Radioactive Waste and Spent Fuel Management activities in the IAEA

Transcription

1 Radioactive Waste and Spent Fuel Management activities in the Gérard Bruno Radioactive Waste and Spent Fuel Management Unit Department of Nuclear Safety and Security International Atomic Energy Agency

2 Contents activities in the Elements of radioactive waste management Waste classification Elements of safety demonstration

3 Waste Management at the Department of Nuclear Safety and Security Nuclear Installation Safety Radiation, Transport and Waste Safety Waste and Environmental Safety Section (safety standards development) Department of Nuclear Energy Nuclear Power Nuclear Fuel Cycle and Waste Technology Waste Technology Section Lecture 1 - International Safety Standards, Course, Clausthal 2010 (B Batandjieva) 3

4 DEVELOPMENT OF SAFETY STANDARDS

5 activities Waste and environmental safety section Statute: 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

6 Safety Standards Categories Fundamental Safety Principles Requirements Legal, Technical, & Procedural Safety Imperatives Safety Fundamentals Safety Requirements Guidance on Best Practice to Meet Requirements Safety Guides

7 Safety Fundamentals Policy document of the Safety Standards Series: States the basic objectives, concepts and principles involved in ensuring protection and safety 1 safety objective 10 safety principles

8 Safety fundamentals SF-1 Objective: Protect people and the environment from harmful effects of ionizing radiation Responsibility for safety Role of government Leadership and management for safety Justification of facilities and activities Optimization of protection Limitation of risks to individuals Protection of present and future generations Prevention of accidents Emergency preparedness and response Protective actions to reduce existing or unregulated radiation risks

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

10 Safety Guides Focus on How safety requirements can be met Guidance on best practices to meet requirements Use should statements

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12 Status of Safety Standards Safety standards are Binding for s own activities Not binding on the Member States (but may be adopted by them) EXCEPT in relation to operations assisted by the : Integrated Regulatory Review Service Technical Cooperation Fund work States wishing to enter into project agreements with the

13 Development of Safety Standards Commission & Committees 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)

14 Steps in the development process STEP 1: Preparing a DPP STEP 2: Internal review of the DPP STEP 3: Review of the DPP by the SSC(s) STEP 4: Review of the DPP by the CSS STEP 5: Preparing the draft safety standard STEP 6: First internal review of the draft safety standard STEP 7: First review of the draft safety standard by the SSC(s) STEP 8: Soliciting comments by Member States STEP 9: Addressing comments by Member States STEP 10: Second internal review of the draft safety standard STEP 11: Second review of the draft safety standard by the SSC(s) STEP 12: Review of the draft safety standard by the CSS STEP 13: Establishing as an safety standard (by the Publications Committee and/or Board of Governors (for SF and SR only)) STEP 14: Publication of the safety standard

15 Safety Standards: Predisposal é Predisposal management HLW of Rw from FCF DS 447 Predisposal Management of RW L/ILW form Reactors DS 448 To be combined with GS-G 3.4

16 Safety Standards for Disposal Near Surface Disposal DS 356 To be combined with GS-G 3.3 Monitoring and Surveillance DS 357

17 Safety Standards - Decommissioning To be combined (DS452) 2006, revision started in 2011 (DS450) Under discussion DS402 DS403 DS404 Decommissioning of Facilities Using NORM Under revision

18 Feedback and Review Feedback Safety standards survey: -Questionnaire (form) - Safety.Standards@iaea.org Review About every 5 years Revision of DPPs Following the process of standards' development (Committees, CSS, BOG, etc)

19 .where you can find the status of SS

20 APPLICATION OF SAFETY STANDARDS

21 Standards Application Dual Cask Models inter- SADRWMS CRAFT Assessment performance Generation DeSa/ FaSa Progress on the DeSa Project Impacts comparison evaluation ILW? ISAM/ Disposal ASAM/ PRISM B. Batandjieva, GEOSAF WSS, NSRW EMRAS I and II MODARIA HIDRA 3 rd EMRAS Project Meeting Safety Demonstration November Framework 2005,, for Vienna Management of Radioactive Waste and Decommissioning

22 SERVICES/ASSISTANCE TO MEMBER STATES

23 Yucca Mountain Site Characterisation Project (USA) Near Surface Disposal (Australia) -EC-Ukraine (WWER review, Ukraine) Site Characterisation (South Korea) and selection (Lithuania) COVRA activities (Netherlands) Disposal (Russia), etc. Peer Reviews 23

24 Safety of Waste Management Improving Waste Storage Safety Assessment Technical Cooperation National, Regional and Interregional projects Upgrading Safety of Disposal Facilities Legal and Regulatory Frameworks 24

25 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 Training Material (30 Modules) and Reference Syllabus Lecture 1 - International Safety Standards, Course, Clausthal 2010 (B Batandjieva) 25

26 Information Exchange 26

27 THE JOINT CONVENTION ON THE SAFETY OF SPENT FUEL MANAGEMENT AND ON THE SAFETY OF RADIOACTIVE WASTE MANAGEMENT

28 Joint Convention (Cont.) A legally binding agreement between CPs The first international binding legislation in the area of safety of spent fuel and radioactive waste management Based on the Safety Fundamentals for RWM (1995) An Incentive convention A sister convention of the Nuclear Safety Convention

29 Joint Convention (Cont.) Objectives of the JC: To achieve and maintain a high degree of safety worldwide in spent fuel and radioactive waste management, To ensure that there are effective defences against potential hazards so that individuals, society and the environment are protected now and in the future To prevent accidents and mitigate their consequences should they occur

30 Joint Convention (Cont.) 67 Countries ratified as of May 2013 Review meetings: 1 st review meeting: November nd review meeting: May rd review meeting: May th review meeting: May

31 Elements of radioactive waste management

32 Waste Arisings Radioactive waste arises from many different activities, for example: Operation and decommissioning of nuclear facilities (e.g. nuclear power plants); Application of radionuclides in industry, medicine, and research; Cleanup of contaminated sites; and Processing of raw materials containing naturally occurring radionuclides. 32

33 Elements of a Waste Management Programme Waste and materials Pre-treatment Effluent discharge Clearance Treatment Conditioning Recycling and re-use Storage Disposal 33

34 PREDISPOSAL MANAGEMENT 34

35 An important concept for waste management Waste minimization Source reduction Recycling and reuse of valuable materials Actions to reduce the volume of waste (e.g. compaction or incineration)

36 Waste Management Approaches (1) Delay and Decay hold waste in storage until sufficient decay has occurred for desired management approach

37 Waste Management Approaches (2) Dilute and Disperse discharge waste in a manner that environmental conditions reduce concentrations to acceptable levels

38 Waste Management Approaches (3) Concentrate and Contain reduce volume and condition and/or containerize waste to limit dispersion in the environment

39 Selection of Management Options Selected options must be consistent with National policies for waste management; Need to consider interdependencies with other predisposal and disposal options; Adequate characterization of waste is critical.

40 The Classification of Radioactive Waste

41 Waste Classification Purpose - for safety, engineering and regulatory aspects: Radioactive waste management strategies, planning and designing waste management facilities Facilitating record keeping and giving a broad indication of the potential hazards involved in the various types of waste at the operational level Communication between interested parties by providing well understood terminology (e.g., Joint Convention) 41

42 Different ways to classify waste By origin: Nuclear fuel cycle, isotope production,.. By physical state: Solid, liquid, gaseous By activity concentration: LLW, ILW, HLW By half-life: Short-lived waste, long-lived waste By Operational or disposal purposes, heat emitting or not 42

43 The Waste Classification GSG-1 Link between types of waste and management options Exempt waste (EW) Very low level waste (VLLW) Very short lived waste (VSLW) Low level waste (LLW) Intermediate level waste (ILW) High level waste (HLW)

44 Exempt Waste (EW) Waste that meets the criteria for clearance, exemption or exclusion from regulation control for radiation purposes as described in Safety Guide RS-G-1.7 Application of the Concepts of Exclusion, Exemption and Clearance (2004)

45 Very Low Level Waste (VLLW) Does not necessarily meet the criteria of exempt waste Does not need a high level of containment and isolation Suitable for disposal in near surface landfill type facilities with limited regulatory control Typical waste includes soil and rubble with low levels of activity concentration Concentrations of longer lived radionuclides are generally very limited

46 Very Short Lived Waste (VSLW) Waste that can be stored for decay over a limited period of up to a few years and subsequently cleared from regulatory control for uncontrolled disposal, use or discharge. This class includes waste containing primarily radionuclides with very short half-lives often used for research and medical purposes.

47 Low Level Waste (LLW) Above clearance levels, but with limited amounts of long lived activity Requires robust isolation and containment for periods of up to a few hundred years Suitable for disposal in engineered near surface facilities LLW cover a broad range of materials and may include: SL radionuclides at higher levels of activity concentration and LL radionuclides but at relatively low levels of activity concentration

48 Intermediate level waste (ILW) Greater degree of containment and isolation than that provided by near surface disposal But no provision for heat dissipation during storage and disposal May contain LL radionuclides, in particular alpha emitting radionuclides Will not decay, during the IC period, to level of activity conc. acceptable for NS disposal Disposal at greater depths than near surface disposal

49 High Level Waste (HLW) Levels of activity concentrations high enough to generate significant quantities of heat by the radioactive decay process or Large amounts of long lived radionuclides that need to be considered in the design of a disposal facility for such waste Disposal in deep, stable geological formations, usually several hundreds m or more is the generally recognized option for disposal

50 Activity content HLW high level waste (deep geologic disposal) ILW intermediate level waste (intermediate depth disposal) LLW low level waste (near surface disposal) VSLW very short lived waste (decay storage) VLLW very low level waste (landfill disposal) EW exempt waste (exemption / clearance) Half-life

51 WASTE TYPES & RELEVANT DISPOSAL OPTIONS VSLW VLLW LLW ILW HLW Activity, half-life

52 Broad Disposal Options Surface and near-surface disposal (with and without engineered barriers) up to 30m Underground cavities (natural or engineered) at few m to few 100 m Geological disposal (a mined facility) several hundreds of m Borehole disposal Other Exotic disposal options (either not considered credible or legal)

53 Waste Disposal Options Near-Surface Disposal Landfill Disposal Near-Surface Disposal 53

54 Waste Disposal Options (cont.) Geological Disposal

55 ELEMENTS OF SAFETY DEMONSTRATION

56 The concept of Safety Case The concept of Safety Case has been circulated for many years now. The NEA defines the Safety Case as : The synthesis of evidence, analyses and arguments that quantify and substantiate a claim that the repository will be safe after closure and beyond the time when active control of the facility can be relied on. defines it as the collection of arguments and evidence to demonstrate the safety of a facility. The SC has to be developed in the early phases of the development of a project. For the operator as a basis for internal decisions (R&D, site selection and evaluation, design conceptualization ) as well as for dialogue with the regulator

57 Project stages / time frame ? Concept Siting Development Operation Post closure Design Excavation IC Beyond IC Government Operator Regulator Safety Case

58 Use of the safety case Comparison of Options Prioritization of Site Characterization and R&D Facility Design and Operation Licensing Derivation of Limits and Conditions Monitoring

59 Stakeholder & Regulatory Involvement Iteration & Design Optimisation Safety Case Context Safety objectives Safety principles Regulations Safety Strategy Isolation, Containment Passive systems, robustness Defence in depth, demonstrability System Description Site and waste characteristics, Safety Functions, Design Options Management System Environmental Impact Assessments Post-Closure radiological impact Operational Safety Limits & conditions e.g. WAC Integration of Safety Arguments Demonstration of robustness, defence in depth system understanding, monitoring, etc Site / Engineering Management of Uncertainty Management System

60 Conclusion Safety is an essential component of waste management The is developing Safety Standards with the Member States Safety standards are continuously updated as necessary Feedback from the MS on their application is important

61 Thank you for your attention