EUROPEAN COMMISSION Brussels, 15.5.2017 SWD(2017) 159 final COMMISSION STAFF WORKING DOCUMENT Progress of implementation of Council Directive 2011/70/EURATOM Accompanying the document REPORT FROM THE COMMISSION TO THE COUNCIL AND THE EUROPEAN PARLIAMENT on progress of implementation of Council Directive 2011/70/EURATOM and an inventory of radioactive waste and spent fuel present in the Community's territory and the future prospects {COM(2017) 236 final}

{SWD(2017) 161 final}



TABLE OF CONTENTS 1.INTRODUCTION 2.STATUS OF IMPLEMENTATION 2.1.National policies and frameworks for the safe and responsible management of spent fuel and radioactive waste 2.1.1.National policies 2.1.2.National programmes, timeframes and key performance indicators 2.1.3.National legal and organisational frameworks 2.1.4.Regulatory framework and competent regulatory authorities 2.1.5.Shipments within EU and to third countries 2.1.6.Self-assessment and international peer reviews 2.1.7.Notification and reporting 2.2.Assuring the safety of spent fuel and radioactive waste management 2.2.1.Licence holder’s responsibilities 2.2.2.Concepts and plans (including post closure) 2.2.3.Safety demonstration 2.2.4.Cost assessment, financing mechanisms and available resources

2.2.5.Expertise and skills 2.2.6.Research and development 2.2.7.Transparency 3.CONCLUSION



LIST OF ABBREVIATIONS AND ACCRONYMS ARTEMIS Integrated review service for radioactive waste and spent fuel management, decommissioning and remediation programmes EIA Enviornmental impact assessment ENSREG European Nuclear Safety Regulators Group EU European Union KPI Key performance indicators HLW High level waste IAEA International Atomic Energy Agency ILW Intermediate level waste LLW Low level waste LTO Lifetime extension IRRS International regulatory review service MS Member State NORM Naturally occuring radioactive material NPP Nuclear power plant RAW Radioactive waste SEA Strategic environmental impact assessment SF Spent fuel URL Underground research laboratory VLLW Very low level waste



1.INTRODUCTION This Staff Working Document presents details on the outcome of the Commission’s assessment of European Union (EU) Member States’ notifications on the implementation of Council Directive 2011/70/EURATOM on responsible and safe management of spent fuel and radioactive waste (further “Directive”). It is based on the information provided in Member States' national programmes and national reports on spent fuel and radioactive waste management, as notified to the Commission by 30 September 2016. It provides background information related to the main findings, progress, challenges, and trends presented in the first Commission report COM(2017)236 to the Council and the European Parliament on progress of implementation of Council Directive 2011/70/Euratom and an inventory of radioactive waste and spent fuel present in the Community's territory and future prospects. On the basis of the notified legal measures transposing the Directive, 27 national programmes on spent fuel and radioactive waste management (5 of which under formal approval by Member States), and 28 national reports on implementation of the Directive, the Commission notes the commitment of Member States towards the safe and responsible management of spent fuel and radioactive waste. This is the first time that Member States report on the implementation of their national programmes for the management of spent fuel and radioactive waste under the Directive. The Staff Working Document pays particular attention to national policies and principles, national frameworks, national programmes and their implementation, competent regulatory authorities, license holders responsibilities, concepts and plans, safety demonstration, financial resources, expertise and skills, research, and transparency. In this first report, the Commission has taken into account information from the national programmes and national reports, relevant for implementation of the Directive in Member States in order to present a comprehensive overview to the Council and European Parliament on spent fuel and radioactive waste management in the EU. 2.STATUS OF IMPLEMENTATION

2.1.National policies and frameworks for the safe and responsible management of spent fuel and radioactive waste 2.1.1. National policies Development of a national policy for management of spent fuel and radioactive waste is a key provision for long term and safe management of spent fuel and radioactive waste. According to the Directive each Member State shall bear ultimate responsibility for the management of the spent fuel and radioactive waste generated in it. It is up to the Member States to take a decision whether they will build a single disposal facility for all radioactive waste or a number of facilities for different waste types. Although the Directive requires that the radioactive waste be disposed of in the Member State in which it was generated, it introduces conditions under which the radioactive waste could be disposed of in another Member State or in a third country (Article 4(4) of the Directive). The export of radioactive waste for disposal in another Member State or in a third country is in practice considered by most Member States without a nuclear programme, or which have one or several research reactors and relatively small quantities of low level waste (LLW) and intermediate level waste (ILW). Article 4 (3) of the Directive defines a number of principles national policies shall be based on: ·Keeping the generation of radioactive waste to the minimum; ·The interdependencies between all steps in spent fuel and radioactive waste management; ·Safe management of spent fuel and radioactive waste and passive safety features for long term safety; ·Graded approach in implementation of measures for spent fuel and radioactive waste management; ·The costs for the management of spent fuel and radioactive waste shall be borne by those who generated those materials; ·Evidence-based and documented decision making process to all stages of spent fuel and radioactive waste management. The majority of Member States has developed national policies for management of spent fuel and radioactive waste, although not all Member States' policies cover all types of their radioactive waste or spent fuel (e.g. research facilities) or all states of their management, in particular long term management. The majority of Member States has developed policies either in stand-alone documents, or reflected in their national frameworks and/or their national programmes. Almost half of the Member States are considering multiple options for disposal of their spent fuel and/or radioactive waste. Operators from a few Member States are currently reprocessing their spent fuel in France, the United Kingdom and the Russian Federation. In the rest of the Member States spent fuel is intended to be disposed of in deep geological facilities without reprocessing. This is particularly valid for spent fuel from new build, and for current spent fuel in some Member States that used to reprocess it in the past. The spent fuel from research reactors is intended for shipment to the supplier (USA or the Russian Federation) in most cases before 2020. Three Member States (Finland, France and Sweden) have concrete plans for development of geological disposal facilities for ILW and high level waste (HLW) in the next 15 years. Based on the Member States' programmes to date, in total fifteen Member States plan to develop geological disposal facilities in the next 100 years in the EU. Thereby, shared disposal facilities remains an option for many Member States. The remaining Member States have either: ·Not defined their long-term policy for spent fuel, HLW and ILW disposal (e.g. national disposal facility, disposal in a third country or shared disposal facilities); or ·Considered two options (e.g. (i) national and shared disposal solutions or (ii) reprocessing and disposal),

and in those cases long term storage in the Member States is foreseen as an interim step. About half of the Member States consider shared solutions in their programmes. Some define it as the primary option for disposal of HLW and spent fuel, other Member States take a dual track approach for a few decades until they will make a decision for a national or shared disposal facility, and a few Member States consider shared disposal as a last and not very realistic option. Member States with small amounts of institutional waste plan interim storage of radioactive waste, while a final solution is being decided: disposal on the territory of the said Member State, export for disposal abroad or a shared disposal solution. The majority of Member States manage radioactive waste on their territory, while a number of Member States send radioactive waste for processing abroad. In the latter cases, as per Article 4(2) of the Directive, the Member State of origin remains responsible for the secondary waste as a by-product generated during the processing. Most Member States established clearly in their laws and regulations the ultimate responsibility of the State for management of the spent fuel and radioactive waste generated on its territory, however in most cases no details on the practical implementation have been provided. Almost all Member States policies address the principles stated in Article 4(3) of the Directive. In general, Member States require in their legislation that these principles are included in the policies. However, information on the practical implementation of the policy principles is not always presented in the national reports, especially in the reports of non-nuclear countries. Overall Member States' policies cover better the principles of (i) keeping the generation of radioactive waste to the minimum and (ii) safety demonstration, than the principles of application of the graded approach, passive safety features for long term safety and interdependencies between radioactive waste management steps. In Member States with defined policies, a few Member States recognize the need for technical solutions for long term management of special radioactive waste (e.g. exotic waste from research). These Member States reported that they have ongoing or planned research activities to address this need. The majority of Member States with nuclear programmes focus on management of spent fuel and radioactive waste from large generators, such as nuclear power plants and therefore do not provide detailed information on management of institutional waste. In particular, for long-term management (e.g. strategy, technical solutions and cost estimates) of radioactive waste and spent fuel coming from the research activities (e.g. research reactors, universities). 2.1.2.National programmes, timeframes and key performance indicators Member States are required to establish national programmes for spent fuel and radioactive waste management, which define the measures, timeframes and milestones for the national policy in practice. They were also required to notify these programmes to the Commission before 23 August 2015. All Member States except one have developed and submitted their national programmes to date, although the programmes of six Member States are expected to be finalised at the end of 2016 or in 2017, mainly due to ongoing Strategic Environmental Assessment (SEA) procedures. Overall the programmes of more than half of the Member States have been subject of SEA as presented in Table 1. The majority of the programmes are recent and adopted in 2015-2016 period, however in two Member States the programmes date as of 2006 and in one as of 2013. Updated submissions of the programmes of two cases (as per Article 13(1) of the Directive) are expected by the Commission. A few Member States have programmes that address most types of spent fuel and radioactive waste and the respective concrete plans from generation to disposal (including deep geological disposal and post-closure measures); although they recognize that there are exotic waste from research activities and remediation waste for which these Member States still need to take decisions. Most Member States with nuclear power plants (NPPs) have developed and approved programmes that cover all stages from generation to disposal. A few Member States have not yet decided a long term solution for the management of their radioactive waste or spent fuel. As mentioned for the national policies, Member States with nuclear programmes provide very detailed information on the management of spent fuel and radioactive waste generated in the nuclear industry, and much less on the management of institutional radioactive waste. All Member States reflected the exclusions of the Directive as per Articles 2(2) and 2(3). Member States without nuclear programmes and having research reactors address all types of radioactive waste and spent fuel generated from research reactor operation. The majority of the national frameworks of these Member States only cover activities up to interim storage and repatriation of spent fuel to the supplier, and have not yet defined policies or routes for the disposal of radioactive waste. Except for one, Member States with no nuclear programmes communicated their national programmes. Most of these Member States cover all types of radioactive waste and have not yet defined a policy or a route for their disposal. Although a final solution has not been defined yet, some Member States have established decision-making milestones to progressively define more concretely the long term management and disposal of radioactive waste. Most of the Member States with no nuclear programmes aim at finding a shared disposal solution. Luxembourg has recently concluded an agreement with Belgium for the management of part of its radioactive waste. Table 1. Member States' National Programmes under Directive 2011/70/EURATOM MS Organisation developing the programme Organisation approving SEA Review and update BE National Committee created by law with Ministry of Economy, ONDRAF/NIRAS and Synatom Federal Ministers of Energy and Economy N Regular update when a national policy is adopted or amended BG Ministry of Energy Government Y 2011 Strategy was revised in 2015. CZ Ministry of Industry and Trade Government Y 2002 Concept updated in 2014 is under review. Next review planned in 2025 DE Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety Federal Cabinet Y Every 3 years FI Ministry on Employment and the Economy Ministry on Employment and the Economy N Every 3 years FR Ministry of Ecology, Sustainable Development and Energy Government, new 2016-2019 programme expected to be approved in 2016 Y Every 3 years HU PURAM and the Ministry of National Development Government after SEA completion Y Every 5 years IT Ministry of Environment and Protection of Land and Sea, Ministry of Economic Development, Ministry of Health Ministry of Environment and Protection of Land and Sea, Ministry of Economic Development Y Every 3 years LT Ministry of Energy on the proposal of a Radioactive Waste Management Organization Government Y Every 7 years at least LV Latvian authorities No available information Planned Concept of Radioactive Waste Storage, developed in 2003, National programme under development (incl. SEA) NL Ministry of Infrastructure and Environment Parliament N At least every 10 years SI Agency for Radioactive Waste Management (ARAO) and Slovenian Nuclear Safety Administration (SNSA) National Assembly N 2006 programme revised in 2016 ES ENRESA Government upon proposal by Ministry of Industry, Energy and Tourism, being heard the CSN and relevant Autonomous Communities Y Periodic review, 2006 programme is being reviewed SE Swedish Radiation Safety Authority Ministry of the Environment and Energy N Regular national and international reviews; Follow-up IRRS mission May in 2016 SK The administrative board of the National Nuclear Fund for decommissioning nuclear installations and managing spent nuclear fuel and radioactive waste (‘NNF’) Government Y Every 6 years RO Nuclear Agency and for Radioactive Waste (ANDR) No available information Y Every 5 years UK Department of Energy and Climate Change Department of Energy and Climate Change N Nuclear Decommissioning Authority strategy review every 5 years AT Government of the Republic of Austria Government Y Regular update DK Danish Radiation Protection Authority at the Danish Health and Medicines Authority (SST/SIS) Ministry of Health N Not defined in the national programme EL Greek Atomic Energy Commission (EEAE) Minister responsible for the EEAE, the Minister for Education, Research and Religious Affairs No data At least once every 3 years and updated by EEAE, upon agreement of the National Committee for Radioactive Waste Management (EEDRA) PL Ministry of Economy Council of Ministers Y Every 4 years PT Regulatory Commission for the Safety of Nuclear Installations (COMRSIN) Council of Ministers Y COMRSIN* Frequency not defined HR State Office for Radiological and Nuclear Safety (SORNS) Ministry of Economy with the prior approval by the Croatian Parliament Y Krško programme every 5 years at least CY Radiation Inspection and Control Service (RICS), Department of Labour Inspection (DLI), Minister of Labour, Welfare and Social Insurance (MLWSI) MLWSI N Every 10 years at least by RICS EE Ministry of the Environment, Environmental Board, Radiation Protection Bureau, Radiation Monitoring Bureau Minister of the Environment Y Regular update at least every 4 years IE Government Department of Environment, Community and Local Government (DECLG) DECLG N Update and revision as necessary LV Minister for Environmental Protection and Regional Development* Council of Ministers* Y 2002 Concept, Programme in preparation LU No available information No data Next review in 2018 MT Radiation Protection Board Radiation Protection Board Under screening As necessary * Information from notifications to the Commission other than the national programme A third of all EU Member States addressed waste with naturally occurring radioactive material (NORM) in their programmes, whereas the rest either explicitly exclude it from the scope of their national programmes, or do not mention it. The overall timescale of Member States' programmes for spent fuel and radioactive waste management vary signifficantly due to the scope and scale of the current nuclear programmes in each Member State. The programmes include measures from a few years up to after 2300, which imposes challenges for the majority Member States (in particular the ones with nuclear programme) to ensure long term safety measures for several decades to centuries in the future.

Clearly defined detailed milestones, timeframes and decision making points are defined by about a third of Member States (incl. shutdown and planned decommissioning of nuclear power plants that will also generate radioactive waste (see Table 2). Table 2 Schedule for Decommissioning of Nuclear Power Plants in EU Member States MS Reactors/Units Operation Shutdown Decommission-ing Comments BG Kozloduy unit 1 1974 2002 ongoing Available data until 2030 Kozloduy unit 2 1975 2002 ongoing Kozloduy unit 3 1980 2006 ongoing Kozloduy unit 4 1982 2006 ongoing Kozloduy unit 5 1987 2017 (2030) Planned LTO by 2030 Kozloduy unit 6 1991 2021 (2030) Planned LTO by 2030 CZ Dukovany 1-4 1978-1987* 2038 - 2047 Planned LTO Temelin units 1-2 2000-2002* 2060-2062 60 years operation Dukovany unit 5 planned no available data 60 years operation Temelin unit 3 planned no available data 60 years operation HU Paks units 1-4 1982-1987 2032-2037 Considering 20 years LTO Paks units 5-6 2025-2026 Planned SK Bohunice V1 (units 1-2) 1978* 1980* 2006 2008 2025 Bohunice V2 (units 1-2) 1984* 1985* 2024 or 2044 2025 or 2045 2031-2048 (40 years operation) 2051-2068 (60 years operation) Possible LTO to 60 years Bohunice A1 1972* 1979 2033 Bohunice unit 3 Planned (2029) 2089 Mochovce units 1-2 1998* 1999* 2028 or 2046 2029 or 2066 2046-2063 (40 years of operation) 2066-2083 (60 years of operation) Possible LTO to 60 years Mochovce units 3-4 Under construction (2021) 2062 2082 2062-2079 (40 years of operation) 2082-2099 (60 years of operation) Possible LTOto 60 years FI Olkiluoto unit 1 1979 2049* 2080-2090 Olkiluoto unit 2 1982 2042* 2080-2090 Olkiluoto unit 3 Under construction 2078* 2075 - 2085 Loviisa unit 1 1977 2027* 2030-2035 Loviisa unit 2 1981 2030* 2030-2035 Hanhikivi Planned 2085-2100 BE Doel unit 1 1975 2025 End of operation dates by Phase-out Law of 31/01/2003 modified by the law of 28/06/2015. Doel unit 2 1975 2025 End of operation dates as established by the Phase-out Law of 31/01/2003 modified by the law of 28/06/2015. Doel unit 3 1982 2022 Doel unit 4 1985 2025 Thiange unit 1 1975 2025 Thiange unit 2 1983 2023 Thiange unit 3 1985 2025 DE 8 reactors shutdown 1975-1984 2011-2015 9 reactors in operation 1984-1989 2015 - 2022 FR 58 reactors and 9 shutdown reactors and EPR Flamanville 1977 – 1999 (operating fleet) Between 2027 and 2078 After 2030 Operating lifetime of 50 years IT Caorso 1978 1990 Ongoing Enrico Fermi 1964 1990 Ongoing Garigliano 1964 1982 Ongoing Latina 1963 1987 Ongoing NL Dodewaard 1968* 1997* After 2045 Borssele 1973* 2033 SI Krško 1983 2023 2023 ES* 2 reactors undergoing decommissioning ( José Cabrera and Vandellos I) 1969-1972 2006 and 1989 1 reactor shutdown (Santa María de Garoña) 1971 2012 7 operating reactors* 1981-1988 2021-2027 Assuming 40 years operation SE 10 operating reactors 2 shutdown 1972-1985 2040 - 2045 After 2040 - 2050 2020 and 2023 Early shutdown of Forsmark 1-2, Ringhals 1-2 could be decided between 2018-2020 UK* 16 (14 AGR, 1 PWR and 1 MAGNOX) reactors in operation 1976-1989 2023-2035 (or 2055) 2023-2083 Possible PWR LTO to 60 years 29 reactors shutdown LT Ignalina unit 1 1983 2004 Ongoing until 2038 Ignalina unit 2 1987 2009 Ongoing until 2038 RO Cernavoda unit 1 1996 2026 2063 Possible LTO to 2046 Cernavoda unit 2 2007 2037 2055 Possible LTO to 2057 Cernavoda units 3-4 Planned 2019-2020 planned immediate dismantling PL New build 2024 2084 *Information from other sources to the Commission than the national programmes/reports In a significant number of cases long term milestones or schedule have not been clearly presented for the whole national programme for spent fuel and radioactive waste management, decision making points are not defined or are postponed for the far future or the presented schedules are outdated. A number of Member States did not present schedules and timeframes for their national programmes or the one notified are very short term or not clearly fixed. The commissioning of deep geological facilities is focused in two main periods – 2022-2030 and 2040-2065. Although part of Member States considers shared disposal solutions, there is no decision or site selected for demonstration that this option is feasible. The majority of Member States have defined in their legal framework the responsibilities for review, update and implementation of the national programmes. A number of Member States still need to define or/present specific arrangements, deadlines and details that are not always detailed in the national programmes/reports (see Table 1). Member States have to allocate responsibilities for the implementation of their national programmes and the key performance indicators to monitor progress towards implementation (see Article 12(1)g of the Directive). Most of Member States have reported the organisations responsible for implementation of the national programmes, as well as its monitoring and the main milestones to be followed. However, majority of Member States have not clearly defined in their programmes the key performance indicators that they apply. 2.1.3. National legal and organisational frameworks Member States shall establish and maintain a national legislative, regulatory and organisational framework (‘national framework’) for spent fuel and radioactive waste management that allocates responsibility and provides for coordination between relevant competent bodies (Article 5(1) of the Directive). Member States were required to transpose the Directive by 23 August 2013. This section of the report presents the status of Member States' legal and organizational frameworks, while the regulatory framework is detailed in Section 2.1.4 below. All Member States have communicated to the Commission their transposition measures and declared full transposition and the Commission is assessing the latest notified legal measures with the view to finalise the conformity assessment. All Member States have presented their national framework with different levels of detail provided in the national reports. Member States have listed the legal arrangements and the provisions for the national framework, however only in some cases the national reports have provided details on how those legal provisions are implemented in practice. The national frameworks in the Member States' national reports cover all types of radioactive waste and spent fuel in the scope of the respective national programmes, although only a few Member States provide details on ILW and HLW disposal and the post-closure stage. Also, a few Member States do not plan institutional control after closure of deep geological facilities. Most Member States require the update and improvement of the national framework as per Article 5(2) of the Directive, and establish the responsibilities for that. About half of Member States have provided information on how in practice the development/review of the national framework takes into account operating experience, insights from the decision-making process, etc. The rest either refer to the requirements established by law or regulations, without providing additional details or do not provide such information. All Member States have in place arrangements for safety and licensing systems with various level of complexity to ensure safety of spent fuel and radioactive waste that correspond to the existing and estimated inventories of spent fuel and radioactive waste in the country. All Member States without nuclear programmes have implemented a national framework for the management of radioactive waste. The national framework contains legal and regulatory provisions mainly for predisposal waste management, which are commensurate with the type and amount of waste that they generate. Most Member States have established dedicated radioactive waste management organisations that operate to date. All nuclear power Member States have such organisations. The majority of these organisations are public ones (see Table 3), while a few are established by the nuclear power plant operators. In both cases, funding of spent fuel and radioactive waste management activities is based on the principle that the generators of spent fuel and radioactive waste cover the costs associated with the management of this material. In addition to the responsibilities for spent fuel and radioactive waste management, in a number of cases, these organisations deal also with decommissioning. In some cases, it is foreseen that the responsibilities for the disposal facilities will be transferred from the radioactive waste management organisations to the State after disposal facility's closure.



Table 3. Radioactive waste management organisations in the EU MS Radioactive waste management organisation Public/ private Responsibilities BE Organisme national des déchets radioactifs

et des matières fissiles enrichies/Nationale instelling voor radioactief afval

en verrijkte splijtstoffen (ONDRAF/NIRAS) Public Managing radioactive waste from all sources, managing spent fuel when declared as radioactive waste, incl. disposal. BG State Enterprise Radioactive Waste (SE RAW) Public Radioactive waste and spent fuel management; and decommissioning. CZ Radioactive Waste Repository Authority (SURAO) Public Operation of all low and intermediate level waste repositories; Monitoring of the now closed Hostim repository, Development of deep geological repository for disposal of HLW and spent fuel. FI POSIVA Private Radioactive waste management facilities - site selection, design, construction, commissioning, operation, rehabilitation and reconstruction, decommissioning and closure/post closure. FR National agency for management of radioactive waste (ANDRA) Public Long-term management of radioactive waste. DE German Service Company for the Construction and Operation of Waste Repositories (DBE) Public Construction and operation of radioactive waste repositories. HU Public Limited Company for Radioactive Waste Management (PURAM) Public Management of all types of radioactive waste, decommissioning of nuclear facilities, as well as related to research and development. IT Company for management of nuclear power plants (SOGIN) Public Decommissioning of nuclear installations and radioactive waste management including waste produced by industrial, research and nuclear medicine activities; siting, design and construction of a national repository. LT State Enterprise Radioactive Waste Management Agency (RATA) Public Management and disposal of radioactive waste generated by the Ignalina nuclear power plant. Construction and operation of the repositories for radioactive waste. NL The Central Organisation For Radioactive Waste (COVRA) Public Implementing the Dutch policy with regard to radioactive waste in the Netherlands. Treatment and storage of all radioactive waste and spent fuel. RO Nuclear Agency for Radioactive Waste (ANDR) Public Promotion, development and monitoring of the nuclear activities. Coordination of the safe management of radioactive waste and spent nuclear fuel, including final disposal, at national level. SK Nuclear and Decommissioning Company (JAVYS) Public Management of spent nuclear fuel and radioactive waste. Decommissioning of the nuclear power plants. SI Agency for Radioactive Waste (ARAO) Public Collecting, transporting, treating, storing and disposing of low and intermediate level waste and for the disposal of HLW. Management of the closed uranium mine. ES National radioactive waste complany (ENRESA) Public Management of radioactive waste and spent fuel. Decommissioning nuclear plants. SE Swedish Nuclear Fuel and Waste Management (SKB) Private Planning and construction of all facilities required for the management of spent nuclear fuel and radioactive wastes as well as for research and development programmes necessary for the provision of such facilities. UK Nuclear Decommissioning Authority (NDA) Public Implementing Government policy on the long-term management of nuclear waste, including the decommissioning and clean-up of the civil public sector nuclear sites. HR Radioactive Waste Management Centre Public Collecting, safeguarding and increasing the value of funds to finance the development, review and implementation of the Programme for the Decommissioning of the Krško NPP. Disposal of radioactive waste and spent fuel, as well as coordinating the preparation and drafting of the National Programme. AT Nuclear Engineering Seibersdorf GmbH (NES) Public/ private Collecting, processing, conditioning and storing radioactive waste, decontaminating installations and laboratories. EL National Center for Scientific Research (NCSR) "Demokritos" Public Interim storage facility of radioactive waste at the Institute of Nuclear and Radiological Sciences & Technology, Energy & Safety (INRSTES) of the National Center for Scientific Research "Demokritos"). A National Radioactive Waste Management Committee is planned to be established. DK Danish Decommissioning (DD) Public Decommissioning and receiving, handling and storage of radioactive waste. Also licensed operator for all radioactive waste. PL Radioactive Waste Management Plant (RWMP) Public Collection, segregation, and treatment, conditioning and interim storage/final disposal of all radioactive waste arising in the country. Operating the National Radioactive Waste Repository in Rozan. PT Higher Technical Institute (ITN) Public Collecting, segregating, conditioning and storing solid and liquid radioactive waste. EE A.L.A.R.A. AS Public Former Paldiski nuclear site and Tammiku radioactive waste repository management and decontamination. LV Latvian Environment, Geology and Meteorology Centre (LVGMC) Public Processing, reprocessing, storage for an extended period of time (long-term storage) and disposal of radioactive waste.

2.1.4.Regulatory framework and competent regulatory authorities Member States are required to establish and maintain a competent regulatory authority in the field of safety of spent fuel and radioactive waste management. This authority shall be independent and be given the legal powers, as well as human and financial resources necessary to fulfil its obligations (Article 6 of the Directive). To date all EU Member States have established national competent authorities with defined responsibilities and legal powers in the area of spent fuel and radioactive waste management (see Table 4). In general, the regulatory authorities also cover nuclear and radiation safety. The majority of Member States have only one competent authority, while in others; two or more organisations have competence and regulatory functions in different aspects of spent fuel and radioactive waste management. In these cases, one of the authorities is competent for regulation and oversight of the management of spent fuel and radioactive waste originating from nuclear facilities, while another one is responsible for the safe management of institutional radioactive waste. In other Member States, there are regional regulatory authorities (such is the case of the United Kingdom and Germany), along with federal or national ones. As a general trend, Member States with nuclear programmes have provided more information and details on the authority that regulates nuclear energy than on the ones responsible for the regulation of the institutional waste. All Member States declare the independence of their regulatory authorities from any other organisation or body (i) promoting or using nuclear energy or (ii) managing spent fuel and radioactive waste. In most cases, functional or administrative independency is established in the relevant national law. The regulatory authority is in some cases embedded in a Ministry, and in others it is an autonomous body which reports to the national Parliament, the Council of Ministries, or the Government. In general terms, regulatory authorities from countries without nuclear power programmes are usually small, corresponding to the radioactive waste inventories to be managed, and often form part of the administrative structure of the State. In one particular case, the national regulatory authority does not have staff, or budget, and carries out its regulatory function through staff of other governmental bodies. The regulatory authorities of two EU Member States (Italy and Portugal) are being reorganised with the objective of reinforcing their functional independence, while the regulatory body of the Netherlands has been reorganised recently. In addition to the functional and administrative independence, technical and financial capacity are also necessary elements for an effectively independent regulatory authority capable of implementing its responsibilities within the licensing system put in place for the safety of radioactive waste and spent fuel. The national reports of most of the Member States have provided information on measures for ensuring technical and financial independency. Examples of such measures include, for instance, ensuring adequate human resources and sufficient funding by law, establishing fees to the licensees, negotiation of the budget, etc. Over half of the Member States have informed on the current status of staff and budget (see Table 4). A few Member States provided information on how the management of the regulatory authority is appointed or dismissed, to show that management is not subject to undue influence in its regulatory mission. Member States (and in particular those without nuclear energy programmes) face challenges with respect to maintaining adequate human resources in the long term. A few Member States have clearly indicated the available limited budget and/or human resources to perform the regulatory functions of the national competent authorities. A few Member States have reported that their regulatory authorities were responsible for storage of disused sources. Table 4. National Competent Authorities for spent fuel and radioactive waste management MS Competent authority Responsibilities for spent fuel and radioactive waste Reporting to Staff (year) AT Federal Ministry of Agriculture, Forestry, Environment and Water Management (BMLFUW) BMLFUW is the licensing and regulatory authority for the construction and operation of radioactive waste management facilities. Federal Government Data not available BE Federal Agency for Nuclear Control (FANC) With regard to the safety of disposal facilities, the competent regulatory authority, i.e. the AFCN/FANC, retains all of its prerogatives Federal Minister of the Interior Data not available BG Nuclear Regulatory Agency of the Republic of Bulgaria (BNRA) BNRA has been assigned responsibility for all regulatory matters concerning radioactive waste and spent fuel management facilities Council of Ministers 103 (2015) HR State Office for Radiological and Nuclear Safety (SORNS) - Establishes the legislative framework in the area of radiological, nuclear and physical safety; - Coordinates the drafting of the Strategy; - Regulates spent fuel and radioactive waste management; - Coordinates the drafting of the National programme for implementation of the Strategy; - Participates in administrative procedures for obtaining permits and authorisations for management facilities included under the Strategy; - Reporting and public information on the management of radioactive waste and spent fuel The Government of the Republic of Croatia 22 (2015) CY Radiation Inspection and Control Service – Department of Labour Inspection (RICS/DLI) The MLWSI, acting through the RICS/DLI, is the regulatory authority for radiation protection and nuclear safety and has the responsibility for the administration of the relevant legislation and authorisation of all sources and practices involving risks of exposure to ionising radiation or release of radioactive materials in the environment. Ministry of Labour, Welfare and Social Insurance (MLWSI) 5 (2015) CZ State Office for Nuclear Safety (SUJB) State administration and supervision of the utilization of nuclear energy and ionizing radiation and in the field of radiation protection Prime Minister 209 (2014) DK National Institute of Radiation Protection As the radiation protection authority, performs duties relating to the use, etc. of radioactive substances, including the management and disposal of radioactive waste Danish Health and Medicines Authority No data Danish Emergency Management Agency International cooperation in the area of nuclear safety Nuclear Division of the Danish Emergency Management Agency No data EE Environmental Board (i) Reviews the applications of the radiation practice licences and the qualified expert licences, provides services ensuring radiation safety; (ii) advises the Environmental Inspectorate, which carries out monitoring and (iii) coordinates and controls the use of the environment and natural resources by applying the coercive measures of the state in the cases determined by law. Ministry of the Environment 17 (2014) FI Radiation and Nuclear Safety Authority (STUK) STUK is responsible for controlling that the Radiation Act and other regulations based on the Act are followed. STUK grants safety licences for the use of radiation. The regulatory rights of STUK are described in the Radiation Act Ministry of Employment and the Economy Ministry of Social Affairs and Health 342 (2014) FR The Parliament, the Government and Nuclear Safety Authority (ASN) Regulates, authorises, controls and helps the public authorities to manage emergencies, participate in the public information The ASN submits regular reports on its activities to Parliament and in particular to the Parliamentary Office for the Evaluation of Scientific and Technological Choices (OPECST) and parliamentary committees 470 (2013) DE The Federal Office for Radiation Protection (BfS) - Approval of interim storage facilities for nuclear fuels; - Planning, construction, operation and decommissioning of repositories; - Repository surveillance Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB) 188 (2014) Federal Office for the Regulation of Nuclear Waste Management (BfE) - Planning approval and licensing of repositories; - Granting of licences in accordance with mining law; - Mining supervision pursuant to Sections 69 to 74 of the Federal Mining Act; - Granting of permits in accordance with water legislation planned BMUB, the Directorate-General Reactor Safety (RS) - Competent authority for nuclear safety and radiation protection; - Legal and technical supervision of the Federal Office for Radiation Protection and of the Federal Office for the Regulation of Nuclear Waste Management; - Responsible for the obligations under the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management 36 (2014) 16 Länder Land Ministry is responsible for licensing and supervision of spent fuel treatment facilities Federal government 270 (2014) EL Greek Atomic Energy Commission (EEAE) Control, regulation and supervision in the fields of nuclear energy, nuclear technology, radiological, nuclear safety and radiation protection. According to its statutory role EEAE has the legal power to exercise the regulatory control of facilities and activities in the fields of radiation protection and radiation and nuclear safety. As described in detail in Article 43, par. 4 of the new Law 4310/2014 the competencies (legal powers) of EEAE include: - development of safety procedures, regulations and legislation; - licensing and inspection procedures; - environmental radioactivity monitoring; - radiological surveillance; - emergency preparedness; - research in the fields of its competence; - public information; - international cooperation and national representations; - education and training; - personal dosimetry and calibration services Minister of Education, Research and Religious Affairs 74 (2014)* HU Hungarian Atomic Energy Authority (HAEA) The supervisory and administrative regulatory competence relating to nuclear safety and physical protection regarding nuclear installations, radioactive waste disposal facilities as well as nuclear and radioactive materials lies with the HAEA in Hungary. The Atomic Energy Act authorises the HAEA to perform is supervisory activity. The Minister appointed by the Prime Minister, currently by the Minister for National Development. 80 (2014) National Public Health and Medical Officer Service, Office of the Chief Medical Officer (NPHMOS-OCMO) The national professional and regulatory body is the granting authority for regulations on radiation protection and the radiohygiene units of priority facilities, also participating in the nuclear safety licensing process as the competent authority for radiohygiene health issues. Minister for Health 49 (2015) IE Environmental Protection Agency (EPA) Regulates radioactive material including practices involving radioactive waste, and radiation sources through a licensing system Department of Environment, Community and Local Government (DECLG) 34 in the Office for Radiological Protection (2015) IT National Inspectorate for Nuclear Safety and Radiation Protection (ISIN) – new competent regulatory authority established by the Legislative Decree n° 45/2014 Nuclear, Technological and Industrial Risk Department of Institute for Environmental Protection and Research (ISPRA) – until ISIN becomes operational The assessment and the inspection activities on nuclear installations, as well as for approving detailed designs or activities related to the construction of nuclear facilities, which are part of the general construction licence granted by the Minister of Economic Development Ministry of Economic Development No available data LV Radiation Safety Centre of the State Environmental Service (SES RSC) The SES RSC ensures national supervision and control in the area of radiation and nuclear safety, and also organises and coordinates training of the personnel whose work is related to radiation safety in order to increase the level of radiation safety in the country. Ministry of Environmental Protection and Regional Development No available data LT State Nuclear Power Safety Inspectorate (VATESI) Regulation and supervision of nuclear safety, radiation safety of nuclear energy activities involving sources of ionizing radiation, physical security of nuclear installations, nuclear materials and/or nuclear fuel cycle materials and accountancy and control of nuclear materials as well as supervision of requirements arising from international nuclear weapon non-proliferation obligations of Republic of Lithuania. The Cabinet of Government and the President 75 (2015) Radiation Protection Centre (RPC) Regulation of radiation protection Ministry of Health 59 (2015) LU Radiation Protection Division (RDP) The RPD is in charge of a) preparing the technical aspects of draft laws, regulations and orders b) lays down the conditions for licences. It has also published several guidelines. Minister for Health 9 (2015) MT Radiation Protection Board (RPB) The functions of the RPB cover all waste activities (and the facilities when they are commissioned). Ministry of Social Dialogue, Consumer Affairs and Civil Liberties (MSDC) No available data NL Authority for Nuclear Safety and Radiation Protection (ANVS) - preparing legislation and regulations and policy (including the national programme); - awarding licences and the accompanying review & assessment and evaluation tasks; - supervision and enforcement; informing interested parties and the public; participating in activities of international organisations; - maintaining relationships with comparable foreign authorities and national and international organisations; - supporting national organisations with the provision of knowledge; - having research in support of the implementation of its tasks. Ministry of Infrastructure and the Environment (I&M) 122 (2016) PL National Atomic Energy Agency (NAEA) Tasks that involve ensuring national nuclear safety and radiological protection, in particular: - supervision over activities; - promulgation of technical and organisational recommendations concerning nuclear safety and radiological protection; - performing the tasks involving the assessment of national radiation situation in normal conditions and in radiation emergency situations, and the transmission of relevant information to appropriate authorities and to the general public; - performing the tasks resulting from the obligations of the Republic of Poland - activities involving public communication, education and popularisation; - cooperation with governmental and local administration authorities in matters involving nuclear safety and radiological protection; - preparing opinions; - cooperation with appropriate foreign national entities and international organisations; - developing the drafts of legal acts; - giving opinions on the draft legal acts developed by authorised bodies Minister competent for environmental matters No available data PT Regulatory Commission for the Safety of Nuclear Installations (COMRSIN) - Licensing, evaluating, monitoring and inspecting facilities and activities relating to the management of spent fuel and radioactive waste (encompassing all phases, from initial choice of siting to decommissioning) COMRSIN is governed by three Commissioners, appointed by the Prime Minister for five year renewable terms, chosen on the basis of academic, scientific and technical merit. 4 (2015) RO National Commission for Nuclear Activities Control (CNCAN) Regulation, licensing, and control of nuclear activities Prime Minister, through the General Secretariat of the Government No available data SK Nuclear Regulatory Authority of the Slovak Republic (ÚJD SR) State regulatory activities in the field of nuclear safety of nuclear installations, including management of radioactive waste, spent fuel and other parts of the fuel cycle, as well as transport and management of nuclear materials including their control and record keeping system. It is responsible for the assessment of goals of nuclear energy programme and of quality of the classified equipment, as well as for commitments of the Slovak Republic under international agreements and treaties in the said field. The Government and subsequently to the National Council 108 (2014) SI Slovenian Nuclear Safety Administration (SNSA) Nuclear safety of facilities and the safety of industrial radiation sources Ministry of Environment and Spatial Planning 41 (2014) Slovenian Radiation Protection Administration (SRPA) Radiation protection in medicine and veterinary practice, medical surveillance of exposed workers, surveillance of workplaces, dosimetry and dose registers and education in the area of radiation protection Ministry of Health No data ES Nuclear Safety Council (CSN) Reporting on nuclear safety and radiological protection and authorisations to nuclear and radioactive installations as well as carrying out inspection and control and issuing Instructions, which take the form of mandatory rules Parliament 205 (2014) SE Swedish Radiation Safety Authority (SSM) SSM supervises the Swedish Nuclear Fuel and Waste Management Co (SKB), the power plant operators and other licensees of nuclear activities in fulfilling their responsibilities for safe operation of facilities and transports as well as in planning for decommissioning and disposal. Ministry of the Environment 321 (2015) UK Office for Nuclear Regulation (ONR, UK) Regulates: - nuclear safety; - nuclear site health and safety; - nuclear security; - nuclear safeguards; - transport Government Department of Energy & Climate Change 330 (2014) Environment Agency (EA, England) - Regulates the accumulation and disposal of radioactive waste from non- nuclear premises - Regulates nuclear and non-nuclear sites in England Government Department of Environment, Food & Rural Affairs No available data Natural Resources Wales (NRW) - Enforces environmental protection legislation; - Regulates nuclear and non-nuclear sites in Wales Welsh Government Scottish Environment Protection Agency (SEPA) - Enforces environmental protection legislation; - Regulates nuclear and non-nuclear sites in Scotland Scottish Government Northern Ireland Environment Agency (NIEA) Regulates non-nuclear sites in Northern Ireland Northern Ireland Assembly Health & Safety Executive (HSE) - Regulate health and safety for England, Wales and Scotland; - Regulate the use of ionising radiation in the non-nuclear sector Government Department of Work & Pensions *Other sources of information 2.1.5.Shipments within EU and to third countries Radioactive waste shall be disposed of in the Member State in which it was generated, unless an agreement with another Member State or third country is in force and the conditions set out in Article 4(4) of the Directive are met. The Directive imposes conditions prior to the shipment of radioactive waste regarding safety arrangements in the destination country, and availability, operation and management of appropriate disposal facilities. This requirement is not applicable to: (i) the repatriation of disused sealed sources to a supplier or manufacturer, (ii) the shipment of spent fuel of research reactors to countries that supply or manufacture research reactor fuel (and according to international agreements), or (iii) Krško nuclear power plant spent fuel or radioactive waste shipped between Slovenia and Croatia. Spent fuel and radioactive waste can be shipped to a Member State or third country for reprocessing and processing. In this case, the ultimate responsibility for the safe and responsible disposal of those materials, including any radioactive waste and by-products that could be generated shall remain with the Member State from which the spent fuel or radioactive waste originates (Article 4 of the Directive).

The majority of Member States have legal requirements in place for the spent fuel and radioactive waste sent for processing or reprocessing abroad, among which the allocation of the ultimate responsibility within the Member State originating the material. In most cases, the ultimate responsibility remains within the Member State or third country in which the spent fuel or radioactive waste was generated. A few Member States have provided the text of the agreements for (re)processing, while others have reported the main provisions of such agreements. In addition, a few Member States report that import of radioactive waste in their territory is excluded by law. The majority of Member States with research reactors foresee the return of their spent fuel back to the supplier (USA and the Russian Federation) before 2020, without returning the possible arising radioactive waste back to the originating countries. A few Member States with research reactors have plans to ship the spent fuel for reprocessing, and a number of Member States with training and demonstration reactors have not yet defined the strategy for the long term management of spent fuel. To date, eight Member States that have opted for spent fuel reprocessing will receive radioactive waste after reprocessing in the EU or outside the EU in the period 2017-2052 (see Table 5). Table 5. Return of By-products from Spent Fuel Reprocessing to EU Member States MS Type of material Timeframe BE Around 16 % of the spent nuclear fuel from NPP has been reprocessed in the past at La Hague (France). Most has been returned and the remaining secondary waste will be returned in 2017 2017 BG Return of HLW from Kozloduy NPP spent fuel reprocessing in Russia After 2025 CZ Return of residual waste from highly enriched Uranium (LRV-15 reactor) sent to Russia 2024-2026 DE Radioactive waste from spent fuel reprocessing in the UK and France is expected to be returned to Germany. Vitrified fission products were already returned from France in the period 1996 - 2011 No information HU Planned return of material from spent fuel from planned Paks NPP units 5 and 6 reprocessing in Russia in case reprocessing is decided. Decision not taken yet IT 98% of NPP spent fuel is shipped to the UK and France. The remaining 2% will be shipped to France in 2016. The return of radioactive waste from the UK is scheduled between 2020 and 2025. 2020-2025 NL Waste from spent fuel reprocessing in the UK returned. Part of vitrified HLW from France received and additional expected to be returned latest in 2052 ES Products from reprocessing that need to be returned to Spain are vitrified high level waste located in France (spent fuel from Vandellos I NPP) and recovered U and Pu in the UK (spent fuel from Santa Maria de Garoña NPP). 2021 Member States are required to include in their national programmes any agreement(s) concluded with a Member State or a third country on management of spent fuel or radioactive waste, including on the use of disposal facilities (Article 12(1)k of the Directive). Only a few Member States submitted their agreement(s) with other Member States or a third country, while most Member States with no nuclear programmes did not notify having such agreements in place to date. To date only two Member States have concluded an agreement for management of small amounts of institutional waste (Luxembourg and Belgium). In addition, two Member States (Slovenia and Croatia) are working towards common disposal solution for spent fuel and radioactive waste generated by the shared nuclear power plant (an agreement is expected by 2023). 2.1.6.Self-assessment and international peer reviews At least every 10 years, Member States shall arrange for self-assessments of their national framework, competent regulatory authority, national programme and its implementation, and to invite international peer review of their national framework, competent regulatory authority and/or national programme. The aim is to ensure that high safety standards are achieved in the safe management of spent fuel and radioactive waste. It is Member State's decision to define the scope, timing and type of international peer reviews as long it complies with provision of Article 14(3) and is carried out by 2023. Member States are required to report the outcomes of these international peer reviews to the Commission and the other Member States, which may be made available to the public, unless there is conflict with security and proprietary information. The majority of Member States address periodic self-assessments and international peer reviews in a general way in their national programmes and reports. Some Member States have clearly defined timeframes for review and update of the national programmes (which is assumed to cover the self-assessment requirement), however only about a third of the Member States provided information on self-assessment of the national framework for spent fuel and radioactive waste management (see Table 6). In most Member States self-assessment of the competent authorities has been established and carried out through the IRRS missions of the IAEA. While the majority of Member States reported IRRS missions, a few Member States provide details on the self-assessment outcomes related to spent fuel and radioactive waste management. Although the majority of IRRS missions’ reports are publicly available, details on the Member States' follow up actions addressing the outcomes of theses reviews for achieving higher level of safety have been reported by a few Member States. Therefore, the implementation of this Article requires specific attention in the future Member States reporting to the Commission. Since 2014 the Commission is supporting the IAEA in development of a self-assessment tool based on the IAEA safety standards and best practice to enable EU Member States to fulfil their obligations for periodic self-assessment (Article 14(3) of the Directive). The first reviews in Poland and France are scheduled for 2017. About a third of the Member States report on the planned international peer reviews related to their spent fuel and waste management, however a few Member States present specific timeframes of planned international peer reviews in their national programmes and reports on spent fuel and radioactive waste management, and clearly explaining the mechanisms for taking into account lessons learned in the review of the national programme. The Commission is aware through ENSREG that eight Member States have specific plans to conduct ARTEMIS peer review service and to host missions until 2023 (for details see Table 6).

Table 6. Recent and planned international peer reviews as per Article 14(3) of the Directive MS National programme and/or National framework Competent regulatory authority BE No information 2013 (IRRS), 2016 (IRRS follow-up) BG No information 2016 (IRRS follow-up) CZ No information 2017 (IRRS) FI 2009 (OSART for the spent fuel disposal facility), 2023 (ARTEMIS) 2012 (IRRS), 2015 (IRRS follow-up), 2023 (IRRS full scope) FR 1996 and 2005, IAEA Review of specific waste management projects 2017 (ARTEMIS) 2014 (IRRS) DE 2019 (ARTEMIS) 2018 (IRRS full scope) HU No information 2012 (IRRS follow-up), 2015 (IRRS) IT No information 2016 (IRRS) LT 2019 (ARTEMIS, self-assessment) 2021 (ARTEMIS) 2016 (IRRS full scope), 2018 (IRRS follow-up) NL 2023 (ARTEMIS) 2014 (IRRS) and 2018 (IRRS follow-up), 2023 (IRRS full scope) RO No information No information SK No information 2012 (IRRS follow –up) SI No information 2011 (IRRS) and 2014 (IRRS follow-up) ES 2018 (ARTEMIS) 2008 (IRRS), 2011 (IRRS follow-up) SE 2009 Plan review through IRRS (2012); SKB post-closure safety case NEA/OECD review (2012); WANO review of SKB SFR and Clab operation (2013) 2012 (IRRS), 2016 (IRRS follow-up) UK OSART for Sizewell B site planned. 2006, 2009, 2013 (IRRS) and 2014 (IRRS follow-up) AT No information No information DK 2019 – 2021 period (ARTEMIS) 2019 – 2021 period (IRRS) EL No information 2012 (IRRS) LV No information No information PL 2017 (ARTEMIS) 2013 (IRRS) PT No information No information HR No information 2015 (IRRS) CY No information 2017 (IRRS) EE No information No information IE No information 2015 (IRRS) MT No information Self-assessment in 2014 and 2015 (IRRS) LU After 2018 2018 (and expanded IRRS) 2.1.7.Notification and reporting To date all Member States have submitted their first reports as required by Article 14(1) and a few Member States (Czech Republic, Germany and Estonia) have notified their Joint Convention reports (dated 2014) for the 5th Joint Convention review meeting (held in May 2015) to the Commission as part of their national programme/reports required under Article 15(4) and Article 14 (1) of the Directive.

With exception of one (Latvia), all Member States submitted to the Commission their final (22 Member States) or draft programmes (5 Member States – Austria, Croatia, Czech Republic, Italy and Portugal) that currently undergo formal approval at a national level. Slovenia and Spain national programmes have been drawn-up in 2006 and therefore some of the information reported is out-dated but both of these countries have presented updated information on the spent fuel and radioactive waste management activities in their national reports, as well as an updated inventory of the spent fuel and radioactive waste. All this information has been used in the preparation of this report. As the Member States' deadline for notification of their national programmes was 23 August 2015, the Commission opened 12 EU pilots for non-communication of the national programmes in October 2015. Three Member States submitted their final programmes in January 2016 and the Commission then proceeded with nine Letters of Formal Notice in April 2016. In response the Commission received three additional national programmes by August 2016. The majority of remaining Member States planned to notify their approved programmes by the end of 2016, although a few Member States foresee submission in 2017 due to the long approval process in the country. 2.2.Assuring the safety of spent fuel and radioactive waste management 2.2.1.Licence holder’s responsibilities Member States shall ensure that the prime responsibility for the safety of spent fuel and radioactive waste management facilities and/or activities rest with the licence holder; and that responsibility cannot be delegated (Article 7 of the Directive). All Member States have reported that measures are in place to ensure that the primary responsibility for spent fuel and radioactive waste management is with the license holders. The provisions presented are mainly legal and focus on legal requirements, license conditions and enforcement actions in case of non-compliance. However, in some cases examples have provided with regard to their practical implementation of these legal provisions. Licence holders shall establish and implement integrated management systems, which give due priority for overall management of spent fuel and radioactive waste to safety and are regularly verified by the competent regulatory authority. Overall the majority of Member States have reported their legal requirements for integrated management system or quality assurance for spent fuel and radioactive waste management that focus on safety. Limited information has been provided in the national reports on how these requirements are implemented in practice by all radioactive waste and spent fuel management license holders. The majority of Member States with nuclear facilities provided more details on integrated management and quality assurance systems within their national operators, bodies or organisations related with nuclear facilities (through examples in some cases), and less within organisations dealing with institutional waste. A few Member States have not addressed management system in their reports. Licence holders have to provide for and maintain adequate financial and human resources to fulfil their obligations for safe long term management of spent fuel and radioactive waste. Overall Member States have legally established requirements in this regard, such as, a license can be granted only in case the applicant does demonstrate sufficient human, technical and financial resources. The majority of Member States with nuclear programmes state that the financial and human resources are enough or adequate, without providing further details. In some cases, these countries establish in their national framework a generic requirement of adequate resources. A few Member States with nuclear facilities have provided very detailed information on human and financial resources currently available in the licensees. 2.2.2.Concepts and plans (including post closure) National programmes shall include the concepts or plans and technical solutions for spent fuel and radioactive waste management from generation to disposal (incl. post-closure phase), in particular related to institutional control and preservation of knowledge in the longer term (see Article 12(1)d and Article 12(1)e of the Directive). Overall the predisposal management of radioactive waste is a practice with long Member States' experience, and Member States either have capacities or plan to develop additional ones until disposal options remain available at national or international level. Concepts and/or plans and technical solutions for predisposal management of spent fuel and radioactive waste are defined in different level of detail by all Member States with present or past nuclear programmes. Due to the long timeframes until geological disposal facilities become operational in most nuclear power plant Member States, the importance of spent fuel, HLW and ILW sufficient storage capacity is increasing. For example, some Member States already have plans for construction of mainly dry storage facilities for spent fuel, either new or expanding the existing capacities. Contrary to this, disposal concepts for ILW, HLW and spent fuel are, instead, not as well developed and detailed in most of the countries. Regarding geological disposal, about over half of Member States have disposal plans spanning up to the next century, and one third of Member States plan to operate such facilities after 2040. A number of Member States with new build programmes have not considered the additional storage/disposal capacities in their national programmes. The plans for spent fuel management in majority of the Member States with existing and planned nuclear programmes are to dispose this fuel without reprocessing, except for the few Member States which are reprocessing (France and the UK) or have ongoing reprocessing arrangements with France, the United Kingdom, and the Russian Federation. There are plans of 15 Member States for geological disposal facilities, the majority planned to be operational after 2065 (the first three in Finland, France and Sweden by 2030, see Table 7). In order to facilitate the development of such complex projects five underground laboratories are in operation in four Member States. Three more laboratories are foreseen in Czech Republic, Poland and Romania as presented in Table 13. Some of the remaining countries consider as an option the disposal either in EU or in a third country (see Table 7). At the same time, a number of Member States presented their plans for finding solutions for disposal of exotic waste from research activities. A few Member States with nuclear programmes did not address all types of radioactive wastes as their programmes mainly focused on nuclear power plant waste and spent fuel. Management solutions for some types of radioactive waste like orphan sources and institutional wastes (e.g. disused sealed sources categorised as radioactive waste) have not been addressed in detail in the national programmes. Table 7. Planned Deep Geological Disposal Facilities in EU Member States MS Siting Commissioning Operation (years) Closure Institutional Control Cost (€) Responsible organization Comment FI Eurajoki (Olkiluoto) site 2022 90 2110 Not foreseen 3.5 bn (2012, 5 units) POSIVA Licence for construction (2015) FR Cigeo: sited in the Border of the Meuse and Haute-Marne 2025 more than 100 After 2125 16.5 bn (2012) ANDRA 100 year reversibility; concept for submission for authorization SE Forsmark site 2019-2030 45 2075-2076 Not foreseen SKB Licence application for construction under review UK 2016 2040 until 2089 2120 9,5 bn £ (2014/2015 ) (undiscounted) NDA 2016 is a formal process of working with communities for potential sites; start receiving ILW and LLW in around 2040 and HLW in 2075 DE After 2031 2050 7.7 bn Federal Office for Radiation Protection The cost is for a new geological disposal facility RO 2025 2055 100 2150 1.02 bn (2 units) to 2.04 bn (2006) USD (4 units) ANDR Siting not started yet HU Site selection ongoing 2064 20 2084 Not yet established 745 278.5 mill HUF (2015) PURAM Research activities are planned SK Site selection first stage (2013-2016) Sit selection in 2030 2065 40-60 2105-2115 Not foreseen 3.7-4.4 bn (2014) JAVYS 3.7 bn for 40 years NPP operation and 4.4 bn for 60 years NPP operation SI Site to be selected (2045-2055) 2065 10 2075 No data Not available ARAO Agreement with Croatia pending HR 2043 2065 Possible agreement wih Slovenia by 2023 CZ 2018 2065 4.1 bn (2011) or 111.400 mill CZK SÚRAO Ongoing site selection; two sites to be selected LT 2033 2066 6 2072 1.89 – 2.6 bn Ignalina NPP/ RATA ES 2016-2050 (including knowledge update) 2050-2069 2069 3 bn (2005) ENRESA BG Prefeasibility study ongoing and 6 potential sites selected Not available SERAO No concepts as yet for ILW / HLW other than interim storage NL Decision in 100 years About 2130 1.5-2.5 (1996-2000) COVRA Costs for "final storage". Decision in 100 years BE No date defined pending national policy Not available 15 years after authorisation is given at least 100 years after construction and operating license 3.2 bn (2012) ONDRAF/NIRAS The disposal cost is for waste category B and category C PL 22nd century 22nd century around 50 years Mid-22nd century Not available RWMP New build In most of the Member States without nuclear programmes the disposal options for radioactive waste are only at a conceptual level and the pertinent research and siting activities have been postponed in some cases for several decades.

Radioactive waste predisposal activities in Member States without nuclear programmes are predominantly related to storage of disused radioactive sources, and return of disused sealed radioactive sources to the supplier. To date over 30 dedicated disposal facilities for VLLW and LLW are in place in 12 Member States. Bulgaria, Latvia and Lithuania categorised their past disposal facilities of RADON type as storage facilities. About half of Member States are planning to build new disposal facilities and capacities in the next decade (see Table 8). The types of facilities range from landfills, trenches to vault type disposal facilities depending on the type and class of radioactive waste disposed. These facilities are mainly in the Member States with nuclear programmes and in a number of cases. In addition to Bulgaria and Lithuania, a few Member States also plan or consider remediation of existing disposal facilities and contaminated sites (e.g. Germany).



Table 8. Near surface and intermediate depth disposal facilities in EU MSe Existing/ planned Siting Commissioning Operation (years) Closure Institutional Control (years) Responsible organization Comment BE Planned LLW (Category A waste) Dessel site 4 y after construction/operation license 54 y after construction/operation license 104 y after construction/operation license 250 ONDRAF/ NIRAS Under licensing application review for construction BG Existing for LLW and ILW (institutional waste) Novi han site 1964 SERAW Used for storage. Planned decommissioning by 2025 Planned near surface Radiana 2021 2086 SERAW CZ Dukovany (existing) Duckovany NPP 1995 2050 300 SÚRAO Capacity until 2050 Hostim (existing) Beroun 1959 1965 Ongoing SÚRAO Closed Bratrstvi (existing) Jáchymov 1974 2020 100 SÚRAO Capacity until 2020 for NORM waste Richard (existing) Litoměřice 1974 2025 100 SÚRAO Capacity until 2025; considered extension afterwards EE Planned 2018 2040 2050 A.L.A.R.A. AS Concept for low and intermediate level waste disposal to be decided FI Lovisa NPP (existing) Lovisa 1998 2060 Not required TVO Olkiloto NPP (existing) Olkiloto 1992 2080 or 2100 Not required FORTUM Hanhikivi (planned) After 2035 2120 Not required FVO FR Centre de L'Aube (existing) Aube district 1992 Later than 2050 300 ANDRA Low level waste and intermediate level waste-short lived



Centre de La Manche (existing) Manche district 1969 1994 300 (since 2003) ANDRA Cires (existing) Morvilliers 2003 Saturation in 2025 ANDRA VLLW disposal facility DE Konrad 2007 2022 Several decades Federal Office for Radiation Protection Under construction Morsleben (existing) Morsleben 1971 Until 1998 In progress BfS Closed under licensing HU Radioactive Waste Treatment and Disposal Facility (RWTDF, (existing) Püspökszilágy 1976 2067 150 PURAM Institutional waste National Radioactive Waste Repository (NRWR, existing) Bataapati 2008 2084 50 PURAM Waste nuclear power plants IT National repository (planned) planned 2015 - 2018 SOGIN Technology parc LT RADON (Existing) Maišiagala 1964 1989 For institutional waste to be retrieved and facility remediated. Site release in 2023 Industrial landfill for VLLW disposal (planned) Ignalina NPP Decision to retrieve or leave 2018 - 2025 RATA Planned investigation for possible conversion of an existing industrial landfill to a VLLW disposal facility VLLW (planned) Ignalina NPP 2018 2038 Active 30 Passive 70 RATA LILW Ignalina (planned) Ignalina NPP 2020 2021 Active 100 Passive 200 RATA



Bituminised Ignalina (planned) Ignalina NPP Decision in 2022 LV Baldone (existing) Baldone 1962 LEGMC Also used for storage PL NRWR (existing) ROZAN 1961 2024-2029 300 RWMP Operating NNRWR (planned) Selection in 2018 2018-2024 2144-2155 300 RWMP Planned RO BaiTa-bihor (existing) 1986 2050-2055 100 active 200 passive ANDR DFDSMA (planned) 2017 2021 2090 100 active 200 passive ANDR SI LILW (Planned) Site selected: Vrbina in 2009 2020 After 2061 ARAO Pending agreement with HR HR Institutional radioactive waste disposal (planned) Cerkezovav 2025 2062 After 2065 NPP waste disposal to be agreed with SI ES LLW and ILW (existing) El Cabril 1992 2040 300 years ENRESA VLLW (existing) El Cabril 2008 2040 60 years ENRESA SK Mochovce LLW (existing) Mochovce 2001 After 2080 Extension to be decided in 2018 several decades active; and 200-300 passive JAVYS Existing; extension to be decided in 2018 Mochovce VLLW (planned) Mochovce 2018 JAVYS SE SFR (low and intermediate level waste) (existing) Forsmark 1983-1988 Extension requested in 2014 2070-2075 SKB AB Expected extension in 2023 SFL (long lived low and intermediate level waste) (existing) License to be submitted in 2030 Planned 2045 2075 SKB AB Forsmark NPP (VLLW) (existing) Forsmark 30 Forsmarks Kraftgrupp AB Operational Oskarshamm NPP (VLLW, existing) Oskarshamm 30 OKG AB Operational Ringhals NPP (VLLW, (existing) Ringhals 30 Ringhals AB Operational



Studsvik (VLLW, (existing) Studsvik 30 AB SVAFO Operational UK Drigg VLLW/LLW (existing vaults and trenches) Sellafield 1950 2050 100 Low Level Waste Repository Limited Foreseen extension of capacity after 2050 for operation until 2129 CLESA (existing) Sellafield 2026 Decommissioning waste and site clearance waste Calder landfill VLLW Sellafield South landfill VVLW (existing) Sellafield Dounreay shaft (existing) Dounreay 2005 closed Dounreay LLW (existing) Dounreay 2014 2028 Dounreay Site Restoration Limited (DSRL) Onsite pits and trenches (existing) Harwell, Springfield, Sellafield, and Dounreay The national programmes should address post-closure measures for disposal facilities and measures for knowledge preservation (Article 12(1)e of the Directive). The majority of countries cover the post-closure period only in very general terms or did not address the post closure measures for the disposal facilities in their notifications. Of the countries with a present or past nuclear programmes, only a few have presented detailed and defined plans for the post-closure period of the disposal facilities. Some of the countries present plans for the post-closure period only for the near-surface disposal facilities while the post-closure period of the deep geological facilities is either not detailed or not foreseen. The main reason provided in this case was either no availability of operational disposal facilities and/or that it is premature to consider this phase now, including the fact that a number of countries leave open the possibility for a regional solution to the disposal of spent fuel and high level wastes. Information on the preservation of knowledge after the closure of the disposal facilities is in particular not available in most of the national programmes submitted. 2.2.3.Safety demonstration The licensees shall regularly assess, verify and continuously improve, as far as is reasonably achievable, the safety of the radioactive waste and spent fuel management facility or activity in a systematic and verifiable manner, by applying the graded approach (see Article 7 of the Directive). The majority of Member States presented the legal basis and provisions for regular safety reviews, however a few concrete examples of how these provisions have been applied in practice were available (e.g. stress test after Fukushima, safety assessment for spent fuel facilities). Safety demonstration shall cover activities and facilities (i.e. development, operation and decommissioning), as well as the post-closure phase of disposal facilities (see Article 7(3) of the Directive). The majority of Member States have addressed safety demonstration in their reports mainly through presentation or reference to established legal requirements. About one third of Member States (mainly Member States with nuclear power plants) have addressed safety demonstration in their reports though concrete examples of safety assessments and safety cases mainly, for large nuclear facilities and producers of spent fuel and radioactive waste. Member States with research reactors and non-nuclear programmes provide little information on practical examples of safety demonstrations and their results, as well as implementation of emergency preparedness measures. 2.2.4. Cost assessment, financing mechanisms and available resources Article 12(1)h of the Directive requires Member States to provide cost assessments for spent fuel and radioactive waste management in their national programmes, including assumptions used and profile over time. Over two-thirds of Member States included information about individual costs (e.g. disposal) or costs estimates for spent fuel and radioactive waste management in their national programmes.

The information on the cost assessments is mainly provided by Member States with nuclear programmes and research reactors, which represent the majority of spent fuel and waste inventory in the EU. While most Member States have estimated the global costs of the actions that are included in their national programmes, in the majority of cases this information is not sufficient to conclude on the completeness and accuracy of the figures reported. Member States with only institutional waste have not provided cost estimation. Based on the reported data, the estimated total cost for the management of spent fuel and radioactive waste in line with the Member States national programmes to date is about EUR 400 bn (see Table 9) which for some Member States includes also costs for decommissioning. A very significant part of the total cost is for the United Kingdom, France and Germany as these Member States have the largest nuclear programmes and inventories of spent fuel and radioactive waste in the EU. The data has not been verified by the Commission. To put this figure in perspective and taking into account the total estimated production of electricity until the end of the NPP lifetime, the estimated cost for implementation of the Member States national programmes represents about 4 to 6% of the electricity generation cost from NPPs. Some of the data differ from the PINC as the national programmes in addition to NPPs cover also other facilities (e.g. research reactors) as well as costs of remediation of contaminated sites from past practices. It can be noted that Member States with nuclear programmes applied two main approaches to cost assessment – different scenarios based on different hypotheses (e.g. including or not life time extension of nuclear power plants) and, variation of parameters for one base or reference scenario. About half of Member States provide information on the assumptions and other data explaining the basis for the estimation, however with different level of detail. The scope of assessments also differs, as some Member States presented only waste disposal costs, other included decommissioning cost (including management of decommissioning waste) as well. In some cases, the cost for management of research reactor spent fuel (i.e. storage in EU and repatriation to the state of origin) was not reported. The cost of management of institutional waste is not often clearly presented in the Member States' programmes. In some cases, the cost presented does not include all facilities, and in other cases, the costs are estimated for a fraction of the programme (for instance only until the next revision of the national programme). Most Member States with large nuclear facilities have established mechanisms for the periodic update and review of the cost estimation. Member States are also required to have adequate financing mechanisms (Article 12(1)i, Article 5(1)h and Article 9 of the Directive). So, all Member States have presented their mechanisms in place for the funding of their national programmes, with diverse levels of details. Member States with nuclear facilities have opted for different arrangements. A few Member States have internal funds (e.g. within the companies generating spent fuel and radioactive waste) established by large electricity producers. Member States with institutional waste declare that the cost of waste management will be covered by the fees that the waste management organisation charges to the radioactive waste/spent fuel generators. Financial mechanisms provide in most cases for regular and independent assessment, and stringent legal constraints to ensure that the funds are in effect spent for the purposes for which they were created. More than half of Member States provided information about the status of the funds for spent fuel and/or radioactive waste management at different level of detail as presented in Table 10. Lithuania and Estonia have indicated their reliance on EU funds for radioactive waste and spent fuel management, while a number of Member States declared insufficiency of funds to date.



Table 9. Estimated total cost of spent fuel and radioactive waste management based on EU Member States' programmes Member State Estimated total costs, bill€ (year) Timeframes Assumptions Generated capacity (TWh, total estimated for the lifetime)30 BE 4.6 (2012) Category A and B disposal costs of: 1.38bill€ for near surface disposal facilities and 3.2bill€ for geological disposal 1748 BG 2.0-4.5 (2015) 2030 Decommissioning, spent fuel processing and. storage for Kozloduy NPP units 1-4 and 5-6. The range of costs depends on the extension or not for units 5 and 6. 807 CZ 4.2 (2011) geological disposal after 2160 Low and intermediate level waste disposal up to 2050 3,250 CZK mill (2013) = 0,11 bill Eur; and 0.037 CZK/€; includes also decommissioning 1334 FI 6.5 (2012) 2110 Not including future NPPs’ 100 mill € for near surface disposal and 3,5 bill € for geological disposal 1041 FR 89 (2011 prices) 2135 Including institutional control; 35 bill€ for legacy sites recovery; 38 bill € decommissioning; 16 bill € for geological disposal (although now reassessed to 25 bill€) 21076 DE 66.9 (2012) 2080 34 bill € for NPP waste, Asse - 5 bill€; Morsleben – 2.4-4.7 bn€; Konrad – 7.5 bn € and new geological disposal facility – 7.7 bn €; public radioactive waste management - 6 bn €; Gorleben site - 2 bn € (40 mill€/year for 50 years until 2065) all at 2012 prices 5234 HU 5.3 (2015) 2064 1 650 402 mill HUF (2015) for:

- Decommissioning of 4 NPP Units in operation;

- Decommissioning of spent fuel interim storage facility (ISFS);

- Radioactive waste disposal facilities;

- HLW disposal facility;

- PURAM operating costs, supervision fees, fund management and support to local governments. 624 IT 18.1 2030 (excluding geological disposal) 1,5 bill € for siting and construction of the Technological Park 143 LT 2.5 (2005-2014) 2038 (but before geological disposal) RAW management and disposal & SF management: 560.2 mill € (decommissioning plan 2014)

Close Maišiagala repository: 4.2 (specific programme 2013)

Other activities: 47.7 (present cost 2014); SF disposal: 1889.0 (feasibility study 2005) 311 NL 1.5-2.5 (1996-2000) No data Cost for "final storage" 202 RO 1.8 to 3.5 Geological repository development should start from 2040 Average of 1.8 and 3.5bill€. 3,5bn € (includes 2 new reactors) and 1.8bn€ without new build 448 SI 0.31 (2005) 2006-2065 Total costs for 2005-2065 extrapolated from 2006-2015 costs 138 SK 8 (2014) 2060 707 ES 20 (2015) 2085 Total cost incurred until the end of 2014-5.2 bn; and future costs (2015) - €14.7 bn 3126 SE 10 (2013) From 2015 onward January 2013 price level 3386 UK 147.5 (2014) NDA costs till 2130 The NDA, having considered a number of scenarios, continues to estimate the undiscounted cost within a potential range from £95 bn (€118 bn) to £218 bn (€272 bn) 3445 HR 0.9 (2015) After 2043 Immediate decommissioning of the Krško NPP after shut-down in 2043, The cost includes, waste management, spent fuel and decommissioning 138 AT No data No data - DK No data No data - EL 4.6 x10-3 Next 5 years Costs cover for collection and storage of disused radioactive sealed source - PL 99x10-3 2025 The cost excludes future NPP and geological repository - PT 2.5x10-3 Cost for the spent fuel transfer to USA remaining fuel & decommissioning - CY 0.5 x 10-3 (2016) Cost of repatriation or disposal, and operational costs of the storage included in Nicosia General Hospital - EE 4.6x10-3 - IE No data No data - LV 1.08 2002 costs for construction radioactive waste management, Improving safety, compensation to Baldone municipality for radioactive waste storage facility - LU No data No data Costs for shipment to Belgium. The government states it is capable of covering any cost - MT No data No data - Table 10. Financial mechanisms and accumulated funds by Member State MS Financial mechanisms (organisation) Gradual Internal (I)/ External (E) Funds accumu lated (bn €) Total accumu lated (date) Preliminary estimate of available funds (%) Comments BG Radioactive waste management fund (SE RAO) Annual fees E 0.845 (2003) 0.845b€ (2003) 19 to 20 (the latter assuming 6 units and LTO) EU funds for Kozloduy NPP units 1 to 4 are taken into account. Recognised insuffiency of fund to date. Decommissioning fund (SE RAO) Annual fees E 1.4 (2015) CZ Nuclear Account for SF & RAW (Ministry of Finance) Annual fees E 1.4 (2014) 1.4 (2014) 33 37.4b CZK, 2014 ( 0.037 CZK/€) HU Central Nuclear Financial Fund Annual fees E 0.8 (2015) 0.8 (2015) 15 Fund to cover the costs for management of waste, spent fuel and decommissioning; 246,386 mill HUF, 2015 (0.0032HUF/€) SK National Nuclear Fund Annual fees E 1.2 (2015) 1.2 (2015) 18 FI The State Nuclear Waste Management Fund Annual fees E 2.5 ( 2016) 2.5 (2016) 38 Does not include new build BE Long-Term Fund (NIRAS/ONDRAF) I No information - - DE Private generators (NPPs) make provisions I 36 (2015) reported for NPPs 36 (2015) 54 Based on the total cost 66.9 bn€ (as at 2012) until 2080 and 2103 FR Licensees create a portfolio of dedicated assets. I 43 (2011) 48 As dedicated internal funds & assets IT State pays for state owned facilities. SOGIN manages the funds for waste management Annual fee No information - - The national programme cost is until 2030 and exclude geological disposal. Private generators shall pay to a fund (no details on the fund available) LT Decommissioning Fund for Ignalina Nuclear Power Plant, State Budget, Ignalina Programme, INPP, Other funds No information No information - The national report states that the funds are sufficient SF and RAW management until 2020. Reliance on EU funds after 2020. Decommissioning continues until 2038 NL Contributions to COVRA E 183 mill (2014) - 8 Temporary surface storage for at least 100 years. Operation of geological disposal in 2130. RO Waste Disposal Fund (ANDR) Annual fees E 102 million (2014) 0.15 (2014) 4 - 8 4% for new build scenario and 8% without new build. Financing mechanism under revision to address the insufficiency of funds



Decommissioning Fund (ANDR) Annual fees E 47 million (2014) 209 million Lei (€47 million) ES Fund for the financing of activities included in the General Radioactive Waste Plan Annual fees E 19.96 (from 2015 onward) 5.2 35 costs to 2085; future costs considered only SI Fund for Financing the Decommissioning and Management of Radioactive Waste from the Krško NPP Annual fees E 0.04 0.04 13 Estimates only made for period 2006-2015. financing the decommissioning of the NPP and for the disposal of NPP radioactive waste SE Nuclear Waste Fund Annual fees E SEK 56 bn. and 19 bn SEK guarantees 76.3 bn SEK (2015) 75 Total of 76.3 bn SEK. Only remaining costs considered. 56% coverage if guarantees are excluded Studsvik Legacy Fund I 1.3 bn SEK (2013) Non-nuclear waste management of orphan sources E 127 mill SEK UK NDA Fund State funds 83.8 (2015) 30-70 depending on the scenarios 67 bn £ = (0.8P/€) (activities until 2130, and total NDA cost between 95-218 bn £) Nuclear Liabilities Fund Annual fee E 8.3 (2015) 8.3 bn £ (2015) HR Fund for Financing the Decommissioning of the Krško Nuclear Power Plant and the Disposal of NPP RAW and SF Annual fees E 0.2 (2013) 22 0.16 bn € as at 2013, if reactor extension is up to 2043 then estimated to 0.54bill €



AT Final disposal fees paid to the Government Fees for treatment and disposal No information - - EL Fund yet to be established No information - - 4.6 mill€ costs over 5 years for collection & storage of disused radioactive sealed sources. DK No information No information - - PT Disposal revenue; General state budget and IST budget Fees from producers No information - - US transfer of remaining fuel to be covered by the State; increase of fees foreseen in 2015 PL RWMP collects fees Fees for disposal, decontamination, and transport No information - - Decommissioning fund for the new build to be established CY Fund planned Currently generators’ fees and State budget No information - - The fund costs will cover waste management (incl. disposal), decommissioning, R&D, etc. EE Estonian environmental fees EU funds Fees from waste producers E No information - - Reliance on EU funds for historical liabilities IE Currently generators’ fees and State budget No information - - The state cost cover orphan sources. The regulators income in 2012 was 5.2 mill € but not specifically for radioactive waste LV Currently generators’ fees and State budget No information - - Provisions for Salaspils research reactor assumed by the State MT Currently generators’ fees No information - - State to cover the cost of orphan sources LU Government will provide necessary resources Currently generators’ fees No information - - Statement for all necessary resource available Limited information has been reported on the funds' investments and management to ensure availability of funds when needed in the future.

2.2.5.Expertise and skills All parties in Member States have to make arrangements for education and training for their staff, as well as research and development activities to cover the needs of the national programme for spent fuel and radioactive waste management in order to obtain, maintain and to further develop necessary expertise and skills (Article 8 of the Directive). The majority of Member States have legal requirements for training and education of staff involved in spent fuel and radioactive waste management. About half of Member States has presented specific measures in place for maintaining skills and competence of generators, operators and competent authorities, although the emphasis was more on training and competence of regulatory body's staff and less on research and development. Overall Member States with nuclear power plants have presented more developed practical arrangements for training and education than the remaining Member States. Some Member States presented very detailed training programmes and information on the costs/investments for training and skills development Member States use national schemes and arrangements that can be summarised as follows: ·Post-graduate courses at universities; ·Training centres (basic and specialized, some of which at nuclear power plants); ·Training programmes or plans (i.e. at national, facility, or organizational entity level); ·Regular self-assessments of staff and needs analysis; ·Specialised, regular training for different levels of staff (e.g. or on-the job training with experienced staff); ·Specialized courses (e.g. for newcomers or experienced staff). International exchange of experience through peer reviews, workshops, conferences, visits, etc. has been recognized by Member States as useful tool in particular for non-nuclear Member States. 2.2.6.Research and development Each Member State programme shall include the research, development and demonstration activities needed in order to implement solutions for safe long term management of spent fuel and radioactive waste (see Article 12(1) f of the Directive). To date the research programmes in the EU are at different level stage of implementation depending on the status of implementation of their national programmes. Member States have long experience in national and international projects (including EC research framework programmes) that cover various aspects of predisposal and disposal. They are mainly developed by the Member States with nuclear programmes, where four Member States currently operate five underground research laboratories for spent fuel, HLW and ILW disposal and four more Member States plan to develop such laboratories after 2020-2030 period to support the national geological disposal projects (see Table 11). Table 11. Underground research laboratories (URL) for Disposal of HLW/Spent Fuel in EU MS URL Site Status Purpose Responsible organization for facility development BE HADES SCK•CEN site at Mol In operation Methodological and non-site-specific URL in Boom clay (poorly-indurated) at ~ 230 m depth on; has been extended as part of ongoing PRACLAY project. EURIDICE (cooperation of ONDRAF/NIRAS & SCK CEN) CZ Planned To be selected 2030 Long term site investigations SURAO DE Gorleben Gorleben Exploration started in 1986. Discontinued in 2013 Salt formation BfS/DBE FI ONKALO Eurajoki In operation Waste characterization, 420 m depth, planned to be incorporated into disposal facility with first disposal about 2025 POSIVA FR Bure Meuse/Haute Marne In operation since 2006 Callovo-Oxfordian clay (hard) at ~ 450 - 500 m depth ANDRA Tournemire Southern Aveyron In operation since 1990 methodological laboratory (former train tunnel) in sediments (hard clay), 250m depth IRSN HU Planned Western Mecsek Planned from 2020 to 2055 Preparation for implementation of the geological disposal programme PURAM BCF Western Mecsek Discontinued in 1998 PL PURL Planned Planned Research for the DGR Minister of Economy, Polish Geological Institute – National Research Institute and other interested institutes RO Planned On the selected site 2030 Confirm the suitability of the underground conditions SE Äspö HRL North of Oskarshamn In operation since 1995 Granite, 200 - 500 m depth; Used for research activities on performance of barriers for spent fuel disposal. SKB Stripa mine Closed in 1991 Granite, former iron ore mine at 360 - 410 m research from 1977 - 1991 SKB Member States with nuclear programmes have presented in different level of detail their research programmes, towards development of disposal solutions for spent fuel and radioactive waste. France, Finland and Sweden have advanced research plans and detailed milestones for their deep geological disposal of spent fuel with the aim to start the geological facilities operation by 2030. In light of the longer timescales for the other nuclear power plant countries (see Table 7) they presented in more general terms the research and development activities and timeframes concerning final disposal of ILW, HLW and spent fuel. A few Member States recognize the need for research in management of exotic waste/fuel, while the institutional waste is usually not mentioned separately.

The majority of research activities in Member States' with nuclear programmes are undertaken by the licensee and/or dedicated research organisations. In some Member States (less than a third) the competent authorities have their own research programmes (including funding) that support the independent regulatory oversight. Member States with research reactors address the research and development measures in the reports, however in most cases without clear roadmap/milestones for final disposal. Member States using radioactive sources only do not have their own research programmes as most of them rely on shared disposal solutions, and participate or plant to take part in international programmes or projects (e.g. the International Atomic Energy Agency, European Commission) in line with their radioactive waste management needs. 2.2.7.Transparency Member States’ programmes shall include the national policy/process for transparency required by Article 10 of the Directive. They shall ensure that necessary information on the management of spent fuel and radioactive waste is made available to workers and the public (including the one from the competent regulatory authority) and that the public is given the necessary opportunities to participate effectively in the decision-making process in accordance with national legislation and international obligations. Overall the majority of Member States have reported on the policy frameworks they have put in place in order to ensure transparency. This information covered the relevant legislation, mechanisms for public information, consultation and public participation. According to Member States' notifications transparency is required at the national level by the constitution, general laws, environmental laws, nuclear laws, radioactive waste management, radiation protection or energy laws. Member States apply the transparency requirements via different mechanisms adopted to allow information and involvement of the public, local communities and other stakeholders in spent fuel and