THE IAEA SAFETY ASSESSMENT EDUCATION AND TRAINING PROGRAMME (SAET)

Transcription

1 THE IAEA SAFETY ASSESSMENT EDUCATION AND TRAINING PROGRAMME (SAET) The Safety Assessment Education and Training (SAET) Programme has been designed to support the Member States with development of required safety assessment capacity and competency. The Programme provides for courses and training necessary to achieve knowledge of safety requirements associated with the design and operation of nuclear facilities, and focuses on development of specialized knowledge essential for assessment and evaluation of safety including performance of safety analyses. SAET takes its roots from the IAEA Safety Standards, especially the Fundamental Safety Principles and the Safety Assessment for Facilities and Activities Requirements. The SAET programme content is based on international best practices and expertise. It sets high educational standards and its elements are compatible with academic course requirements. The training programme addresses education and training needs for a wide range of personnel, from those with little or no experience in safety assessment to those seeking to gain specialized expertise in certain areas of safety assessments. Incorporating a broad scope of safety assessment training modules, the multi-level programme is organized to accommodate the training of staff from differing professional backgrounds and educational levels. The safety assessment knowledge is organized in a modular way, so that training programmes for safety analysts, for professionals focusing on regulatory reviews, as well as for management and other decision-making personnel can be tailored based on actual needs. Essential Knowledge I. Fundamentals of Safety Assessment II. Deterministic Safety Assessment IV. Integrated Risk-Informed Decision-Making III. Probabilistic Safety Assessment Practical Applications II.B - Design Basis Analysis II.C - Beyond Design Basis Analysis III.A - Level I PSA III.B - Level II PSA IV. IRIDM III.C - Level III PSA

2 SAET ESSENTIAL KNOWLEDGE The safety assessment knowledge modules are divided into two groups: essential knowledge and practical applications. The essential knowledge curriculum addresses the fundamental aspects of safety assessment, providing the basis for subsequent specialized training in the areas of deterministic and probabilistic safety assessment. As seen in the previous diagram, the Essential Knowledge Programme is composed of four topics: Fundamental Knowledge Deterministic Safety Assessment (DSA) Probabilistic Safety Assessment (PSA) Integrated Risk Informed Decision Making (IRIDM) Training in this curriculum will provide regulators, operators and TSOs with the knowledge necessary for undertaking informed decision-making in their countries. A table demonstrating the content, estimated modular training durations and the IAEA Safety Standards and technical documents upon which the programme is based is provided below and more detailed content outlines for each module follow. SAET ESSENTIAL KNOWLEDGE MODULE

3 WORKSHOPS PLANNED IN 2011* 1 ST Quarter 2011 Fundamental Knowledge Workshop on Fundamental Safety Assessment Knowledge Workshop on Generic Reactor Safety Review Methodology 2 nd Quarter Safety Analysis I & VI Workshop on Introduction to DSA and PSA Workshop on Integrated Risk Informed Decision-Making (IRIDM) 3 rd Quarter 2011 Safety Analysis II & III Workshop on DSA Methodology (Design Basis) Workshop on Level 1 PSA Methodology 4 th Quarter 2011 Safety Analysis IV & V Severe Accident Analysis Level 2 PSA *Workshop durations are of one week each. Venues to be announced.

4 FUNDAMENTAL KNOWLEDGE Preparing for Safety Analysis Scope of safety assessment Responsibility for the safety assessment Purpose of the safety assessment Radiation protection Addressing radiation risks Timing and update of safety assessments Determination of provision of adequate defence in depth Verification of calculational methods and computer codes Process of safety assessment Results of the safety assessment Preparation for the safety assessment Expertise and skills needed Information Tools Safety criteria defined in national regulations Deterministic and probabilistic approaches General features of DSA General features of PSA Criteria for judging safety

5 INTRODUCTION TO DSA AND PSA Introduction to Deterministic Safety Assessment Introduction to Deterministic Safety Assessment Deterministic Safety Assessment Scope of Deterministic Safety Assessment Deterministic Analysis: Summary of Technical Areas and Overview of Codes Approaches to Deterministic Assessment Fundamentals of Nuclear System Modelling Basic Code Modelling Introduction to Probabilistic Safety Assessment Introduction to Probabilistic Safety Assessment Probabilistic Safety Assessment Basic Concepts Scope of Probabilistic Analysis Fundamentals of System Modelling and Analysis Intro to Level 1 PSA Intro to Level 2 PSA Intro to Level 3 PSA

6 DSA METHODOLOGY (Design Basis) Deterministic Safety Analysis Methodology overview Scope of safety analysis Approaches for DSA and consideration of conservative assumptions Identification and categorization of initiating events Acceptance Criteria Computer Codes Deterministic Safety Analysis preparation Tools for DSA Verification and Validation of Computer Codes, QA of computer codes, Code user requirements and training Model building data collection, database, engineering handbook, QA programme, model qualification (SETs, ITF, operational events) Deterministic Safety Analysis performance Qualification of computer codes (range of application) Code user qualification and user effect Basic steps in analysis Treatment of uncertainties Sensitivity analysis Deterministic Safety Analysis evaluation Presentation and evaluation of the results Assessment of the fulfilment of related acceptance criteria, Quality assurance Deterministic Safety Analysis areas of application Design Licensing Emergency Operating Procedures and plant simulators PSA supporting analysis Accident Management and Emergency planning PSR Operational events Regulatory audit calculations Regulatory review of the deterministic safety analysis Legislative framework Independent verification of the results by licensee Process of review Technical support to regulator Outcomes of the regulatory review

7 LEVEL 1 PSA METHODOLOGY Introduction to PSA Basic concepts and techniques. Level-1 PSA Organization, management and tasks outline. Level-1 PSA tasks Analysis of initiating events and accident sequences modelling System Analysis Exercices (FTs, ETs, MCSs, boolean logic, etc) Reliability and statistical data analysis. Analysis of dependencies including common cause failures Human Reliability Analysis PSA quantification and Analysis of results. PSA software Probabilistic analysis of Internal hazards Fire PSA Flood PSA PSA for other internal hazards Probabilistic analysis of external hazards Introduction to Seismic PSA PSA for other External hazards PSA for low power and shutdown operation modes Overview of Level 2 and Level-2 PSA Level 2 PSA Assessment of Large radioactive releases Overview of Level 3 PSA Assessment of off-site consequences PSA and DSA Role of deterministic calculations in PSA Integration of deterministic and probabilistic safety assessment Use of PSA Applications of PSA by NPP Operators Living PSA and Risk Monitors Applications of PSA by designers Regulatory uses of PSA Risk informed decision making Recent IAEA publications in the area of PSA Exercises on Level-1 PSA

8 SEVERE ACCIDENTS Introduction to Severe Accidents In-vessel Phenomena Primary system thermal hydraulics Core degradation phenomena Corium behaviour in the lower head Ex-vessel Phenomena Containment thermal hydraulics Aerosol and Iodine behaviour Melt behaviour Modelling and Analyses of Severe Accidents Modelling of Severe Accident Phenomena Modelling of the in-vessel phenomena Modelling of the ex-vessel phenomena Severe Accident Codes Detailed codes Integral codes Dedicated codes Application of Severe Accident Analyses Application and usage of severe accident analyses Accident Progression & Source Term Analysis

9 LEVEL 2 PSA Role of Level 2 PSA concepts in Risk-Informed Regulation Level 2 PSA Process (major tasks & interfaces) Level 1-2 Interface Definition of Plant Damage State (PDS) Initial and boundary conditions needed to conduct a Level 2 PSA Techniques for transferring results of a Level 1 PSA into PDSs Accident progression modelling and containment analysis Analysis of containment performance during severe accidents Analysis of the progression of severe accidents Probabilistic framework for characterizing plant response to severe accidents Accident Progression Event Tree (APET) or Containment Event Tree (CET) Development and quantification of CET (APET) Techniques for quantifying basic events within the CET/APET Source Term Assessment Definition of the release categories Grouping of containment event tree end states into release categories Source term analysis Results of the source term analysis Quantification / Sensitivity and Uncertainty Analysis Level-2 PSA quantification Sources of uncertainties in Level-2 PSA Sensitivity and uncertainty analyses Appropriate method for addressing uncertainties in characterizing plant performance in response to severe accidents Format & Content of typical Level 2 PSA Results Typical metrics for expressing the results of a Level 2 PSA Documentation and interpretation of Level-2 PSA results Use and Application of Level-2 PSA Risk informed decision making approach Comparison with probabilistic safety criteria Design evaluation Severe accident management Emergency planning Off-site consequences (Level 2/Level3 PSA interface) Other PSA applications Safety Assessment and Verification with Level 2 PSA

10 INTEGRATED RISK-INFORMED DECISION MAKING Integration of PSA and DSA Advantages and limitations of DSA Advantages and limitations of PSA Integration process Expected benefits Framework of IRIDM process INSAG-25 Guideline for IRIDM process Draft TECDOC Integrated Risk Informed Decision Making Guidance IRIDM: use by operator IRIDM: use by regulator IRIDM in specific applications categories Support for increasing revenue Enhancing safety Regulatory activities support IRIDM in specific applications categories Practical examples of decisions made in Member States with the application of IRIDM

11 IAEA SAFETY ASSESSMENT EDUCATION AND TRAINING PROGRAMME (SAET) For additional information, please contact S. Michael Modro, Safety Assessment Section, NSNI