Safety Assessment of Nuclear Power Plants to Assist ... · ⇒ No. NS-G-1.2 “Safety Assessment and Verification for Nuclear Power Plants” ... Training material Lecture notes for

IAEA Workshop Training Course

Safety Assessment of Nuclear Power Plants to Assist Decision Making

XX Month – XX Month Year

(City Country)

WWOORRKKSSHHOOPP MMAANNUUAALL

Prepared/Modified: XX/XX/200X

Workshop Manual – Country 200X Based on Standard Training Event No-X

CONTENT

WORKSHOP PLAN .......................................................................................................................1

Aims and objectives of the workshop .........................................................................................1 Intended countries .......................................................................................................................2 Participants ..................................................................................................................................2 Workshop structure .....................................................................................................................2

WORKSHOP SYLLABUS.............................................................................................................1

LECTURE PLAN ...........................................................................................................................4

WORKSHOP PROGRAMME 1st WEEK, xx-xx Month Year.................................................19

WORKSHOP PROGRAMME 2nd WEEK, xx-xx Month Year................................................20

RESPONSIBILITIES....................................................................................................................21

Responsibility of the Workshop Director .................................................................................21 Responsibility of the IAEA Technical Officer..........................................................................21

TECHNICAL ASPECTS ..............................................................................................................22

Faculty.......................................................................................................................................22 Equipment and supplies ............................................................................................................22 Identity badges and certificates .................................................................................................22 Exposure control .......................................................................................................................22 Training material for the participants........................................................................................22

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WORKSHOP PLAN

Aims and objectives of the workshop

The main aims of the workshop are to provide the participants with the knowledge and tools to be able: (a) To develop and implement a deterministic safety assessment of a nuclear power plants, (b) To develop and implement a probabilistic safety assessment of a nuclear power plants, and (c) To develop an integrated safety assessment of a nuclear power plants, taking into account both

deterministic and probabilistic approaches. Learning objectives are as follows. By the end of the workshop, the participants will: ⇒ Understand the basic concepts of safety objectives and requirements, regulation and standards. ⇒ Understand the basic principles of Dephence-in-deph and Safety Margins and Safety Culture

philosophy. ⇒ Understand the safety assessment process performed of General Design Aspects and Plant

Modifications: single failure, redundancy, independence, diversity, system interactions and dependencies.

⇒ Understand a Integrated Safety Assessment Program. ⇒ Understand the safety assessment process performed during renewal of Operating Licence and

Periodic Safety Reviews. ⇒ Understand the approaches applied in accident analysis: Design Basis Accidents and Incidents,

Beyond Design Basis Accidents and Severe Accidents. Computer Codes. Verification and Validation. Conservative and Best-estimate approaches.

⇒ Understand the Sensitivity and Uncertainty Analysis and Quality Assurance requirements. ⇒ Understand the Probabilistic Safety Analysis (PSA) objectives, methodology, structure, scope and

tasks. ⇒ Understand PSA applications: Technical Specifications, Test and In-service Inspection intervals, Risk

Monitors, etc. ⇒ Understand the Integrated decision making process and the Risk-Informed Licensing Framework. ⇒ Be familiar with IAEA documents that can be used in developing safety assessments to include:

⇒ SS No. 75 – INSAG-4 “Safety Culture” ⇒ No. GS-G-1.2 “Review and Assessment of Nuclear Facilities by the Regulatory Body” ⇒ No. NS-G-1.2 “Safety Assessment and Verification for Nuclear Power Plants” ⇒ No. NS-G-2.3 “Modifications to Nuclear Power Plants” ⇒ No. NS-G-2.10 “Periodic Safety Review of Nuclear Power Plants” ⇒ SS No. 50-P-01 “Application of the Single Failure Criterion” ⇒ SS No. 50-P-04 “Procedures for Conducting PSA of NPP (Level 1)” ⇒ SS No. 50-P-01 “Procedures for Conducting PSA of NPP (Level 2)” ⇒ SS No. 50-P-01 “Procedures for Conducting PSA of NPP (Level 3)” ⇒ TECDOC 1101 “A framework for a Quality Assurance Programme for PSA” ⇒ TECDOC 1162 “Living Probabilistic Safety Assessment (LPSA)” ⇒ TECDOC-1144 “Probabilistic Safety Assessments of Nuclear Power Plants for Low Power

and Shutdown Modes” ⇒ TECDOC-1200 “Applications of Probabilistic Safety Assessments (PSA) for Nuclear Power

Plants” ⇒ TECDOC-1229 “Regulatory Review of Probabilistic Safety Assessments (PSA) Level 2”

⇒ Know the means by which the IAEA can assist in development of national capabilities

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Intended countries

The workshop is intended for countries with nuclear power plants with safety assessment responsibilities.

Participants

Countries wanting to participate in the workshop should nominate a team of proposed participants composed of (as appropriate): 1. A regulator responsible for safety assessment of nuclear power plants, 2. A member of nuclear power plants staff familiar with its operations and who is responsible for safety

assessment, and 3. A member of other organisations involved in the licensing, design, engineering, etc who is

participating in safety assessment activities.

Workshop structure

The workshop will be held for 2x5 working days (2 weeks) and it is structured in the following way:

Opening of the workshop

1st week Lecture sessions

2nd week Lecture sessions

Evaluation of the workshop

Closing of the workshop

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WORKSHOP SYLLABUS The workshop syllabus has a modular structure. It is divided into parts, modules and lessons. Part is a generic term to describe main blocks of training. It is built of modules. The term module is used to describe a specific narrow block of training. Modules are further divided into learning units – lessons. Lesson can be a whole or a part of a lecture, exercise, technical visit, video presentation, assessment session or any combination of these activities. The workshop syllabus follows the structure of IAEA Safety Guide No. NS-G-1.2 Syllabus for training in Safety Assessment and Verification for Nuclear Power Plants. BLOCK A Training Administration PART I OPENING AND CLOSING SESSIONS Modules I 1 Opening

I 1_1 Registration session I 1_2 Formal opening session I 1_3 Training information session

I 2 Closing

I 2_1 Closing session BLOCK B – Lecture Sessions PART II BASIC CONCEPTS Modules II 1 Defence-In-Depth and Safety Culture

Lessons II 1_1 Safety Objectives II 1_2 The defence-in-depth concept and applications II 1_3 Safety culture

II 2 Needs for Safety Assessment

Lessons II 2_1 Licensing and renewing of operating license II 2_2 Periodic safety review II 2_3 Plant modification, upgrading and modernisation projects II 2_4 Assessment of operational experience II 2_5 Updating of safety analysis report II 2_6 Updating of operational limits and conditions, EOPs, etc.

II 3 The Safety Assessment Process

Lessons II 3_1 Designer/Utility/Operator perspective II 3_2 Regulatory perspective

II 4 General Approach and Criteria

Lessons II 4_1 Basic safety standards II 4_2 Approach and objectives

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PART III ENGINEERING ASPECTS OF SAFETY ASSESSMENT Modules III 1 Safety Assessment of General Design Aspects

Lessons III 1_1 Implementation of defence-in-depth III 1_2 Proven practices and experience, incl. conservative approach and safety margins III 1_3 Conformance with codes, standards, guides III 1_4 Single failure assessment and redundancy/independence/diversity; fail safe design III 1_5 System interactions and dependencies III 1_6 Man-machine interface III 1_7 Equipment qualification III 1_8 ISI, monitoring, maintenance and repairs III 1_9 Ageing and surveillance

PART IV SAFETY ANALYSIS Modules IV 1 Event Classification

Lessons IV 1_1 Postulated initiating events, identification, internal and external initiating events IV 1_2 Anticipated operational occurrences IV 1_3 Design basis accidents IV 1_4 Beyond design basis accidents and severe accidents

IV 2 Overview of Deterministic Safety Analysis

Lessons IV 2_1 Areas of analysis (thermal-hydraulics, neutronics, structural, etc. IV 2_2 Computer codes and applications IV 2_3 Input data preparation IV 2_4 Verification and Validation IV 2_5 Conservative and best estimate approaches (incl. Various applications of both approaches) IV 2_6 Sensitivity and uncertainty analysis (incl. User effects) IV 2_7 Quality assurance in safety analysis

IV 3 Overview of Probabilistic Safety Analysis (PSA)

Lessons IV 3_1 Basic concepts and techniques (fault trees, event trees, etc.) IV 3_2 Level 1 analysis, CDF calculations IV 3_3 Level 2 analysis, large release probability IV 3_4 Level 3 analysis, off-site consequences IV 3_5 Data requirements IV 3_6 Role of deterministic calculations in PSA IV 3_7 Special issues: common cause failures, human reliability analysis, propagation of uncertainty, internal and external hazards, etc. IV 3_8 Verification and Validation IV 3_9 Living PSA IV 3_10 PSA for Low Power and Shutdown modes IV 3_11 PSA Applications

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BLOCK C – Practical Sessions PART EX EXERCISES Demonstrations

V II2D_1 Integrated Safety Assessment Program for Krsko Modernisation Project V II2D_2 Krsko NPP Periodic Safety Review

Summary of activities

Sessions Duration [hrs]

Opening and closing 3 Lectures 47 Exercises 3 Assessment 1

Sum 54

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LECTURE PLAN BLOCK A Workshop Administration I 1_1 Lesson Registration session Purpose To register participants

To distribute training and other materials and identity badges Duration [hrs] ½ Resources Appropriately prepared classroom, training and other materials, identity badges I 1_2 Lesson Formal opening session Purpose To welcome guests and participants

To declare the workshop opened Learning objectives To feel welcomed by the IAEA and by the host country

To be aware of Agency’s expectations of the participants To feel inspired to learn, ask questions, and make contacts

Content Welcome addresses General introduction to the training Agency’s expectations of the participants

Duration [hrs] ½ Training material None References None Resources Appropriately prepared and equipped lecture room for 30 participants and guests I 1_3 Lesson Training information session. Presentation/Discussion Purpose To present basic information (training aims, training plan, training programme, training

material, administration and logistic arrangements) To check if all training material is available

Learning objectives To know the training aims To be informed on the training plan To be familiar with the training administration and logistic arrangements To be informed on training material received To get to know other participants – participants introduce themselves

Content Aims of the training within the overall framework of safety assessment of NPPs Training plan and programme Training administration and logistic arrangements (inc. food, travel, accommodation, payments, social events, etc.) Self introduction of the participants

Duration [hrs] ½ for I 1_3.1,I 1_3.2, I 1_3.3 and I 1_3.4 Training material Programme, list of participants, checklist for training administration and logistic

arrangements References None Resources Computer projector, overhead projector, screen, PC, PowerPoint 2000®

I 2_1 Lesson Formal closing session Purpose To deliver closing addresses

To deliver certificates of attendance To close the training

Learning objectives To be encouraged to continue activities started at the training Content Closing addresses by host country and IAEA representative

Presenting training Certificates Duration [hrs] 1 Training material None References None Resources Training Certificates

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BLOCK B Lecture Sessions II 1_1 Lesson Safety Objectives Purpose To present and explain the Safety objectives and Requirements, regulation, Guides and

Standards Learning objectives To be able to differentiate between nuclear safety and radiological protection objectives

To know legal requirements pyramid To understand responsibilities of different organisations To understand safety culture concept To know regulatory approaches: licensing vs. inspection

Content IAEA Safety Standards for design of NPPs Legal basis and Regulatory Framework Example of a specific country practice

Duration [hrs] 1 Training material Lecture notes for Lesson II 1_1 References INTERNATIONAL ATOMIC ENERGY AGENCY, No. GS-G-1.2 “Review and

Assessment of Nuclear Facilities by the Regulatory Body”, IAEA, Vienna (2002) Resources Computer projector, screen, PC, PowerPoint 2000®

II 1_2 Lesson Defence in Depth. Purpose To present and explain the basic principles of safety assessment Learning objectives To know the basic idea of multiple level of protection

To be able to list typical physical barriers To be able to understand management measures

Content Type of barriers Barriers independence Continuous safety enhancement Accident management Operating procedures Off-site emergency response

Duration [hrs] ½ Training material Lecture notes for Lesson II 1_2 References None Resources Computer projector, screen, PC, PowerPoint 2000®

II 1_3 Lesson Safety Culture Purpose To present and explain the safety culture concept Learning objectives To know Safety culture principles Content Features of Safety culture

Implementation in different groups of Organisations Duration [hrs] ½ Training material Lecture notes for Lesson II 1_3 References INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Series, No. 75.-.INSAG-4

“Safety Culture”, IAEA, Vienna (1991) Resources Computer projector, screen, PC, PowerPoint 2000®

II 2_1 Lesson Needs for Safety Assessment. The Safety Assessment Process. Regulatory view Purpose To present and explain the needs for safety assessment and the safety assessment process

under a regulatory point of view Learning objectives To understand the goals for safety assessment

To know the Plant related areas subject to safety assessment To understand the deterministic and probabilistic approaches

Content Plant related areas requiring safety assessment Deterministic and probabilistic approaches Risk-Informed approach Review and assessment during Plant life cycle Example of Slovene practice

Duration [hrs] 1½ Training material Lecture notes for Lesson II 2_1 and II 3_2 References None Resources Computer projector, screen, PC, PowerPoint 2000®

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II 2_2 Lesson Licensing Renewal of Operating License. Periodic Safety Review. Regulatory point

of view Purpose To present main purposes for periodic safety Review from a regulatory point of view Learning objectives To know NPPs license constrains during operating period

To understand regulatory framework that supports periodical safety review process Content Regulatory responsibilities

Type of licenses for NPPs along its life cycle Periodical safety reviews Example

Duration [hrs] 2 Training material Lecture notes for Lesson II 2_2 References INTERNATIONAL ATOMIC ENERGY AGENCY, No. NS-G-2.10 “Periodic Safety

Review of Nuclear Power Plants”, IAEA, Vienna (2003) Resources Computer projector, screen, PC, PowerPoint 2000®

II 2_3 Lesson Safety Assessment Process. Plant Modification. Regulatory point of view Purpose To present and explain basic principles for safety assessment of Plant modifications from

Regulatory point of view Learning objectives To understand the responsibilities of different organisations involved in safety assessment

process To understand the basic process of modifications

Content Safety asssessment tasks and participants Basic roles and responsibilities Example of a specific country approach

Duration [hrs] 2 Training material Lecture notes for Lesson II 2_3 References INTERNATIONAL ATOMIC ENERGY AGENCY, No. NS-G-1.2 “Safety Assessment

and Verification for Nuclear Power Plants”, Vienna (2001) INTERNATIONAL ATOMIC ENERGY AGENCY, No. NS-G-2.3 “Modifications to Nuclear Power Plants”,, Vienna (2001)

Resources Computer projector, screen, PC, PowerPoint 2000®

II 3_1 Lesson Use and Conduct of Safety Analysis Purpose To present main purposes for safety assessment Learning objectives To understand what is a safety assessment

To understand different types and Plant stages for safety assessment Content IAEA an Legal requirements

How is safety assessed Allowable limits Examples of Plant safety assessments

Duration [hrs] 2 Training material Lecture notes for Lesson II 3_1 References INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Standard 50-SG-G2

“Information to be Submitted in Support of Licensing Applications for Nuclear Power Plants”, IAEA, Vienna (1979) INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Standard DS309 “Format and Content of Safety Analysis Reports for NPPs”, IAEA, Vienna (Draft)

Resources Computer projector, screen, PC, PowerPoint 2000®

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III 1_1 Lesson Safety Assessment of General Design Aspects of NPPs (Part 1) Purpose To explain and discuss safety assessment process of general design aspects of NPPs. Learning objectives To have an historical perspective of reasons and milestones of nuclear safety evolution

To understand defence in depth concept and related single failure criteria To understand basis and approaches applied to maintain design margins To know the hierarchy of safety codes, standards and guides

Content Nuclear safety evolution Defence in depth principle Safety margins principle Conformance with regulations, codes and standards

Duration [hrs] 2 Training material Lecture notes for Lesson III 1_1 References None Resources Computer projector, screen, PC, PowerPoint 2000®

III 1_2 Lesson Safety Assessment of General Design Aspects of NPPs (Part 2) Purpose To explain and discuss safety assessment process of general design aspects of NPPs. Learning objectives To deep into single failure criterion

To know differences between redundancy, independence and diversity To know fail-safe concept To understand system interactions and dependencies

Content Single failure criterion Redundancy Independence Diversity Fail-safe design Interactions and dependencies Failure Mode and Effect Analysis

Duration [hrs] 2 Training material Lecture notes for Lesson III 1_2 References None Resources Computer projector, screen, PC, PowerPoint 2000®

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IV 1 Lesson Safety Analysis. Event Classification Purpose To explain the safety analysis process and system of event classification for deterministic

safety analysis Learning objectives To understand the legal basis of safety analysis and international common safety

principles To understand the role of design basis events into safety analysisTo be able to classify postulated initiating events into different groupsTo understand the use of acceptance criteria

Content Deterministic safety analysis approach Normal operation events Anticipated operational occurrences Accidents and beyond design basis accidents Grouping by expected frequency Deterministic/probabilistic analysis

Duration [hrs] 2 Training material Lecture notes for Lesson IV 1_1 and IV 1_2 References None Resources Computer projector, screen, PC, PowerPoint 2000®

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IV 2_1 Lesson Overview of Deterministic Safety Analysis (Part 1) Purpose To present and explain the different areas of analysis (thermal-hydraulic, neutronics, etc.)

and the computer codes used Learning objectives To be aware of different evaluation methodologies applied in safety analysis

To understand different areas to be calculated within safety analysis To understand the difference between conservative and best estimate analysis To have a view of the different type of codes employed and their areas of application

Content Evaluation Models Thermal-hydraulic, neutronic, structural and radiological calculations Conservative/BE analysis Computer codes and applications

Duration [hrs] 1½ Training material Lecture notes for Lesson IV2_1 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 2_2 Lesson Overview of Deterministic Safety Analysis (Part 2) Purpose To present and explain requirements for input data preparation, and verification and

validation of computer codes, and to deep into conservative/BE approaches Learning objectives To be aware of requirements for preparation of data to be input in safety analysis

To understand processes of verification and validation applied in the different phases of life cycle of computer codes To deep and understand the difference between conservative and best estimate approaches

Content Criteria used in the preparation of input data Verification and validation of computer codes Conservative/BE approaches

Duration [hrs] 2 Training material Lecture notes for Lesson IV2_2 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 2_3 Lesson Overview of Deterministic Safety Analysis (Part 3) Purpose To present and explain the sensitivity and uncertainty analysis performed and the quality

assurance requirements Learning objectives To be aware of uncertainty and sensitivity analysis requirements in safety analysis

To understand differences between uncertainty and sensitivity analysis To be aware of CSAU methodology To have a view of the user effect To know the QA requirements of evaluation models

Content Sensitivity and uncertainty analysis Sources of uncertaintiy Code, Scaling, Applicability and Uncertainty (CSAU) Evaluation Methodology Quality Assurance Plan and process

Duration [hrs] 2 Training material Lecture notes for Lesson IV2_3 References None Resources Computer projector, screen, PC, PowerPoint 2000®

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IV 3_1 Lesson Probabilistic Safety Analysis (PSA) Fundamentals and Overview Purpose To present and explain the fundamentals of Probabilistic Assessment Methodology and its

relationship with the Deterministic Approach Learning objectives To get an global overview of PSA approach and scope

To understand differences between probabilistic techniques and reasons for the specific approach implemented in a PSA model To be aware of relevance of adequate definition of PSA boundaries To have a view of reliability basic concepts and reliability data requirement To know the most usual PSA organisation by Tasks and different PSA scopes

Content PSA terminology Boolean concepts Inductive and deductive methods Reliability basic principles Quality Assurance process requirements

Duration [hrs] 1 Training material Lecture notes for Lesson IV 3_1 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_2.1 Lesson Initiating Event Analysis Purpose To present and explain the Initiating Event (IE) Analysis Task Learning objectives To get an global overview of IE Analysis Task within PSA Tasks framework

To understand IE Analysis Task objectives and IE concept To be aware of IE identification approaches To have a view of grouping criteria To know the most usual IE examples and typical mistakes

Content IE definition IE identification Safety functions and system requirements IE grouping IE mutually exclusive criteria

Duration [hrs] 1 Training material Lecture notes for Lesson IV 3_2.1 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_2.2 Lesson Accident Sequence Analysis Purpose To present and explain the Accident Sequence (AS) Analysis Task Learning objectives To get an global overview of Accident Analysis Task within PSA Tasks framework

To understand Accident Analysis Task objectives To understand Safety Function and Success Criteria concepts To know the significance of a good dependency and human action representation To understand Core Damage and Plant Damage State concepts

Content Safety Function and Success Criteria Event Tree (ET)models. ET headings Accident Sequence techniques Event Tree/Fault Tree interface Plant Familiarisation


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IV 3_2.3 Lesson System Analysis Purpose To present and explain the System Analysis Task Learning objectives To get an global overview of System Analysis Task within PSA Tasks framework

To understand System Analysis Task objectives To understand Fault Tree Methodology and representation To know basic Boolean algebra To understand System Analysis Task process To understand Fault Tree Linking Method and Accident Sequence Interface

Content Front Line and Support Systems Fault Tree Methodology Boolean Laws and Operators Cutsets and Core Damage Equation


IV 3_3 & 4 Lesson Overview of Level 2 and Level 3 PSA Purpose To present an Overview of Level 2 and Level 3 PSA Tasks Learning objectives To get an global overview of Level 2 and Level 3 Task within PSA Tasks framework

To understand Level 2 PSA methodology (CET; DET; STC;etc) To know specific Codes used for Level 2 PSA To understand Level 3 PSA methodology To know specific inputs required for Level 3 PSA To know specific Codes used for Level 3 PSA To know possible countermeasure emergency actions

Content Plant Damage State Containment Event Tree Containment failure modes Severe Accident Phenomena Decomposition Event Tree Source Term analysis Complementary Cumulative Distribution Function

Duration [hrs] 1 Training material Lecture notes for Lesson IV 3_3 and IV 3_4 References IAEA Safety Series No. 50-P-8 and 50-P-12 Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_5 Lesson Reliability Data Analysis Purpose To present and explain the Reliability Data Analysis Task Learning objectives To get an global overview of Reliability Data Analysis Task within PSA Tasks

framework To understand Reliability Data Analysis Task objectives To know type of Reliability Data required within a PSA To know the sources of Reliability Data To understand Plant information gathering process to obtain reliability data

Content Sources of Reliability Data Component unavailability models Data gathering process


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IV 3_7.1 Lesson Human Reliability Analysis Purpose To present and explain the Human Reliability Analysis Task Learning objectives To get an global overview of Human Reliability Analysis Task within PSA Tasks

framework To understand Human Reliability Analysis Task objectives To understand Fault Tree Methodology and representation To know basic Boolean algebra To understand human action classification To understand SHARP framework

Content Types of human error Performance shaping factors Behaviour types Representation methodologies Quantification methodologies


IV 3_7.2 Lesson Common Cause Failure Analysis Purpose To present and explain the Common Cause Failure (CCF) Analysis Task Learning objectives To get an global overview of CCF Analysis Task within PSA Tasks framework

To understand CCF Analysis Task objectives To understand CCF significance and types of dependencies modelled within a PSA To know CCF experience To understand CCF parametric models of quantification

Content CCF root cause and coupling mechanism CCF parametric models Basic parameter, β-factor, alpha factor, MGL and BFR models


IV 3_7.3 Lesson PSA Quantification. Interpretation of results: importance, uncertainty and sensitivity analysis

Purpose To present and explain the PSA Quantification Task Learning objectives To get an global overview of PSA Quantification and Importance, uncertainty and

sensitivity analysis Tasks within PSA Tasks framework To understand PSA quantification and importance, uncertainty and sensitivity analysis Task objectives To understand quantification principles and algorithms To know Core Damage Frequency determination process To understand main Importance measures To understand sensitivity and uncertainty analysis

Content Minimal Cut Set Rare Event and Minimal Cut Set Upper Bound approximations Truncation/Cut off Delete Term approach


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IV 3_7.4 Lesson Internal and External Hazard Analysis Purpose To present and explain the Internal and External Hazard Analysis Learning objectives To get an global overview of Internal and External Hazard Analysis within PSA

framework To understand specific characteristics of Internal and External Hazard Analysis To understand specificities of main phenomena and analysis methodologies applied to Internal and External Hazards. To know qualitative and quantitative screening process

Content Internal Fire Analysis Internal Flood Analysis Seismic Analysis Hazard and fragility curves

Duration [hrs] 1½ Training material Lecture notes for Lesson IV 3_7.4 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_10 Lesson Low Power and Shutdown PSA Purpose To present and explain the PSA Analysis for Low Power and Shutdown Modes Learning objectives To get an global overview of PSA Quantification and Importance, uncertainty and

sensitivity analysis Tasks within PSA Tasks framework To understand PSA quantification and importance, uncertainty and sensitivity analysis Task objectives To understand quantification principles and algorithms To know Core Damage Frequency determination process To understand main Importance measures To understand sensitivity and uncertainty analysis

Content Minimal Cut Set Rare Event and Minimal Cut Set Upper Bound approximations Truncation/Cut off Delete Term approach


IV 3_11.1 Lesson PSA Applications: Methodologies and Approaches. Status in OECD Countries Purpose To present and explain the methodologies and approaches used in PSA applications Learning objectives To get an global overview of PSA applications.

To understand how PSA applications complement traditional deterministic regulation To know PSA applications requirements and methods To know international status of risk-informed regulation

Content USNRC PSA Policy Statement Regulatory applications Utility applications


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IV 3_11.2 Lesson Diablo Canyon NPP Probabilistic Risk Assessment Program Purpose To present and explain the Probabilistic Risk Assessment Program implemented in Diablo

Canyon NPP Learning objectives To get an global overview of an Utility Risk Management Program and its motivation.

To know PSA Program History To know PSA applications and configuration control process To know Expert Panel organisation and responsibilities

Content Risk Management Program PSA Configuration Control Utility/Regulatory applications


IV 3_11.3 Lesson Diablo Canyon NPP Risk-Informed In-service Inspection Purpose To present and explain the Risk-Informed In-service Inspection implemented in Diablo

Canyon NPP Learning objectives To get an global overview of an Utility Risk-Informed In-service Inspection application

and its motivation. To know a Risk-Informed In-service Inspection process To know RI-ISI Expert Panel process To know main similarities and differences between EPRI and WOG methodologies

Content RI-ISI scope definition RI-ISI segment definition RI-ISI consequence evaluation RI-ISI failure probability assessment process Presentation format

Duration [hrs] 1½ Training material Lecture notes for Lesson IV 3_11.3 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_11.4 Lesson Diablo Canyon NPP Maintenance Rule Program Purpose To present and explain the Maintenance Rule Program implemented in Diablo Canyon

NPP Learning objectives To get an global overview of an Utility Maintenance Rule Program application and its

motivation. To know a Maintenance Rule Program scope and process To know the method for determining SSC risk significance To know the method for assigning performance criteria to SSC To understand PSA contribution to Maintenance Rule To understand Maintenance Rule implementation

Content Maintenance Rule scoping process SSC risk significant SSC performance criteria SSC risk monitoring


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IV 3_11.5 Lesson Diablo Canyon NPP Proposed Fire Risk Meter Purpose To present and explain the Fire Risk Meter tool proposed in Diablo Canyon NPP Learning objectives To get an global overview of an Utility Maintenance Rule Program application and its

motivation. To understand the motivation for a Fire Risk Meter tool To know the objectives and requirements for the Fire Risk Meter tool To know the expected costs and benefits of the Fire Risk Meter tool

Content Fire protectionrequirements NFPA-805 Fire Risk Meter expert system


IV 3_11.6 Lesson Risk Monitoring tools: Requirements of Risk Monitors, relation with the Living PSA, applications of Risk Monitors

Purpose To present and explain requirements of Risk Monitors, the relation with the Living PSA and applications of Risk Monitors

Learning objectives To get an global overview of Risk Monitors requirements he relation with the Living PSA and applications of Risk Monitors To know Living PSA concept and requirements To know Risk Monitors concept, uses and requirements To understand the difference between average and instantaneous risk and technical differences.

Content Living PSA Risk Monitor Time dependent Risk Risk Monitor development History


IV 3_11.7 Lesson Temelin NPP Risk Panel: A PSA and Safety Monitor application Purpose To present and explain Temelin NPP Risk Panel: A PSA and Safety Monitor application Learning objectives To get an global overview of a PSA and Safety Monitor application: Temelin NPP Risk

Panel. To understand the Safety Monitor and Temelin NPP Risk Panel features.

Content Safety Monitor tool Temelin Risk Panel tool Risk Panel main screens


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IV 3_11.8 Lesson Integrated Decision-making Process for PSA Applications. Spanish Experience Purpose To present and explain an Integrated Decision-making Process for PSA Applications:

Cofrentes NPP experience Learning objectives To get an global overview of an Integrated Decision-making Process for PSA

Applications To know Spanish PSA applications To know Cofrentes NPP GADE panel

Content Reg. Guide 1.174 and SRP 19 Risk Informed In-service Testing Risk Informed In-service Inspection Risk Informed Allowed Outage Time Maintenance Rule

Duration [hrs] 1½ Training material Lecture notes for Lesson IV 3_11.8 References Reg. Guide 1.174 and SRP 19 Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_11.9 & 10 Lesson

Consejo de Seguridad Nuclear PSA Applications Program PSA Information System

Purpose To present and explain the PSA Applications Program implemented by the CSN and the PSA Information System

Learning objectives To get an global overview of the PSA Applications Program implemented by the CSN and the PSA Information System To know Risk informed regulation preconditions and expected benefits To understand Spanish background for a Risk informed regulation framework To know main goals of CSN PSA Applications Project To know main features of CSN PSA Information System

Content Risk informed regulation CSN PSA Information System CSN Risk based Inspection

Duration [hrs] 1 Training material Lecture notes for Lesson IV 3_11.9 and IV 3_11.10 References None Resources Computer projector, screen, PC, PowerPoint 2000®

IV 3_11.11 Lesson Overview of Risk Informed Inspection Purpose To present and explain the CSN approach to a Risk Informed Inspection Learning objectives To get an global overview of the CSN approach to a Risk Informed Inspection framework

To get an global overview of the current Inspection programme of CSN To understand the required developments for a Risk Informed Inspection To understand objectives and features of a Risk Informed Inspection Program To understand objectives of Asco NPP RII Pilot application To present following transition action plan

Content Regulatory inspection activities Risk Informed Inspection Risk-Information Matrix Significance Determination Process (SDP)


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IV 3_11.12 Lesson Risk informed On-line Maintenance at Cofrentes NPP Purpose To present and explain the Risk informed On-line Maintenance Program at Cofrentes

NPP Learning objectives To get an overview of the Risk informed On-line Maintenance Program at Cofrentes NPP

To understand objectives and motivations for a Risk informed On-line Maintenance Program To understand main constrains of traditional On-line Maintenance Program To know Current Scope of the Risk informed On-line Maintenance Program To understand general approach implemented at Cofrentes NPP

Content Traditional On-line Maintenance Program features Risk informed On-line Maintenance Program at Cofrentes NPP Risk Monitor


IV 3_11.13 Lesson Incident Evaluation and Ranking of Operational Events Purpose To present and explain the incident evaluation and ranking of operational events Learning objectives To get an global overview of processes applied for incident evaluation and ranking of

operational events To understand the PSA applicability to the analysis of operational events To get an global overview of international practices of Regulatory Bodies assessment of operational events To understand objectives and practices of NRC Precursor Analysis To understand objectives and practices of CSN Precursor Analysis

Content Precursor Event Analysis Standardised Plant Analysis Risk Models


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18

BLOCK C Practical Sessions Demonstrations V II2D_1 Lesson Integrated Safety Assessment Program for Krsko Modernisation Project Purpose To explain an example of Integrated Safety Assessment Program as it was implemented

in Krsko NPP Learning objectives To be able to understand the different aspects that are involved and should be considered

in a complex and important Plant modification and modernisation project such as that implemented in Krsko NPP. To know how it is performed an Integrated Safety Assessment Program for such project

Demonstration tasks Justification and goals for SG replacement Krsko NPP Modernisation project scope Analysis for SGR and Power uprate Licensing process Start-up Program after SGR and Power increase Integrated Safety Assessment approach to evaluate Plant Changes (Plant modernisation)

Duration [hrs] 1½ Training material Lecture notes for Lesson VII2D_1 Resources Computer projector, screen, PC, PowerPoint 2000®

V II2D_2 Lesson Krsko NPP Periodic Safety Review (PSR) Purpose To explain an example of Periodic Safety Review as it was implemented in Krsko NPP Learning objectives To know general objectives, requirements and content of a Periodic Safety Review

To have an overview of international experience in Periodic Safety Review To know general methodologies for performing the assessment of current Plant status

Demonstration tasks Justification and goals of (PSR) General methodologies applied Inputs from PSA and operational experience PSR Checklists Assessment of plant status and ranking of safety issues

Duration [hrs] 1½ Training material Lecture notes for Lesson VII2D_2 Resources Computer projector, screen, PC, PowerPoint 2000®

Workshop Manual – Country 200X Based on Standard Training Event No. X

WORKSHOP PROGRAMME 1st WEEK, xx-xx Month Year

Time Monday Tuesday Wednesday Thursday Friday 830 – 900 Arrival of Participants and

Lectures, Registration Local organisers Lesson I 1_1

900 – 1030 Opening and training admin. Support for SA of NPPs Strengthening SA capabilities IAEA SG-Safety Ass and Ver Host Authorities and IAEA officer Lesson: I 1_2 and I 1_3.1/2/3

Licensing Renewal of Operating License Periodic Safety Assessment Regulatory Point of View Lecturer Lesson: II 2_2

Use and Conduct of Safety Analysis Lecturer Lesson: II 3_1

Safety Assessment of General Design Aspects of NPPs (Part 2) Single failure. Redun./ Indep./ Diversity. System interact./ depend.. FMEA Lecturer Lesson: III 1_2

Safety Analysis: Deterministic Safety Analysis (Part 2) Input data, Verif. and valid., Conserv./BE approaches Lecturer Lesson: IV 2_2

1030 – 1100 Coffee break 1030 – 1130

1130 – 1230

Safety Objectives and Requirements Defence in depth. Safety Culture Lecturer Lesson: II 1_3.1, II 1_2 and II 1_3

Safety Assessment Process. Plant Modification Regulatory point of view Lecturer Lesson: II 2_3

Safety Assessment of General Design Aspects of NPPs (Part 1) Defence in depth. Safety margins. Proven practices. Lecturer Lesson: III 1_1

Safety Analysis Safety Analysis: Event Classification Lecturer Lesson: IV 1-1 and IV 1-2

Safety Analysis: Deterministic Safety Analysis (Part 3) Sensitiv./Uncert. Analysis. QA Lecturer Lesson: IV 2_3

1230 – 1400 Lunch break 1400 – 1530

Needs for Safety Assessment The Safety Assessment Process Lecturer Lesson: II 2_1 and II 3_2

Integrated Safety Assessment Program for Krsko Modernisation Project Lecturer Lesson: V II2D_1

Periodic Safety Review for Krsko NPP Overview of PSR approach and methodology Lecturer Lesson: V II2D_2

Safety Analysis: Deterministic Safety Analysis (Part 1) Areas of analysis and Computer codes Lecturer Lesson: IV 2_1

PANEL Lecturers

1530 – 1600 Break 1600 – 1700 PANEL

Lecturers

PANEL Lecturers

PANEL Lecturers

PANEL Lecturers

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B

Workshop Manual – Country 200X ased on Standard Training Event No. X

WORKSHOP PROGRAMME 2nd WEEK, xx-xx Month Year

Time Monday Tuesday Wednesday Thursday Friday 830 – 900 Introduction to the 2nd week

Lecturers/Participants Programme Overview IAEA officer Lesson I 1_3.2

Reliability Data Analysis Lecturer Lesson: : IV 3_5

Overview of Level 2 and Level 3 PSA Lecturer Lesson: IV 3_3 and: IV 3_4

Diablo Canyon NPP Maintenance Rule Program Lecturer Lesson: IV 3_11.4

CSN PSA Applications Program PSA Information system Lecturer Lesson: IV 3_11.9 and IV 3_11.10

900 – 1030 Course Objectives and Organisation. PSA Fundamentals and Overview IAEA officer Lesson: I 1_3.4 and IV 3_1

Human Reliability Analysis Lecturer Lesson: IV 3_7.1

Low Power and Shutdown PSA Lecturer Lesson: IV 3_10

Diablo Canyon NPP Proposed Fire Risk Meter Lecturer Lesson: IV 3_11.5

Overview of Risk Informed Inspection Lecturer Lesson: IV 3_11.11

1030 – 1100 Coffee break 1030 – 1130

Initiating Events Analysis Lecturer Lesson: IV 3_2.1

Common Cause Failure Analysis Lecturer Lesson: : IV 3_7.2

PSA applications methodologies and approaches Status in OECD countries Lecturer Lesson: IV 3_11.1

Risk Monitoring Tools: Requirements, Living PSA, Risk Monitors Lecturer Lesson: IV 3_11.6

Risk informed On-line Maintenance at Cofrentes NPP Lecturer Lesson: IV 3_11.12

1130 – 1230 Accident Sequence Analysis Lecturer Lesson: IV 3_2.2

PSA Quantification. Interpretation of results. Lecturer Lesson: : IV 3_7.3

Diablo Canyon NPP PRA Program Lecturer Lesson: : IV 3_11.2

Temelin NPP Risk Panel: A PSA and Safety Monitor application Lecturer Lesson: IV 3_11.7

Incident Evaluation and Ranking of Operational Events Lecturer Lesson: IV 3_11.13

1230 – 1400 Lunch break 1400 – 1530

System Analysis Lecturer Lesson: IV 3_2.3

Internal and External Hazard Analysis for PSA Lecturer Lesson: IV 3_7.4

Diablo Canyon NPP Risk-Informed In-service Inspection Lecturer Lesson: IV 3_11.3

Integrated Decision Making Process for PSA applications. Spanish experience Lecturer Lesson: IV 3_11.8

Evaluation of the Training Course Feedback from participants Closure of the Training Course

1530 – 1600 Break 1600 – 1700 PANEL

Lecturers

PANEL Lecturers

PANEL Lecturers

PANEL Lecturers

Workshop Manual Based on Standard Training Event No-X

RESPONSIBILITIES

Responsibility of the Workshop Director

Beside general responsibilities of the Workshop Director (WD) outlined in IAEA guidelines for organisation of training courses the WD is also responsible: 1) To make all arrangements to ease the customs formalities for the IAEA workshop equipment (if any); 2) To ensure that all needed equipment will be available and ready for use at the beginning of the workshop; 3) To organize pick-up at the airport and transportation for all participants and lecturers or to prepare clear

information about transport arrangements; 4) To maintain administrative office throughout the workshops to be responsible for providing local support,

make arrangements, solve problems, as required; 5) To ensure that computer projector, overhead projector, slide projector, video and flipcharts will be available

throughout the workshops; 6) To ensure photocopier will be available for unlimited use (within reason); 7) To prepare general information about workshop venue; 8) To arrange, if possible, that all field exercises will be video taped (if any); 9) To ensure that arrangements will be made for a workshop photo; 10) To ensure that cold drinks and coffee will be available during breaks.

Responsibility of the IAEA Technical Officer

Besides general responsibilities outlined in IAEA guidelines for organization of training courses the Technical Officer (TO) has also the following responsibilities: 1) To ensure that equipment which needs to be purchased for the workshops (if any) is ordered in time; 2) To take all in-house administrative steps required to send IAEA owned equipment, needed for the

workshops, to the host institution in time; 3) To ensure that workshops’ Certificates are prepared and send to the host institution in time; 4) To ensure that IAEA radiation protection surveillance is implemented (if needed); 5) To ensure that all workshop training materials are prepared and send to the host institution in time; 6) To evaluate candidates and to propose selection of participants; 7) To check all arrangements for the workshops before beginning of the workshop; 8) To act as an IAEA representative.

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TECHNICAL ASPECTS

Faculty

Names Position Tel: Fax: e-mail: Local lecturers

Faculty Lectures Session moderation Name

Equipment and supplies

The following equipment and supplies are needed for this workshop.

Equipment item Minimum number

Required/ Optional Remark

Standard workshop supplies Photocopier 1 R PC computer 2 R Printer 1 R

Internet access O To give participants the opportunity to send or receive e-mails

Digital camera 1 R To take some workshop photos Video projector (computer linked) 1 R Overhead projector 1 R Stationery (paper, pens, pencils, etc.) R The host institution will provide all needed equipment and supplies.

Identity badges and certificates

IAEA Certificates of the workshop attendance and identity badges will be prepared for all participants.

Exposure control

At this workshop there is no need for exposure control.

Training material for the participants

The following training material and documents should be available for each participant:

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1. Workshop Manual 2. Lecture Notes 3. Documents:

a. INTERNATIONAL ATOMIC ENERGY AGENCY, Safety Assessment and Verification for Nuclear Power Plants, IAEA-No. NS-G-1.2, IAEA, Vienna (2001)

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