INT9176 INTERREGIONAL WORKSHOP ON

1. IAEA Safety Standards Related to Disposal of Radioactive Waste and Disused Sealed Radioactive Sources INT9176 INTERREGIONAL WORKSHOP ON REGULATORY REQUIREMENTS TO ENSURE SAFE DISPOSAL OF DSRS (OPERATORS AND REGULATORS) Monika Kinker 7 April 2014

2. Outline • Organization • IAEA Safety Standards relevant to RWM • Application in disposal of DSRS overview of safety standards

3. Waste Management at the IAEA • Department of Nuclear Safety and Security • Nuclear Installation Safety • Radiation, Transport and Waste Safety • Waste and Environmental Safety Section • Department of Nuclear Energy • Nuclear Power • Nuclear Fuel Cycle andWaste Technology • Waste Technology Section overview of safety standards

4. Activities of the Division • Safety Standards Development • Support for International Conventions • Application of Standards: • Information Exchange (e.g. Conferences, ...) • Research & Development • Technical Cooperation • Training & Education • Appraisals, Peer Reviews overview of safety standards 4

5. IAEA Safety Standards overview of safety standards 5

6. Vision for the IAEA Safety Standards Outcome: • A harmonized high level of protection for people and the environment worldwide based on the IAEA safety standards as the global reference Output: • Global reference for protecting people and the environment from harmful effects of ionizing radiation. • Integrated, comprehensive and consistent • Up-to-date, user friendly, fit-for-purpose and high quality • Provide for a worldwide harmonized high level of protection for people and the environment from harmful effects of ionizing radiation.

7. Strategies • Clear categories of safety standards consistent with Member States’ needs and use • Clear, logical and integrated structure based on a unified philosophy of safety • Consensus at the highest level on what constitutes a high level of safety and the related best international practices • Transparency and rigour of the process • Effective feedback mechanisms • User - friendliness • Manageable number of safety standards • Clear scope: areas covered and level of detail • Harmonized terminology

8. Safety Standards Categories Safety Requirements Fundamental Safety Principles Requirements – Legal, Technical, & Procedural Safety Imperatives Safety Fundamentals Guidance on Best Practice to Meet Requirements Safety Guides

9. SafetyRequirements Safety Fundamentals • Policy document of the IAEA Safety Standards Series: • States the basic objectives, concepts and principles involved in ensuring protection and safety • Comprised of 10 safety principles • Principle 7: Protection of present and future generations. People and the environment, present and future, must be protected against radiation risks Safety Fundamentals SafetyGuides overview of safety standards

10. Safety Requirements Safety Requirements • Elaborate on the basic objectives and concepts of SF-1 as they apply to a specific activity or facility • Should be concise and reflect the ‘What’ and ‘Who’ of safety management  associated explanatory text should describe ‘Why’ the requirements exist • Use “shall” statements Safety Fundamentals SafetyGuides overview of safety standards

11. SafetyRequirements Safety Guides • Focus on ‘How’ safety requirements can be met • Guidance on best practices to meet requirements • Use “should” statements Safety Fundamentals Safety Guides overview of safety standards

12. Status of Safety Standards • IAEA Safety standards are • Binding for IAEA’s own activities • Not binding on the Member States (but may be adopted by them) EXCEPT in relation to operations assisted by the IAEA: • Integrated Regulatory Review Service • Technical Cooperation Fund work • States wishing to enter into project agreements with the IAEA overview of safety standards

13. Development of Safety Standards Commission on Safety Standards (CSS) Nuclear Safety Standards Committee (NUSSC) Radiation Safety Standards Committee (RASSC) Waste Safety Standards Committee (WASSC) Transport Safety Standards Committee (TRANSSC) Outline and work plan Prepared by the Secretariat Review by the SafetyStandardsCommittees and the Commission on Safety Standards Review period: about every 5 years Drafting or revising of safety standard by the Secretariat and Consultants Review by the Safety Standards Committee(s) Member States Endorsement by Commission on Safety Standards * Safety Requirements approved by BoG * Safety Guides approved by DG Approvalby the IAEA’s Director General or BoG * overview of safety standards

14. Safety Fundamentals: Current Structure Thematic Areas Facilities & Activities Legal & governmental infrastructure Nuclear power plants Emergency preparedness & response Research reactors Management systems Fuel cycle facilities Assessment & verification Radiation related facilities & activities Site evaluation Waste treatment and disposal facilities Radiation safety Radioactive waste management Decommissioning Rehabilitation of contaminated areas Transport of radioactive material Overview of IAEA Safety Standards overview of safety standards

15. Currentstatusofdevelopment of IAEA SafetyRequirements 2010 Under development Under development Published in 2011-12 Published in 2011 Under development 2009 Under development 2009 Published in 2011 Under development Published in 2012 Under development

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

17. Safety Standards - Disposal • Site Aspects • Design • Construction • Operation • Closure • Post Closure • Safety Assessment • Management System DS 356 DS 357 Monitoring and Surveillance of Disposal Facilities Near Surface disposal of RW Specific Safety Guide Specific Safety Guide overview of safety standards

18. Safety Standards - Disposal DS 356 Near Surface disposal of RW Specific Safety Guide

19. SSR-5: Disposal of Radioactive Waste Req. 1-3: Responsibilities of Government, RB, operator Req. 4: Importance of safety in the process of development, operation of disposal facility Req. 11: Step by step development and evaluation of disposal facilities Req. 12-14: Safety Case/Safety Assessment Req. 16-17: Design and construction Req. 18: Operation of a disposal facility Req. 20: Waste acceptance Req. 21: Monitoring programmes overview of safety standards

20. SSG-23:The Safety Case and Safety Assessment for Disposal of RW 1. INTRODUCTION 2. DEMONSTRATING THE SAFETY OF RW DISPOSAL 3. SAFETY PRINCIPLES AND SAFETY REQUIREMENTS 4. THE SAFETY CASE FOR DISPOSAL OF RW 5. RADIOLOGICAL IMPACT ASSESSMENT FOR THE PERIOD AFTER CLOSURE 6. SPECIFIC ISSUES Evolution of the safety case Graded approach Defence in depth Robustness Time frame for the assessment Human intrusion Institutional control Retrievability of waste Appraisal of options 7. DOCUMENTATION AND USE OF THE SAFETY CASE 8. REGULATORY REVIEW PROCESS

21. International and Harmonization Projects • CRAFT (successor to SADRWMS) • Application of GSG-3, SADRWMS methodology & SAFRAN Tool • Illustrative examples to complement SG (DS284) • PRISM • Safety case development / implementation for near-surface disposal • Barrier performance • Uncertainty • GEOSAF I / II • Safety on geological disposal • Regulatory expectations throughout development and operation • Assessment – engineering, site, radiological impact, integration • Working Group for the Dual Use Cask for Spent Nuclear Fuel • Safety case covering both transportation / storage • Extended periods of storage and meeting transport requirements • HIDRA • Human intrusion for both geological / near-surface disposal facilities • Relationship with siting/ designing/ waste acceptance criteria overview of safety standards

22. Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management • WES coordinates as the Secretariat of the Joint Convention • Number of Contracting Parties: 64 (Latest update: Bosnia & Herzegovina entry into force on 31 Oct 2012) • Review meetings: • 1st review meeting: November 2003 • 2nd review meeting: May 2006 • 3rd review meeting: May 2009 • 4th review meeting: May 2012 • 5th review meeting: May 2015 overview of safety standards

23. Peer Reviews • Yucca Mountain Site Characterisation Project (USA) • Near Surface Disposal (Australia) • IAEA-EC-Ukraine (WWER review, Ukraine) • Site Characterisation (South Korea) and selection (Lithuania) • COVRA activities (Netherlands) • Disposal (Russia, planned), etc. overview of safety standards 23

24. Information Exchange http://www-pub.iaea.org/MTCD/meetings/meetings.asp overview of safety standards

25. Disposal of DSRS overview of safety standards 25

26. DSRS Long Term Management Options • Return to Commercial Suppliers • Return to Country of Origin (Repatriation) • Reuse/Recycle • Storage at User Facility • Storage in Dedicated (“Centralized”) Facility • Decay to clearance levels iaw national regulations • Interim storage pending future actions • Long Term (between 50 and 100 yr) • Disposal

27. Why Storage is not a Sustainable Management Strategy • Not a sustainable option in the long-term • On-going financial liabilities • Poor or no regulatory control in certain countries • Limited expertise or capacity for managing sources • Institutional and social stability • Potential health and environmental hazard • Safety, Security concerns (potential for malicious use)

28. Disposal Options • Disposal at Landfill • Near-surface Repository Disposal • (with and without engineered barriers) including underground cavities (natural or engineered) at relatively shallow depths • Geological Repository Disposal • Borehole Disposal Co-disposal might be an option e.g. NSR & BDC

29. Factors Affecting Choice of Disposal Option • Nature of the waste (activity, half-life, toxicity) • Quantity and location(volume, where is it?) • Site Characteristics (nature of the rock, water flow & chemistry, stability) • Preferences concerning repository design and nature of engineered barriers • Other Factors (national policy and strategy, availability of resources, stakeholder consensus)

30. Borehole Disposal Concept • Originally designed for disposal of relatively small inventories of DSRS in AFRA member states • Developed in collaboration with Necsa (South Africa) • Suitable for a range of environments • Saturated vs unsaturated • Aerobic vs anaerobic • Fractured hard rock vs porous sedimentary rock • Depending on the inventory, saline vs freshwater

31. Disposal Borehole Design & Construction Borehole Diameter – 260mm Length – variable Casing Diameter – 160mm Length - variable Disposal Container Diameter – 115mm Length – 250mm Capsule Diameter - 21/48mm Length – 110/121mm

32. Emplacement and Borehole Closure

33. Benefits • Accommodate a range of inventories, sites • Small footprint and other features against intrusion • Uses readily available technology • Small volume excavation → less environmental impact • Cost-effective compared with other options • Meets all safety requirements for disposal

34. IAEA Publications 34

35. BDC - SAFETY CASE • The collection of arguments evidence that aim to demonstrate the safety of a facility based on a sound understanding of • the site • the safety functions and the processes that support them • For a disposal facility it is the main part of the operator’s submission to the regulatory body • Must meet regulatory requirements including dose/risk constraints or targets • It may be separate, within or part of an EIA

36. SA - Methodological Approach • The ISAM Methodology developed under an IAEA Coordinated Research Project • Now applied in a wide range of countries

37. Generic Safety Assessment (GSA) • A SA undertaken on a site-generic rather than site-specific basis using a synthetic system • Can provide useful input to decisions concerning a variety of issues: • suitable designs, site characteristics & activity limits • Use of the GSA • Starting point for the post-closure SA of a specific site • Worked example that can be used to guide/inform a site-specific assessment • Identify key waste and site attributes that need to be characterised as part of a waste and site characterisation programme

38. Concluding Remarks • Although valuable RWM experience has been collected worldwide, we are all still learning • This week is a good change for exchange of experiences between participants • We are looking for intensive and open discussion! • Try to use the presence of this group of experts from different countries to get maximal benefit for your project! overview of safety standards