International Atomic Energy Agency Disposal Facility & Engineered Barrier System (EBS) Design PRISM: Practical Illustration and use of the Safety Case Concept in the Management.
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International Atomic Energy Agency Disposal Facility & Engineered Barrier System (EBS) Design PRISM: Practical Illustration and use of the Safety Case Concept in the Management of Near-surface Disposal David Bennett 2 April 2009 Design Working Group • • • • • • • • • • • David Bennett Nadja Zeleznik Bernhard Großmnn Gyula Dankó Sandi Virsek Michael Tichauer Peter Salzer Janez Perko Dody Ivan Marija Kališnik Stasys Motiejunas [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] [email protected] International Atomic Energy Agency Working Group Objective • To share information and communicate good practice on: • How decisions on the design, extension and improvement of near-surface waste disposal facilities can be informed by, and justified using the Safety Case • How the Safety Case can be used on an ongoing basis to support management decisions on facility design and modification • We will also acknowledge the role of the EIA process in the early stages of facility design and implementation International Atomic Energy Agency Proposed Work Areas 1) Designing and upgrading near-surface radioactive waste disposal facilities using the safety case: 1a) Review of past and current practice on design • Will take examples from near-surface facilities in the WG’s experience • Will also seek information to cover a wider range of facilities and waste types • Will actively seek assistance from other project participants and relevant organisations • Have developed some terms of reference for this ‘data gathering’ • Will also review relevant IAEA and NEA documents International Atomic Energy Agency Proposed Work Areas 1b) Analysis of review findings to identify lessons on good practice in facility design • Have begun to identify and consider the many factors that affect facility design • Will describe expectations of facility design information at different stages of facility development • Will describe relationships between facility and EBS design and the safety case at different stages • Will discuss optimisation of EBS (ALARA) • e.g., iterative schemes International Atomic Energy Agency Terms of Reference for Data Gathering • • • • • • Safety / design philosophy • Both for operations and post-closure General description of facility development history, e.g: • • Waste type and inventory Influence of regulations/guidance Commentary on reasons for the design of each engineered component (e.g., package, backfill, walls, cap, drains etc) • e.g., size, shape, material, monitoring History of any design changes and their rationale Functions assigned to engineered components (if any) Treatment of barriers and barrier degradation in the safety case / assessment International Atomic Energy Agency Facilities Covered by Working Group • Dessel, Belgium • CSM, CSA, Morvilliers, France • Konrad, Germany • Püspökszilágy & Pecs, Hungary • Maišiagala & new prototype near-surface • • • repository, Lithuania Mochovce, Slovakia Slovenian silo concept LLWR, UK International Atomic Energy Agency Broadening Our Scope • Borehole facilities • Previous IAEA projects • South Africa, Russia, US • Mine tailings • Previous IAEA projects • Wismut? • Forsmark, Olkiluoto type facilities • Swedish/Finnish input • Cavern type facilities • Richard – Czech Republic? • ‘Deeper’ concepts for LLW/ILW? • France, Canada? International Atomic Energy Agency Requirements & Constraints on Design • • • • • • • • • • • • • • • • • • Safety requirements (e.g., dose constraint, ALARA) Design philosophy (passive safety, isolation, containment….) Waste type / characteristics Stakeholders (public, local communities, scientific community and committees, others) Past practice / experience Operational factors (e.g., infrastructure, waste handling, waste QA checking) Site characteristics Monitoring Knowledge of any pre-existing facilities on the site (disposal and other) Safety assessors, facility operators Availability of barrier materials & technology Barrier performance/degradation Safety assessment assumptions and results, existing WAC Project timescales and feasibility Allowing for flexibility and iterations of the safety case Costs vs benefits (of alternatives) Regulations Government & Policy International Atomic Energy Agency Design in the Facility Lifecycle • Stages (will vary by country and site) Design & assessment • • • • • • • Site screening, investigation, characterisation, selection Design options and concept selection Detailed design Construction Operational phase • • • • • Refinement of design Upgrading if necessary Closure Institutional Control overlap, iteration, variation in stages • Plan to discuss the design and related safety case activities for each stage Will consider a range of facility types Will consider the relative importance of various factors & influences on design at each stage Will work closely with Group 1 on timeline International Atomic Energy Agency Planning • Roles and responsibilities of group members • • defined and agreed Provisional schedule outlined Deliverables identified International Atomic Energy Agency Provisional Schedule • Terms of reference for data gathering • • • • (drafted Apr 2009) Data gathering (by Oct 2009) Working group meeting to discuss findings and begin drafting report (Nov-Dec 2009) Improve report draft of report (Spring 2010) Presentations to next plenary in Spring 2010 • Workshop style day International Atomic Energy Agency Main Deliverables • Terms of reference for data gathering • Notes on relevance to the group’s work of • • existing IAEA and NEA documents Papers on various disposal facilities Table of contents for report • 2 part structure as described above • Detail to be developed • 1st Draft of report International Atomic Energy Agency International Atomic Energy Agency Issues List • Project website • Project newsletter • Draft IAEA safety guides International Atomic Energy Agency Interfaces with other WGs • Generic WAC • Design changes to manage uncertainties International Atomic Energy Agency Roles & Responsibilities • Review of ISAM, ASAM documents and other IAEA documents on engineered barriers, facility closure and design • • • • • Put relevant documents on website (all) TR433, upgrading of NS repositories, SR35,surveillance and monitoring of NS repositories, ASAM cross-cutting report on engineered barriers Be aware of draft safety guides (DS334, 354, 355, 357) (SM / all) Close cooperation with Group 1 at early stage (DB) Data gathering on our facilities (all) • • Send results to DB by 30 September, copy to others in group Everyone to read before group meeting International Atomic Energy Agency Roles & Responsibilities • Arrange next group meeting (DB, DI?) • IAEA funding support (DB,JR) • 2 or 3 days to discuss findings and lessons • Prepare 1st draft of report (DB, GD, JP, PS) • Begin drafting at the meeting and continue after • Rest of group will review • Presentations to next plenary (all data • gatherers, authors) Ongoing communication with other groups via plenarys and Coordinating Committee International Atomic Energy Agency