Status of the IAEA safety standards and Relation to the CRAFT … Documents/2012 Technical... ·...
Transcript of Status of the IAEA safety standards and Relation to the CRAFT … Documents/2012 Technical... ·...
IAEA International Atomic Energy Agency
Technical Meeting
Practical Application of
Safety Assessment
Methodologies
(CRAFT Project)
IAEA Headquarters, 11-15 June 2012 Monika Kinker
Radioactive Waste and Spent Fuel Management Unit
Division of Radiation, Transport and Waste Safety - NSRW
Status of the IAEA safety standards and
Relation to the CRAFT project
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• Support to Member States in establishing proper safety framework for management of radioactive waste and spent fuel:
Development of Safety Standards
Provisions for use and application of Safety Standards
Joint Convention on the Safety of Spent Fuel and Radioactive Waste Management
Radioactive Waste and Spent Fuel
Management Unit
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http://www-ns.iaea.org/standards/default.asp
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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
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Development of Safety Standards
Outline and work plan Prepared by the Secretariat
Review by the Safety Standards Committees and the Commission on Safety Standards
Drafting or revising of safety standard
by the Secretariat and Consultants
Review by the Safety
Standards Committee(s)
Endorsement by Commission on Safety Standards
Member States
Approval by the IAEA’s Director General or BoG *
* Safety Requirements approved by BoG
* Safety Guides approved by DG
Member States = YOU !
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)
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New Structure of the Safety Standards
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Safety Standard Categories
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Safety Case &
Assessment
Predisposal
DS 284
Small
Generators RW
Storage
Classification
2010
2009
2006
2008
Management
Systems
L/ILW Reactors
DS 448
HLW FCFs
DS 447
RW in the Safety Standards
Spent Fuel
Storage
2012
Fundamental
Safety Principles
DS 454
2011
(2012?)
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Safety Standards: Predisposal RWM
Safety Case, Safety Assessment
Safety Case, Assessment Predisposal
DS 284
2009 2009
(2012?)
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1. Government responsibilities 2. National Policy & Strategy
3. Regulatory Responsibilities
4. Operator Responsibilities
5. Safety/Security
6. Interdependences
7. Management systems
8. Waste minimization
9. Characterization and classification
10. Waste treatment
11. Waste storage
12. Waste acceptance for processing, storage and/or disposal
13. Prepare safety case and supporting safety assessment
14. Safety case scope and regulatory compliance
15. Safety case documentation
16. Periodic safety review
17. Facilities location and design
18. Facility construction and commissioning
19. Facilities operation, maintenance, emergency preparedness
20. Decommissioning
21. Nuclear safeguards
22. Existing facilities
GSR Part 5, Safety Requirements for
Predisposal Management of RW
1. Introduction
2. Protection of
Human Health &
Environment
3. Responsibilities
4. Steps in the
Predisposal
Management of
RW
5. Development and
Operation of RWM
Facilities &
Activities
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DS 284: Safety Guide for SC and SA
1. Introduction
2. Demonstrating the Safety of Predisposal Management of Radioactive Waste
3. Objectives and Development of the Safety Case for Predisposal
4. Safety Assessment
5. Specific Issues
6. Documenting and Using the Safety Case
7. Regulatory Review Process
Annex A EXAMPLES OF HAZARDS AND INITIATING EVENTS
Annex B TOPICAL ISSUES FOR THE SAFETY ASSESSMENT REVIEW FOR RADIOACTIVE WASTE PREDISPOSAL FACILITIES AND ACTIVITIES
Annex C TEMPLATE OF REGULATORY REVIEW REPORT
Annex D SADRWMS
Safety Case &
Assessment
Predisposal
DS 284
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IAEA Requirements for
Safety Case, Safety Assessment …
• GSR Part 5, DS284: 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 , DS284: 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.
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Safety Assessment
Ma
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yste
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En
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Non
rad
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Radiological
Impact
Scenarios
Models
Calculations
Safety Assessment: GSR Part 4, DS284
DS284
GSR Part 4
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The safety case for a predisposal radioactive waste management
facility shall include a description of how all the safety aspects of the
site, the design, operation, shutdown and decommissioning of the
facility, and the managerial controls satisfy the regulatory
requirements. The safety case and its supporting safety assessment
shall demonstrate the level of protection provided and shall provide
assurance to the regulatory body that safety requirements will be met.
• Design and operation considered and justified in the safety case
• Primary aim to ensure safety objectives and criteria set by regulatory body are met
• The safety case addresses operational safety and all safety aspects of the facility and activities
• Considerations for reducing hazards to workers, public and environment - normal operation and accident conditions
• Commensurate with the complexity of the operations and the magnitude of the hazards
GSR Part 5, Requirement 14:
Scope of the Safety Case and Regulatory Compliance
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DS284: Components of the
Safety Case and Safety Assessment
Safety Assessment
Ma
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Non
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dio
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nviro
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imp
act
Op
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fety
Radiological Impact
Scenarios
Models
Calculations
Safety Case
Safety Assessment
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• In order to provide additional guidance on
the level of depth and detail warranted for
safety cases, it was proposed that the IAEA
would develop illustrative safety reports
with example safety cases
-> CRAFT PROJECT
DS284:
Proposal to June 2010 WASSC for Approval
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International Intercomparison and
Harmonization Projects
• CRAFT (successor to SADRWMS) • SADRWMS Methodology and SAFRAN Tool
• Illustrative examples to complement SG (DS284)
• PRISM • Safety case
• Barrier performance
• WAC
• Uncertainty
• GEOSAF • Regulatory expectations throughout development and operation
• Review process
• Assessment – engineering, site, radiological impact, integration
• Working Group for the Dual Use Cask for Spent Nuclear Fuel • Safety case
• extended periods of storage and meeting transport requirements
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Long-term Project • 1st Plenary Meeting in 2003
• Final Plenary in 2011,
numerous consultancies,
workshops
Objectives: 1. EXAMINE the application of
safety assessment
methodology (ISAM, ASAM)
2. DEVELOP, document • Safety Assessment
Methodology
• Regulatory Review
• ---> DS284…
3. INTEGRATE methodology
into software tool (SAFRAN)
SADRWMS Project Safety Assessment Driving Radioactive Waste Management Solutions
Safety Case &
Assessment
Predisposal
DS 284
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http://www-ns.iaea.org/tech-areas/waste-safety/sadrwms/default.asp?s=8&l=69
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SADRWMS Project Results
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SAFRAN Tool
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CRAFT (Complimentary Safety Reports, Development and
Application to Waste Management Facilities)
3 Year Project • 1st Plenary Meeting May 2011
• Regional Meetings in • Stockholm Oct 2011
• Vietnam May 2012
Objectives: 1. APPLY DS284, SADRWMS
methodology & SAFRAN Tool
2. PROVIDE a forum for application
of the methodology and SAFRAN tool
3. DEVELOP, document Safety Reports illustrating
application of DS284 • Facility/process specific
• Safety Case Process/Regulatory Review
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Fukushima Accident: WASSC
Discussions on Lessons Learnt
GSR Part 5 • Requirement 12 (WAC)
• No change required
• Application implies consideration of other
parameters when developing the SC for wastes
arising from an accident or remediation activities
• Could imply re-examination of safety cases for
existing facilities to accept wastes arising from
accidents or need of new facilities
• Examples of its application to be included in
lower tier documents
IAEA 23 Thank you!