1. Overview of IAEA Safety Standards regarding radioactive waste management Yumiko Kumano ARAB 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 Waste Tunis, 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
Fundamental Safety Principles
Requirements – Legal, Technical, & Procedural Safety Imperatives
Safety Fundamentals
Guidance on Best Practice to Meet Requirements
Safety Requirements
Safety Guides

8. Safety Fundamentals Safety Fundamentals Safety Requirements
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
Safety Requirements
Safety Guides
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9. 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 Guides
Safety Requirements
Safety Fundamentals
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10. Safety Guides Focus on ‘How’ safety requirements can be met
Guidance on best practices to meet requirements
Use “should” statements
Safety Guides
Safety Requirements
Safety Fundamentals
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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
Outline and work plan
Prepared by the Secretariat
Review by the Safety Standards Committees
and the Commission on Safety Standards
Commission
on Safety Standards
(CSS)
Nuclear Safety Standards
Committee
(NUSSC)
Radiation Safety Standards
(RASSC)
Waste Safety Standards
(WASSC)
Transport Safety Standards
(TRANSSC)
Drafting or revising
of safety standard
by the Secretariat and Consultants
Review
by the Safety
Standards
Committee(s)
Member
States
Review period: about every 5 years
Endorsement
by Commission on Safety Standards
Approval by the IAEA’s
Director General or BoG *
* Safety Requirements approved by BoG
* Safety Guides approved by DG
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13. Overview of IAEA Safety Standards
Emergency preparedness & response
Management systems
Assessment & verification
Site evaluation
Radiation safety
Radioactive waste management
Decommissioning
Rehabilitation of contaminated areas
Thematic Areas
Nuclear power plants
Research reactors
Fuel cycle facilities
Radiation related facilities & activities
Waste treatment and disposal facilities
Facilities & Activities
Safety Fundamentals: Current Structure
Legal & governmental infrastructure
Transport of radioactive material
overview of safety standards

14. Fundamental Safety Principles
Safety Objective
The fundamental safety objective is to protect people and the environment from harmful effects of ionizing radiation.
Safety Fundamentals
Safety Requirements
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
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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
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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.
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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.
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19. Current status of development of IAEA Safety Requirements
2010
Under development
Under development
Published in
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 448
DS 447
DS 454
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21. GSG-1: Classification of RW

22. Safety Standards - Disposal
Site Aspects
Design
Construction
Operation
Closure
Post Closure
Safety Assessment
Management System
Near Surface disposal
of RW
DS 356
Specific Safety Guide
Monitoring and Surveillance of Disposal Facilities
DS 357
Specific Safety Guide
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23. Safety Standards - Disposal
SSR-5
Disposal of RW
DS 356
Near Surface Disposal
SSG-23
SC and SA for disposal
SSG-14
Geological Disposal
Near Surface disposal
of RW
DS 356
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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 : safety case/safety assessment
Req : Design and construction
Req. 18: Operation of a disposal facility
Req. 20: Waste acceptance
Req. 21: Monitoring programmes
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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 Assessment28

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
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32. WES coordinates as the Secretariat of the Joint Convention
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
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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.
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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.
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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
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36. Information Exchange
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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!
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38. Thank you
This project is conducted by the IAEA, with funding by the European Union, among others.