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  1. Overview of IAEA Safety Standards regarding radioactive waste management Yumiko KumanoARAB ATOMIC ENERGY AGENCY/ARAB NETWORK OF NUCLEAR REGULATORS (ANNuR)FORUM OF NUCLEAR REGULATORY BODIES IN AFRICA (FNRBA) Regional Workshop on Management and Safe Disposal of Radioactive WasteTunis, 17-21, March 2014

  2. Outline • Overall structure of standards relevant to waste management • Safety Fundamentals • Safety Requirements • Safety Guides • Application overview of safety standards

  3. Evolution of Safety Standards Programme • In the early years, IAEA safety standards were developed on an “as needed” basis. • The programme was ad hoc, and far from being comprehensive. • Over a 50 year period the programme has evolved into one that is structured and comprehensive.

  4. 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: IAEA safety standards will be seen as the global reference for protecting people and the environment from harmful effects of ionizing radiation. They will constitute an integrated, comprehensive and consistent set of up-to-date, user friendly and fit-for-purpose safety standards of high quality, which through their use and application in the Member States will provide for a worldwide harmonized high level of protection for people and the environment from harmful effects of ionizing radiation.

  5. 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

  6. Strategies(Cont’d) • User - friendliness • Manageable number of safety standards • Clear scope in terms of areas covered and level of detail in each category • Harmonized terminology • Effective knowledge management • Promotion of the safety standards

  7. 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

  8. 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 Safety Fundamentals SafetyGuides overview of safety standards

  9. 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

  10. 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

  11. 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

  12. 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

  13. 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

  14. Fundamental Safety Principles Safety Requirements Safety Objective The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation. Safety Fundamentals Basis for IAEA Safety Requirements and Guides Safety Guides overview of safety standards

  15. Safety Principles 1/4 • Principle 1: Responsibility for safety The prime responsibility for safety must rest with the person or organization responsible for facilities and activities that give rise to radiation risks. interdependencies between all steps • Principle 2: Role of government An effective legal and governmental framework for safety, including an independent regulatory body, must be established and sustained. • Principle 3: Leadership and management for safety Effective leadership and management for safety must be established and sustained in organizations concerned with, and facilities and activities that give rise to, radiation risks.  link to establish a Safety Culture overview of safety standards 15

  16. Safety Principles 2/4 • Principle 4: Justification of facilities and activities Facilities and activities that give rise to radiation risks must yield an overall benefit. • Principle 5: Optimization of protection • Protection must be optimized to provide the highest level of safety that can reasonably be achieved (impacts should be ALARA) • Optimization means using good practices and common sense to avoid radiation risks as far as is practical • Optimization requires judgements about the relative significance of various factors, including the magnitude and likelihood of radiation exposures as well as economic, social and environmental factors • The resources devoted to safety (and regulation) have to be commensurate with the magnitude of the risks overview of safety standards 16

  17. Safety Principles 3/4 • Principle 6: Limitation of risks to individuals Measures for controlling radiation risks must ensure that no individual bears an unacceptable risk of harm. • Principle 7: Protection of present and future generations People and the environment, present and future, must be protected against radiation risks • Radioactive waste must be managed in such a way as to avoid imposing an undue burden of future generations • The generations that produce the waste have to seek and apply safe, practicable and environmentally acceptable solutions for its long term management. • The generation of radioactive waste must be kept to the minimum practicable level by means of appropriate design measures and procedures, such as the recycling and reuse of material. overview of safety standards 17

  18. Safety Principles 4/4 • Principle 8: Prevention of accidents All practical efforts must be made to prevent and mitigate nuclear or radiation accidents.  Safety considerations from siting to closure of a facility. • Principle 9: Emergency preparedness and response Arrangements must be made for emergency preparedness and response for nuclear or radiation incidents. • Principle 10: Protective actions to reduce existing or unregulated radiation risks Protective actions to reduce existing or unregulated radiation risks must be justified and optimized. overview of safety standards 18

  19. Current status of development of IAEA Safety Requirements 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

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

  21. GSG-1: Classification of RW

  22. 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

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

  24. SSR-5: Disposal of Radioactive Waste Req. 1-3: Responsibilities of regulatory body, operator, Government 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

  25. DS356:Near Surface Disposal Facilities for Radioactive Waste 1. INTRODUCTION 2. OVERVIEW OF NEAR SURFACE DISPOSAL AND ITS IMPLEMENTATION 3. LEGAL AND ORGANIZATIONAL INFRASTRUCTURE 4. SAFETY APPROACH IMPORTANCE OF SAFETY CONTAINMENT / ISOLATION / MULTIPLE SAFETY FUNCTIONS PASSIVE SAFETY / SURVEILLANCE AND CONTROL 5. SAFETY CASE AND SAFETY ASSESSMENT PREPARATION / SCOPE / DOCUMENTATION ADEQUATE UNDERSTANDING AND CONFIDENCE IN POST-CLOSURE SAFETY 6. ELEMENTS IN A STEPWISE APPROACH TO THE DEVELOPMENT OF A NEAR SURFACE DISPOSAL FACILITY SITE CHARACTERIZATION / DESIGN / WAC / CONSTRUCTION / OPERATION / CLOSURE 7. ASSURANCE OF SAFETY MONITORING PROGRAMMES POST-CLOSURE AND INSTITUTIONAL CONTROLS ACCOUNTING / SECURITY / MANAGEMENT SYSTEMS 8. EXISTING DISPOSAL FACILITIES

  26. 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

  27. Progress in IAEA Requirements for Safety Case, Safety Assessment … • GSR Part 4: 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, 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.

  28. GSR Part 4: Overview of Safety Assessment 28

  29. 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 29

  30. Application • International level • Joint Convention • Regional level • International projects • IAEA or other technical assistance • Member States • Legal and regulatory framework • Development, operation and termination of facilities and activities overview of safety standards

  31. 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

  32. 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: 69 • Review meetings: • 1st review meeting: November 2003 • 2nd review meeting: May 2006 • 3rd review meeting: May 2009 • 4th review meeting: May 2012 overview of safety standards

  33. 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 33

  34. IAEA Technical Cooperation • Safety of Waste Management • Improving Waste Storage • Safety Assessment • Upgrading Safety of Disposal Facilities • Legal and Regulatory Frameworks (e.g. Georgia), etc. overview of safety standards 34

  35. Training Courses and Workshops • Safety of Radioactive Waste Management • Safety Assessment for Near Surface Disposal • Waste Acceptance Criteria • Legal and Regulatory framework • Decommissioning • Discharge Control • Remediation overview of safety standards

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

  37. 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, not a series of lectures! • 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

  38. Thank you This project is conducted by the IAEA, with funding by the European Union, among others.

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