IAEA International Atomic Energy Agency Technical Meeting on the Demonstration of Operational and Long Term Safety of Predisposal Management Facilities.

Slides:



Advertisements
Similar presentations
EMS Checklist (ISO model)
Advertisements

National Statement Country II. Current Status of the Country 1. Nuclear power stations are not planned in the county. 2. Widespread of SRS for industrial.
IAEA International Atomic Energy Agency. IAEA Outline Learning objectives Introduction Functions of Regulatory Body (RB) on EPR Appraisal guidance: Part.
Licensing of Nuclear Power Plants in Pakistan
School for drafting regulations Nuclear Safety Decommissioning Vienna, 2-7 December 2012 Tea Bilic Zabric.
INSAG DEVELOPMENT OF A DOCUMENT ON HIGH LEVEL SAFETY RECOMMENDATIONS FOR NUCLEAR POWER Milestone Issues: Group C. Nuclear Safety. A. Alonso (INSAG Member)
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.7 Commissioning Geoff Vaughan University of Central.
Regulatory Body MODIFIED Day 8 – Lecture 3.
Role of Independent Regulatory Body for Safe Operation of NPPs Zia Hussain Shah Director, Centre for Nuclear Safety Pakistan Nuclear Regulatory Authority.
Protection Against Occupational Exposure
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.
Ship Recycling Facility Management System IMO Guideline A.962
Authorization and Inspection of Cyclotron Facilities Authorization for the Decommissioning of the Facility.
IAEA International Atomic Energy Agency SAFETY REQUIREMENTS FOR PREDISPOSAL MANAGEMENT OF RADIOACTIVE WASTE Luc Baekelandt Safety.
Module 1.11 Management System Requirements Phil Metcalf Regional Training Course on Drafting Regulations on Waste Management and Public Exposure Including.
IAEA International Atomic Energy Agency LICENSING OF RADIOACTIVE WASTE MANAGEMENT FACILITIES Luc Baekelandt Safety of radioactive.
IAEA International Atomic Energy Agency David Bennett (David 14 – 18 December 2014 JAEC, Amman, Jordan National Policy and Strategies.
Segment SCD 4.3 Module SCD 4: Safety Case Segment SCD 4.3 Documentation and use of the safety case.
School for drafting regulations Nuclear Safety Operation Vienna, 26 November -7 December 2012 Tea Bilic Zabric.
IAEA International Atomic Energy Agency ESTABLISHING THE SAFETY INFRASTRUCTURE FOR A NUCLEAR POWER PROGRAMME IAEA WORKSHOP ON LEADERSHIP AND MANAGEMENT.
International Atomic Energy Agency IX.4.4. Pre-disposal waste management Safety Standards.
IAEA International Atomic Energy Agency. IAEA Outline Learning objectives Introduction Authorization Inspection Enforcement 2 Basic IRRS Training - Reviewing.
Programme Performance Criteria. Regulatory Authority Objectives To identify criteria against which the status of each element of the regulatory programme.
IAEA International Atomic Energy Agency. IAEA Outline Learning Objectives Introduction IRRS review of regulations and guides Relevant safety standards.
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.
IAEA International Atomic Energy Agency Summary and Overview of TECDOC Russel Edge Decommissioning and Remediation Unit Division of Radiation,Transport.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/1 Design Geoff Vaughan University of Central Lancashire,
MODULE “PREPARING AND MANAGEMENT OF DOCUMENTATION” SAFE DECOMMISSIONING OF NUCLEAR POWER PLANTS Project BG/04/B/F/PP , Programme “Leonardo da Vinci”
56th Regular Session of the IAEA General Conference
IAEA International Atomic Energy Agency School of Drafting Regulations – November 2014 Government and Regulatory Body Functions and Responsibilities IAEA.
Regulatory Framework for Uranium Production Facilities in the U.S.
Specific Safety Requirements on Safety Assessment and Safety Cases for Predisposal Management of Radioactive Waste – GSR Part 5.
Organization and Implementation of a National Regulatory Program for the Control of Radiation Sources Inspection Part III.
International Atomic Energy Agency Roles and responsibilities for development of disposal facilities Phil Metcalf Workshop on Strategy and Methodologies.
IAEA International Atomic Energy Agency IAEA Safety Standards for Research Reactors W. Kennedy Research Reactor Safety Section Division of Nuclear Installation.
International Atomic Energy Agency V. Nys Definition and practical application of demonstration of operational and long-term safety for predisposal RWM.
IAEA International Atomic Energy Agency Technical Meeting on the Demonstration of Operational and Long Term Safety of Predisposal Management Facilities.
International Atomic Energy Agency Regulatory Review of Safety Cases for Radioactive Waste Disposal Facilities David G Bennett 7 April 2014.
International Atomic Energy Agency School for Drafting Regulations on Radiation Safety RER/9/096 Vienna, 3 May, 2010 Adriana Nicic, Regulatory Activities.
International Atomic Energy Agency Meeting Summary Technical meeting of the International Project on Demonstration of Operational and Long-Term Safety.
Milestones for Nuclear Power Infrastructure Development Establishment of A Regulatory Framework Gustavo Caruso, Section Head, Regulatory Activities Section.
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.
IAEA International Atomic Energy Agency Technical Meeting on Regulatory Oversight of Human and Organizational Factors Vienna, Austria | December.
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. IAEA Outline Learning objectives Introduction Authorization Inspection Enforcement 2 Basic IRRS Training - Reviewing.
Role and Development of the Safety Case Components of the Safety Case.
International Atomic Energy Agency FUNDAMENTAL SAFETY PRINCIPLES AND ROLES OF ORGANIZATIONS IN THE DEVELOPMENT OF DISPOSAL FACILITIES Daniela E. Alvarez,
IAEA ASN – Paris1 Work group 1 Outcome of the discussions Topic 2 and 3.
International Atomic Energy Agency V. Nys Definition and practical application of demonstration of operational and long-term safety for predisposal RWM.
Organization and Implementation of a National Regulatory Program for the Control of Radiation Sources Program Performance Criteria.
By Annick Carnino (former Director of IAEA Division of Nuclear Installations Safety) PIME, February , 2012.
Nuclear decommissioning: Turning waste into Wealth
-EL ABBARI Younes, FADIL Najib (CNESTEN) -SADIQ Younes (AMSSNuR)
Module 2.5 – Predisposal Management of Radioactive Waste
Why is Licensing Process important?
THE ROLE OF TSOs IN THE NATIONAL SAFETY ORGANIZATION
IAEA Safety Guidance on Licensing and Oversight Activities
Communication and Consultation with Interested Parties by the RB
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.
IAEA General Conference Regulatory Cooperation Forum Regulatory Approach Prescriptive vs Performance Based David Senior Executive Director -
Regulatory Oversight of HOF in Finland
USNRC IRRS TRAINING Lecture18
SAFETY REQUIREMENTS FOR PREDISPOSAL MANAGEMENT OF RADIOACTIVE WASTE
IAEA International Workshop on Safe Disposal of LLW
Presentation transcript:

IAEA International Atomic Energy Agency Technical Meeting on the Demonstration of Operational and Long Term Safety of Predisposal Management Facilities for Radioactive Waste – 5-9 Oct Phil Metcalf Considerations in the safety case for the conceptualisation, siting, design, operation and decommissioning of RW management facilities

IAEA THE SAFETY CASE FOR PREDISPOSAL Role of the safety case Integrating relevant scientific (and other) information in a structured, traceable and transparent way, developing and demonstrating an understanding of the potential behavior and performance of the facilities Demonstrating that consideration has been given to the subsequent steps of management and their compatibility. Both short medium and long term aspects should be considered and the possible need for future handling and treatment of the waste and the risks and doses that may be associated with these activities. 2

IAEA THE SAFETY CASE FOR PREDISPOSAL Role of the safety case (cont.) Compatibility with a disposal option should be demonstrated, in the event that a disposal option has not been identified at that stage, assumptions should be made about the likely options and clearly set down. Identifying uncertainties in the performance of the facilities, describing the possible significance of the uncertainties, and identifying approaches for the management of significant uncertainties 3

IAEA THE SAFETY CASE FOR PREDISPOSAL Role of the safety case (cont.) Demonstrating operational safety and providing reasonable assurance that the facilities will perform in a manner that protects human health and the environment, and fulfil relevant criteria. Aiding decision making on the authorization / licensing of the facilities. Facilitating communication amongst stakeholders on issues relating to the facilities. 4

IAEA Regulatory process Establishment of standards, regulations, guidance Evaluation of “safety case” Determination of conditions for authorisation Authorisation Compliance assurance – routine reports, incident reports, inspection (routine, reactive, announced, unannounced) Licence termination 5

IAEA Regulatory Hold Points: Nuclear Installations 6

IAEA 7

StageConceptSitingDevelopment – design, construct Commission, operate DecommissionSite release Gover nmen t Establish operator and regulator Legislation Decision Oversight Custodianship? Assign responsibility Opera tor Establishment Identify options Start SC Develop siting process Investigate/rese arch Stakeholder Generic SC Propose site(s) R & D Design, construct, commissioning plan SA + SC for licence Stakeholder Commission Operate Surveillance Reporting Periodic safety review Finalise decommissioning plan Decommission Decommissioning report Terminate Care and maintenance Regul ator Establishment Input to legislation Standards Develop process Comment Interaction Guidance Comment Review SC Approve? Interaction Guidance Comment Review SC Approve Compliance assurance Approve modifications Review periodic safety review Approve Approve decommissioning plan Compliance assurance Release from regulatory control Terminate Advise to responsible authority Monitoring Safet y Case Structure Process to develop (+MS) Initial – basic elements Inform Site identified Concept design Safety assessment Management system Design, construction, commissioning Safety assessment Management system Update on the basis of modifications Present periodic safety review Decommissioning plans MS Decommissioning plan Waste management Site release Safety assessment MS Preserve knowledge Care and maintenance programme Safety case evolution 8

IAEA Concept ElementConsiderations Safety case contextLaws, licensing process, assessment approach Safety strategyPrinciples, design concept, waste product System descriptionConcept – site requirements Radiological impactStyalised Site/engineeringApproach; site investigation and facility design Non rad operationalStyalised Non rad environmentalStyalised Management systemOrganisation, resources, processes Limits controls conditionsConceptual – some generic Management uncertaintyApproach Iteration & design optimisationApproach Stakeholder / regulatory processesApproach Application of management system Arrangements 9

IAEA Site ElementConsideration Safety case contextSiting approach Safety strategySite influences System descriptionDegree of characterisation Radiological impactSite specific + styalised Site/engineeringCompatibility, suitability Non rad operationalSite + styalised Non rad environmentalSite + styalised Management systemFeedback, evolution Limits controls conditionsSite influence Management uncertaintyApplication to site investigation Iteration & design optimisationSite implications Stakeholder / regulatory processesInitiation and implementation Application of management systemOutcomes, feedback 10

IAEA Design ElementConsideration Safety case contextDesign approach constraints Safety strategyProven design, codes, innovation System descriptionFull description Radiological impactNormal, accidents, worker, public, environ Site/engineeringCompliance with requirements – waste product, operational safety, decommission Non rad operationalNormal, accidents, worker, public, environ Non rad environmentalNormal, accidents, worker, public, environ Management systemFeedback, evolution Limits controls conditionsFor commissioning and operation Management uncertaintyApplication to design Iteration & design optimisationImplementation Stakeholder / regulatory processesImplementation Application of management systemImplementation and feedback 11

IAEA Commissioning and operation ElementConsideration Safety case contextOperation – normal, incident, accident Safety strategyConfirmation – adequacy, compliance System descriptionFull description + operation + modification Radiological impactNormal, accidents, worker, public, environ Site/engineeringSurveillance (monitoring, testing, inspection), maintenance, upgrades Non rad operationalNormal, accidents, worker, public, environ Non rad environmentalNormal, accidents, worker, public, environ Management systemImplementation, feedback, evolution Limits controls conditionsOperating specifications, procedures, normal, incidents, emergencies - wac Management uncertaintyApplication full assessment Iteration & design optimisationModifications, periodic review Stakeholder / regulatory processesOn-going implementation Application of management systemImplementation and feedback 12

IAEA Decommissioning and site release ElementConsideration Safety case contextLegal/regulatory, policy, end state, finance Safety strategyImmediate, deferred, end state, WM strategy System descriptionEnd of life state – radiological status, proposed D & D Radiological impactNormal, accidents, worker, public, environ Site/engineeringProgressive system removal, new systems Non rad operationalNormal, accidents, worker, public, environ Non rad environmentalNormal, accidents, worker, public, environ Management systemModified organisation, implementation Limits controls conditionsFor decommissioning Management uncertaintyApplication to decommission & site release Iteration & design optimisationImplementation Stakeholder / regulatory processesImplementation Application of management systemImplementation and feedback 13

IAEA 14