2013 relative to the implementation of a final management solution for the Malvési legacy waste in a near-surface repository. Orano’s responses are currently being examined. With the 5th edition of the PNGMDR in view, ASN issued its opinion 2020-AV-0357 of 6 August 2020 which details the work focuses it recommends for the management of LLW-LL waste. It more particularly urges continuation of the work undertaken under the PNGMDR 2016-2018, such as the consolidation of the inventories of the various families of LLW-LL waste and the periodic reassessment of storage needs, notably in order to allow the decommissioning of the nuclear facilities. ASN considers that, on the basis of a multi-criteria analysis, Andra should submit the outlines of various technical and safety options for the near-surface disposal facilities for LLW-LL waste, comparing the health and environmental effects of the various options envisaged. All of the stakeholders concerned, in particular the representatives of the localities actually or liable to be involved, must be involved more actively in defining LLW-LL waste management solutions. A pluralistic working group could ASN Report on the state of nuclear safety and radiation protection in France in 2020 361 14 – RADIOACTIVE WASTE AND CONTAMINATED SITES AND SOILS 14