SAET Draft Syllabus 01 14

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SAFETY ASSESSMENT EDUCATION AND TRAINING PROGRAMME CURRICULUM STRUCTURE
MAIN ELEMENTS
I. Fundamentals of Safety
Assessment*
II. Assessment of Engineering
Aspects Important to Safety*
III. Deterministic Safety Assessment*
IV. Probabilistic Safety Assessment*
Essential Safety Assessment Knowledge
MODULES
MODULES
MODULES
A – Introduction to Safety Assessment
A – Overview of Engineering Aspects
1.
Fundamental Safety Principles and
1. Implementation of defence in depth
overview of IAEA Safety Standards
2. Operational experience
1.
Safety Requirements: Safety Assessment
3. Radiation protection
2.
GSR Part 4 and Design Safety SSR-2/1
4. Classification of structures systems and
2.
3.
Basic Safety Concepts
4.
Scope of Safety Assessment
Note:
For additional training in nuclear safety
fundamentals, please refer to the IAEA
Basic Professional Training Course on
Nuclear Safety (BPTC) at:
A – Overview of Deterministic Safety
Basic Risk Concepts and Techniques
Deterministic Safety Assessment
2.
General Objectives and Scope of PSA
Scope of Deterministic Analysis
3.
Overview of Level 1, 2, and 3 PSAs
3.
Overview of DSA Applications
4.
Level-1 PSA organization, management and
4.
Licensing Analyses
5. Equipment qualification
5.
Development of EOPs and SAMGs
6. Aging and wear-out mechanisms
6.
Safety Analyses in Support of Periodic
7. Human factors in NPP design and
operation
8. Protection against internal fire and
explosions
Safety Reviews
7.
Shut-down and Low Power Analyses
8.
Analyses in Support of Modifications and
bpc.asp?s=100&l=105
B - Fundamentals of Safety Analysis
tasks outline
5.
9. Protection against internal hazards other
Level 2 PSA Process - Major Tasks & Interfaces
and Project Arrangements
6.
Role of PSA concepts in Risk Informed
Regulations
7.
Life Extension
Safety Assessment and Verification with Level 1
PSAs
8.
than fire and explosions
Overview of PSA Applications and Regulatory
Use of PSAs
10. Protection against earthquakes
http://www-ns.iaea.org/training/ni/fund-
A – Probabilistic Safety Assessment (PSA)
1.
components
Assessment (DSA)
MODULES
9.
Living PSAs and Risk Monitors
11. Protection against external events
excluding earthquakes
B – Safety Assessment of the Design of the
B - Design Basis Analysis - System
* Modules may contain exercises and quizzes as additional training aids
B - Level 1 PSA
Main Systems
1. Scope of safety analysis
1. Intro to Design Basis Analysis: Scope,
Objectives, Methodology
1. Analysis of Initiating Events
2. Accident Sequence Modelling
2. Preparing for safety analysis
1. Reactor Core
2. Identification and Grouping of Initiating Events
3. System Analysis and Fault Tree Development
3. Criteria for Judging Safety and Acceptance
2. Reactor coolant system and associated
3. Acceptance Criteria
4. Reliability and Statistical Data Analyses
4. Basic Code Modelling
5. Analyses of Dependencies including Common
Criteria
4. Overview of Deterministic Safety Analysis
Methods
5. Overview of Probabilistic Safety Analysis
Methods
systems
3. Reactor containment systems
5. Code Verification and Validation
Cause Failures
4. Emergency power systems
6. Separate Effects Tests Modelling
6. PSA Quantification and Analysis of Results
5. Fuel handling and storage systems
7. Integral Effects Tests Modelling
7. Overview of PSA Software
6. Supporting and auxiliary systems
8. Nuclear Power Plant Modelling
8. Human Reliability Analysis
6. Use of Computer Codes
7. Instrumentation and control systems
9. Conservative approach
9. Fire Risk Analysis
7. Uncertainty and Sensitivity Analysis
Safety Systems
10. Best Estimate plus Uncertainty
10. Flood Risk Analysis
8. Use of Data from Operating Experience
11. Sensitivity Analysis
11. PSA of Internal Hazards
9. Interpretation of Results
12. Fundamentals of Conservative vs. Best
12. Overview of PSA for External Hazards Including
10.Quality Assurance (find new title)
11.Integrate Risk Informed Decision Making
Estimate Analysis
13. Uncertainty Evaluation
Introduction to Seismic PSA
13. Applications
14. Applications
C –Design Basis Analysis - Fuel Behaviour
C - Level 2 PSA
1. CPR/DNBR
1. Overview of Severe Accident Phenomena
2. Reactivity coefficient
2. Sample Calculations of Severe Accident
3. Shutdown margin
4. Enrichment
5. Crud deposition
Progression
3. Containment Designs and Structural
Performance
6. Strain level
4. Probabilistic Event Progression Modelling
7. Oxidation
5. Probabilistic Analysis Interfaces
8. Hydride concentration
6. Format and Content of Typical Level 2 PSA
9. Internal gas pressure
10. Thermal mechanical loads
11. PCI
12. Fuel fragmentation (RIA)
13. Cladding embrittlement/PCT
14. Cladding embrittlement / Oxidation
* Modules may contain exercises and quizzes as additional training aids
Results.
7. Applications
15. Blow down /seismic loads
16. Assembly hold-down force
17. Coolant activity
18. Gap activity
19. Source term
20. Applications
D – Design Extension Conditions
1.
2.
1. Basic Structure and Methodology of Level 3 PSA
overview of severe accidents
2. Release Categories and Frequencies
In vessel severe accident progression and
3. Atmospheric Dispersion
phenomena
4. Evaluation of Consequences
-
Thermal hydraulics
5. Modelling of Health Effects
-
Oxidation of core materials
6. Codes used in Level 3 PSA
-
Loss of core geometry
7. Uncertainty Analyses and Problems
-
Melt progression with and without
8. Applications
reflooding
-
Corium characteristic and crust-melt
interface
-
Heat transfer in corium pools
3.
Core degradation experimental programmes
4.
Modelling of in vessel accident progression
with computer codes
5.
Lower head behaviour and failure
6.
High pressure accidents – phenomena and
analyses
7.
Hydrogen release and behaviour – generation,
distribution, mixing and combustion
8.
D - Level 3 PSA
Intro to Design Extension Conditions –
Direct containment heating
-
DCH phenomena
-
Vessel failure modes
-
Phenomena in containment
* Modules may contain exercises and quizzes as additional training aids
9.
-
Experimental data base
-
Modelling
Steam explosions – phenomena, and
modelling
10. Ex vessel debris formation and coolability
11. Corium spreading
-
phenomena, experiments
-
analytical models
12. Corium concrete interaction
13. Fission Product Release and transport
-
FP chemistry and aerosols
-
FP behaviour in RCS
-
Release of FP to the containment and
transport
14. FP modelling
15. Determination of the Source Term
16. Severe accident management
-
objectives and scope
-
severe accident management techniques
-
development of SAMGs
17. Applications
Practical Applications Skills
A – Crosscutting Topics
A - Design Basis Analysis
1. Integrated Risk-Informed Decision Making
1. Typical architecture of thermal-hydraulic
(IRIDM)
 Relation between DSA and PSA
 IRDM Framework
 Integrated use of DSA and PSA
 IRDM and regulatory applications
system codes
2. Modelling principles using thermal-hydraulic
system codes
3. Description of thermal-hydraulic system codes
structure and syntax
* Modules may contain exercises and quizzes as additional training aids
Level 1 PSA
(TO BE COMPLETED)
1. Use of PSA Codes
2. Evaluation of Uncertainties
3. Presentation of Results
Integrated use of DSA and PSA
-
Hydrodynamic
 IRDM and regulatory applications
-
Heat structures
-
Balance of plant
-
Neutron kinetics
-
Time step control
-
Output files
-
Post processing
2. Periodic Safety Review
 Periodic Safety Review within the
Regulatory Framework
 Methodology and Guidelines used for
Performing PSR
 PSR Conduct
 Current Experience with PSR
4. Component models of thermal-hydraulic
system codes
-
General - volume, junction, pipe, branch,
cross flow
3. Design Safety Reviews – evaluation of
-
pressurizer, separator, ECC mixer,
Safety Cases
turbine
 Generic Reactor Safety Review
 Review od safety documentation
against IAEA standards and other
relevant criteria
Specialized – valve, pump, accumulator,
5. Special process models of thermal-hydraulic
system codes
-
Hydrodynamic –critical flow, pressure
drop, stratification, counter-current flow
4.Regulatory Review
limitation, interphase mass transfer
5.Integrated Management Systems
-
Heat transfer – critical heat flux,
radiation, wall heat transfer
6. Development of input models (from analytical
and basic experiments and separate effects
experiments through integral experiments to
NPPs)
7. Scaling, verification, validation
8. NPP Accident Analyses
9. Sensitivity analysis and uncertainty evaluation
B – Design Extension Conditions (Syllabus
currently under preparation)
Level 2 PSA
(Syllabus currently under preparation)
1. Building interface to Level 1 PSA
* Modules may contain exercises and quizzes as additional training aids
1. Modelling of in-vessel phenomena
2. Estimation of Plant Damage States
2. Modelling of ex-vessel phenomena and
3. Severe Accident Modelling (from Beyond
containment performance
3. Fission Product Transport
4. Determination of Source Term
design Basis analysis Module)
4. Containment performance analysis (CET and
quantification)
5. Source term Analysis
Level 3 PSA
(Syllabus currently under preparation)
* Modules may contain exercises and quizzes as additional training aids
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