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Miscellaneous Technical Training Courses on WWER Technology

Training Courses

1. Preparation of the bid invitation for the first NPP

Training Modules

  1. Russian reactor technology and NPP system design (focusing VVER)

Provides understanding of organization of  VVER based NPP, its supply chain, general concepts of refueling and maintenance.

  1. Fuel cycles: from mining to waste disposal

Provides understanding of  procedures to treat special nuclear and non-nuclear materials as well as operational wastes and spent fuel.

  1. Siting procedures and criteria

Provides understanding of  principles and consideration in site evaluation including issues on radionuclides migration (atmosphere and hydrology) and human induced events.

  1. Fuel cycle economics

Provides understanding of  the main financial needs to support life cycle of NPP.

  1. Radiation & Environmental safety

Provides understanding of  radiation effects, radioecological safety,  environmental monitoring, international  and Russian standards.

  1. Safety culture

Provides understanding of  general principles of safety culture and its implementation along NPP life cycle.

  1. Licensing issues

Provides understanding of  licensing procedure

  1. National and International Safeguards and Accounting Standards

Provides understanding of general principles and technologies of  material control, accounting and physical protection.

  1. Planning and organization of commissioning (split package and turnkey approaches)

Provides understanding of organizational structure of commissioning procedure,  IAEA and vendor recommendations

  1. Education & Training programmes in vendor country (Russian federation) supporting nuclear capacity building

Provides understanding of Russian university programmes (BS, MS, specialists) oriented to NPP HR capacity building, on-the-job training programmes, specifics of career development for NPP operators.

  1. Preparation of bid invitation specification

Provides understanding of procedures and specifics of bid invitation

  1. Final test

100 h total (86h of lectures + 14h of hands-on sessions)

2. Site selection and qualification

Training Modules

  1. Russian reactor technology and NPP system design

Provides understanding of  organization of  VVER based NPP, its general layout, configuration and arrangement with special reference to site.

  1. Nuclear legislation relevant to siting: international guidelines and Russian standards

Provides understanding of  basic site criteria and objectives of evaluation

  1. Safety culture

Provides understanding of  general principles of safety culture and its implementation along NPP life cycle with special emphasis to site.

  1. Licensing issues

Provides understanding of  licensing procedure

  1. Seismology

Provides understanding of  methodology to evaluate a ground motion hazard.cycle.

  1. Site selection and qualification guidelines: international standards and Russian experience

Provides understanding of  guidelines and recommendation s, experience and best practices.

  1. Probabilistic safety analysis

Provides understanding of implementation of probability safety assessments (PSAs) to identify and understand key plant vulnerabilities affecting specifics of site selection; PSA- level 2 and methodology of source term calculation.

  1. Migration of radionuclides (hydrogeology and atmosphere)

Provides understanding of radioactive  source  parameters, migration modeling and associated hazards.

  1. External human induced events in site evaluation

Provides understanding of general approaches and identification of potential sources of human induced hazard.

  1. Social and economics issues

Provides understanding of best practices in cooperating with social organizations

  1. Recommendations on preparing  documents on site selection and evaluation

Provides understanding of best practices in preparation of site qualification report.

  1. Final test

100 h total (81 h of lectures + 19 h of hands-on sessions)

3. Characteristics and design of nuclear fuel, including safety margins

Training Modules

  1. Fuel cycles: from introductory concepts to fuel design

Provides understanding of fuel cycle from the view point of fuel management (from fuel fabrication through transportation  to waste disposal) .

  1. Reactor operation and control (VVER)

Provides understanding of  normal reactor operation and transients.

  1. Fuel burnup and economics

Provides understanding of  irradiation effects  on NPP plants efficiency

  1. Economics of fuel cycle

Provides understanding of the main financial needs to support life cycle of NPP focusing fuel management.

  1. Guidelines for quality and reliability assurance programmes

Provides understanding of  methods and procedures associated with quality and reliability assurance.

  1. Fuel behavior under irradiation

Provides understanding of  changing fuel properties under normal reactor operation and transients, essential degradation mechanisms capable to deteriorate properties which are relevant for NPP reliability and safety

  1. Fuel Quality and Reliability for Water Cooled Reactors. Quality Assurance and Quality Control Aspects

Provides understanding of experimental methods an norms applied for fuel management along fuel cycle.

  1. Deterministic safety analysis. Part I: Methodology

Provides understanding of radioactive  source  parameters, migration modeling and associated hazards.

  1. Deterministic safety analysis. Part II: Practical examples 

Provides an experience with simulation of thermohydraulics parameters under normal and normal operation conditions.

     10. Deterministic safety analysis. Part III- Russian computer codes

Provides experience with simulation of accidents

    11. Full-scale transients in VVER-type reactors. Based on RAINBOW  code.

Provides experience of source data preparation and transients calculation by RAINBOW code.

    12. Final test

100 h total (54 h of lectures + 46 h of hands-on sessions)

4. Security and physical protection of NPPs and the relationship with safety and safeguards

Training Modules

  1. Basic principles of nuclear fuel cycle from nuclear physics to waste management and protection against unauthorized proliferation

Provides understanding of nuclear fuel cycle and waste management from the view point of material properties related to non-proliferation

  1. Effect of radiation, safety and radiation protection

Provides understanding of  radiation effects, radioecological safety,  environmental monitoring, international  and Russian standards

  1. National and International Safeguards and Accounting Standards

Provides understanding of  standards from the view point of safety, security and safeguards.

  1. Threat assessment

Provides understanding of basic concepts and relationships between protection features and threat .

  1. Physical protection systems design and evaluation

Provides understanding of  infrastructure and procedures for detection and response  to incidents involving nuclear and other radioactive materials

  1. Physical protection technologies and equipment

Provides understanding of  technology and equipment  for detection and response  to incidents involving nuclear and other radioactive materials

  1. Radioactive waste management

Provides understanding of spent fuel and nuclear waste treatment.

  1. Measurement methods  in material control and accounting system

Provides understanding of principles and applications of non-destructive methods.

  1. Use of non-destructive and destructive analysis methods for MC&A

Provides an experience with simulation of principles and applications of non-destructive methods

  1. Statistical analysis of inventory difference  in MC&A

Provides understanding of advanced methods in accounting nuclear materials

  1. Final test

100 h total (79 h of lectures + 21 h of hands-on sessions)

5. Non-proliferation of Nuclear Materials

Training Modules

  1. Physical foundations for proliferation resistance

Provides understanding of physical foundations from the view point of nuclear physics (nuclear cross-sections and other fundamental characteristics of essential nuclides involved in nuclear power generation)

  1. Barriers against proliferation

Provides understanding of  mechanisms to create barrier against unsanctioned proliferation of Plutonium as an essential issue of sustainable nuclear power generation

  1. Protected fuel cycles

Provides understanding of  isotope transformation within nuclear fuel cycle and specifics of organizing the protected fuel cycles

  1. Proliferation resistance assessment methodology

Provides understanding of existing approach to characterization and evaluation of non-proliferation issues of nuclear fuel cycle.

  1. Physical protection systems design and evaluation

Provides understanding of  Legal base of non-proliferation of nuclear materials

  1. Final test

100 h total (87 h of lectures + 13 h of hands-on sessions)

6. Training Course for Top Managers of NEPIO: Start-up of nuclear power programme

Training Modules

  1. Rosatom Tech experience in NPP personnel training

1.1 International Centre for NPP Personnel Training at Rosatom Tech – Goals and Program

1.2 Centre for Technical Competence at Rosatom Tech

1.3 Human factor reliability support in nuclear facilities – Russian experience

1.4 Experience in the development and introduction of Computer-based Training Systems at enterprises of ROSATOM

  1. Introduction to activities related to the NPP lifecycle and requirements for the development of human resources

               2.1 Features of power generation at NPP

               2.2 NPP maintenance and repair

  1. NPP  structure on the basis of qualifications and competences

               3.1 NPP structure. Competences. Qualifications

               3.2 Individual trajectories of training for foreign NPPs

  1. Staffing at the NPP

               4.1 The scheme of training for foreign NPPs

               4.2 Personnel training for operation of state-of-the-art Russian design NPPs abroad

  1. Organizational and financial schemes for NPP construction

               5.1 Economic aspects of nuclear power plant construction

               5.2 Nuclear power infrastructure  development: supplier to customer assistance

5.3 Stages of Testing and Commissioning

  1. Quality management during NPP construction

               6.1 Management system of Operating Organization (Utility)

               6.2 Requirements to Suppliers during NPP construction

  1. NPP’s  staff,  knowledge  inspection and recruitment policy

               7.1 NPP’s emergencies

               7.2 Internet Nuclear Resources

               7.3 Definitions  of  terms  in  the  field  of Nuclear  Knowledge  Management

               7.4 NPP stages and staff re-changing

               7.5 NPPs  lessons  learned

              7.6 Systems Engineering

             7.7 Requirements to the range of knowledge

            7.8 NPP’s  indicators

  1. Practical implementation of personnel policy at Russian NPPs

               8.1 Technical Tour to Novovoronezhskaya NPP-1

               8.2 Technical Tour to Novovoronezhskaya NPP-2

  1. Full-scale simulators for NPP personnel training

               9.1 Technical Tour to VNIIAES

  1. Final test

   100 h total (50 h of lectures + 50 h of hands-on sessions)

7. Russian computer codes for safety analysis

Training Modules

  1. Containment at NPP with VVER reactor and design -basis and beyond design-basis accidents scenarios
  2. Modeling gas dynamics processes in the code KUPOL-M

               2.1 Motion equation and pressure equation

               2.2 Algorithm for solving the gas dynamics problem

               2.3 Gas dynamics for high-velocity flow

  1. Modeling heat and mass transfer processes in  the code KUPOL-M

               3.1 Energy equation and mass transfer equations

               3.2 Numerical solution

  1. Modeling heat and mass transfer on equipment and wall surfaces in the code KUPOL-M

               4.1 Analogy of heat and mass transfer

               4.2 Calculation of heat transfer coefficients

  1. Modeling volume condensation  and wall thermal conductivity in  the code KUPOL-M

               5.1 Volumetric condensation

               5.2 Equation for thermal conductivity and numerical solution peculiarities

  1. Models for hydrogen recombination  and burning. Sprinkler system

               6.1 Hydrogen recombination

               6.2 Hydrogen burning model

               6.3 Spray model

  1. Working with the code KUPOL-М

               7.1 Code compilation

               7.2 Initial data file

  1. Demonstration calculations using basic data

               8.1 Initial data and their preparation

               8.2 Analysis of obtained results

  1. Calculations of key accident  processes in VVER containment

               9.1 Initial data and their preparation

               9.2 Analysis of obtained results

  1. Final test

    72 h total (14 h of lectures + 58 h of hands-on sessions)

8. Project Management for NPP Construction

Training Modules

  1. The main features of the modern project management
  2. Fuel production and quality and reliability assurance

               2.1 Nuclear fuel behavior under irradiation

               2.2 Technical requirements. Manufacturing. Quality assurance. Reliability

               2.3 Advanced nuclear fuels

               2.4 Technical tour to “Mashinostroitelny Zavod” (OAO MSZ). The process of fuel fabrication. Organizing work for acceptance of goods by foreign customers.

  1. Organizational and financial schemes for NPP construction

               3.1 NPP prices. Financing sources of NPP construction projects

               3.2 Introduction of Safety Culture at pre-operational phases of a newly built NPP

               3.3 Scope of construction. NPP economic efficiency

               3.4 Financing schemes of NPP construction projects. Risk assessment in NPP construction

  1. Contracts for NPP construction: designing, concluding and implementing

               4.1 The general concepts of the contract, the basic maintenance

               4.2 The construction contract, general provisions

               4.3 The construction contract on a turnkey basis

               4.4 Features of contracts on construction of NPP

  1. Quality management during NPP construction

               5.1 Key provisions of IAEA documents setting requirements to management systems at nuclear facilities

               5.2 Quality audits and inspections during NPP construction

  1. Project “AES-2006” with the reactor VVER-1200. Basic technological solutions

               6.1 Basic provisions of LNPP-2 project. Construction site of LNPP-2. Technical Tour to LNPP-2

               6.2 Principal heat scheme. Modes of operation

               6.3 Reactor and primary circle. Reactor pressure vessel

               6.4 Control rod drive

               6.5 Steam turbine K-1200-6,8/50

               6.6 Hydraulic systems. Technical water supply for the turbine and other equipment

               6.7 Electrical systems

               6.8 Technical Tour to LNPP-1

  1. General plan for the first two power units of LNPP-2

               7.1 Technical Tour to LNPP-2

  1. Project management in the NPP construction based on the Oracle Primavera software

               8.1 Project management processes. Project risk management processes

               8.2 Information system for project management (Composition of system, information system based on the Oracle Primavera software

               8.3 Time management for the NPP construction project (role structure, development of schedules of 1st, 2nd and 3rd level)

  1. Final test

     100 h total (74 h of lectures + 26 h of hands-on sessions)

9. Nuclear power plants with nuclear reactors of small power in Russia

Training Modules

  1. Russian nuclear power plant projects with small-power nuclear reactors
  2. Reactor plant of small capacity RUTA
  3. Small-power nuclear reactor  EGP-6
  4. Small power plant SVBR-100: The concept of nuclear technology based on the modular fast reactors with lead-bismuth coolant SVBR-100
  5. Floating NPP  small  nuclear reactor KLT-40S

               5.1 Elaboration of  Floating Nuclear Heat and Power Plant by Afrikantov Experimental Machine-Building Design Bureau

               5.2 General technical and economic characteristics of KLT-40S

               5.3 Principal characteristics of KLT-40S

               5.4 Safety systems, radiation and environmental safety, analysis of non-proliferation problems

               5.5 Basic technical characteristics of Floating Nuclear Heat and Power Plant

               5.6 Safety and environmental impact of Floating Nuclear Heat and Power Plant

               5.7 Operational management and economics of Floating Nuclear Heat and Power Plant

  1. Fundamentals of heat transfer in nuclear reactor

               6.1 Fundamentals of heat transfer in nuclear reactors

               6.2 General aspects concerning reactor safety and severe accidents

               6.3 Heat transfer in severe accidents in Light water reactors

  1. Regulatory control of physical protection system, control and accounting of nuclear materials and radioactive substances

               7.1 Regulatory control of Physical Protection of the Facility Using Nuclear Energy

               7.2 Regulatory control of nuclear and  radioactive material control and accounting system

  1. Regulation of technical nuclear safety
  2. Legal and regulatory framework for licensing nuclear power plants with nuclear small-power reactors
  3. Nuclear and Radiation Safety of Nuclear Power Plant
  4. National and International  Safeguards and Accounting Standards
  5. Concluding session and testing
  6. Final test

    100 h total (96 h of lectures + 4 h of hands-on sessions)

10. Reactor Island: Physics and Equipment of primary circuit for Engineers

Training Modules

  1. Entry briefing
  2. The design of the reactor unit and NPP main equipment plant

               2.1 The visit to Balakovo NPP. Route-1

               2.2 The visit to Balakovo NPP. Route-2

  1. Measuring parameters of the reactor island

               3.1 Technical tools for measuring key process parameters (pressure, flow, level, temperature)

               3.2 Safety systems controllers

               3.3 The visit to Balakovo NPP. Route-3

  1. Emergency protection and alarm system formation. Reactor unit management

               4.1 The appointment, device, operating principles, maintenance and repair of the neutron flux control equipment, emergency protection, alarm systems, accelerated unit unloading, and their specific faults

               4.2 The visit to Balakovo NPP. Route-4

               4.3 The appointment, device, operating principles, maintenance and repair of the power limit regulator, the automatic power regulator, group and individual management system, the search for specific faults. Maintain the accuracy of neutron power at 100% and 104% of N. The operational principle of electromagnetic step actuator of control and protection system

               4.4 The visit to Balakovo NPP. Route-5

  1. Operational modes of the reactor unit

               5.1 Training on simulators “Reactor unit start-up, the output of the reactor unit (RU) at the minimum controlled power level, power level change, power unit unloading, turbo generator shutdown and the shift of reactor unit into a hot state”

               5.2 Training on simulators “Beyond design basis accident”

               5.3 Training on simulators “Violation of the conditions of normal operation, the leaks of the primary circuit coolant, compensated by a makeup-purge system of the primary circuit”

               5.4 Training on simulators “Violation of the conditions of normal operation, shutdown of all makeup units”

               5.5 Training on simulators “Violation of the conditions of normal operation. Opening and unclosing of one of BRU-A valves”

               5.6 Training on simulators “The cool down of the power unit from the emergency control room”

  1. Chemical technology of the primary circuit

               6.1 Norms of water chemistry of the primary circuit, chemicals dosing in the process of maintaining water chemistry of the primary circuit, the appointment of special water purification system

               6.2 The visit to Balakovo NPP. Route-6

  1. Reactor physics

               7.1 Reactor physics. Introduction

               7.2 The Next Generation Nuclear Plants

               7.3 Kinetics

               7.4 Principal physics of non-proliferation

  1. Final test

      100 h total (43 h of lectures + 57 h of hands-on sessions)

11. Thermo Hydraulics, engineering and Equipment of secondary circuit (Turbine Island) for Engineers

Training Modules

  1. Entry briefing-personnel actions in case of emergency.
  2. The main equipment of the turbine island.

               2.1 Thermal circuit and the main equipment of the secondary circuit.

               2.2 The visit to Balakovo NPP. Route-1

               2.3 The visit to Balakovo NPP. Route-2

  1. The system of automatic control and turbine protection

               3.1 Control over the mechanical parameters of К-1000-60/1500-2 turbine

               3.2 The system of automatic control and protection of steam turbine К-1000-60/1500-2.

               3.3 Operating modes of electro-hydraulic system of turbine control.

               3.4 The visit to Balakovo NPP. Route-3

  1. Measuring the turbine island parameters

                4.1 Measuring the turbine island parameters

                4.2 The visit to Balakovo NPP. Route-4

  1. Turbine protection

               5.1 General principles of forming the technological protection

               5.2 Technological protection of steam turbine К-1000-60/1500-2.

6 Operating modes of the turbine island equipment

               6.1 Training on simulators “Turbine startup, the inclusion of the generator to the network and a set of power up to 300 mW”.

               6.2 Training on simulators “The rise of power unit capacity from 40% N up to 80% N”.

               6.3 Training on simulators “The leak from the pipeline of the main condensate”.

               6.4 Training on simulators “Spontaneous opening of steam generator control element by one SG at RU operation on low power level”.

               6.5 Training on simulators “Spontaneous opening of steam generator control element by one SG at RU operation on low power level”.

               6.6 Training on simulators “Disabling of one electric condensate pump of the first stage with the failure of automatic transfer switch”.

  1. Chemical technology of the secondary circuit

               7.1 Chemical technology of the secondary circuit

               7.2 The visit to Balakovo NPP. Route-4

  1. Final exam

      72 h total (26 h of lectures + 46 h of hands-on sessions)

12. Financial Aspects of NPP Construction

Training Modules

  1. The main aspects of the national nuclear power programme development. Nuclear fuel: review of the market and world prices, cost projections

               1.1 Primary conditions: the resources of the country, long-term contracts, geopolitics, strategic partners

               1.2 Transmission facilities infrastructure, projections, assessment of the extent of nuclear programme and economy of scale

               1.3 Costs of nuclear fuel management. Overview of the market and world prices for nuclear fuel. Forecasts of nuclear fuel costs and examples of their indexing

  1. The NPP construction cost.

               2.1 Structure of CAPEX.

               2.2 Methodology for CAPEX assessment. Review of the world prices

  1. Analysis of cost effectiveness for investment project of NPP construction

               3.1 Basic terms: net present value, payback period, discounted payback period

               3.2 Methodology for cost effectiveness analysis

  1. Project financing schemes. Contractual schemes for NPP construction

               4.1 The most common methods of financing the NPP construction projects

               4.2 Types of contracts for NPP construction, examples

  1. Project cost management: methodology, theory and practice

               5.1 Cost management methodology of the investment project

               5.2 Practical issues of creation and operation of the cost management system for NPP construction

      6. The most common scenarios for NPP decommissioning. Cost estimates for NPP decommissioning

               6.1 Common scenarios of NPP decommissioning

               6.2 Analysis of NPP decommissioning costs

  1. Final exam

     36 h total (26 h of lectures +10 h of hands-on sessions)

13. Risks Assessment and Risk Management

Training Modules

  1. The fundamental principles of risk management

               1.1 The fundamental principles of risk management

  1. The risk management process.

               2.1 The risk management process

  1. The role of risk management in managing the NPP operation. Risk classification. The main types of risks

               3.1 The role of risk management in managing the NPP operation. Risk classification. The main types of risks

  1. Methods and tools of risk assessment. Approaches to risk assessment in the nuclear power industry

               4.1 Methods and tools of risk assessment. Approaches to risk assessment in the nuclear power industry

  1. Risk management strategies in the nuclear power industry

               5.1 Risk Management Strategies in the nuclear power industry

  1. Final exam

     36 h total (26 h of lectures +10 h of hands-on sessions)

14. NPP Safety Assessment based on Preliminary Safety Analysis Report

Training Modules

  1. Contents and purpose of Preliminary Safety Analysis Report

               1.1 Content and purpose of Preliminary Safety Analysis Report

  1. Regulation of nuclear and radiation safety

               2.1 Nuclear safety regulation

               2.2 Radiation safety regulation

  1. Using special purpose software for NPP safety assessment

               3.1 The use of RADUGA software for independent safety assessment

               3.2 The use of SCALE software for independent radiation safety assessment

               3.3 The use of SERPENT software for independent nuclear safety assessment

  1. Analysis of NPP design documentation. Forming a list of initiating events. Forming a list of design-basis accidents

               4.1 Procedure for evaluating the documents substantiating nuclear and radiation safety of nuclear installations

               4.2 Defining a list of design-basis accidents

  1. Operation of the systems under normal operation, occurrences and emergency; establishing safety limits

               5.1 Classification of systems and components on the effect on safety

               5.2 Description of operations of the systems under normal operation, occurrences and emergency, and establishing safety limits

               5.3 Limits and conditions of safe operation

  1. Results of deterministic and probabilistic safety analysis

               6.1 Deterministic safety analysis

               6.2 Probabilistic safety analysis

  1. Final list of beyond design basis accidents based on PSA. Measures to manage beyond-design basis accidents and to mitigate their consequences

               7.1 Guidance on accident management

               7.2 Diagnosis of beyond-design basis accidents and accident management instructions

               7.3 Analysis of beyond-design basis accidents

  1. Final exam

    72 h total (52 h of lectures +20 h of hands-on sessions)

15. Safety analysis for NPP with WWER reactors

Training Modules

  1. Key criteria and principles of safety assurance for NPP with WWER

               1.1 Fundamentals of industrial safety

               1.2 Fundamentals of fire safety

               1.3 Fundamentals of nuclear safety

  1. International safety policies and practices
    1. 1 NPP safety international policies and practices
  1. NPP site evaluation
    1. 1 NPP site evaluation
  1. Evaluation of NPP civil engineering structures
    1. 1 Evaluation of NPP civil engineering structures
  1. Operation of the systems under normal operation, occurrences and emergency; establishing safety limits
    1. 1 Safety concept for NPPs with WWER
  1. Assessment of the current safety status for NPP and analysis of event
    1. 1 Assessment of the current safety status for NPP and analysis of events
  1. NPP safety analysis. Emergency management
    1. 1 NPP safety analysis. Emergency management
  1. Personnel preparedness in the emergency response system.
    1. 1 Emergency preparedness of nuclear power facilities (including transportation)
  1. NPP quality assurance and reliability

               9.1 Quality assurance programme for NPP

               9.2 Fuel quality assurance and reliability for NPP with WWER

               9.3 Non-proliferation issues

  1. Final exam

    72 h total (59 h of lectures +13 h of hands-on sessions)

16. Specifics of WWER Design: Safety Issues

Training Modules

  1. Layout of NPP with WWER-type reactor

               1.1 WWER-technology, R&D history

               1.2 NPP layout with WWER-type reactor

               1.3 Evolution of layout solutions of NPP with WWER-type reactor

  1. Reactor facility and refueling system design

               2.1 Reactor vessel and internals

               2.2 Reactor head and upper unit

               2.3 Reactor core

               2.4 MPS-type refueling machine

               2.5 The evolution of reactor facility with WWER-type reactor

               2.6 Configuration of ventilation and air conditioning system equipment

       3. WWER fuel. The use of burnable absorber. Storage and processing. Ionizing radiation sources and radioactive waste management

               3.1 WWER nuclear fuel

               3.2 The use of burnable absorber

               3.3 Radioactive waste disposal and recycling

               3.4 Radioactive waste and radioactive sources storage

               3.5 Nuclear fuel storage

       4. Safety fundamentals for NPP with WWER. Different designs of safety systems for new units with WWER-type reactors

               4.1 Safety fundamentals for NPP with WWER

               4.2 Safety systems. Evolution of safety systems used at NPP with WWER

               4.3 Safety levels for NPP with WWER

         5. Turbine hall layout for NPP with WWER

               5.1 The operation principles of steam turbine

               5.2 Steam turbine operation fundamentals and controlled parameters

        6. Reactor unit data collecting and processing for NPP with WWER. Reactor control. NPP operating modes

               6.1 Data collecting and processing for reactor unit

               6.2 Nuclear chain reaction control in WWER-type reactors

               6.3 Operating modes

               6.4 NPP start-up

         7. Ensuring the safe operation of NPP with WWER and operation documentation

               7.1 Ensuring NPP with WWER safe operation

               7.2 WWER water chemistry

         8.1 NPP personnel management. Plan for the personnel and public protection

               8.1 NPP personnel management. Requirements for NPP operating personnel. Specific features of personnel management for NPP under construction

               8.2 Personnel and population protection action plan in case of emergency

         9. Final exam

    144 h total (107 h of lectures +37 h of hands-on sessions)

17. Radiation Safety and Health Protection

Training Modules

  1. Ionizing radiation sources

               1.1 Characteristics of nuclei and nuclear transformations

               1.2 Radiation spectra. Characteristics of radionuclide sources

               1.3 Primary interaction of ionizing radiation with matter. Radiation energy transfer

2. Biological effects of ionizing radiation and health effects

               2.1 Modern view on biological effects of ionizing radiation. Health effects

               2.2 Acute and chronic radiation syndromes

               2.3 Biological effects of radionuclides intake and internal exposure dose

        3. Dosimetry and assessment of risks associated with doses

               3.1 Penetrating power and protection

               3.2 Assessment of dose related risks

               3.3 The system of dosimetry quantities in radiation safety

               3.4 Dosimetry of ionizing radiation

         4. Sources of external and internal exposure at NPP and specifics of radiation protection

               4.1 Equipment containing radioactive substances. Sources of ionizing radiation at NPP

               4.2 Design specifics of radiation protection

          5. Fundamentals and requirements for radiation safety standards

               5.1 Radiation safety standards

               5.2 Main rules of radiation safety assurance

               5.3 Handling of radiation sources at NPP with WWER

           6. Radiation safety rules at NPP

               6.1 Requirements and rules of radiation safety assurance

               6.1 Requirements for radiation monitoring at NPP with WWER

         7. Radioactive waste management

               7.1 Radioactive wastes and their sources at NPP with WWER

               7.2 Radiation safety of radioactive waste management

               7.3 Requirements for receipt and dispatch of radioactive wastes

               7.4 Emergency response for radioactive waste management

         8. Radiation control. Dose reduction measures at NPP with WWER

               8.1 Organization of radiation control at NPP with WWER

               8.2 General requirements for radiation work management at NPP with WWER. Dose assessment and planning

               8.3 Staff responsible for specific safe working procedures

               8.5 Task order and radiation work permit management

        9. Basics of ALARA principle

               9.1 Concept and fundamentals of ALARA methodology. Implementation of the ALARA methodology at NPP

               9.2 Application of ALARA methodology during activities associated to radiation risks

        10. Investigation of emergency and accidental exposure of the personnel

               10.1 The dose constraint for administrative decision making. Levels of emergency and accidental exposure

               10.2 Documentation requirements in case of emergency or accidental exposure of NPP personnel. Preparation and implementation of preventive and corrective measure

        11. Personnel and public protection measures in case of radiation accidents

               11.1 General and derivative criteria of radiation accident classification. Emergency response and prevention system

               11.2 Planning and implementation of protection measures for the public

               11.3 Phases of protective measures

         12. Final exam

    72 h total (49 h of lectures + 23 h of hands-on sessions)

18. Policy on Decommissioning and Regulatory Control

Training Modules

  1. The basic concepts of NPP decommissioning

               1.1 The decommissioning process

               1.2 Basis for the organization of decommissioning

               1.3 Primary interaction of ionizing radiation with matter. Radiation energy transfer

      2. World and national practices of NPP decommissioning

               2.1 World practice of decommissioning

               2.2 National practice of decommissioning

       3. Regulatory and safety issues of NPP decommissioning

               3.1 The regulation of decommissioning

               3.2 Safety analysis at decommissioning

       4. NPP decommissioning project management

               4.1 Theoretical basis for the decommissioning project management

               4.2 Conducting the SWOT-analysis of a decommissioning project

       5. Technological issues of NPP decommissioning projects

               5.1 Technological issues of decommissioning projects

        6. Economics of NPP decommissioning

               6.1 Economics of decommissioning

       7. Social aspects and managing human resources issues within the context of the NPP decommissioning

               7.1 Social aspects of decommissioning

               7.2 Managing human resources in decommissioning projects

        8. Analysis of the world practice in NPP decommissioning

               8.1 Analysis of the world practice of decommissioning

        9. Final examination

        36 h total (36 h of lectures + 28 h of hands-on sessions)

19. Development and implementation of integrated programmes on remediation of uranium production legacy sites

Training Modules

  1. Introduction the environmental assessment and remediation in areas affected by uranium production legacy sites

               1.1 Environmental impacts of uranium production

               1.2 Conceptual Site Model for uranium production legacy sites

               1.3 Radioactivity and radiation. Behavior of radionuclides in the environment

               1.4 System of radiological protection

               1.5 Safety culture in remediation programmes

               1.6 Regulatory framework for remediation programmes

               1.7 Interaction with regulatory bodies

               1.8 Involvement of stakeholders

       2. Remediation planning for uranium production legacy sites

               2.1 Environmental remediation: terms, concepts, phases

               2.2 Data collection for uranium legacy site

               2.3 Remediation purposes

               2.4 Planning process for remediation programmes

               2.5 Training of the personnel

        3. Implementation of the remediation programmes

               3.1 Overall management for remediation programmes

               3.2 Development and realization of monitoring strategies in compliance with remediation criteria

               3.3 Safety assurance and safety control programme

               3.4 Soil and groundwater remediation techniques, tools, and methods

               3.5 Waste management

               3.6 Cost estimate

               3.7 Report on completion of  a remediation programme

      4. Post-remediation management at uranium production legacy sites

               4.1 Post-remediation monitoring

               4.2 Data management

               4.3 Long-term stewardship, institutional control, liability management

               4.4 National good practices (study cases)  in remediation of uranium production legacy sites

               4.5 World good practices (study cases)  in remediation of uranium production legacy sites

  1. Final examination

    72 h total (48 h of lectures + 19 h of hands-on sessions)

20. General aspects of WWER technology. Russian computer codes for safety assessment

Training Modules

  1. Layout of NPP with WWER-type reactor
  2. WWER Safety Systems
  3. Analytical Simulator  WWER-1000
  4. WWER fuel

4.1 Chemical composition, types and basic operational characteristics of nuclear fuel. Fuel behavior under irradiation. Modern technical requirements for nuclear fuel

4.2 WWER fuel. The use of burnable absorber

4.3 Nuclear fuel fabrication techniques. Perspective fuel types

4.4 Technological scheme of nuclear fuel fabrication: from the powder to fuel. Tech Tour to MSZ.

  1. Personnel Management for NPP with WWER-type Reactor
  2. Computer codes for safety assessment

6.1 Codes and computational tasks

6.2 Russian computer codes for safety assessment

6.3 Status of MCU code. A modular structure of MCU code. Input data, geometry, source and tally description. Sample problems and practice

  1. Management issues of NPP with WWER

7.1 Reactor Island

7.2 Turbine Island

7.3 NPP under the operation. Technical Tour to NPP

  1. Deterministic safety analysis in severe accident analysis. Computer code SOCRAT

8.1 Getting started with SOCRAT modeling: general description of SOCRAT and modeling of thermal hydraulics

8.2 Modeling of core degradation

8.3 Modeling of the late stage of a severe accident (in-vessel and ex-vessel stages)

8.4 Modeling of fission products build-up, release, transport and deposition

8.5 Examples of practical application of SOCRAT code in resolving the safety issues

  1. Methods ensuring efficiency and correctness of estimations of radiation situation and radiation consequences for the environment and population. Russian computer codes designed for that purpose.

9.1 SI in the site selection process, public debates and hearings

9.2 RSES (State Unified System of Prevention and Response to Emergence Situations). Russian emergency response systems to radiation hazards.

9.3 Practical studies with demonstration of software packages for forecasting of radiation situation after NPP accident (input of the initial data, calculation, results’ analysis, use of meteorological data)

9.4 Examples of the use of software packages to predict radiation situation after the accident at Fukushima

  1. Final test

    216 h total (122 h of lectures + 94 h of hands-on sessions)

21. Methodology and Practices for Industrial Involvement

Training Modules

  1. Industry Procurement Standard

1.1 Introduction to the simulator of WWER-1000

1.2 Practice on the WWER-1000 simulator

1.3 Practice on the WWER-1000 simulator

  1. Industrial Involvement and Procurement. Technical Tour to ZiO Podolsk

         2.1 Basic principles of design, manufacturing and supply of equipment

         2.2 Industrial Involvement and procurement

  1. Becoming a knowledgeable customer: build up the technical competences for owner/operator

         3.1 Build up technical competences For owner/operator at the pre-construction stage

         3.2 Build up technical competences For owner/operator at the stage of NPP construction, operation and commissioning

  1. Technical Tour to Novovoronezh NPP

         4.1 Operation and construction activities of NV NPP

         4.2 NPP personnel training

  1. Technical Tour to Novovoronezh NPP

         5.1 Maintenance, repair and reconstruction of nuclear power plants. Determination of repair scope, organization of delivery of spare parts & equipment supply, repair planning & performing

         5.2 Maintenance personnel training

         5.3 Licenses of safety authorities for responsible works and production activities in the nuclear industry and power engineering

  1. NPP Maintenance Staffing
  2. Training on Industrial Involvement and Staffing

         7.1 Local market analysis for suppliers of goods and services for the NPP construction needs

         7.2 Development of specifications for suppliers. Procurement procedures

         7.3 Staffing of contractors and subcontractors

  1. Test
22. Quality Management and Quality Assurance

Training Modules

  1. The QM system of ROSATOM

         1.1 The Quality Management System of the ROSATOM. The main activities of the ROSATOM QMS.

         1.2 QMS development directions

  1. The legislation of the Russian Federation in the field of QA&QM. Specific issues

         2.1 Fundamentals and scope of the standard series ISO 9000

         2.2 The legislation of the Russian Federation in the field of QA&QM. Specific issues

  1. Integrated QMS of JSC “Concern Rosenergoatom”

         3.1 Quality assurance during NPP construction

         3.2 Quality assurance system during NPP startup and adjustment works

  1. Quality Control Organization on the NPP Construction Site

         4.1 Concept of QMS Implementation in the Directorate of NPP during construction

         4.2 Organization and description of the QMS process

  1. Nondestructive control

         5.1 Nondestructive control and technical diagnostics

         5.2 Resource management equipment of methods nondestructive control and technical diagnostics

         5.3 Economic indicators use nondestructive control of equipment

  1. Tech tour to Research Institute of Introscopy and National Research University MPEI

         6.1 The latest trends in the field of non-destructive testing. MSIA SPECTRUM

         6.2 Visit to NDC laboratory of MPEI

  1. The organization of incoming inspection of  the documents, equipment and expediting during construction phase on NPP site

         7.1 The organization of incoming inspection of the documents and equipment.

         7.2 The organization of expediting construction and installation work

  1. The organization of incoming inspection of  the documents, equipment and expediting during construction phase on NPP site

         8.1 Project management framework using  Microsoft Office Project 2010

         8.2 Project management Cases.

  1. Planning and quality control of work on the NPP pre-construction phase

         9.1 Case 1. Initial and boundary condition definition

         9.2 Project management Cases

  1. Planning and control quality of work on the NPP construction and installation work phases

         10.1 Case 2. Initial and boundary condition definition

         10.2 Project management Cases.

  1. Planning and control quality of work on the NPP construction and installation work phases

         10.1 Case 2. Initial and boundary condition definition

         10.2 Project management Cases.

  1. Tech tour to Leningrad NPP

         11.1 NPP under construction

         11.2 NPP personnel training

  1. Tech tour to TK OMZ-Izhora (Izhorskiy Zavod)
  2. Final test

    72 h total (34 h of lectures + 38 h of hands-on sessions)

23. Stakeholder Involvement

Training Modules

  1. Basic elements of SI

         1.1 International and national requirements and recommendations for SI

         1.2 Outline of SI programme

         1.3 General approaches to the SI strategy and plan development

         1.4 Practical exercise “Stakeholder matrix”

  1. Organization’s activities in the area of  SI

         2.1 NEPIO, Owner/Operator and Regulator functions, roles and responsibilities for SI

         2.2 Activities at the various stages of the nuclear power implementation programme.

         2.3 Risk management of the SI programme implementation.

         2.4 Practical exercise “Development of the strategy and general plan for SI”

  1. Methods and instruments for   SI

         3.1 SI principles

         3.2 Methods and instruments of involvement

         3.3 Collaboration between the newcomer and vendor countries

         3.4 Youth involvement

         3.5 Russian experience

         3.6 Practical exercise “Methods and instruments of involvement”

         3.7 Practical exercise “Youth involvement”

  1. Risk communication

         4.1 Hazards and risks associated with the nuclear power

         4.2 Risk perception and public acceptance of risks

         4.3 Public communication on the risks associated with the nuclear power

         4.4 Practical exercise: “Risk communication”

  1. Information center

         5.1 Information center goals and structure

         5.2 Methods and instruments used in the information center

         5.3 Practical exercise “Visit to Information Centre”

  1. SI during public consultations  for the site selection process and NPP construction

         6.1 SI in the site selection process, public debates and hearings

         6.2 Communication with the international organizations and neighboring countries

         6.3 Practical exercise “Scenario for public hearings”

  1. Final test

    36 h total (25 h of lectures + 11 h of hands-on sessions)

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