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
Date: 2017-05-15
Institutions: Directorate-General for Energy, European Commission
Subjects: EU policy - national policy, application of EU law, decommissioning of power stations, energy production, irradiated fuel, nuclear policy, nuclear power station, nuclear safety, radioactive waste, waste management

EN 

   EN 

   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. 

2. 

2.1. 

INTRODUCTION ........................................................................................................ 4 

STATUS OF IMPLEMENTATION ............................................................................ 4 

National policies and frameworks for the safe and responsible management of           
spent fuel and radioactive waste ................................................................................... 4 

2.1.1.  National policies ........................................................................................................... 4 

2.1.2.  National programmes, timeframes and key performance indicators ............................ 6 

2.1.3.  National legal and organisational frameworks ........................................................... 12 

2.1.4.  Regulatory framework and competent regulatory authorities .................................... 15 

2.1.5.  Shipments within EU and to third countries .............................................................. 23 

2.1.6.  Self-assessment and international peer reviews ......................................................... 24 

2.1.7.  Notification and reporting .......................................................................................... 27 

2.2. 

Assuring the safety of spent fuel and radioactive waste management ....................... 27 

2.2.1.  Licence holder’s responsibilities ................................................................................ 27 

2.2.2.  Concepts and plans (including post closure) .............................................................. 28 

2.2.3.  Safety demonstration .................................................................................................. 35 

2.2.4.  Cost assessment, financing mechanisms and available resources .............................. 36 

2.2.5.  Expertise and skills ..................................................................................................... 44 

2.2.6.  Research and development ......................................................................................... 44 

2.2.7.  Transparency .............................................................................................................. 46 

3. 

CONCLUSION .......................................................................................................... 48 

2 

 
 
 
 
 
 
 
 
 
 
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 

KPI  

HLW 

IAEA 

ILW 

LLW 

LTO 

IRRS 

MS 

  European Union 

  Key performance indicators 

  High level waste 

International Atomic Energy Agency 

Intermediate level waste 

  Low level waste 

  Lifetime extension 

International regulatory review service 

  Member State 

NORM 

  Naturally occuring radioactive material 

NPP 

RAW 

SEA 

SF 

URL 

  Nuclear power plant 

  Radioactive waste 

  Strategic environmental impact assessment 

  Spent fuel 

  Underground research laboratory 

VLLW 

  Very low level waste 

3 

 
 
 
 
 
 
 
 
 
 
 
 
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”)1.  It  is  based  on  the  information  provided  in  Member  States'  national 
programmes2 and national reports3 on spent fuel and radioactive waste management, as notified to 
the Commission by 30 September 20164. It provides background information related to the main 
findings,  progress,  challenges,  and 
the  first  Commission  report 
trends  presented 
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.  

in 

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. 
2.1. 

STATUS OF IMPLEMENTATION 
National policies and frameworks for the safe and responsible management of spent 
fuel and radioactive waste 
National policies 

2.1.1. 

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 

1  

2  
3  
4  

Council  Directive  2011/70/EURATOM  of  19  July  2011  establishing  a  Community  framework  for  the 
responsible and safe management of spent fuel and radioactive waste. 
Article 13(1) and Article 15(4) of the Directive. 
Article 14(1) of the Directive. 
The final programme of Hungary and revised programme of Slovenia have not been taken into account and 
are under assessment. 

4 

 
 
 
  
                                                 
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 
option5 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 

5  

Recital  33  of  the  Directive  2011/70/Euratom.  Luxembourg  has  recently  concluded  an  agreement  with 
Belgium for the management of its radioactive waste. 

5 

 
 
                                                 
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  waste6  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  cases7  (as  per  Article  13(1)  of  the  Directive)  are  expected  by  the 
Commission.  

6  
7  

Radioactive waste generated outside of the nuclear fuel cycle facilities. 
The revised Slovenian programme was adopted in April 2016 and submitted to the Commission at the end of 
September 2016. France and Spain are working on the update of their existing programmes. 

6 

 
 
                                                 
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/EURATOM8 

Organisation approving 

SEA 

Review and update 

MS9 

BE 

Organisation developing the 
programme 
National Committee created by law with 
Ministry of Economy, ONDRAF/NIRAS 
and Synatom  

Federal Ministers of 
Energy and Economy 

BG  Ministry of Energy 

Government 

CZ  Ministry of Industry and Trade  

Government 

N 

Y 

Y 

Y 

Regular update when a 
national policy is 
adopted or amended 
2011 Strategy was 
revised in 2015.  

2002 Concept updated 
in 2014 is under 
review. Next review 
planned in 2025 
Every 3 years 

Federal Ministry for the Environment, 
Nature Conservation, Building and 
Nuclear Safety 
Ministry on Employment and the 
Economy 

Federal Cabinet 

Ministry on Employment 
and the Economy  

N 

Every 3 years  

The information in this table takes into account the data provided by Member States in ENSREG Working 
Group 2. 
Member States (MS) abbreviations in this report are as follows: Austria (AT), Belgium (BE), Bulgaria (BG), 
Czech Republic (CZ), Germany (DE), Finland (FI), France (FR), Hungary (HU), Italy (IT), Lithuania (LT), 
Latvia (LV), The Netherlands (NL), Slovenia (SI), Slovakia (SK), Spain (ES), Sweden (SE), Romania (RO) 
and the United Kingdom (UK). 

7 

DE 

FI 

8  

9  

 
 
                                                 
FR  Ministry of Ecology, Sustainable 
Development and Energy 

HU 

IT 

PURAM and the Ministry of National 
Development 
Ministry  of  Environment  and  Protection 
of Land and Sea, 
Ministry  of  Economic  Development, 
Ministry of Health 

LT  Ministry  of  Energy  on  the  proposal  of  a 
Management 

Radioactive  Waste 
Organization 
Latvian authorities10 

LV 

Government, new 2016-
2019 programme expected 
to be approved in 2016 
Government after SEA 
completion  
Ministry  of  Environment 
and Protection of Land and 
Sea, 
Ministry 
Development 
Government 

of  Economic 

Y 

Every 3 years 

Y 

Y 

Every 5 years 

Every 3 years  

Y 

Every 7 years at least 

No available information 

Plann
ed 

NL  Ministry 

of 

Infrastructure 

and 

Parliament 

SI 

Environment 
Agency 
Radioactive  Waste 
Management  (ARAO)  and  Slovenian 
Nuclear Safety Administration (SNSA)11   

for 

National Assembly 

ES 

ENRESA12 

SE 

Swedish Radiation Safety Authority 

Government upon proposal 
by Ministry of Industry, 
Energy and Tourism, being 
heard the CSN and 
relevant Autonomous 
Communities 
Ministry of the 
Environment and Energy 

N 

N 

Y 

N 

Concept of Radioactive 
Storage, 
Waste 
in  2003, 
developed 
National 
programme 
under 
development 
(incl. SEA) 
At least every 10 years 

2006 
revised in 2016 

programme 

Periodic review, 2006 
programme is being 
reviewed 

Regular national and 
international reviews; 
Follow-up IRRS 
mission May in 2016 

SK 

RO 

UK 

10  

11  

12  

The administrative board of the National 
Nuclear Fund for decommissioning 
nuclear installations and managing spent 
nuclear fuel and radioactive waste 
(‘NNF’) 
Nuclear Agency and for Radioactive 
Waste (ANDR) 
Department of Energy and Climate 
Change 

Government 

Y 

Every 6 years 

No available information 

Department of Energy and 
Climate Change 

Y 

N 

Every 5 years 

Nuclear 
Decommissioning 
Authority strategy 
review every 5 years 

The Ministry of Environment issued the 2003 Concept of Radioactive Waste Storage after approval by the 
Cabinet.  
ARAO provides the technical basis for the revision of the Programme and based on this, SNSA prepares a 
draft National Programme which is adopted by National Assembly. 
The legal basis requires ENRESA to submit to the Ministry of Industry, Energy and Tourism every 4 years, 
or whenever so required by this Ministry, a draft update of the programme. 

8 

 
 
 
 
 
 
 
 
                                                 
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) 
Every 4 years  
COMRSIN* 
Frequency not defined 
Krško programme 
every 5 years at least 

Every 10 years at least 
by RICS 

Council of Ministers 
Council of Ministers 

Ministry of Economy with 
the prior approval by the 
Croatian Parliament 

MLWSI 

Y 
Y 

Y 

N 

PL 
PT 

HR 

Ministry of Economy  
Regulatory Commission for the Safety of 
Nuclear Installations (COMRSIN) 
State Office for Radiological and 
Nuclear Safety (SORNS) 

CY 

Radiation Inspection and Control Service 
(RICS), Department of Labour 
Inspection (DLI), 
Minister of Labour, Welfare and Social 
Insurance (MLWSI) 
EE  Ministry of the Environment, 

Environmental Board, Radiation 
Protection Bureau, Radiation Monitoring 
Bureau 
Government Department of 
Environment, Community and Local 
Government (DECLG) 

IE 

Minister of the 
Environment 

Y13 

Regular update at least 
every 4 years 

DECLG 

Update and revision as 
necessary 

2002 Concept, 
Programme in 
preparation 
Next review in 2018 

N 

Y 

No 
data 

LV   Minister for Environmental Protection 
and Regional Development* 

Council of Ministers*  

LU 

Radioprotection  Division  (DRP)  within 
the Department of HEalth 

No available information 

MT   Radiation Protection Board 

Radiation Protection Board  Under 
screen
ing 

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.  

13  

The programme states that SEA is available. 

9 

 
 
 
 
 
 
                                                 
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 States14 

MS 

Reactors/Units 

Operation 

Shutdown  

BG 

CZ 

HU 

SK 

FI 

14  

Kozloduy unit 1 

Kozloduy unit 2 

Kozloduy unit 3 

Kozloduy unit 4 

Kozloduy unit 5 

Kozloduy unit 6 

Dukovany 1-4 

1974 

1975 

1980 

1982 

1987 

1991 

1978-1987* 

Temelin units 1-2 

2000-2002* 

Dukovany unit 5 

Temelin unit 3 

Paks units 1-4 

Paks units 5-6 
Bohunice V1 (units 
1-2) 
Bohunice V2 (units 
1-2)  

planned 

planned 

1982-1987 

2025-2026 
1978* 
1980* 
1984* 
1985* 

2002 

2002 

2006 

2006 

2017 (2030) 

2021 (2030) 
2038 - 2047 

2060-2062 

no available 
data 
no available 
data 
2032-2037 

2006 
2008 
2024 or 2044 
2025 or 2045 

Bohunice A1 

1972* 

Bohunice unit 3 

Planned (2029) 

1979 

2089 

Mochovce units 1-2 

1998* 
1999* 

2028 or 2046 
2029 or 2066 

Mochovce units 3-4 

Olkiluoto unit 1 

Olkiluoto unit 2 
Olkiluoto unit 3  

Loviisa unit 1 

Under 
construction 
(2021) 

1979 

1982 
Under 
construction 
1977 

2062 
2082 

2049* 

2042* 
2078* 

2027* 

At the time of reporting to the Commission (2015). 

10 

Comments 

Available data 
until 2030 

Planned LTO by 
2030 
Planned LTO by 
2030 

Planned LTO  
60 years 
operation 

60 years 
operation 
60 years 
operation 
Considering 20 
years LTO 

Planned 

Possible LTO to 
60 years 

Possible LTO to 
60 years 

Possible LTOto 
60 years 

Decommission-
ing 

ongoing 

ongoing 

ongoing 

ongoing 

2025 
2031-2048 (40 
years operation) 
2051-2068 (60 
years operation) 

2033 

2046-2063 (40 
years of 
operation) 
2066-2083 (60 
years of 
operation) 
2062-2079 (40 
years of 
operation) 
2082-2099 (60 
years of 
operation) 

2080-2090 
2080-2090 

2075 - 2085 
2030-2035 

 
 
  
  
  
  
  
 
 
 
 
 
  
  
  
 
 
 
 
  
 
 
 
  
  
  
 
 
 
 
 
 
 
 
                                                 
Loviisa unit 2 
Hanhikivi 
Doel unit 1 

1981 
Planned 
1975 

2030* 

2025 

2030-2035 
2085-2100 

Doel unit 2 

Doel unit 3 

1975 

1982 

2025 

2022 

Doel unit 4 

Thiange unit 1 

Thiange unit 2 

Thiange unit 3 

1985 

1975 

1983 

1985 

2025 

2025 

2023 

2025 

8 reactors shutdown 

1975-1984  

2011-2015  

1984-1989 

2015 - 2022 

1977 – 1999 
(operating fleet) 

Between 2027 
and 2078 

End of 
operation dates 
by Phase-out 
Law of 
31/01/2003 
modified by the 
law of 
28/06/2015. 
End of 
operation dates 
as established 
by the Phase-out 
Law of 
31/01/2003 
modified by the 
law of 
28/06/2015.  

Operating 
lifetime of 50 
years 

BE 
DE 

FR  

IT  

NL 

SI 

ES* 

SE 

9 reactors in 
operation 
58 reactors and 9 
shutdown reactors 
and EPR Flamanville 
Caorso 

Enrico Fermi 

Garigliano 

Latina 

Dodewaard 

Borssele 
Krško  

2 reactors undergoing 
decommissioning ( 
José Cabrera and 
Vandellos I) 

1 reactor shutdown 
(Santa María de 
Garoña) 

1978 

1964 

1964 

1963 

1968* 

1973* 
1983 

1969-1972 

1971 

7 operating reactors* 

1981-1988 

10 operating reactors 
2 shutdown 

1972-1985 

1990 

1990 

1982 

1987 
1997* 

2033 

2023 

After 2030 

Ongoing 

Ongoing 

Ongoing 

Ongoing 

After 2045 

2023 

2006 and 1989 

2012 

2021-2027 

2040 - 2045 

11 

Assuming 40 
years operation 
Early shutdown 
of Forsmark 1-
2, Ringhals 1-2 
could be 
decided between 
2018-2020 

After 2040 - 
2050 
2020 and 2023 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
UK*  

 LT 

 RO 

16 (14 AGR, 1 PWR 
and 1 MAGNOX)15 
reactors in operation 
29 reactors shutdown 

Ignalina unit 1 

Ignalina unit 2 

1983 

1987 

Cernavoda unit 1  

1996 

Cernavoda unit 2  

Cernavoda units 3-4  

2007 
Planned  
2019-2020 

2024 

PL 

New build 

1976-1989 

2023-2035 (or 
2055) 

2023-2083 

Possible PWR 
LTO to 60 years 

Ongoing until 
2038 

Ongoing until 
2038 

2063 

2055 
immediate 
dismantling 

2004 

2009 

2026 

2037 

planned 

2084 

Possible LTO to 
2046 
Possible LTO to 
2057 

*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.  
 National legal and organisational frameworks  
2.1.3. 

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. 

15  

At the time of reporting to the Commission, the Magnox reactor was planned for shutdown in 2015 and the 
Sizewell/B (PWR) - in 2055. Currently there are 15 operating nuclear power reactors in the UK. In addition, 
new reactors are planned to be built.  

12 

 
 
  
 
 
 
 
 
 
 
  
 
 
 
                                                 
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. 

13 

 
 
 
 
Table 3. Radioactive waste management organisations in the EU 

MS 

BE 

BG 

CZ 

Radioactive waste 
management 
organisation 

Organisme national des 
déchets radioactifs 
et des matières fissiles 
enrichies/Nationale 
instelling voor radioactief 
afval 
en verrijkte splijtstoffen 
(ONDRAF/NIRAS) 
State Enterprise 
Radioactive Waste (SE 
RAW) 
Radioactive Waste 
Repository Authority 
(SURAO) 

FI 

POSIVA 

FR 

DE 

HU 

IT 

LT 

NL 

RO 

SK 

National agency for 
management of 
radioactive waste 
(ANDRA) 
German Service Company 
for the Construction and 
Operation of Waste 
Repositories (DBE) 
Public Limited Company 
for Radioactive Waste 
Management (PURAM) 
Company for management 
of nuclear power plants 
(SOGIN)  

State Enterprise 
Radioactive Waste 
Management Agency 
(RATA) 
The Central Organisation 
For Radioactive Waste 
(COVRA) 

Nuclear Agency for 
Radioactive Waste 
(ANDR) 

Nuclear and 
Decommissioning 
Company (JAVYS) 

Public/ 
private 

Public 

Public 

Public 

Responsibilities 

Managing radioactive waste from all sources, managing spent 
fuel when declared as radioactive waste, incl. disposal.  

Radioactive  waste  and  spent  fuel  management;  and  de-
commissioning.  

Operation of all low and intermediate level waste repositories; 
repository, 
Monitoring  of 
Development  of  deep  geological  repository  for  disposal  of 
HLW and spent fuel. 

closed  Hostim 

the  now 

Private16   Radioactive  waste  management  facilities  -  site  selection, 
design, construction, commissioning, operation,  rehabilitation 
and reconstruction, decommissioning and closure/post closure. 
Long-term management of radioactive waste. 

Public 

Public 

Construction and operation of radioactive waste repositories. 

Public 

Public 

Public 

Public 

of 

of 

all 

Management 
radioactive  waste, 
types 
decommissioning  of  nuclear  facilities,  as  well  as  related  to 
research and development. 
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. 
Management  and  disposal  of  radioactive  waste  generated  by 
the  Ignalina  nuclear  power  plant.  Construction  and  operation 
of the repositories for radioactive waste. 

Implementing  the  Dutch  policy  with  regard  to  radioactive 
waste  in  the  Netherlands.  Treatment  and  storage  of  all 
radioactive waste and spent fuel. 

Public 

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. 
Management  of  spent  nuclear  fuel  and  radioactive  waste. 
Decommissioning of the nuclear power plants. 

16  

Owned by the NPP operators Teollisuuden Voima Oyj and Fortum Power & Heat Oy. 

14 

 
 
 
 
 
 
                                                 
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 

SE 

UK 

HR 

AT 

EL 

DK 

PL 

PT 

EE 

LV 

National radioactive waste 
complany (ENRESA) 
Swedish Nuclear Fuel and 
Waste Management 
(SKB) 

Nuclear Decommissioning 
Authority (NDA) 

Radioactive Waste 
Management Centre  

Nuclear Engineering 
Seibersdorf GmbH (NES) 
National Center for 
Scientific Research 
(NCSR) "Demokritos" 

Danish Decommissioning 
(DD) 

Radioactive Waste 
Management Plant 
(RWMP) 

Higher Technical Institute 
(ITN)  
A.L.A.R.A. AS 

Latvian Environment, 
Geology and Meteorology 
Centre (LVGMC) 

Public17  Management  of 

radioactive  waste 

and 

spent 

fuel. 

Private18 

Public 

Public 

Public/ 
private 

Public 

Public 

Public 

Public 

Public 

Public 

Decommissioning nuclear plants.  
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. 
Implementing  Government  policy  on 
long-term 
management of nuclear waste, including the decommissioning 
and clean-up of the civil public sector nuclear sites. 
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. 
Collecting,  processing,  conditioning  and  storing  radioactive 
waste, decontaminating installations and laboratories. 

the 

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. 
Decommissioning  and  receiving,  handling  and  storage  of 
radioactive  waste.  Also  licensed  operator  for  all  radioactive 
waste. 
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. 
Collecting,  segregating,  conditioning  and  storing  solid  and 
liquid radioactive waste. 
Former  Paldiski  nuclear  site  and  Tammiku  radioactive  waste 
repository management and decontamination. 
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 

17  
18  

State-owned company CIEMAT (80%) and SEPI (20%). 
Reactors licensees. 

15 

 
 
 
 
                                                 
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.  

16 

 
 
 
 
 
 
 
Table 4. National Competent Authorities for spent fuel and radioactive waste management19 

Competent 
authority 

Responsibilities for spent fuel and 
radioactive waste 

Reporting to 

BMLFUW is the licensing and regulatory 
authority for the construction and 
operation of radioactive waste 
management facilities. 

Federal 
Government 

Staff 
(year) 

Data not 
available 

MS 

AT 

BE 

BG 

HR 

Federal Ministry of 
Agriculture, Forestry, 
Environment and Water 
Management 
(BMLFUW) 
Federal Agency for 
Nuclear Control 
(FANC) 

Nuclear Regulatory 
Agency of the Republic 
of Bulgaria (BNRA) 

State Office for 
Radiological and 
Nuclear Safety 
(SORNS) 

CY 

Radiation Inspection and 
Control Service – 
Department of Labour 
Inspection (RICS/DLI) 

CZ 

State Office for Nuclear 
Safety (SUJB) 

DK  National Institute of 
Radiation Protection 

Danish Emergency 
Management Agency  

With regard to the safety of disposal 
facilities, the competent regulatory 
authority, i.e. the AFCN/FANC, retains all 
of its prerogatives 
BNRA has been assigned responsibility for 
all regulatory matters concerning 
radioactive waste and spent fuel 
management facilities 
- 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 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. 
State administration and supervision of the 
utilization of nuclear energy and ionizing 
radiation and in the field 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 
International cooperation in the area of 
nuclear safety 

Federal Minister 
of the Interior 

Data not 
available 

Council of 
Ministers 

The Government 
of the Republic of 
Croatia 

103 
(2015) 

22 
(2015) 

5 
(2015) 

Ministry of 
Labour, Welfare 
and Social 
Insurance 
(MLWSI) 

209 
(2014) 

No data 

No data 

Prime Minister 

Danish Health 
and Medicines 
Authority 

Nuclear Division 
of the Danish 
Emergency 
Management 
Agency 

19  

The data does not include staff of separate technical support organisations that exist in some Member States. 

17 

 
 
 
 
 
 
 
                                                 
EE 

Environmental Board 

FI 

Radiation and Nuclear 
Safety Authority 
(STUK) 

FR 

The Parliament, the 
Government and 
Nuclear Safety 
Authority (ASN)  

(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. 
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 
Regulates, authorises, controls and helps 
the public authorities to manage 
emergencies, participate in the public 
information 

DE20  The Federal Office for 

Radiation Protection 
(BfS) 

Federal Office for the 
Regulation of Nuclear 
Waste Management 
(BfE) 

BMUB, the Directorate-
General Reactor Safety 
(RS) 

- Approval of interim storage facilities for 
nuclear fuels; 
- Planning, construction, operation and 
decommissioning of repositories; 
- Repository surveillance 
- 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 
- 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 

Ministry of the 
Environment 

17 
(2014) 

Ministry of 
Employment and 
the Economy 
Ministry of Social 
Affairs and 
Health 
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 
Federal Ministry 
for the 
Environment, 
Nature 
Conservation, 
Building and 
Nuclear Safety 
(BMUB)  

342 
(2014) 

470 
(2013) 

188 
(201421) 

planned 

36 22 
(2014) 

20  

21  

22  

Germany  as  a  federal  state,  the  “regulatory  body”  and  consists  of  authorities  of  the  Federation  and  the 
Länder – the regulatory structure comprised of BMUB, BfE, BfS and the Land Ministry. The Federal Office 
of Economics and Export Control (BAFA) is responsible for the import and export of radioactive materials. 
Department of Safety of Nuclear Waste Management and its six divisions. It is supported by 30 independent 
experts. 
Directorate RS III (Nuclear Fuel Cycle). 

18 

 
 
 
 
 
 
                                                 
16 Länder 

EL  Greek Atomic Energy 
Commission (EEAE) 

HU  Hungarian Atomic 
Energy Authority 
(HAEA) 

National Public Health 
and Medical Officer 
Service, Office of the 
Chief Medical Officer 
(NPHMOS-OCMO) 

IE 

Environmental 
Protection Agency 
(EPA) 

the Joint Convention on the Safety of 
Spent Fuel Management and on the 
Safety of Radioactive Waste 
Management 
Land  Ministry  is  responsible  for  licensing 
and  supervision  of  spent  fuel  treatment 
facilities 
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 
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 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. 
Regulates radioactive material including 
practices involving radioactive waste, and 
radiation sources through a licensing 
system 

Federal 
government 

Minister of 
Education, 
Research and 
Religious Affairs 

27023 
(2014) 

74 
(2014)* 

80 
(2014) 

The Minister 
appointed by the 
Prime Minister, 
currently by the 
Minister for 
National 
Development. 

Minister for 
Health 

49 
(2015) 

Department of 
Environment, 
Community and 
Local 
Government 
(DECLG) 

34 in the 
Office for 
Radiologic
al 
Protection 
(2015) 

23  

About 120 staff working on radioactive waste management and 150 staff working on support the nuclear 
authorities of the Länder either at subordinate authorities or as authorised experts. 

19 

 
 
 
                                                 
 
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 

LV  Radiation Safety Centre 

of the State 
Environmental Service 
(SES RSC) 

LT 

State Nuclear Power 
Safety Inspectorate 
(VATESI) 

Radiation Protection 
Centre (RPC) 
LU  Radiation Protection 
Division (RDP) 

MT  Radiation Protection 
Board (RPB) 

NL  Authority for Nuclear 
Safety and Radiation 
Protection (ANVS) 

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 

Ministry of 
Environmental 
Protection and 
Regional 
Development 

No 
available 
data 

The Cabinet of 
Government and 
the President 

75 
(2015) 

Ministry of 
Health 
Minister for 
Health 

59 
(2015) 
9 
(2015) 

Ministry of 
Social Dialogue, 
Consumer Affairs 
and Civil 
Liberties 
(MSDC) 
Ministry of 
Infrastructure and 
the Environment 
(I&M) 

No 
available 
data 

122 
(2016) 

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. 
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. 
Regulation of radiation protection 

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. 
The functions of the RPB cover all waste 
activities (and the facilities when they are 
commissioned).  

- 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 

20 

 
 
 
 
 
 
 
 
 
 
 
 
 
PL  National Atomic Energy 
Agency (NAEA) 

PT 

Regulatory Commission 
for the Safety of Nuclear 
Installations 
(COMRSIN) 

national and 
international organisations; 
- supporting national organisations with 
the provision of knowledge; 
- having research in support of the 
implementation of its tasks. 
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 

- 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) 

RO  National Commission for 
Nuclear Activities 
Control (CNCAN) 

Regulation, licensing, and control of 
nuclear activities 

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 

21 

Minister 
competent for 
environmental 
matters 

No 
available 
data 

4 
(2015) 

No 
available 
data 
108 (2014) 

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. 
Prime Minister, 
through the 
General 
Secretariat of the 
Government 
The Government 
and subsequently 
to the National 
Council 

 
 
 
 
 
 
 
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. 
Nuclear safety of facilities and the safety 
of industrial radiation sources 

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 
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 
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. 
Regulates: 
- nuclear safety;  
- nuclear site health and safety;  
- nuclear security;  
- nuclear safeguards;  
- transport  
- Regulates the accumulation and disposal 
of radioactive waste from non- nuclear 
premises  
- Regulates nuclear and non-nuclear sites 
in England 

SI 

Slovenian Nuclear Safety 
Administration (SNSA) 

Slovenian Radiation 
Protection 
Administration (SRPA) 

ES 

Nuclear Safety Council 
(CSN) 

SE 

Swedish Radiation 
Safety Authority (SSM) 

UK24  Office for Nuclear 

Regulation (ONR, UK) 

Environment Agency 
(EA, England) 

Natural Resources 
Wales (NRW) 

Scottish Environment 
Protection Agency 
(SEPA) 

- Enforces environmental protection 
legislation; 
- Regulates nuclear and non-nuclear sites 
in Wales 
- Enforces environmental protection 
legislation; 
- Regulates nuclear and non-nuclear sites 
in Scotland 

Ministry of 
Environment and 
Spatial Planning 
Ministry of 
Health 

41 
(2014) 

No data 

Parliament 

205 
(2014) 

Ministry of the 
Environment 

321 
(2015) 

Government 
Department of 
Energy & 
Climate Change 

33025 
(2014) 

No 
available 
data 

Government 
Department of 
Environment, 
Food & Rural 
Affairs 

Welsh 
Government 

Scottish 
Government 

24  

25  

The  environment  agencies  regulate  the  accumulation  of  radioactive  substances  and  the  disposal  of 
radioactive wastes at all sites, with the exception of radioactive wastes at nuclear sites which are regulated 
by ONR. 
Nuclear safety specialists. 

22 

 
 
 
 
 
                                                 
Northern Ireland 
Environment Agency 
(NIEA) 
Health & Safety 
Executive (HSE) 

Regulates non-nuclear sites in Northern 
Ireland 

Northern Ireland 
Assembly 

- 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).  

23 

 
 
 
Table 5. Return of By-products from Spent Fuel Reprocessing to EU Member States 

MS 

BE 

BG 

CZ 

DE 

HU 

IT 

NL 

ES 

Type of material 

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 

Return  of  HLW  from  Kozloduy  NPP  spent  fuel  reprocessing  in 
Russia 

Return of residual waste from highly enriched Uranium (LRV-15 
reactor) sent to Russia 

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 

Planned  return  of  material  from  spent  fuel  from  planned  Paks 
NPP units 5 and 6 reprocessing in Russia in case reprocessing is 
decided. 

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. 

Timeframe 

2017 

After 2025 

2024-2026 

No information 

Decision not 
taken yet 

2020-2025 

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 

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). 

202126  

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 

26  

When interim spent fuel /HLW storage facility is available. 

24 

 
 
 
 
 
                                                 
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 IRRS27 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  ARTEMIS28  peer 
review service and to host missions until 2023 (for details see Table 6). 

27  
28  

Integrated Regulatory Review Service of the International Atomic Energy Agency. 
Since  2014  the  Commission  is  supporting  the  development  of  a  self-assessment  tool  by  the  IAEA  for  the 
ARTEMIS  review  service  to  assist  those  Member  States  that  decide  to  use  this  international  peer  review 
service. 

25 

 
 
 
 
                                                 
Table 6. Recent and planned international peer reviews as per Article 14(3) of the 
Directive29 

MS 

BE 
BG 
CZ 
FI 

FR  

DE 
HU 
IT 

LT 

NL 

RO 
SK 
SI 
ES 
SE 

UK  

AT 
DK 
EL 
LV 
PL 
PT 
HR 
CY 
EE 
IE 
MT 
LU 

National programme and/or  
National framework 

No information 
No information 
No information 
2009 (OSART30 for the spent fuel 
disposal facility), 2023 (ARTEMIS) 
1996 and 2005, IAEA Review of 
specific waste management projects  
2017 (ARTEMIS) 
2019 (ARTEMIS) 
No information 
No information 

2019 (ARTEMIS, self-assessment) 
2021 (ARTEMIS) 
2023 (ARTEMIS) 

No information 
No information 
No information 
2018 (ARTEMIS)  
2009 Plan review through IRRS 
(2012); SKB post-closure safety case 
NEA/OECD review (2012); WANO 
review of SKB SFR and Clab 
operation (2013) 
OSART for Sizewell B site planned. 

No information 
2019 – 2021 period (ARTEMIS) 
No information 
No information 
2017 (ARTEMIS)31 
No information 
No information 
No information  
No information 
No information 
No information 
After 2018 

Competent regulatory authority 

2013 (IRRS), 2016 (IRRS follow-up) 
2016 (IRRS follow-up) 
2017 (IRRS) 
2012 (IRRS), 2015 (IRRS follow-up), 2023 
(IRRS full scope) 
2014 (IRRS) 

2018 (IRRS full scope) 
2012 (IRRS follow-up), 2015 (IRRS) 
2016 (IRRS) 

2016 (IRRS full scope), 2018 (IRRS follow-
up) 
2014  (IRRS)  and  2018  (IRRS  follow-up), 
2023 (IRRS full scope) 
No information 
2012 (IRRS follow –up) 
2011 (IRRS) and 2014 (IRRS follow-up) 
2008 (IRRS), 2011 (IRRS follow-up) 
2012 (IRRS), 2016 (IRRS follow-up) 

2006,  2009,  2013  (IRRS)  and  2014  (IRRS 
follow-up) 
No information 
2019 – 2021 period (IRRS) 
2012 (IRRS) 
No information 
2013 (IRRS) 
No information 
2015 (IRRS) 
2017 (IRRS) 
No information 
2015 (IRRS)  
 Self-assessment in 2014 and 2015 (IRRS) 
2018 (and expanded IRRS) 

29  

30    

31  

The  information  in  grey  is  provided  by  Member  State  through  the  ENSREG  Working  Group  2  or  other 
source (e.g. IAEA), however not included in the national programmes and reports of Member States. 
IAEA  Operational  Safety  Review  Team  for  peer  reviews  of  operational  safety  performance  at  a  nuclear 
power plants. 
Information to Commission after the notification of the Polish programme and report. 

26 

 
 
                                                 
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  Convention32 
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 report33. 

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. 
2.2.1.  Licence holder’s responsibilities 

Assuring the safety of spent fuel and radioactive waste management  

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.  

32 
33  

Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Management. 
The  updated  national  programme  of  Slovenia  has  not  been  taken  into  account,  as  it  is  currently  under 
assessment. 

27 

 
 
                                                 
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.  

28 

 
 
Table 7. Planned Deep Geological Disposal Facilities34 in EU Member States 

MS 

Siting 

Com-
mis-
sioning 

Opera-
tion 
(years) 

Closure 

Institu-
tional 
Control 

Cost (€35) 

Comment 

Respon-
sible 
organi-
zation 

2022 

90 

2110 

Not 
foreseen 

3.5 bn (2012, 
5 units) 

2025 

more than 
100  

After 
2125 36 

16.5 bn 
(2012) 37 

FI 

FR 

Eurajoki 
(Olkiluoto) 
site  
Cigeo:  sited 
in 
the 
of 
Border 
the  Meuse 
and  Haute-
Marne  

SE 

Forsmark 
site 

2019-
2030 

45 

2075-
2076 

Not 
foreseen 

UK 

2016 

2040 

until 2089 

2120 

9,5 bn £ 
(2014/2015 ) 
(undis-
counted) 

SKB 

ANDRA 

POSIVA  Licence for 
constructio
n (2015) 
100 year 
reversibi-
lity; 
concept for 
submission 
for au-
thorization 
Licence 
application 
for con-
struction 
under 
review 
2016 is a 
formal 
process of 
working 
with 
communi-
ties for 
potential 
sites;  
start 
receiving 
ILW and 
LLW in 
around 
2040 and 
HLW in 
2075  

NDA 

DE 

After 2031 

2050 

7.7 bn 

RO 

2025 

2055 

100 

2150 

1.02 bn (2 
units) to 2.04 
bn (2006) 
USD (4 
units) 

Federal 
Office 
for Ra-
diation 
Protec-
tion  
ANDR 

The cost is 
for a new 
geological 
disposal 
facility 

Siting not 
started yet 

34 

35  
36  
37  

The terms near surface, intermediate depth and deep geological disposal are used in the meaning of IAEA 
Safety Guide GSG-1 “Classification of Radioactive Waste”, 2009. 
Otherwise specified. 
Law on reversibility (100 years) passed in 2016. 
http://cigeo.com/en/project-cost. 

29 

 
 
 
 
 
 
 
 
 
 
                                                 
MS 

Siting 

Com-
mis-
sioning 

Opera-
tion 
(years) 

Closure 

Institu-
tional 
Control 

Cost (€35) 

2064 

2038 

208439 

Not yet 
establish
ed 

745 278.5 
mill HUF 
(2015) 

2105-
2115 

Not 
foreseen 

3.7-4.4 bn 
(2014) 

Comment 

Respon-
sible 
organi-
zation 

JAVYS 

PURAM  Research 
activities 
are 
planned 
3.7 bn for 
40 years 
NPP 
operation 
and 4.4 bn 
for 60 
years NPP 
operation 

2065 

40-60  

2065 

10 

2065 

2065 

2066 

6 

2050-
2069 

2069 

2075 

No data  Not available 

ARAO  Agreement 

with 
Croatia 
pending 
Possible 
agreement 
wih 
Slovenia 
by 2023 
SÚRAO  Ongoing 

site 
selection; 
two sites to 
be selected 

4.1 bn (2011) 
or 111.400 
mill CZK 

2072 

1.89 – 2.6 bn 

Ignalina 
NPP/ 
RATA 
3 bn (2005)40  ENRESA 

HU 

SK 

SI 

HR 

CZ 

LT 

ES 

BG 

Site 
selection 
ongoing 

Site 
selection 
first 
stage 
(2013-2016) 
Sit  selection 
in 2030 

to  be 

Site 
selected 
(2045-2055) 

2043 

2018 

2033 

2016-2050 
(including 
knowledge 
update) 

Prefeasibi-
lity 
study 
ongoing  and 
6  potential 
sites 
selected 

Not available 

SERAO  No con-
cepts as 
yet for 
ILW / 
HLW other 
than 
interim 
storage  

COVRA  Costs for 

"final 
storage". 
Decision in 
100 years 

NL 

Decision  in 
100 years 

1.5-2.5 
(1996-2000) 

About 
2130 

38  

39  
40  

If  Hungary  opts  for  reprocessing  of  the  spent  fuel  of  the  new-built,  the  operation  of  the  deep  geological 
disposal will be 50-60 years instead. 
Could be 2114-2124.  
Data  from  the  6th  General  Radioactive  Waste  Plan.  In  addition,  the  estimated  total  cost  for  spent  fuel 
management is about 7 bn (2015) for a 40 years NPP operation scenario. 

30 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                 
MS 

Siting 

Com-
mis-
sioning 

Opera-
tion 
(years) 

Closure 

Institu-
tional 
Control 

Cost (€35) 

Respon-
sible 
organi-
zation 

3.2 bn (2012)  ONDRA
F/NIRAS 

BE 

date 

No 
defined 
pending 
national 
policy 

PL 

22nd century 

at least 
100 
years 
after 
construct
ion and 
operatin
g license 
Mid-22nd 
century 

15 years 
after 
authorisati
on is 
given 
around 50 
years 

Not 
available 
22nd 
century 

Comment 

The 
disposal 
cost is for 
waste 
category B 
and 
category C 

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 41 
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). 

41  

“RADON” type facilities for institutional waste built in the 1960s. 

31 

 
 
 
 
 
                                                 
BE 

BG 

CZ 

Table 8. Near surface and intermediate depth disposal facilities in EU 

MSe  Existing/ 
planned 

Siting 

Commis
sioning 

Operation 
(years) 

Closure 

Planned  LLW 
(Category  A 
waste) 

Dessel site 

Existing 
for 
LLW and ILW 
(institutional 
waste) 

han 

Novi 
site 

4  y  after 
construc
tion/ope
ration 
license 
1964 

54  y  after 
constructio
n/operation 
license  

y 

104 
after 
constructi
on/operati
on license 

Institution
al  Control 
(years) 

250  

Responsi
ble 
organizat
ion 
ONDRAF
/ 
NIRAS 

SERAW 

Planned  
near surface 

Dukovany 
(existing) 
Hostim 
(existing) 
Bratrstvi 
(existing) 

Richard 
(existing) 

Radiana 

2021 

2086 

SERAW 

Duckovany 
NPP 
Beroun 

1995 

1959 

2050 

300 

SÚRAO 

1965 

Ongoing 

SÚRAO 

Jáchymov  

1974 

2020 

100 

SÚRAO 

Litoměřice  

1974 

2025 

100 

SÚRAO 

EE 

Planned 

2018 

2040 

2050 

FI 

FR 

Lovisa NPP 
(existing) 
Olkiloto NPP 
(existing) 
Hanhikivi 
(planned) 
Centre de 
L'Aube 

(existing) 

Lovisa 

1998 

Olkiloto 

1992 

After 
2035 
1992 

Aube 
district 

2060 

2080 
2100 
2120 

or 

Later than 
2050 

Not 
required 
Not 
required 
Not 
required 
300 

A.L.A.R.
A. AS 

TVO 

FORTU
M 
FVO 

ANDRA 

32 

Comment 

Under 
licensing 
application 
review 
for 
construction  
Used 
for 
storage. 
Planned 
decommissi
oning 
2025 

by 

Capacity 
until 2050 
Closed 

Capacity 
until 
2020 
for  NORM 
waste 
Capacity 
until  2025; 
considered 
extension 
afterwards 
Concept  for 
low 
and 
intermediate 
level  waste 
to 
disposal 
be decided  

level 
Low 
waste 
and 
intermediate 
level  waste-
short lived 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Centre de La 
Manche 

Manche 
district 

1969 

1994 

300  (since 
2003) 

ANDRA 

(existing) 
Cires  

Morvilliers 

2003 

(existing) 

DE42  Konrad  

2007 

2022 

Saturatio
n in 2025 

Several 
decades 

In 
progress 

ANDRA  VLLW 
disposal 
facility 
Under 
construction 

Federal 
Office  for 
Radiation 
Protection  
BfS 

Closed 
under 
licensing 
Institutional 
waste 

Morsleben 

1971 

Until 1998 

Püspökszilá
gy 

1976 

2067 

150 

PURAM 

Bataapati 

2008 

2084 

50 

PURAM  Waste 
nuclear 
power plants 

planned 

- 

2015 
2018 

SOGIN 

Technology 
parc 

Maišiagala 

1964 

1989 

Morsleben 
(existing) 

Radioactive 
Waste 
Treatment and 
Disposal 
Facility 
(RWTDF, 
(existing) 
National 
Radioactive 
Waste 
Repository 
(NRWR, 
existing) 
National 
repository 
(planned) 
RADON 
(Existing) 

HU 

IT 

LT 

release 

For 
institutional 
waste  to  be 
retrieved and 
facility 
remediated. 
Site 
in 2023 
Planned 
investigation 
for  possible 
conversion 
of 
existing 
industrial 
landfill  to  a 
VLLW 
disposal 
facility  

an 

Ignalina 
NPP  

for 

Industrial 
landfill 
VLLW 
disposal 
(planned) 

RATA 

Decision 
to retrieve 
leave 
or 
2018 
- 
2025 

VLLW 
(planned) 
LILW 
Ignalina 
(planned) 

Ignalina 
NPP 
Ignalina 
NPP 

2018 

2020 

2038 

2021 

RATA 

RATA 

Active  30 
Passive 70 
Active  100 
Passive 
200 

42  

Asse II salt mine remediation is planned around 2033. 

33 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                 
LV 

PL 

RO 

Bituminised 
Ignalina  
(planned) 
Baldone 
(existing) 
NRWR 
(existing) 
NNRWR 
(planned) 
BaiTa-bihor 
(existing) 

DFDSMA 
(planned) 

SI 

LILW 
(Planned) 

HR 

ES 

SK 

SE  

Institutional 
radioactive 
waste disposal 
(planned) 
LLW and ILW 
(existing)  
VLLW 
(existing) 
Mochovce 
LLW  
(existing) 

Mochovce 
VLLW 
(planned) 
SFR  (low  and 
intermediate 
level waste) 
(existing) 
SFL 
(long 
lived  low  and 
intermediate 
level waste) 
(existing) 
Forsmark NPP 
(VLLW) 
(existing) 

Ignalina 
NPP 

Decision 
in 2022 

Baldone 

1962 

ROZAN 

1961 

Selection in 
2018 

2018-
2024 
1986 

2017 

2021 

2020 

Site 
selected: 
Vrbina 
2009 
Cerkezovav  2025 

in 

2024-
2029 
2144-
2155 
2050-
2055 

2090 

After 
2061 

After 
2065 

2062 

LEGMC 

RWMP 

used 

Also 
for storage 
Operating  

RWMP 

Planned 

300 

300 

100  active 
200 
passive 
100  active 
200 
passive 

ANDR 

ANDR 

ARAO 

Pending 
agreement 
with HR 

NPP  waste 
to 
disposal 
be 
agreed 
with SI 

El Cabril 

1992 

2040 

300 years 

ENRESA 

El Cabril 

2008 

2040 

60 years 

ENRESA 

Mochovce 

2001 

After 2080 

Mochovce 

2018 

Forsmark 

1983-
1988 

Planned 
2045 

to 

License 
be 
submitted 
in 2030 

Forsmark 

Extension 
to 
be 
decided 
in 2018 

several 
decades 
active;  and 
200-300 
passive  

JAVYS 

JAVYS 

Existing; 
extension  to 
be  decided 
in 2018 

2070-2075  SKB AB 

Extension 
requested 
in 2014 

Expected 
extension  in 
2023 

2075 

SKB AB 

30  

Operational 

Forsmark
s 
Kraftgrup
p AB 

30  

OKG AB  Operational 

30  

Ringhals 
AB 

Operational 

Oskarsham
m 

Ringhals 

NPP 

Oskarsham
m 
(VLLW, 
existing) 
Ringhals 
NPP 
(VLLW, 
(existing) 

34 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
Studsvik 

30  

Sellafield 

1950 

2050 

100  

UK 

Studsvik 
(VLLW, 
(existing) 
Drigg 
VLLW/LL
W  (existing 
vaults 
and 
trenches) 

2026 

2005 

2028 

CLESA 
(existing) 

Sellafield 

Calder 
landfill 
VLLW 
South 
landfill 
VVLW 
(existing) 
Dounreay 
shaft 
(existing) 
Dounreay 
LLW 
(existing) 

Sellafield 

Sellafield 

Dounreay 

Dounreay 
2014 

Onsite  pits 
and trenches 
(existing) 

Harwell, 
Springfield, 
Sellafield, 
and 
Dounreay 

AB 
SVAFO 

Low 
Level 
Waste 
Repositor
y Limited 

Operational 

Foreseen 
extension 
of 
capacity  after 
2050 
for 
operation  until 
2129 
Decommission
ing  waste  and 
site  clearance 
waste 

closed 

Dounreay 
Site 
Restoratio
n  Limited 
(DSRL) 

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 
35 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
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 
NPPs43. Some of the data differ from the PINC44 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 

43  
44  

Assuming average cost of 20 to 30 cents per kWh. 
Communication  from  the  Commission  Nuclear  Illustrative  Programme  presented  under  Article  40  of  the 
Euratom Treaty for the opinion of the European Economic and Social Committee {COM(2017)237}. 

36 

 
 
                                                 
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. 

37 

 
 
 
 
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)45  

BG 

2.0-4.5 (2015) 

 2030 

CZ 

4.2 (2011) 

geological 
disposal after 
2160 

FI 

FR 

6.5 (2012) 

2110 

89 (2011 prices)  

2135 

DE 

66.9 (2012)  

2080 

HU 

5.3 (2015) 

2064 

includes 

spent 
storage 

Category A and B disposal costs of: 
1.38bill€  for  near  surface  disposal 
facilities  and  3.2bill€  for  geological 
disposal  
fuel 
Decommissioning, 
processing 
for 
and. 
Kozloduy  NPP  units  1-4  and  5-6. 
The  range  of  costs  depends  on  the 
extension or not for units 5 and 6. 
Low  and  intermediate  level  waste 
disposal up to 2050 3,250 CZK mill 
(2013)  =  0,11  bill  Eur;  and  0.037 
CZK/€; 
also 
decommissioning 
Not including future NPPs’ 100 mill 
€  for  near  surface  disposal  and  3,5 
bill € for geological disposal 
Including  institutional  control;  35 
bill€  for  legacy  sites  recovery;  38 
bill € decommissioning; 16 bill € for 
geological  disposal  (although  now 
reassessed to 25 bill€) 
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  manage-
ment - 6 bn €; Gorleben site - 2 bn € 
(40  mill€/year  for  50  years  until 
2065) all at 2012 prices 
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 facili-
ties; 
- HLW disposal facility; 
- PURAM operating costs, supervi-
sion fees, fund management and 
support to local governments. 
1,5 bill € for siting and construction 
of the Technological Park 

RAW  management  and  disposal  & 
SF  management:  560.2  mill  € 

1748 

807 

1334 

1041 

21076 

5234 

624 

143 

311 

18.1 

2.5 (2005-2014) 

2030 (excluding 
geological 
disposal) 
2038 (but before 
geological 

IT 

LT 

45  

Based on data provided by the Belgian Ministry of Economy the cost for radioactive waste management in 
Belgium  is  €9.2  bn  and  for  decommissioning  –  4.6  bn  €,  in  total  €13.8  bn  (see  footnote  132  of  PINC 
SWD(2017)158). 

38 

 
 
 
                                                 
disposal) 

Geological 
repository 
development 
should start 
from 2040 
2006-2065 

plan 

programme 

(decommissioning 
2014) 
Close  Maišiagala  repository:  4.2 
(specific 
2013) 
Other  activities:  47.7  (present  cost 
2014); 
1889.0 
SF 
(feasibility study 2005) 
Cost for "final storage" 
Average of 1.8 and 3.5bill€.  
3,5bn  €  (includes  2  new  reactors) 
and 1.8bn€ without new build 

disposal: 

Total 
extrapolated from 2006-2015 costs 

2005-2065 

costs 

for 

1.5-2.5 (1996-2000)  No data 
1.8 to 3.5 

0.31 (2005) 

8 (2014) 
20 (2015) 

2060 
2085 

10 (2013) 

147.5 (2014) 

From 2015 
onward 
NDA costs till 
2130 

Total  cost  incurred  until  the  end  of 
2014-5.2 bn; and future costs (2015) 
- €14.7 bn 
January 2013 price level 

The  NDA,  having  considered  a 
number  of  scenarios,  continues  to 
estimate 
cost 
within a potential range from £95 bn 
(€118 bn) to £218 bn (€272 bn) 

the  undiscounted 

NL 
RO 

SI 

SK 
ES 

SE 

UK 

HR 

0.9 (2015) 

After 2043 

AT 

DK 

EL 

PL 

PT 

CY 

EE 

IE 

LV  

No data 

No data 

4.6 x10-3 

No data 

No data 

Next 5 years 

99x10-3 

2025 

2.5x10-3 

0.5 x 10-3 (2016) 

4.6x10-3 

No data 

1.08 

No data 

Immediate  decommissioning  of  the 
Krško NPP after shut-down in 2043, 
waste 
cost 
The 
management, 
and 
decommissioning  

includes, 
spent 

fuel 

for  collection  and 
Costs  cover 
storage of disused radioactive sealed 
source 
The  cost  excludes  future  NPP  and 
geological repository 

Cost  for  the  spent  fuel  transfer  to 
USA  remaining  fuel  &  decommis-
sioning 
Cost  of  repatriation  or  disposal,  and 
operational  costs  of 
the  storage 
included in Nicosia General Hospital  

costs 

2002 
construction 
for 
radioactive  waste  management,  Im-
to 
proving  safety,  compensation 
Baldone municipality for radioactive 
waste storage facility  

39 

202 

448 

138 

707 
3126 

3386 

3445 

138 

- 

- 

- 

- 

- 

- 

- 

- 

- 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
LU  

No data 

No data 

MT 

No data 

No data 

Costs  for  shipment  to  Belgium.  The 
government  states  it  is  capable  of 
covering any cost 

- 

- 

Table 10. Financial mechanisms and accumulated funds by Member State 

MS  Financial 

Gradual 

mechanisms 
(organisation) 

Annual 
fees 

Internal 
(I)/ 
External 
(E) 
E 

Funds 
accumu 
lated (bn €) 

Total 
accumu 
lated (date) 

0.845 (2003)  0.845b€  

(2003) 

Preliminary 
estimate of 
available 
funds46 (%) 
 19 to 20 (the 
latter 
assuming 6 
units and 
LTO) 

BG  Radioactive 
waste 
management 
fund (SE 
RAO) 
Decommission
ing fund (SE 
RAO) 

CZ  Nuclear 

Account for 
SF & RAW 
(Ministry of 
Finance) 

HU  Central 
Nuclear 
Financial 
Fund 

Annual 
fees 

Annual 
fees 

E 

E 

1.4 (2015) 

1.4 (2014) 

1.4 (2014) 

33 

Annual 
fees 

E 

0.8 (2015) 

0.8 (2015) 

15 

Comments 

EU funds for 
Kozloduy NPP 
units 1 to 4 are 
taken into 
account. 
Recognised 
insuffiency of 
fund to date. 
37.4b CZK, 2014 
( 0.037 CZK/€) 

Fund to cover the 
costs for 
management of 
waste, spent fuel 
and 
decommissioning; 
246,386 mill 
HUF, 2015 
(0.0032HUF/€) 

Does not include 
new build 

Annual 
fees 
Annual 
fees 

SK  National 

FI 

Nuclear Fund 
The State 
Nuclear Waste 
Management 
Fund 
BE  Long-Term 
Fund 
(NIRAS/OND
RAF) 

DE  Private 

generators 

E 

E 

I 

I 

1.2 (2015) 

1.2 (2015) 

18 

2.5 ( 2016) 

2.5 (2016) 

38 

- 

No 
information 

- 

36 (2015) 
reported for 

36 (2015) 

54 

Based on the total 
cost 66.9 bn€ (as 

47  

The costs notified by Member States have not been verified by the Commission. The figure in the column is 
indicative  and  is  based  on  the  available  financial  resources  vs  total  costs  in  the  national  programme  and 
report reported by a Member State. 

40 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                 
 
 
 
 
 
(NPPs) make 
provisions47 

NPPs 

FR  Licensees 

I 

43 (2011) 

48 

- 

Annual 
fee 

No 
information 

- 

No 
information 

No 
information  

- 

IT 

create a 
portfolio of 
dedicated 
assets. 
State pays for 
state owned 
facilities. 
SOGIN 
manages the 
funds for 
waste 
management 

LT  Decommission

ing Fund for 
Ignalina 
Nuclear Power 
Plant, State 
Budget, 
Ignalina 
Programme, 
INPP, Other 
funds 

NL  Contributions 

to COVRA  

E 

183 mill 
(2014)48  

- 

8 

RO  Waste 

Disposal Fund 
(ANDR) 

Annual 
fees 

E 

102 million 
(2014) 

0.15 (2014) 

4 - 8  

at 2012) until 
2080 and 2103 
As dedicated 
internal funds & 
assets 

The national 
programme cost 
is until 2030 and 
exclude 
geological 
disposal. Private 
generators shall 
pay to a fund (no 
details on the 
fund available) 
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 
Temporary 
surface storage 
for at least 100 
years. Operation 
of geological 
disposal in 2130. 
4% for new build 
scenario and 8% 
without new 
build. Financing 
mechanism under 
revision to 
address the 
insufficiency of 
funds 

47  

48  

For public generators of spent fuel/radioactive waste, resources are entered in the respective current budget 
for the decommissioning and dismantling costs. 
Ministry report states that "final storage" reserves at the end 2014 € 68 mill, "long term storage" reserves € 
102  mill,  and  additional  costs  of  €  13  mill.  The  long-term  reserves  are  made  increased  yearly  by  4.3  % 
(2.3% real+ 2% inflation).  

41 

 
 
 
 
 
 
 
 
 
 
 
 
                                                 
Annual 
fees 

Annual 
fees 

E 

E 

47 million 
(2014) 

19.96 (from 
2015 
onward) 

5.2 

3549  

Annual 
fees 

E 

0.04 

0.04 

13 

ES 

SI 

  Decommission

ing Fund 
(ANDR) 
Fund for the 
financing of 
activities 
included in the 
General 
Radioactive 
Waste Plan  
Fund for 
Financing the 
Decommission
ing and 
Management 
of Radioactive 
Waste from 
the Krško NPP 

76.3 bn SEK 
(2015) 

75 

30-70 
depending on 
the scenarios 

SEK 56 bn. 
and 19 bn 
SEK 
guarantees 
1.3 bn SEK 
(2013) 
127 mill 
SEK  

 83.8 (2015) 

8.3 (2015) 

0.2 (2013) 

22 

E 

I 

E 

E 

E 

SE  Nuclear Waste 

Fund 

Annual 
fees 

Studsvik 
Legacy Fund 
Non-nuclear 
waste manage-
ment of 
orphan 
sources 

UK  NDA Fund 

State 
funds 

Annual 
fee 

Annual 
fees 

Nuclear 
Liabilities 
Fund 
HR  Fund for Fi-
nancing the 
Decommis-
sioning of the 
Krško Nuclear 
Power Plant 
and the Dis-
posal of NPP 
RAW and SF 

209 million Lei 
(€47 million) 

costs to 2085; 
future costs 
considered only  

Estimates only 
made for period 
2006-2015. 
financing the 
decommissioning 
of the NPP and 
for the disposal of 
NPP radioactive 
waste  
Total of 76.3 bn 
SEK.  
Only remaining 
costs considered. 
56% coverage if 
guarantees are 
excluded 

67 bn £ = (0.8P/€) 
(activities until 
2130, and total 
NDA cost 
between 95-218 
bn £) 
8.3 bn £ (2015) 

0.16 bn € as at 
2013, if reactor 
extension is up to 
2043 then 
estimated to 
0.54bill €  

49  

Future costs (€14.7 bn) considered only. 

42 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
                                                 
AT  Final disposal 

fees paid to 
the 
Government 
Fund yet to be 
established  

EL 

Fees for 
treatment 
and dis-
posal 

DK  No 

information 

PT  Disposal 
revenue; 
General state 
budget and 
IST budget 

Fees from 
producers 

collects fees 

PL  RWMP 

Fees for 
disposal, 
decon-
tamina-
tion, and 
transport 
CY  Fund planned   Currently 

EE 

IE 

LV 

genera-
tors’ fees 
and State 
budget 

Estonian 
environm
ental fees 
EU funds 
Fees from 
waste 
producers 
Currently 
gene-
rators’ 
fees and 
State 
budget 

Currently 
gene-
rators’ 
fees and 
State 
budget 

- 

- 

- 

- 

- 

- 

- 

- 

- 

No 
information 

No 
information 

No 
information 
No 
information 

- 

- 

- 

- 

No 
information 

- 

No 
information 

- 

E 

No 
information 

- 

No 
information 

- 

No 
information 

- 

43 

4.6 mill€ costs 
over 5 years for 
collection & 
storage of disused 
radioactive sealed 
sources.  

US transfer of 
remaining fuel to 
be covered by the 
State; increase of 
fees foreseen in 
2015 
Decommissioning 
fund for the new 
build to be 
established 

The fund costs 
will cover waste 
management 
(incl. disposal), 
decommissioning, 
R&D, etc. 
Reliance on EU 
funds for 
historical 
liabilities 

The state cost 
cover orphan 
sources. The 
regulators income 
in 2012 was 5.2 
mill € but not 
specifically for 
radioactive waste 
Provisions for 
Salaspils research 
reactor assumed 
by the State 

 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
 
MT 

LU   Government 
will provide 
necessary 
resources 

Currently 
gene-
rators’ 
fees  
Currently 
gene-
rators’ 
fees 

No 
information 

No 
information 

- 

- 

- 

- 

State to cover the 
cost of orphan 
sources 

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.  

44 

 
 
 
 
 
 
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 
EU50 

MS 

URL 

Site 

Status 

Purpose 

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.  

Responsible 
organization for 
facility 
development 

EURIDICE 
(cooperation of 
ONDRAF/NIRAS 
& SCK CEN)  

CZ 

DE 

Planned 

Gorleben 

To be 
selected 
Gorleben 

FI 

ONKALO 

Eurajoki  

Exploration 
started  in  1986. 
in 
Discontinued 
2013 
In operation  

2030 

Long term site investigations 

SURAO 

Salt formation 

BfS/DBE 

FR 

Bure 

Meuse/Haute 
Marne 

In operation since 
2006 

Tournemire 

HU 

Planned 

Southern 
Aveyron 

Western 
Mecsek 

In operation since 
1990 

Planned 
2020 to 2055 

from 

BCF 

PL 

PURL 

Western 
Mecsek 
Planned 

in 

Discontinued 
1998 
Planned 

Research for the DGR 

Waste characterization, 420 m 
depth, planned to be 
incorporated into disposal 
facility with first disposal 
about 2025 
Callovo-Oxfordian clay (hard) 
at ~ 450 - 500 m depth 

methodological laboratory 
(former train tunnel) in 
sediments (hard clay), 250m 
depth  
Preparation 
implementation 
geological 
programme 

for 
the 
disposal 

of 

POSIVA 

ANDRA 

IRSN 

PURAM 

of 
Minister 
Economy, 
Polish 
Geological  Institute 
– National Research 
Institute  and  other 
interested 
institutes51 

50  

51  

Several  Member  States  carry  out  experimental  work  in  the  Grimsel  Test  Site  (Switzerland),  which  is  in 
operation since 1984. The facilities in grey are not in operation any longer. 
The  minister  responsible  for  the  economy,  the  Polish  Geological  Institute  –  National  Research  Institute 
(PIG-PIB) and other interested institutions to sign an agreement for supporting the concept of deep disposal 
of radioactive waste and the construction of an URL and initiating integrated research in these areas. 

45 

 
 
 
 
 
 
 
                                                 
RO52 

Planned 

SE 

Äspö HRL  

the 

On 
selected site 
North 
Oskarshamn 

of 

2030 

In operation since 
1995 

Stripa mine  

Closed in 1991 

Confirm the suitability of the 
underground conditions  
Granite, 200 - 500 m depth; 
Used for research activities on 
performance of barriers for 
spent fuel disposal. 
Granite, former iron ore mine 
at 360 - 410 m research from 
1977 - 1991 

SKB 

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 radioactive waste management presented in Table 12 below. 

52  

The National Agency for Radioactive Waste is responsible for the research and development. 

46 

 
 
 
 
                                                 
Table 12. Overview of main information and involvement mechanisms  

1. Information 

2. Consultation 

a. Internet 

b. Printed information 

a. Public meetings and 
workshops 

c. Public events 

d. Media relations 

e. Other tools 

b. Surveys and opinion polls 

c. Public consultations/hearings 

d. Other tools 

3. Participation 

a. Working groups 

b. Voluntary 
arrangements  

c. National 
commissions 

d. Advisory bodies 

In general, the Member States' national programmes and reports contain a details on how Member 
States allow and provide information and ensure opportunities for public consultation (e.g. in the 
framework  of  SEA  and  environmental  impact  assessment  (EIA)  procedures).  The  Commission 
noted that in some case, information on the transparency policy and its implementation in practice 
has not been included in the national programme as required by Article 12(1)j of the Directive but 
rather in the Member State's report, or vice versa. 

Almost  all  Member  States  have  clearly  indicated  the  responsibility  of  the  national  regulator  to 
provide  information  to  the  public  about  the  safety  and  security  of  nuclear  energy  decisions  and 
activities, including spent fuel and radioactive waste management. In some cases, Member States 
specify that the public can access the regulator's acts on the basis of the right of public access to 
official records if such acts are not covered by secrecy. Some Member States have reported that 
documents about the licensing procedure of nuclear and radioactive waste management facilities 
are made public and easily accessible on the authorities' websites as requested by national laws. 
National laws also assign a legal obligation of information to the licence holders (i.e. operator of 
nuclear facilities or implementer for radioactive waste management facilities): e.g. licence holders 
have a duty to inform the general public and the affected local community. Finally, other bodies 
(usually at ministerial level) may also be responsible for the provision of information. 

Information  to  the  public  and  other  stakeholder  is  provided  by  Member  States  through  several 
mechanisms that can be summarized as follows: 

a)  Internet – mostly reported tool, mainly in the form of corporate websites; 

b)  Printed  information  –  e.g.  newsletters  (or  e-newsletter),  leaflets,  brochures  and 
publications;  studies  and  reports  (e.g.,  annual  reports,  progress  reports  and  technical 
reports; 

c)  Public events – e.g. exhibitions, public conferences and presentations; 

d)  Media  relations  –  e.g.  press  releases,  press  conferences,  TV  programmes,  newspaper 
article or insert, etc. Official journals are also used for information, for instance about new 
legislation and regulation; 

e)  Other tools - social media and blogs as their channel of communication with the public; 
information  centres  (for  instance  those  located  in  a  given  facility's  site)  and  open  days 
(such as site visits). 

Most  Member  States'  national  programmes  are  public  documents  that  have  been  used  as  an 
instrument  for  informing  the  general  public  about  national  policy  and  plans  for  spent  fuel  and 
radioactive  waste  management.  Although  the  techniques  for  information  are  similar  both  in 

47 

 
 
 
Member States with nuclear power plants and without nuclear power plants, these techniques and 
their use are explained more in detail by Member States with nuclear power plants.  

The  majority  of  Member  States  have  mechanisms  in  place  to  ensure  public  information  and 
opportunities for public consultation in line with Article 10 of the Directive (e.g. in the framework 
of strategic environmental assessment and environmental impact assessment procedures).  

However, about half of the Member States have not reported on mechanisms in place to ensure 
public participation in the decision-making process beyond public consultation, such as working 
groups, advisory bodies or national commissions. Member States should in the future present or 
explain  further  the  extent  of  public  involvement  in  the  decision-making  for  spent  fuel  and 
radioactive waste management. 

In  general  institutions  exist  at  the  local  level  (e.g.,  municipalities)  and  regional  level  (e.g., 
counties)  to  ensure  representation  of  local  interests  in  the  national  policy-making.  In  addition, 
mechanisms for participation have been reported aiming to enhance participation of citizens in the 
decisions about radioactive waste management, particularly in the case of those localities that are 
directly  involved  in  the  storage  and  disposal  of  radioactive  waste.  These  mechanisms  of 
participation of stakeholders are: 

-  Working  groups  -  involving  (in  a  formal  way)  representatives  from  a  broad  range  of 
interests, from state authorities, regulators and implementers to associations from the civil 
society  and  non-governmental  organisations;  focus  on  a  specific  project  (e.g.,  deep 
geological disposal) or can be used for the preparation of strategic documents. Bodies for 
local  information  (called  "commissions",  "committees",  etc.)  are  also  established  in 
several Member States on specific nuclear power plant or radioactive waste management 
sites, as well as associations of local governments created with the purpose of information 
and social monitoring of given Radioactive Waste management facilities. 

-  Voluntary arrangements – allowing local communities to express their support or dissent 

about radioactive waste management projects. 

-  National commissions - promoting public participation in radioactive waste management. 

-  Advisory bodies - involving state and non-state actors (often at the national level). 

With regard to the principle of public information and participation in international law, less than 
half of Member States refer explicitly to the application of the Aarhus and Espoo Conventions in 
their  programmes  and  reports,  although  all  EU  Member  States  are  parties  to  these  international 
legal instruments. 
3. 

CONCLUSION 

The Commission has reviewed the notified national reports of all Member States and the national 
programmes  of  27  Member  States  submitted  until  September  2016.  Having  reviewed  these 
notifications, the Commission prepared its first report to the Council and the European Parliament 
on implementation of this Directive. It identified progress, trends and challenges in the spent fuel 
and radioactive waste management.  

The next Member States reports to be submitted to the Commission are due by 23 August 2018.  

48