TM-48103 TM on the Safe Disposal of Intermediate Level Waste IAEA Safety Standards and Activities on the Disposal of Intermediate Level Waste TM-48103 TM on the Safe Disposal of Intermediate Level Waste Yumiko Kumano Radioactive Waste and Spent Fuel Management Unit Division of Radiation, Transport and Waste Safety - NSRW

Overview IAEA Safety Standards and previous discussions on ILW disposal Activities in 2013 / 2014 Way forward The presentation will successively go through the problem definition then will explain and give the outcomes of the consultancy we organized and finally will propose the position of the IAEA regarding the issue of intermediate level waste disposal and intermediate depth disposal

IAEA Safety Requirements 2010 Under development Under development 2011-12 Published in 2014 Under development 2009 Under development 2009 2011 Published in 2014 2012 Under development

Safety Standards: Predisposal Classification Storage Safety Assessment Safety Case Management System DS 448 DS 447 DS 454 overview of safety standards

Safety Standards - Disposal Site Aspects Design Construction Operation Closure Post Closure Safety Assessment Management System Published in 2014 Published in 2014 5

GSG-1(2009): Classification of RW WASTE CLASSES LLW: Above the clearance level, limited amounts of long lived Rn. Requires robust isolation and containment for periods up to a few hundred years. Suitable for disposal in engineered near surface facilities typically from the surface to 30 m depth ILW: content in long lived RN → greater degree of containment and isolation than that provided by NS disposal facilities. Disposal at greater depth than that of NS disposal facilities i.e. order of tens of m to a few hundred m (intermediate depth disposal) HLW: high levels of activity concentrations, heat generation by radioactive decay or waste with large amounts of long lived Rn. Disposal in deep, stable geological formations of several hundred meters depth or more below the surface. The suitability of waste for disposal in a particular disposal facility is required to be demonstrated by the safety case and supporting safety assessment for that facility As you know as well The IAEA safety guide on the classification published in 2009 defines the different types of radioactive waste and makes links with disposal options. I am not going to give the definitions of VLLW, VSLW and Exempt waste which are given in the SG but I will just give the definitions of those waste of interest for our issue. LLW are defined as waste which are above clearance level, with limited amounts of long lived Rn. These waste requires robust isolation and containment for periods up to a few hundred years . They are suitable for disposal in engineered near surface facilities typically from the surface to 30 m ILW: are defined as waste with a content in long lived radionuclides which implies the need for a greater degree of containment and isolation than that provided by near surface disposal facilities, which is provided by disposal at greater depth than that of near surface disposal facilities i.e. in the order of tens of meters to a few hundred meters High levek waste are defined in the classification as waste with high levels of activity concentrations, which generates heat by radioactive decay or waste with large amounts of long lived radioanuclides. Because of these characteristics these waste should be disposed of in deep stable geological formations of several hundred meters or more below the surface In addition to these definitions one very important element which is given in the classification is that the suitability of waste in a particular disposla facility is required to be demonstrated by the safety case and supporting safety assessment for that facility EW, VSLW, VLLW This new classification applies to all types of radioactive waste. It is based primarily on long term safety. It is meant to facilitate communication and information exchange within and among states. In order to take into account comments made on the previous classification, a generic linkage has been made between the classes of waste and potential disposal options but one essential element which is mentioned in the classification is that the suitability of waste for disposal in a particular disposal facaility is required to be demonstrated by the safety case and supporting safety assessment for that facility

The classification of radioactive waste In complement It is necessary to summarize the situation with regards to ILW and Intermediate depth disposal. The classification of rw makes the link between types of radioactive waste and disposal options. In particular the classification gives this graph and we often have feedback on it that it could be perceived that there is a direct link between intermediate level waste and intermediate depth disposal, in particular if this graph is taken alone without reading the document.

SSR-5(2009): Disposal of RW DISPOSAL OPTIONS Near surface disposal: disposal in a facility […] constructed on the ground surface or up to a few tens of metres below ground level. Such a facility may be designated as a disposal facility for low level radioactive waste (LLW) Disposal of intermediate level waste: […] Disposal could be by emplacement in facilities constructed […] at least a few tens of metres below ground level and up to a few hundred metres below ground level Geological disposal: disposal in a facility constructed […] in a particular geological formation (e.g. in terms of its long term stability and its hydrogeological properties) at least a few hundred metres below ground level. Such a facility could be designed to receive high level radioactive waste […]. However, with appropriate design, a geological disposal facility could receive all types of radioactive waste. In terms of disposal the recently published safety requirements on disposal of radioactive waste (SSR5) defines the different disposal options. Near surface disposal is defined as disposal in a facility constructed on the ground surface or up to a few tens of metres below ground level. Such a facility may be designated as a disposal facility for low level radioactive waste (LLW) The safety requirements publication also indicates that concerning disposal of intermediate level waste, depending on its characteristics, (ILW) can be disposed of in facilities of different types. Disposal could be by emplacement in facilities constructed at least a few tens of metres below ground level and up to a few hundred metres below ground level. It could include purpose built facilities and facilities developed in or from existing mines. It could also include facilities developed by drift mining into mountainsides or hillsides, in which case the overlying cover could be more than 100 metres deep Finally geological disposal is defined as disposal in a facility constructed in a particular geological formation (e.g. in terms of its long term stability and its hydrogeological properties) at least a few hundred metres below ground level. Such a facility could be designed to receive high level radioactive waste . However with appropriate design a geological disposal facility could receive all types of radioactive waste

Safety Standards - Disposal SSR-5 Disposal of RW SSG-29 Near Surface Disposal SSG-23 SC and SA for disposal SSG-14 Geological Disposal LLW HLW +ILW? 9

Previous discussions Mar 2011 & WASSC31 No specific SG for ILW disposal – already covered by SSG-14 Develop a safety report to address specific issues of ILW disposal Apr 2013 &WASSC35 Start drafting on “Safety-related issues for the disposal of ILW Sept 2013 &WASSC36 TM on the disposal of ILW - discuss current status and issues - to review and draft technical document HLW ILW LLW In complement It is necessary to summarize the situation with regards to ILW and Intermediate depth disposal. The classification of rw makes the link between types of radioactive waste and disposal options. In particular the classification gives this graph and we often have feedback on it that it could be perceived that there is a direct link between intermediate level waste and intermediate depth disposal, in particular if this graph is taken alone without reading the document. VLLW

TM on the disposal of ILW - overview Meeting: 9-13, September with 18 participants from 14 Member States Chair: Mr. Jean-Michel Hoorelbeke (ANDRA, France) Objectives: Information sharing on various national activities Discussion on common issues / Topics to be addressed in the Safety Report Drafting of the Safety Report Outcome: Agreed on developing a Safety Report Report outline & project plans

TM on the disposal of ILW - Discussions(1) 1st WG session – Identification of issues related to ILW disposal (draft report Chapter 3) Definitions, scope of ILW with regard to IAEA SSs Waste characteristics Time scales (post-closure) Site issues with regard to containment and isolation Design considerations for long term performance Operational issues (including transport)

TM on the disposal of ILW - Discussions(2) 2nd WG session – Gap Analysis of identified issues related to ILW disposal and current IAEA SSs /other publications Reference: SSR-5 (Disposal or RW) SSG-14 (Geological Disposal Facilities for RW) DS-356 (Near Surface Disposal Facilities for RW) Nuclear Energy Series NW-T-1.20 (Disposal Approaches for Long Lived L/ILW)

TM on the disposal of ILW - Discussions(3) NW-T-1.20 Review Very technical & still current Comprehensive in scope – Social, stakeholder involvement, economic issues, borehole Examples given – useful background info for predisposal disposal and disposal options Half of document is devoted to examples – Description rather than guidance Definitions don’t match current IAEA SS Lacks some practical details (e.g.) Gaps (Institutional Control, Timescales, operational issues)

TM on the disposal of ILW - Discussions(4) 3rd WG session – Draft outline of several chapters / refinement of structure Final Plenary session Finalization of the outcome document Discussion & agreement on future activities …. to prepare draft SR in 1 year

Activity plans agreed at the TM in 2013 Meetings Core meetings in 2014 (Apr.2014 +?) – further develop document Plenary meeting – 3-7, Nov. 2014 -- finalize the outcome document  move forward for publication as SR? Contributions from meeting participants Comment to current document National example by Dec.2013

This week Objectives exchange information on the progress of national projects related to the disposal of intermediate level waste (ILW) discuss specific safety issues that need to be taken into account in the development of an ILW disposal facility review and further improve Expected Outcome Updated draft Safety Report … hopefully final version agreed by TM participants!! Agreement on further contribution (national examples etc.)

Thank You