Overview of IAEA activities related to Storage of Spent Nuclear Fuel

Transcription

1 Overview of IAEA activities related to Storage of Spent Nuclear Fuel Yumiko Kumano Radioactive Waste and Spent Fuel Management Unit Division of Radiation, Transport and Waste Safety - NSRW International Workshop on the Development and Application of a Safety Case for Dual Purpose Casks for Spent Nuclear Fuel IAEA Headquarters, Vienna, Austria May 2014

2 Overview Introduction IAEA Safety Standards and Application Department of Nuclear Safety and Security Activities on Storage of Spent Fuel from Nuclear Power Reactors Department of Nuclear Energy Safety Case 2 2

3 Spent Fuel Management at the IAEA (1) Department of Nuclear Safety and Security (NS) Division of Radiation, Transport and Waste Safety (NSRW) Department of Nuclear Energy (NE) Division of Nuclear Fuel Cycle and Waste Technology (NEFW) 3

4 Spent Fuel Management at the IAEA (2) Department of Nuclear Safety and Security Nuclear Security Nuclear Installation Safety Radiation, Transport and Waste Safety Waste and Environmental Safety Section Development of IAEA Safety Standards Secretariat for Joint Convention on the Safety of SF Management and on the Safety of RW Management 4

5 Spent Fuel Management at the IAEA (3) Department of Nuclear Energy (NE) Division of Nuclear Power Division of Nuclear Fuel Cycle and Waste Technology (NEFW) Nuclear Fuel Cycle and Materials Section (NFCMS) 5 4 Subprogrammes: B1 Uranium, B2 Fuel, B3 Spent Fuel and B4 Advanced Nuclear Fuel Cycles B3 Management *of Spent Fuel from Nuclear Power Reactors Subprogramme: Mr Paul Standring, Mr Arturo Bevilacqua (*Disposal: Waste Technology Sec.) Technical Publications: Output of Programmmatic Activities and Coordinated Research Projects

6 IAEA Safety Standards Development and Application Department of Nuclear Safety and Security 6

7 Configuration of IAEA Safety Standards 7

8 International and Harmonization Projects Joint Working Group for the Dual Purpose Cask for Spent Nuclear Fuel Safety case covering both transportation / storage Extended periods of storage and meeting transport requirements CRAFT Application of GSG-3, SADRWMS methodology & SAFRAN Tool Illustrative examples to complement GSG-3 PRISM / PRISMA Safety case development Use of the safety case in the decision making process during the lifetime of a near surface disposal facility. GEOSAF I / II Safety on geological disposal Regulatory expectations throughout development and operation Assessment engineering, site, radiological impact, integration HIDRA Human intrusion for both geological / near-surface disposal facilities Relationship with siting/ designing/ waste acceptance criteria ILW Draft technical document on disposal of ILW 8

9 Joint WG for the DPC for Spent Nuclear Fuel (1) Background Growing amount of SNF in storage caused by delays in decision on SF disposition Necessity of additional storage capacity 1. Wet storage 2. Dry storage Includes DPCs designed for both transport / storage Intention is to provide guidance to MSs for integrating safety cases for storage and transport in a holistic manner Establishment of a joint international working group Objective 1.To provide an IAEA document containing recommendations and guidance for the structure and contents of an Integrated Safety Case for a dual purpose storage and transport cask. 2.Recommendation for changes to be made to existing IAEA documents 9

10 Joint WG for the DPC for Spent Nuclear Fuel (2) April 2011: 1 st Plenary meeting Adoption of the Terms of Reference Drafting outline and contents Base document: April 2012: 2 nd Plenary meeting Review / Comment / Revise the first draft Major issues Definition of Safety Case for DPCs? How to address Acceptance Criteria? How to discuss aging issues? Technical Guide Package Design Safety Reports for the Transport of Radioactive Material (PDSAR) by European Association of Competent Authorities April 2013: 3 nd Plenary meeting Mostly finalized document Recommendations to WASSC / TRANSSC Future activities WG webpage 10

11 Activities on Storage of Spent Fuel from Nuclear Power Reactors Department of Nuclear Energy 11

12 B3 Programmatic Activities on Spent Fuel Storage Coordinated Research Project (CRP) on SPAR III (Spent Fuel Performance and Research Third Phase). Third RCM, November 2013, Republic of Korea CRP on Demo (Demonstrating Performance of Spent Fuel and Related Storage System Components during Very Long Term Storage). First RCM, April 2013, Argentina. Second RCM, November 2014, Japan Spent Fuel Storage (SFS) Options. First TM, July 2013, IAEA Headquarters, Vienna, Austria Management of Decay Heat in Spent Fuel Storage. First CS, December 2013, IAEA Headquarters, Vienna, Austria 12

13 B3 Programmatic Activities on Spent Fuel Storage (cont.) Collecting, Analysing and Assembling Relevant Data from Fukushima Daiichi Spent Fuel Storage Facilities Events. First Progress Report, September Third CS, June 2014, IAEA Headquarters, Vienna, Austria International Conference on Managing Spent Fuel from Nuclear Power Reactors - An integrated approach to the Back-End of the Fuel Cycle, June 2015, IAEA Headquarters, Vienna, Austria 13

14 Current B3 Programmatic Activities on SFS: CRP on SPAR III Former CRP on BEFAST (Behaviour of Spent Fuel Assemblies during Extended Storage) BEFAST I ( ), II ( ) and III ( ), and SPAR I ( ), II ( ) and III ( ) totalizing more than 30 years of SF behaviour, performance assessment and research Need for continuous work: Higher Burnup and MOX, Longer storage periods and Incidents at Spent Fuel (Wet and Dry) Storage Facilities (Fukushima Daiichi) As recommended in June 2013 by the Technical Working Group on Nuclear Fuel Cycle Options and Spent Fuel Management results from BEFAST I to SPAR III will be consolidated. First CS, August 2014, Vienna, Austria 14

15 Current B3 Programmatic Activities: Extending Spent Fuel Storage beyond the Long Term (Originally Technical Aspects of Spent Fuel Management, then refocused to Very Long Term Storage of Used Nuclear Fuel, the after SSG-15 beyond the Long Term) Addresses technical and non-technical considerations including institutional, finance, public acceptance, political commitment and human resources Final Draft being prepared for sending to the Publication Committee in 2013 Publication expected in

16 Current B3 Programmatic Activities: Spent Fuel Storage Options Overall Objective: Establish which storage systems are currently available or under design, design innovations to meet latest safety standards and fuel cycle demands, to review operating experience and impact of Fukushima Attended by: 39 experts from 23 Member States (>90% of the world s stored fuel) Meeting material available: epository/ spent-fuel-vienna.html 16

17 Current B3 Programmatic Activities: Management of Decay Heat in Spent Fuel Storage Overall Objective: To gather information on and to formulate the basis for producing a technical guidance document on managing decay heat in spent fuel storage Output: Information on managing decay heat in spent fuel storage is embedded in a variety of documents, then opportunity to pull all facts into one document 17

18 Safety Case in the context of RW management 18

19 International WS on the Development and Application of a Safety Case for DPCs for SNF Objectives: 1.to enhance the understanding of the concept of an integrated safety case; 2.to analyse the gap between the current practices within Member States and the proposed concept; 3.to discuss further improvements of the application of the integrated safety case concept. What is a Safety Case? What is a Safety Case for DPCs? How can we utilize the concept? 19

20 Configuration of IAEA Safety Standards GSR Part 4 GSR Part 5 20

21 Definition of Safety Assessment and Safety Case GSR Part 4 (SA for facilities and activities): Safety Assessment 1. Assessment of all aspects of a practice that are relevant to protection and safety; for an authorized facility, this includes siting, design and operation of the facility. This will normally include risk assessment and probabilistic SA. 2. Analysis to predict the performance of an overall system and its impact, where the performance measure is the radiological impact or some other global measure of the impact on safety. 3. The systematic process that is carried out... to ensure that all the relevant safety requirements are met by the proposed (or actual) design. Safety assessment includes, but is not limited to, the formal safety analysis. GSR Part 5 (Predisposal management of RW), GSG-3: Safety Case A collection of arguments and evidence in support of the safety of a facility or activity. This will normally include the findings of a safety assessment and a statement of confidence in these findings. 21

22 GSR Part 4: Overview of Safety Assessment 22

23 GSR Part 5 & GSG-3 & SSG-23: Components of the Safety Case Definition of Safety Case in GSR Part 5 A collection of arguments and evidence in support of the safety of a facility or activity. This will normally include the findings of a safety assessment and a statement of confidence in these findings 23

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25 GSG-3 The Safety Case and Safety Assessment for the Predisposal Management of Radioactive Waste INTRODUCTION BACKGROUND, OBJECTIVE, SCOPE, STRUCTURE 2. DEMONSTRATING THE SAFETY OF PREDISPOSAL MANAGEMENT OF RADIOACTIVE WASTE 3. SAFETY FUNDAMENTALS AND REQUIREMENTS SF, REQUIREMENTS FOR SC / SA 4. SC FOR PREDISPOSAL MANAGEMENT OF RW ROLE AND DEVELOPMENT OF THE SC, COMPONENTS, UNCERTAINTIES, DESIGN OPTIMIZATION, INTERACTION 5. RADIOLOGICAL IMPACT ASSESSMENT APPROACH, CONTEXT, DESCRIPTION SCENARIO DEVELOPMENT AND JUSTIFICATION MODELS, PERFORMANCE AND ANALYSIS OF THE RESULT 6. SPECIFIC ISSUES EVOLUTION OF THE SC, GRADED APPROACH DEFENCE IN DEPTH, RELIABILITY EXPECTED LIFETIME OF THE FACILITY LONG TERM STORAGE 7. DOCUMENTING AND USING THE SAFETY CASE 8. REGULATORY REVIEW PROSESS 25

26 SSG-15 Storage of Spent Nuclear Fuel 1. INTRODUCTION BACKGROUND, OBJECTIVE, SCOPE, STRUCTURE 2. PROTECTION OF HUMAN HEALTH AND ENVIRONMENT 3. ROLES AND RESPONSIBILITIES GENERAL RESPONSIBILITIES OF THE GOVERNMENT RESPONSIBILITIES OF THE OPERATER SAFEGUARDS & PHYSICAL PROTECTION SYSTEMS 4. MANAGEMENT SYSTEM SPENT FUEL MANAGEMENT RESOURCE MANAGEMENT PROCESS IMPLEMENTATION 5. SAFETY CASE AND SAFETY ASSESSMENT DOCUMENTATION OF THE SAFETY CASE 6. GENERAL SAFETY CONSIDERATIONS FOR STORAGE OF SPENT FUEL GENERAL DESIGN OF SPENT FUEL STORAGE FACILITIES COMMISSIONING OF SPENT FUEL STORAGE FACILITIES OPERATION OF SPENT FUEL STORAGE FACILITIES DECOMMISSIONING OF SPENT FUEL STORAGE FACILITIES 26

27 Safety Case (1) Radioactive waste must be managed in such a way as to avoid imposing an undue burden on future generations The generations that produce the waste have to seek and apply safe, practicable and environmentally acceptable solutions for its long term management IAEA Safety Requirements for radioactive waste management require that a safety case (including a supporting safety assessment) to be developed 27

28 Safety Case (2) The safety case is: the collection of scientific, technical, administrative and managerial arguments and evidence in support of the safety of a facility The arguments cover the suitability of the site and the design, construction and operation of the facility, the assessment of radiation risks and the assurance of the adequacy and quality of all of the safety related work associated with the disposal facility a well-defined, formal set of documents produced by the operator and reviewed by the regulator 28

29 Safety Case (3) Safety assessment is an integral part of the safety case It provides an understanding of the behaviour of the facility under normal conditions and disturbing events, considering the time frames over which the radioactive waste remains hazardous It includes a systematic quantification of radiation doses and risks that may arise from the facility for comparison with dose and risk criteria 29

30 Scope of the Safety Case Relevant facilities / activities: Disposal facilities Processing of radioactive waste Clearance and Discharges Storage facilities Transport Intervention situations (e.g. old storage facilities) All types of wastes low level to high level waste disused sealed sources NORM 30 of 49 30

31 Use of the Safety Case Comparison of Options Prioritization of Site Characterization and R&D Facility Design and Operation Licensing Derivation of Limits and Conditions Monitoring Staff Training Safety Case for DPCs? 31

32 Conclusions and Future activities Joint Working Group for the Dual Purpose Cask for Spent Nuclear Fuel: The guidance document is under publication process Draft document is available at Workshop on the development and application of DPC safety case (This week) 1. to enhance understanding of the concept of an integrated safety case 2. to analyze gaps between current practices and proposed concept 3. to discuss further improvements of the application of the concept Your active involvement for the discussion is essential for successful meeting & further evolution of the concept!! 32

33 Thank You