1. IAEA Approach to the Safety Case and Safety Assessment for Predisposal Management of Disused Sealed Radioactive Sources and Radioactive Waste
INT9176 INTERREGIONAL WORKSHOP
Application of the IAEA Methodology and SAFRAN Tool for the Safety Case and Safety Assessment for Predisposal Management of DSRS
Monika Kinker, WES/NSRW

2. INT9176 “Mediterranean Project”
Objectives
Improved capacities and capabilities for the cradle to grave management of SRS
Staff of RBs & DSRS management organizations trained in … SA methodologies and tools
Key Activities Implemented: Safety Demonstration
Implementation in SAFRAN Tool of a Generic SC & SA for Predisposal Management of DSRS
Provision of Assistance in the development of SC and SA for DSRS end of life management options
Original MSs : Slovenia, Croatia, Albania, Bosnia and Herzegovina, Cyprus, Greece, Malta, Montenegro, Turkey, Lebanon, Egypt, Libya, Morocco, Tunisia.
Joined the project in 2012: Ghana, Tanzania, Nigeria, Jordan, and The Frmr.YugRep. of Macedonia
Did not join yet, but invited: Algeria, Israel, Syria

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 and Waste Technology
Waste Technology Section
overview of safety standards

4. Activities of the Division
Safety Standards Development
Support for International Conventions
Joint Convention, Code of Conduct
Application of Standards:
Information Exchange (e.g. Conferences, workshops, meetings, ...)
Technical Cooperation
Training & Education
Appraisals, Peer Reviews
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5. 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.

6. 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

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
Principle 7: Protection of present and future generations. People and the environment, present and future, must be protected against radiation risks
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. 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

14. Life Cycle of a Radiation Source
The parts of the lifecycle in which RS are most under control (for commercial reasons) include
- Manufacturing (production of radionuclide, encapsulation, equipment manufacturing)
- Distribution to users (transportation, storage)
- Application period (medical therapy, industry, etc)
The parts of the lifecycle during which control becomes weaker, with the potential that control is lost (resulting in sources becoming orphan sources) include the “transition period(s)” when they are not under a dedicated WMO system, and when they become disused or spent
The transition period includes: Transportation, Temporarily out of use, Waiting for another application/user, or are Taken out of use but no plans for further management/disposition

15. Issues in Long Term management of DSRS
Waste or Resource?
Disused Source: “a radioactive source which is no longer used, and is not intended to be used, for the practice for which an authorization has been granted” (Code of Conduct)
Radioactive Waste: “Radioactive material in gaseous, liquid or solid form for which no further use is foreseen…, and which is controlled as radioactive waste by a regulatory body under the legislative and regulatory framework …” (Joint Convention)

16. Disused sources in the Safety Standards

17. 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

18. 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

19. 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

20. 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)

21. Sustainable Management
Requires:
Adequate Legal and Regulatory Framework
National Policy, Strategies that consider
Existing, future inventories
COMPLETE lifecycle
Adequate Resources and Infrastructure (technical, human, financial)
Regulatory Body with well defined responsibilities and functions
Authorization through process of licensing 21

22. RWM Licensing, Authorization in the Safety Standards
2010
2013 22 22

23. IAEA Requirements for RW Safety Case, Safety Assessment …
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.
GSR Part 4 , GSG-3: Safety Assessment
1. Assessment of all aspects of a practice that are relevant to protection and safety; includes siting, design & operation of the facility. This normally includes 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.

24. GSG-3: Safety Guide Proposal to June 2010 WASSC -> CRAFT
Demonstrating the Safety of RWM
Safety Case
Role, Components, Documentation and Use
Safety Assessment
Approach, Scenarios, Models, Analysis of Results
Specific Issues
SC evolution, graded approach, DID, facility lifetime, LTS
Regulatory Review Process
Annex I Examples of Hazards and Initiating Events
Annex II Topical Issues for Review of SC
Annex III Template of Regulatory Review Report
Annex IV SADRWMS Project
Proposal to June 2010 WASSC
-> CRAFT
NEW!!!

25. GSG-3: Guidance on the SC and SA
Safety Case
Safety Assessment
Safety Assessment
Management System
Site and Engineering
Non radiological environmental impact
Operational Safety
Radiological Impact
Scenarios
Models
Calculations 25

26. Elements of Safety Case: GSG-3
INCLUDES: Context; safety strategy; facility description; safety assessment; limits, controls and conditions (LCOs); iteration and design optimization; uncertainty management; integration of safety arguments
NOT SPECIFIED but implied: criticality, radiation, hazardous material, surveillance & maintenance, emergency preparedness and response, decommissioning, management systems, interface with LCOs from other facilities (e.g., waste acceptance criteria)

27. CRAFT (Complimentary Safety Reports: Development and Application to Waste Management Facilities)
4 Year Project
1st Plenary May 2011
2nd, 3rd Plenaries 2012, 2013
Final Plenary October 2014
Objectives:
APPLY GSG-3, SADRWMS methodology, SAFRAN Tool
PROVIDE a forum for application of the methodology and SAFRAN tool
DEVELOP, document TECDOCs illustrating application of GSG-3
Facility/process specific
Safety Case Process/Regulatory Review 27

28. SADRWMS Project Safety Assessment Driving Radioactive Waste Management Solutions
Long-term Project
1st Plenary Meeting in 2003
Final Plenary in 2010
Objectives:
1. EXAMINE the application of safety assessment methodology (ISAM, ASAM)
2. DEVELOP, document
Safety Assessment Methodology
Regulatory Review
---> GSG-3
3. INTEGRATE methodology into software tool (SAFRAN)

29. CRAFT Working Methods Radon Type Facility Application Case
develop illustrative test case(s) for applying the IAEA methodology/tools to RADON type facilities (basis: RW retrieval activity at Murmansk RADON);
Storage and Processing Facility
Apply IAEA methodology/tools to facilities for the storage and processing of RW
Central Storage Facility in Slovenia,
Waste Processing Facility in Serbia,
LTS Facility in Cuba
Regulatory Interactions
Apply IAEA methodology/tools in regulatory review of WG application cases, and provide recommendations 29

31. 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 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

32. 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

33. Thank you!