Safety Case Components and Documentation

Slides:



Advertisements
Similar presentations
Fieldwork assessment The difference between AS and A2 David Redfern
Advertisements

D:\data\PowerPoint\Maravic\NCP-EURATOM Meeting - CCAB ppt Slide 1 National Contact Points for EURATOM- Information Exchange Meeting October 16,
Specific issues to be considered in the safety case.
Disposal Facility & Engineered Barrier System (EBS) Design PRISM: Practical Illustration and use of the Safety Case Concept in the Management of Near-surface.
School for drafting regulations Nuclear Safety Decommissioning Vienna, 2-7 December 2012 Tea Bilic Zabric.
Presentation on recent IAEA activities on RWM Y. Kumano WES / NSRW
SÄTEILYTURVAKESKUS STRÅLSÄKERHETSCENTRALEN RADIATION AND NUCLEAR SAFETY AUTHORITY Protection of the environment from ionising radiation - views of a regulator.
MODULE “STRATEGY DEVELOPMENT”
ToR of GEOSAF2 WG on Operational Safety Review of WG2.
Challenges in developing a Safety Case WG5. How to Develop a Safety Case SC can be a tool for providing information to stakeholders other than regulators.
IAEA International Atomic Energy Agency International Workshop on the Safe Disposal of Low Level Radioactive Waste WG3 debriefing.
Definition, Role and Documentation of the Safety Case: Quick Review
Safety Assessment Methodologies and Implementation of Monitoring and Control Programmes Dr. Japie van Blerk AquiSim Consulting (Pty) Ltd Wednesday, 24.
TM Technical Meeting on the Disposal of Intermediate Level Waste
IAEA Technical Meeting on Future Human Actions at Disposal Sites IAEA, Vienna, Austria September 24-28, 2012 Overview of NRC Approach to Human Intrusion.
IAEA International Atomic Energy Agency LICENSING OF RADIOACTIVE WASTE MANAGEMENT FACILITIES Luc Baekelandt Safety of radioactive.
IAEA International Atomic Energy Agency LICENSING OF RADIOACTIVE WASTE MANAGEMENT FACILITIES, part 2 Luc Baekelandt Safety of.
Segment SCD 4.3 Module SCD 4: Safety Case Segment SCD 4.3 Documentation and use of the safety case.
International Atomic Energy Agency IX.4.4. Pre-disposal waste management Safety Standards.
MODULE “PROJECT MANAGEMENT AND CONTROL” SAFETY ASSESSMENT DURING DECOMMISSIONING SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP ,
Nicolas Solente Workshop on Regulatory Requirements to Ensure Safe Disposal of Disused Sealed Sources for Operators and Regulators Amman, JORDAN 7-11 April.
IAEA ANSN RWMTG National Workshop: Application of IAEA Methodology and Tools for the Safety Case and Safety Assessment for Predisposal Management of Radioactive.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
Evaluation of the radiological consequences of tritium present in radioactive components from fusion reactors Task TW4-TSW-001-D1b: Waste and decommissioning.
IAEA International Atomic Energy Agency Roger Seitz Lucy Bailey HIDRA Human Intrusion in the context of Disposal of RadioActive waste Closing Summary for.
David G Bennett December 2014
International Atomic Energy Agency Group 3 Moderator: Jack Rapporteur: Joerg.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
International Atomic Energy Agency Roles and responsibilities for development of disposal facilities Phil Metcalf Workshop on Strategy and Methodologies.
International Atomic Energy Agency Definition and overview of required safety documentation (e.g., safety case and safety assessment) Phil Metcalf Workshop.
-1- UNRESTRICTED / ILLIMITÉ Demonstrating the Safety of Long-Term Waste Management Facilities Dave Garrick 2015 September.
International Atomic Energy Agency Regulatory Review of Safety Cases for Radioactive Waste Disposal Facilities David G Bennett 7 April 2014.
Safety-related Issues for the Disposal of Intermediate Level Waste (ILW) Dr. Jürgen Wollrath Federal Office for Radiation Protection (BfS) Department Safety.
IAEA International Atomic Energy Agency Technical Meeting on the Demonstration of Operational and Long Term Safety of Predisposal Management Facilities.
Working Group 3 Murmansk. SC structure – Assessment context has to be more elaborate and detailed – Optimization. Provide justification based on the document.
WG2. §1. Introduction Simplification of the introduction, e.g.: – New structure 1.Background 2.Objectives 3.Scope – Synthesize some of the information.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Siting Strategies.
IAEA International Atomic Energy Agency Monika Kinker Radioactive Waste and Spent Fuel Management Unit Division of Radiation, Transport and Waste Safety.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Requirements for.
SITEX WP2.1 NEEDS FOR TECHNICAL GUIDANCE F. Lemy - F. Bernier - 1GEOSAF II TM – SITEX WP2.1 – 28/05/2014.
IAEA International Atomic Energy Agency Roger Seitz Potential Working Groups.
Role and Development of the Safety Case Components of the Safety Case.
IAEA International Atomic Energy Agency MANAGEMENT OF THE REVIEW PROCESS Luc Baekelandt Safety of radioactive waste management.
Development of a disposal concept WG5. How to deal with the RP Principle Need to educate the public to put the risks in context Public want to see the.
IAEA International Atomic Energy Agency TM Technical Meeting to Discuss Human Intrusion and Future Human Actions in relation to Disposal of Radioactive.
IAEA ASN – Paris1 Work group 1 Outcome of the discussions Topic 2 and 3.
IAEA International Atomic Energy Agency Presenter Name School of Drafting Regulations for Borehole Disposal of DSRS 2016 Vienna, Austria Developing a safety.
Danyl Pérez Sánchez CIEMAT-SPAIN
Structure of a Safety Case (NEA). The Multibarrier Concept each barrier acting passively in concert with the others to isolate, contain and reduce impacts.
International Atomic Energy Agency V. Nys Definition and practical application of demonstration of operational and long-term safety for predisposal RWM.
In the name of God. Common Technical Document On Biotech.
1 Introduction to safety case and safety assessment: purpose and content of safety case Ian Crossland Crossland Consulting
1 Waste volumes and categories Low active waste Medium active waste High active waste Short livedCategory A Category C Long livedCategory B Category C.
Technical Services. Objectives To identify the technical services needed within the infrastructure for an effective implementation of regulatory programme.
NRCan Community Roundtable Presentation Meliadine Gold Project Rob Johnstone Deputy Director Sustainable Mining and Materials Policy Division Minerals,
The Safety Case Radioactive Waste and Spent Fuel Management Unit
-EL ABBARI Younes, FADIL Najib (CNESTEN) -SADIQ Younes (AMSSNuR)
Report on the outcome from the consultancy
J. Scott Kirk, CHP Vice President of Licensing & Regulatory Affairs
South Carolina Perspective on Part 61 Proposed Revisions
HSE Case: Risk Based Approach.
Earl Fordham, Deputy Director, Office of Radiation Protection
Joint WG on Guidance for an Integrated Transport and Storage Safety Case for Dual Purpose Casks TM TM to Produce Consolidated Drafts of the IAEA’s.
For more information, please visit the CAST website at:
Intrusion scenarios in radwaste repositories
Introduction: IAEA activities / Documents on human intrusion
Status of the IAEA safety standards and Relation to the CRAFT project
Addressing Future Human Actions for Safety Assessment
Integrated Safety Assessment as an Instrument for Waste Acceptance Criteria Derivation The inventory and maximal specific activity of radionuclides are.
TM Technical Meeting on the Disposal of Intermediate Level Waste
Presentation transcript:

Safety Case Components and Documentation David G Bennett 8 April 2014

Safety Case Components

Safety Case Context The safety case context comprises: Regulatory requirements and criteria for the safety case The particular decision step in the lifecycle of the disposal facility Key disposal system characteristics e.g. the nature of the waste and the site The purpose of the safety assessment The assessment timeframes Assessment philosophy (e.g. conservative, realistic) Assessment end-points (e.g. dose, risk, fluxes, others)

Safety Strategy The safety strategy comprises: The high-level approach for achieving safe disposal The overall management strategy for the activities required in planning, operation and closure of a disposal facility The preferred strategy for the management of all radioactive waste is containment and isolation from the accessible biosphere [SSR-5] The set of intended safety functions the timeframes over which they will be available explanation of system robustness and defence in depth

System Description The system description: Related terms: Provides information on the disposal system Demonstrates system understanding Provides the basis for safety assessment Helps to determine needs for further system characterisation and facility design work Related terms: The system description includes much of what is sometimes called the “assessment basis” or the “phenomenological basis” Also closely related to the “site descriptive model”

System Description The system description should provide information on: The facility design and the reasons for its selection The “near-field”: The wastes (e.g., origin, quantities, properties, radionuclide inventory), The engineering (e.g., waste conditioning and packaging, disposal units, engineered barriers, disposal facility cap, drainage) The zone disturbed by excavations The “far-field” - e.g., geology, hydrogeology, geochemistry, tectonic and seismic conditions, erosion rates The “biosphere” - e.g., climate and atmosphere, water bodies, human activities, biota, surface geology, topography

Safety Assessment

Limits, Controls and Conditions The safety case should be used to assist in the establishment of limits, controls and conditions, e.g: Site-specific limits on the total waste inventory, on acceptable concentration levels for specific radionuclides in the waste, and other waste acceptance criteria (WAC) Particularly relevant for near-surface disposal facilities Controls and conditions on repository construction and on the manufacture, materials and quality of engineered barriers and their emplacement Conditions for a monitoring and surveillance programme

Integration of Safety Arguments Showing that safety assessment results comply with regulatory criteria is not sufficient Multiple lines of reasoning should be used, including discussion of: The use of best available techniques The history of design optimisation Waste isolation and containment Passive safety Robustness and defence in depth QA and peer review Conservatisms in safety assessment Natural (and other) analogue information Application of limits, controls and conditions

Integration of Safety Arguments In summary, the safety case should: synthesise the available evidence, arguments and analyses highlight the principal reasons why planning, development and use of the disposal system should continue acknowledge any limitations of currently available evidence describe the approach that will be used to manage any open questions and uncertainties

Safety case documentation Clear Logical structure Transparent Traceable Should always explain why? Need to include accurate summary documents Written for their intended audience(s)