Status of the IAEA safety standards and Relation to the CRAFT project
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1 Status of the IAEA safety standards and Relation to the CRAFT project Technical Meeting Practical Application of Safety Assessment Methodologies (CRAFT Project) IAEA Headquarters, June 2012 Monika Kinker Radioactive Waste and Spent Fuel Management Unit Division of Radiation, Transport and Waste Safety - NSRW IAEA International Atomic Energy Agency
2 Radioactive Waste and Spent Fuel Management Unit 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 IAEA 2
3 IAEA 3
4 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 IAEA 4
5 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) 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 Nuclear Safety Standards Committee (NUSSC) Radiation Safety Standards Committee (RASSC) Waste Safety Standards Committee (WASSC) Member States = YOU! Transport Safety Standards Committee (TRANSSC) Approval by the IAEA s Director General or BoG * * Safety Requirements approved by BoG * Safety Guides approved by DG IAEA 5
6 New Structure of the Safety Standards IAEA 6
7 Safety Standard Categories IAEA 7
8 RW in the Safety Standards 2010 Fundamental Safety Principles Classification Management Systems Small Generators DS 454 RW Storage Spent Fuel Storage FCFs HLW DS 447 L/ILW Reactors DS 448 (2012?) Safety Case & Assessment Predisposal IAEA DS 284 8
9 Safety Standards: Predisposal RWM Safety Case, Safety Assessment (2012?) Safety Case, Assessment Predisposal DS 284 IAEA 9
10 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 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 IAEA 10
11 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 Safety Case & Assessment Predisposal DS 284 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 IAEA 11
12 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. IAEA 12
13 Management System Non radiological environmental impact Safety Assessment: GSR Part 4, DS284 DS284 Safety Assessment GSR Part 4 Radiological Impact Scenarios Models Calculations Operational Safety Site and Engineering IAEA 13
14 GSR Part 5, Requirement 14: Scope of the Safety Case and Regulatory Compliance 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 IAEA 14 14
15 DS284: Components of the Safety Case and Safety Assessment Management System Non radiological environmental impact Safety Case Safety Assessment Safety Assessment Radiological Impact Scenarios Models Calculations IAEA 15 Operational Safety Site and Engineering
16 DS284: Proposal to June 2010 WASSC for Approval 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 IAEA 16
17 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 IAEA 17
18 SADRWMS Project Safety Assessment Driving Radioactive Waste Management Solutions Long-term Project 1 st 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 ---> DS INTEGRATE methodology into software tool (SAFRAN) Safety Case & Assessment Predisposal DS 284 IAEA 18
19 IAEA 19
20 SADRWMS Project Results SAFRAN Tool IAEA 20
21 CRAFT (Complimentary Safety Reports, Development and Application to Waste Management Facilities) 3 Year Project 1 st 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 IAEA Safety Case Process/Regulatory Review 21
22 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 22
23 IAEA Thank you! 23
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