Home » Training programs » Miscellaneous technical courses oriented to WWER Technology

Miscellaneous technical courses oriented to WWER Technology

1. Preparation of the bid invitation for the first NPP

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

 

 

 

 

 

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

7

7

0

Objective: to achieve a good understanding of organization of  VVER based NPP, its supply chain, general concepts of refueling and maintenance.
2 Fuel cycles: from mining to waste disposal

8

6

2

Objective: to achieve a good understanding of  procedures to treat special nuclear and non-nuclear materials as well as operational wastes and spent fuel.
3 Siting procedures and criteria

8

6

2

Objective: to achieve a good understanding of  principles and consideration in site evaluation including issues on radionuclides migration (atmosphere and hydrology) and human induced events.
4 Fuel cycle economics

6

6

 

Objective: to achieve a good understanding of  the main financial needs to support life cycle of NPP.
5 Radiation & Environmental safety

10

8

2

Objective: to achieve a good understanding of  radiation effects, radioecological safety,  environmental monitoring, international  and Russian standards.
6 Safety culture

6

6

 

Objective: to achieve a good understanding of  general principles of safety culture and its implementation along NPP life cycle.
7 Licensing issues

10

10

 

Objective: to achieve a good understanding of  licensing procedure

8

 

National and International Safeguards and Accounting Standards

8

8

0

Objective: to achieve a good understanding of general principles and technologies of  material control, accounting and physical protection.
9

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

 

8

8

 

Objective: to achieve a good understanding of organizational structure of commissioning procedure,  IAEA and vendor recommendations.
10 Education & Training programmes in vendor country (Russian federation) supporting nuclear capacity building

10

10

 

Objective: to achieve a good 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.

11

Preparation of bid invitation specification

15

11

4

Objective: to achieve a good understanding of procedures and specifics of bid invitation.

12

Examination (final test)

4

 

4

  Total

100

86

14

2. Site selection and qualification

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

 

 

 

 

 

1

Russian reactor technology and NPP system design

7

7

0

Objective: to achieve a good understanding of organization of  VVER based NPP, its general layout, configuration and arrangement with special reference to site.

2

Nuclear legislation relevant to siting: international guidelines and Russian standards

6

4

2

Objective: to achieve a good understanding of basic site criteria and objectives of evaluation

3

Safety culture

6

6

 

Objective: to achieve a good understanding of  general principles of safety culture and its implementation along NPP life cycle with special emphasis to site.

4

Licensing issues

10

10

 

Objective: to achieve a good understanding of  licensing procedure

5

Radiation & Environmental safety

10

8

2

Objective: to achieve a good understanding of  radiation effects, hazard evaluation ,  environmental monitoring, international  and Russian standards.

6

Seismology

10

8

2

Objective: to achieve a good understanding of methodology to evaluate a ground motion hazard.

7

Site selection and qualification guidelines: international standards and Russian experience

10

10

 

Objective: to achieve a good understanding of guidelines and recommendation s, experience and best practices.

8

Probabilistic safety analysis

10

6

4

Objective: to achieve a good 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.

9

Migration of radionuclides (hydrogeology and atmosphere)

10

6

4

To achieve a good understanding of radioactive  source  parameters, migration modeling and associated hazards.

10

External human induced events in site evaluation

10

8

2

To achieve good  understanding  of general approaches and identification of potential sources of human induced hazard.

11

Social and economics issues

6

6

 

To achieve good  understanding  of  best practices in cooperating with social organizations

12

Recommendations on preparing  documents on site selection and evaluation

4

2

2

To achieve good  understanding  of  best practices in preparation of site qualification report.

13

Examination (final test)

1

 

1

  Total

100

81

19

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

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

 

 

 

 

 

1

Fuel cycles: from introductory concepts to fuel design

10

8

2

Objective: to achieve a good understanding of fuel cycle from the view point of fuel management (from fuel fabrication through transportation  to waste disposal) .

2

Reactor operation and control (VVER)

10

10

0

Objective: to achieve a good understanding of normal reactor operation and transients.

3

Fuel burnup and economics

6

6

0

Objective: to achieve a general understanding of irradiation effects  on NPP plants efficiency

4

Economics of fuel cycle

6

6

0

Objective: to achieve a good understanding of  the main financial needs to support life cycle of NPP focusing fuel management.

5

Guidelines for quality and reliability assurance programmes

6

6

0

Objective: to achieve a good understanding of  methods and procedures associated with quality and reliability assurance.

6

Fuel behavior under irradiation

10

8

2

Objective: to achieve a good 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

7

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

10

8

2

Objective: to achieve a good understanding of experimental methods an norms applied for fuel management along fuel cycle.

8

Deterministic safety analysis .

Part I : Methodology

14

 

14

Objective: to gain an experience with simulation of neutronics parameters under normal and normal operation conditions

9

Deterministic safety analysis.

Part II – Practical examples 

14

 

14

Objective: to gain an experience with simulation of thermohydraulics parameters under normal and normal operation conditions

10

Deterministic safety analysis.

Part III- Russian computer codes

8

 

8

Objective: to gain an experience with simulation of accidents

11

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

5

2

3

Objective: to gain an experience of source data preparation and transients calculation by RAINBOW code

12

Examination (final test)

1

 

1

  Total

100

54

46

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

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

 

 

 

 

 

1

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

10

8

2

To achieve a good understanding of nuclear fuel cycle and waste management from the view point of material properties related to non-proliferation

2

Effect of radiation, safety and radiation protection

10

10

 

To achieve a good understanding of radiation effects, radioecological safety,  environmental monitoring, international  and Russian standards

3

National and International Safeguards and Accounting Standards

10

10

 

To achieve a good understanding of standards from the view point of safety, security and safeguards.

4

Threat assessment

6

6

To achieve a good understanding of basic concepts and relationships between protection features and threat 

5

Physical protection systems design and evaluation

11

5

6

To achieve a good understanding of  infrastructure and procedures for detection and response  to incidents involving nuclear and other radioactive materials

6

Physical protection technologies and equipment

14

6

8

To achieve a good understanding of  technology and equipment  for detection and response  to incidents involving nuclear and other radioactive materials

7

Radioactive waste management

10

10

 

To achieve a good understanding of spent fuel and nuclear waste treatment

8

Measurement methods  in material control and accounting system

10

8

2

To achieve a good understanding of principles and applications of non-destructive methods

9

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

8

8

To achieve a good understanding of principles and applications of non-destructive methods

10

Statistical analysis of inventory difference  in MC&A

10

8

2

To achieve a good understanding of advanced methods in accounting nuclear materials

11

Examination (final test)

1

 

1

  Total

100

79

21

5. Non-proliferation of Nuclear Materials

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

 

 

 

 

 

1

Physical foundations for proliferation resistance

15

13

2

Objective: to achieve a good 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)

2

Barriers against proliferation

20

18

2

Objective: to achieve a good understanding of mechanisms to create barrier against unsanctioned proliferation of Plutonium as an essential issue of sustainable nuclear power generation

3

Protected fuel cycles

30

28

2

Objective: to achieve a general understanding of  isotope transformation within nuclear fuel cycle and specifics of organizing the protected fuel cycles

4

Proliferation resistance assessment methodology

20

16

4

Objective: to achieve a good understanding of existing approach to characterization and evaluation of non-proliferation issues of nuclear fuel cycle

5

Legal base of non-proliferation of nuclear materials

14

12

2

Objective: to achieve a good understanding of  international legislative basis foe non-proliferation measures and activities

6

Examination (final test)

1

 

1

  Total

100

87

13

6. Training Course for Top Managers of NEPIO: Start-up of nuclear power programme
No

Blocks and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

1 CICE&T experience in NPP personnel training

8

8

1.1 International Centre for NPP Personnel Training in CICE&T – Goals and Program

2

2

1.2 Centre for Technical Competence in CICE&T

2

2

1.3 Human factor reliability support in nuclear facilities – Russian experience

2

2

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

2

2

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

4

4

2.1 Features of power generation at NPP

2

2

2.2 NPP maintenance and repair

2

2

3 NPP  structure on the basis of qualifications and competences

12

4

8
3.1 NPP structure. Competences. Qualifications

4

4

3.2 Individual trajectories of training for foreign NPPs

8

8
4 Staffing at the NPP

8

8

4.1 The scheme of training for foreign NPPs

4

4

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

4

4

5 Organizational and financial schemes for NPP construction

8

8

5.1 Economic aspects of nuclear power plant construction

2

2

5.2 Nuclear power infrastructure  development:
supplier to customer assistance

2

2

5.3 Stages of Testing and Commissioning

4

4

6 Quality management during NPP construction

4

4

6.1 Management system of Operating Organization (Utility)

2

2

6.2 Requirements to Suppliers during NPP construction

2

2

7 NPP’s  staff,  knowledge  inspection and recruitment policy

14

14

7.1 NPP’s emergencies

2

2

7.2 Internet Nuclear Resources

1

1

7.3 Definitions  of  terms  in  the  field  of Nuclear  Knowledge  Management

1

1

7.4 NPP stages and staff re-changing

3

3

7.5 NPPs  lessons  learned

3

3

7.6 Systems Engineering

2

2

7.7 Requirements to the range of knowledge

1

1

7.8 NPP’s  indicators

1

1

8 Practical implementation of personnel policy at Russian NPPs

32

32
8.1 Technical Tour to Novovoronezhskaya NPP-1

16

16
8.2 Technical Tour to Novovoronezhskaya NPP-2

16

16
9 Full-scale simulators for NPP personnel training

8

8
9.1 Technical Tour to VNIIAES

8

8
 
Examination (final check)

2

2
  Total

100

50

50
7. Russian computer codes for safety analysis

No

Sections, disciplines and topics

Total,

hours

Including

Exam form

Lectures

On-site training, probation, business plays etc.

Handsonsessions,laboratorywork,workshops

1

2

3

4

5

6

7

1

Containment at NPP with VVER reactor and design -basis and beyond design-basis accidents scenarios

4

4

0

0

 

2

Modeling gas dynamics processes in the code KUPOL-M

4

2

0

2

 

2.1

Motion equation and pressure equation

2

1

0

1

 

2.2

Algorithm for solving the gas dynamics problem

1

0

0

1

 

2.3

Gas dynamics for high-velocity flow

1

1

0

0

 

3

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

4

2

0

2

 

3.1

Energy equation and mass transfer equations

2

1

0

1

 

3.2

Numerical solution

2

1

0

1

 

4

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

4

2

0

2

 

4.1

Analogy of heat and mass transfer

2

2

0

0

 

4.2

Calculation of heat transfer coefficients

2

2

0

0

 

5

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

4

2

0

2

 

5.1

Volumetric condensation

2

2

0

0

 

5.2

Equation for thermal conductivity and numerical solution peculiarities

2

0

0

2

 

6

Models for hydrogen recombination  and burning. Sprinkler system

4

2

0

2

 

6.1

Hydrogen recombination

2

0

0

2

 

6.2

Hydrogen burning model

1

0

0

1

 

6.3

Spray model

1

0

0

1

 

7

Working with the code KUPOL-М

10

0

0

10

 

7.1

Code compilation

1

0

0

1

 

7.2

Initial data file

7

0

0

7

 

8

Demonstration calculations using basic data

16

0

0

16

 

8.1

Initial data and their preparation

10

0

0

10

 

8.2

Analysis of obtained results

6

0

0

6

 

9

Calculations of key accident  processes in VVER containment

20

0

0

20

 

9.1

Initial data and their preparation

14

0

0

14

 

9.2

Analysis of obtained results

6

0

0

6

 

10

Test

2

0

0

2

 

Total

72

14

0

58

 

8. Project Management for NPP Construction

No

Blocks and topics

 

Total,

hours

including

lectures

Field classes, business games

hands-on sessions

1

2

3

4

5

6

1

The main features of the modern project management

4

4

0

0

2

Fuel production and quality and reliability assurance

16

8

8

0

2.1

Nuclear fuel behavior under irradiation

2

2

0

0

2.2

Technical requirements. Manufacturing. Quality assurance. Reliability

4

4

0

0

2.3

Advanced nuclear fuels

2

2

0

0

2.4

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

8

0

8

0

3

Organizational and financial schemes for NPP construction

18

18

0

0

3.1

NPP prices. Financing sources of NPP construction projects

8

8

0

0

3.2

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

2

2

0

0

3.3

Scope of construction. NPP economic efficiency

4

4

0

0

3.4

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

4

4

0

0

4

Contracts for NPP construction: designing, concluding and implementing

8

8

0

0

4.1

The general concepts of the contract, the basic maintenance

2

2

0

0

4.2

The construction contract, general provisions

2

2

0

0

4.3

The construction contract on a turnkey basis

2

2

0

0

4.4

Features of contracts on construction of NPP

2

2

0

0

5

Quality management during NPP construction

8

8

0

0

5.1

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

4

4

0

0

5.2

Quality audits and inspections during NPP construction

4

4

0

0

6

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

24

16

8

0

6.1

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

4

2

2

0

6.2

Principal heat scheme. Modes of operation

2

2

0

0

6.3

Reactor and primary circle. Reactor pressure vessel

4

2

0

0

6.4

Control rod drive

4

4

0

0

6.5

Steam turbine K-1200-6,8/50

4

2

0

0

6.6

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

4

2

0

0

6.7

Electrical systems

2

2

0

0

6.8

Technical Tour to LNPP-1

0

0

6

0

7

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

8

0

8

0

7.1

Technical Tour to LNPP-2

8

0

8

0

8

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

12

12

0

0

8.1

Project management processes. Project risk management processes

2

2

0

0

8.2

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

4

4

0

0

8.3

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

6

6

0

0

 
Examination (final check)

2

0

2

0

  Total

100

74

26

0

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

Sections and topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

1

Russian nuclear power plant projects with small-power nuclear reactors

2

2

0

2

Reactor plant of small capacity RUTA

2

2

0

3

Small-power nuclear reactor  EGP-6

2

2

0

4

Small power plant SVBR-100 : The concept of nuclear technology based on the modular fast reactors with lead-bismuth coolant SVBR-100

2

2

0

5

Floating NPP  small  nuclear reactor KLT-40S

28

28

0

5.1

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

2

2

0

5.2

General technical and economic characteristics of KLT-40S

2

2

0

5.3

Principal characteristics of KLT-40S

4

4

0

5.4

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

2

2

0

5.5

Basic technical characteristics of Floating Nuclear Heat and Power Plant

8

8

0

5.6

Safety and environmental impact of Floating Nuclear Heat and Power Plant

6

6

0

5.7

Operational management and economics of Floating Nuclear Heat and Power Plant

4

4

0

6

Fundamentals of heat transfer in nuclear reactor

18

18

0

6.1

Fundamentals of heat transfer in nuclear reactors

6

6

0

6.2

General aspects concerning reactor safety and severe accidents

6

6

0

6.3

Heat transfer in severe accidents in Light water reactors

6

6

0

7

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

10

10

0

7.1

Regulatory control of Physical Protection of
the Facility Using Nuclear Energy

4

4

0

7.2

Regulatory control of nuclear and  radioactive material control and accounting system

6

6

0

8

Regulation of technical nuclear safety

12

12

0

9

Legal and regulatory framework for licensing nuclear power plants with nuclear small-power reactors

6

6

0

10

Nuclear and Radiation Safety of Nuclear Power Plant

6

6

0

11

National and International  Safeguards and Accounting Standards

8

8

0

12

Concluding session and testing

4

0

4

  Total

100

96

4

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

Topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

1

Entry briefing-personnel actions in case of emergency.

Organizational matters (instructions, pass registration, etc.)

4

4

2

The design of the reactor unit and NPP main equipment plant

12

4

8

2.1

Design and operation of the reactor and the system of the primary circuit

4

4

2.2

The visit to Balakovo NPP. The round on the route: main control room of power unit №1→ turbine island of power unit №1 →Diesel generating standby electric power station -1→ onshore pump station – 1→ power unit №4→ cooling ponds → nitrogen– oxygen plant, an overview of the industrial area of the nuclear power plant

4

4

2.3

The visit to Balakovo NPP. The round with the visit of controlled area of power unit №1: safety systems premises (СБ А-036/1,2,3, 123/1,2,3, 327/1,2,3), oiling systems of the main circulation pump А-315/1,2, and oiling systems of makeup unit plant (А-018/1,2,3), makeup unit plant premises (119/1,2,3), the premises of active gas purification system (А-626/1,2,3 and gas purification).

4

4

3

Measuring parameters of the reactor island

7

3

4

3.1

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

1

1

3.2

Safety systems controllers

2

2

3.3

The visit to Balakovo NPP. The round on the route of safety systems premises (АЭ-408/1,2,3 thermal automatics and measurement shop) → the premises of automated system of turbine control (automatic control system of technological process-1000 ЭК-1203, thermal automatics and measurement shop)

4

4

4

Emergency protection and alarm system formation. Reactor unit management

16

8

8

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

4

4.2

The visit to Balakovo NPP. The round on the route of safety systems premises (АЭ-725 (thermal automatics and measurement shop), neutron flux control equipment (АЭ-438 (thermal automatics and measurement shop)

4

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

4.4

The visit to Balakovo NPP. The round on the route: premises .АЭ-729 (power limit regulator, automatic power regulator, alarm system), АЭ-733 (group and individual management system)

4

4

5

Operational modes of the reactor unit

32

32

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”

6

6

5.2

Training on simulators “Beyond design basis accident”

6

6

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”

6

6

5.4

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

6

6

5.5

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

4

4

5.6

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

4

4

6

Chemical technology of the primary circuit

8

4

4

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

4

4

6.2

The visit to Balakovo NPP. The round on the route: all NPP auxiliary building → makeup demineralizer → reagents block of the secondary circuit → turbine island → condensate purification plant → special water purification system → reagents block of the primary circuit

4

4

7

Reactor physics

20

20

7.1

Reactor physics. Introduction

8

8

7.2

The Next Generation Nuclear Plants

2

2

7.3

Kinetics

3

3

7.4

Principal physics of non-proliferation

7

7

 

8

Final exam

1

1

 

Total

100

43

57

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

Topics

Total,

hours

including

lectures

hands-on sessions

1

2

3

4

5

1

Entry briefing-personnel actions in case of emergency.

Organizational matters (instructions, pass registration, etc.)

4

4

2

The main equipment of the turbine island

12

4

8

2.1

Thermal circuit and the main equipment of the secondary circuit.

4

4

2.2

The visit to Balakovo NPP. The round on the route: main control room of power unit №1→ turbine island of power unit №1 (turbine island equipment)

4

4

2.3

The visit to Balakovo NPP. The round on the route: main control room of power unit №1→ turbine island of power unit №1 →Diesel generating standby electric power station -1→ onshore pump station – 1→power unit №4→ cooling ponds → nitrogen– oxygen plant, an overview of the industrial area of the nuclear power plant.

4

4

3

The system of automatic control and turbine protection

10

6

4

3.1

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

2

2

3.2

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

2

2

3.3

Operating modes of electro-hydraulic system of turbine control.

2

2

3.4

The visit to Balakovo NPP. The round on the route: turbine island 15,0 → → the premises of automated system of turbine control -1000 EК-1203.

4

4

4

Measuring the turbine island parameters

8

4

4

4.1

Measuring the turbine island parameters

4

4

4.2

The visit to Balakovo NPP. The round on the route: the premises of automatic control system of technological process ЭК-1206 (the boxes of unified set of technical tools), ЭК-1610 (the panel of sensors and the panel of regulators) thermal automatics and measurement shop.

4

4

5

Turbine protection

4

4

5.1

General principles of forming the technological protection

2

2

5.2

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

2

2

6

Operating modes of the turbine island equipment

24

24

6.1

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

4

4

6.2

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

4

4

6.3

Training on simulators “Unloading of power unit, disconnection of generator from the network and the transfer of the reactor unit into a hot state”.

5

5

6.4

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

3

3

6.5

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

4

4

6.6

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

5

4

7

Chemical technology of the secondary circuit

8

4

4

7.1

Chemical technology of the secondary circuit

4

4

7.2

The visit to Balakovo NPP. The round on the route: makeup demineralizer → condensate purification plant → laboratory of chemical analysis of the secondary circuit → the block of preparation and reagents input.

4

4

8

Final exams

2

2

 

Total

72

26

46

12. Financial Aspects of NPP Construction

Modules

Total,

hours

Including

Form of

control

lectures

practice

1

Module FF-11.01

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

7

5,5

1,5

Oral questioning

1.1

Lesson FF-11.01.1

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

2,5

2,5

1.2

Lesson FF-11.01.2

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

1,5

1

0,5

1.3

Lesson FF-11.01.3

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

3

2

1

2

Module FF-11.02

The NPP construction cost

6

5

1

Oral questioning

2.1

Lesson FF-11.02.1

Structure of CAPEX

3

3

2.2

Lesson FF-11.02.2

Methodology for CAPEX assessment. Review of the world prices

3

2

1

3

Module FF-11.03

Analysis of cost effectiveness for investment project of NPP construction

6

4,5

1,5

Oral questioning

3.1

Lesson FF-11.03.1

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

2

2

3.2

Lesson FF-11.03.2

Methodology for cost effectiveness analysis

4

2,5

1,5

4

Module FF-11.04

Project financing schemes. Contractual schemes for NPP construction

5

4

1

Oral questioning

4.1

Lesson FF-11.04.1

 

The most common methods of financing the NPP construction projects

2

2

4.2

Lesson FF-11.04.2

Types of contracts for NPP construction, examples

3

2

1

5

Module FF-11.05

Project cost management: methodology, theory and practice

6

5

1

Oral questioning

5.1

Lesson FF-11.05.1

Cost management methodology of the investment project

3

3

5.2

Lesson FF-11.05.2

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

3

2

1

6

Module FF-11.06

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

4

2

2

Oral questioning

6.1

Lesson FF-11.06.1

Common scenarios of NPP decommissioning

2

1

1

6.2

Lesson FF-11.06.2

Analysis of NPP decommissioning costs

2

1

1

7

Final examination

2

2

Written test

Total

36

26

10

13. Risks Assessment and Risk Management

Modules

Total, hours

Including

Form of control

lectures

practice

 

Instruction (organizational issues)

1/2

1/2

1

Module MA-15.01

The fundamental principles of risk management

5 1/2

3 1/2

2

Oral questio-

ning

1.1

Lesson MA-15.01.1 The fundamental principles of risk management

5 1/2

3 1/2

2

2

Module MA-15.02

The risk management process

8

5

3

Oral questio-

ning

2.1

Lesson MA-15.02.1

The risk management process

8

5

3

3

Module MA-15.03

The role of risk management in managing theNPP operation. Risk classification. The main types of risks

6

5

1

Oral questio-

ning

3.1

Lesson MA-15.03.1

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

6

5

1

4

Module MA-15.04

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

8

6

2

Oral questio-

ning

4.1

Lesson MA-15.04.1

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

8

6

2

5

Module MA-15.05

Risk management strategies in the nuclear power industry

7

5

2

Oral questio-

ning

5.1

Lesson MA-15.05.1

Risk Management Strategies in the nuclear power industry

7

5

2

6

Final examination

1

1

Written test

 

Total

36

24 1/2

11 1/2

14. NPP Safety Assessment based on Preliminary Safety Analysis Report

Modules

Total hours

Including

Form of control

lectures

practice

1

2

3

4

5

6

1

Module NS-12.01

Contents and purpose of Preliminary Safety Analysis Report

8

7

1

Oral questio-

ning

1.1

Lesson NS-12.01.1

Content and purpose of Preliminary Safety Analysis Report

8

7

1

2

Module NS-12.02

Regulation of nuclear and radiation safety

8

6

2

Oral questio-

ning

2.1

Lesson NS-12.02.1

Nuclear safety regulation

6

4

2

2.2

Lesson NS-12.02.2

Radiation safety regulation

2

2

3

Module NS-12.03

Using special purpose software for NPP safety assessment

19

15

4

Oral questio-

ning

3.1

Lesson NS-12.03.1

The use of RADUGA software for independent safety assessment

15

11

4

3.2

Lesson NS-12.03.2

The use of SCALE software for independent radiation safety assessment

2

2

3.3

Lesson NS-12.03.3

The use of SERPENT software for independent nuclear safety assessment

2

2

4

Module NS-12.04

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

6

4

2

Oral questio-

ning

4.1

Lesson NS-12.04.1

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

3

2

1

4.2

Lesson NS-12.04.2

Defining a list of design-basis accidents

3

2

1

5

Module NS-12.05

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

13

9

4

Oral questio-

ning

5.1

Lesson NS-12.05.1

Classification of systems and components on the effect on safety

1

1

5.2

Lesson NS-12.05.2

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

5

4

1

5.3

Lesson NS-12.05.3

Limits and conditions of safe operation

7

4

3

6

Module NS-12.06

Results of deterministic and probabilistic safety analysis

8

5

3

Oral questio-

ning

6.1

Lesson NS-12.06.1

Deterministic safety analysis

6

3

3

6.2

Lesson NS-12.06.2

Probabilistic safety analysis

2

2

7

Module NS-12.07

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

8

6

2

Oral questio-

ning

7.1

Lesson NS-12.07.1

Guidance on accident management

3

2

1

7.2

Lesson NS-12.07.2

Diagnosis of beyond-design basis accidents and accident management instructions

3

2

1

7.3

Lesson NS-12.07.3

Analysis of beyond-design basis accidents

2

2

8

Final examination

2

2

Written test

 

Total

72

52

20

15. Safety analysis for NPP with WWER reactors

Modules

Total hours

Including

Form of control

lectures

practice

1

2

3

4

5

6

1                    

Module NS-13.01

Key criteria and principles of safety assurance for NPP with WWER

19

13

6

Oral questio-

ning

1.1               

Lesson NS-13.01.1

Fundamentals of radiation safety

5

3

2

1.2               

Lesson NS-13.01.2

Fundamentals of nuclear safety

5

3

2

1.3               

Lesson NS-13.01.3

Fundamentals of industrial safety

5

4

1

1.4               

Lesson NS-13.01.4

Fundamentals of fire safety

4

3

1

2                    

Module NS-13.02

International safety policies and practices

8

8

0

Oral questio-

ning

2.1               

Lesson NS-13.02.1

NPP safety international policies and practices

8

8

3                    

Module NS-13.03

NPP site evaluation

4

4

0

Oral questio-

ning

3.1               

Lesson NS-13.03.1

NPP site evaluation

4

4

4                    

Module NS-13.04

Evaluation of NPP civil engineering structures

4

4

0

Oral questio-

ning

4.1               

Lesson NS-13.04.1

Evaluation of NPP civil engineering structures

4

4

5                    

Module NS-13.05

Safety concept for NPP with WWER

5

5

0

Oral questio-

ning

5.1               

Lesson NS-13.05.1

Safety concept for NPPs with WWER

6

6

6                    

Module NS-13.06

Assessment of the current safety status for NPP and analysis of events

4

4

0

Oral questio-

ning

6.1               

Lesson NS-13.06.1

Assessment of the current safety status for NPP and analysis of events

4

4

7                    

Module NS-13.07

NPP safety analysis. Emergency management

6

6

0

Oral questio-

ning

7.1               

Lesson NS-13.07.1

NPP safety analysis. Emergency management

6

6

8                    

Module NS-13.08

Personnel preparedness in the emergency response system.

Emergency preparedness of nuclear power facilities (including transportation)

4

4

0

Oral questio-

ning

8.1               

Lesson NS-13.08.1

Personnel preparedness in the emergency response system.

Emergency preparedness of nuclear power facilities (including transportation)

4

4

9                    

Module NS-13.09

NPP quality assurance and reliability

16

11

5

Oral questio-

ning

9.1               

Lesson NS-13.09.1

Quality assurance programme for NPP

4

3

1

9.2               

Lesson NS-13.09.2

Fuel quality assurance and reliability for NPP with WWER

6

4

2

9.3               

Lesson NS-13.09.3

Non-proliferation issues

6

4

2

10                 

Final examination

2

2

Written test

  Total

72

59

13

 

16. Specifics of WWER Design: Safety Issues

Module

Total, hours

Including

Form of control

lectures

practice

1

Module NS-21.01

Layout of NPP with WWER-type reactor

12

10

2

Oral questio-

ning

1.1

Lesson NS-21.01.1

WWER-technology, R&D history

2

2

1.2

Lesson NS-21.01.2

NPP layout with WWER-type reactor

8

6

2

1.3

Lesson NS-21.01.3

Evolution of layout solutions of NPP with WWER-type reactor

2

2

2

Module NS-21.02

Reactor facility and refueling system design

22

18

4

Oral questionning

2.1

Lesson NS-21.02.1

Reactor vessel and internals

6

4

2

2.2

Lesson NS-21.02.2

Reactor head and upper unit

4

3

1

2.3

Lesson NS-21.02.3

Reactor core

5

4

1

2.4

Lesson NS-21.02.4

MPS-type refueling machine

2

2

2.5

Lesson NS-21.02.5

The evolution of reactor facility with WWER-type reactor

1

1

2.6

Lesson NS-21.02.6

Configuration of ventilation and air conditioning system equipment

4

4

3

Module NS-21.03

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

28

22

6

Oral questioning

3.1

Lesson NS-21.03.1

WWER nuclear fuel

5

4

1

3.2

LessonNS-21.03.2

The use of burnable absorber

5

4

1

3.3

Lesson NS-21.03.3

Radioactive waste disposal and recycling

8

6

2

3.4

Lesson NS-21.03.4

Radioactive waste and radioactive sources storage

5

4

1

3.5

Lesson NS-21.03.5

Nuclear fuel storage

5

4

1

4

Module NS-21.04

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

24

14

10

Oral questioning

4.1

Lesson NS-21.04.1

Safety fundamentals for NPP with WWER

6

4

2

4.2

Lesson NS-21.04.2

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

16

8

8

4.3

Lesson NS-21.04.3

Safety levels for NPP with WWER

2

2

5

Module NS-21.05

Turbine hall layout for NPP with WWER

10

10

0

Oral questioning

5.1

Lesson NS-21.05.1

The operation principles of steam turbine

8

8

5.2

Lesson NS-21.05.2

Steam turbine operation fundamentals and controlled parameters

2

2

6

Module NS-21.06

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

24

18

6

Oral questioning

6.1

Lesson NS-21.06.1

Data collecting and processing for reactor unit

6

5

1

6.2

Lesson NS-21.06.2

Nuclear chain reaction control in WWER-type reactors

8

5

3

6.3

Lesson NS-21.06.3

Operating modes

4

4

6.4

Lesson NS-21.06.4

NPP start-up

6

4

2

7

Module NS-21.07

Ensuring the safe operation of NPP with WWER and operation documentation

8

6

2

Oral questioning

7.1

Lesson NS-21.07.1 Ensuring NPP with WWER safe operation

8

6

2

8

Module NS-21.08

WWER water chemistry

4

3

1

Oral questioning

8.1

Lesson NS-21.08.1

WWER water chemistry

4

3

1

9

Module NS-21.09

NPP personnel management. Plan for the personnel and public protection

6

6

Oral questioning

9.1

Lesson NS-21.09.1

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

2

2

9.2

Lesson NS-21.09.2

Personnel and population protection action plan in case of emergency

4

4

10

Final examination

6

6

Written

test

 

Total

144

107

37

17. Radiation Safety and Health Protection

Modules

Totalhours

Including

Form of control

lectures

practice

1

ModulePR-11.01

Ionizing radiation sources

4

4

0

Oral questioning

1.1

Lesson PR-11.01.1

Characteristics of nuclei and nuclear transformations

1

1.2

Lesson PR-11.01.2

Radiation spectra. Characteristics of radionuclide sources

1

1.3

Lesson PR-11.01.3

Primary interaction of ionizing radiation with matter. Radiation energy transfer

2

2

Module PR-11.02

Biological effects of ionizing radiation and health effects

4

3

1

Oral questioning

2.1

Lesson PR-11.02.1

Modern view on biological effects of ionizing radiation. Health effects

1

0.5

2.2

Lesson PR-11.02.2

Acute and chronic radiation syndromes

1

0.5

2.3

Lesson PR-11.02.3

Biological effects of radionuclides intake and internal exposure dose

1

3

Module PR-11.03

Dosimetry and assessment of risks associated with doses

8

5

3

Oral questioning

3.1

Lesson PR-11.03.1

Penetrating power and protection

0.5

1

3.2

Lesson PR-11.03.2

Assessment of dose related risks

1

3.3

Lesson PR-11.03.3

The system of dosimetry quantities in radiation safety

1

1

3.4

Lesson PR-11.03.4

Dosimetry of ionizing radiation

2.5

1

4

Module PR-11.04

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

4

3

1

Oral questioning

4.1

Lesson PR-11.04.1

Equipment containing radioactive substances. Sources of ionizing radiation at NPP

2

4.2

Lesson PR-11.04.2

Design specifics of radiation protection

1

1

5

Module PR-11.05

Fundamentals and requirements for radiation safety standards

8

7

1

Oral questioning

5.1

Lesson PR-11.05.1

Radiation safety standards

4

5.2

Lesson PR-11.05.2

Main rules of radiation safety assurance

1.5

5.3

Lesson PR-11.05.3

Handling of radiation sources at NPP with WWER

1.5

1

6

Module PR-11.06

Radiation safety rules at NPP

9

6

3

Oral questioning

6.1

Lesson PR-11.06.1

Requirements and rules of radiation safety assurance

5

6.2

Lesson PR-11.06.2

Requirements for radiation monitoring at NPP with WWER

1

3

7

Module PR-11.07

Radioactive waste management

7

5

2

Oral questioning

7.1

Lesson PR-11.07.1

Radioactive wastes and their sources at NPP with WWER

0.5

7.2

Lesson PR-11.07.2

Radiation safety of radioactive waste management

2.5

7.3

Lesson PR-11.07.3

Requirements for receipt and dispatch of radioactive wastes

1.5

7.4

Lesson PR-11.07.4

Emergency response for radioactive waste management

0.5

2

8

Module PR-11.08

Radiation control. Dose reduction measures at NPP with WWER

8

5

3

Oral questioning

8.1

Lesson PR-11.08.1

Organization of radiation control at NPP with WWER

1.5

8.2

Lesson PR-11.08.2

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

2.5

8.3

Lesson PR-11.08.3

Staff responsible for specific safe working procedures

0.5

8.4

Lesson PR-11.08.4

Task order and radiation work permit management

0.5

3

9

Module PR-11.09

Basics of ALARA principle

4

2

2

Oral questioning

9.1

Lesson PR-11.09.1

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

1

9.2

Lesson PR-11.09.2

Application of ALARA methodology during activities associated to radiation risks

1

2

10

Module PR-11.10

Investigation of emergency and accidental exposure of the personnel

5

3

2

Oral questioning

10.1

Lesson PR-11.10.1

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

1

10.2

Lesson PR-11.10.2

Organization of investigation of emergency or accidental exposure

1

10.3

Lesson PR-11.10.3

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

1

2

11

Module PR-11.11

Personnel and public protection measures in case of radiation accidents

9

6

3

Oral questioning

11.1

Lesson PR-11.11.1

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

1

11.2

Lesson PR-11.11.2

Planning and implementation of protection measures for the public

4

11.3

Lesson PR-11.11.3

Phases of protective measures

1

3

12

Final examination

2

0

2

Written test

Total:

72

49

23

 

18. Policy on Decommissioning and Regulatory Control

Modules

Total,

hours

Including

full-time

Form of control

lectures

practice

1

Module RW-12.01

The basic concepts of NPP decommissioning

4

3

1

Oral question-ning

1.1

Lesson RW-12.01.1

The decommissioning process

2

2

1.2

Lesson RW-12.01.2

Basis for the organization of decommissioning

2

1

1

2

Module RW-12.02

World and national practices of NPP decommissioning

3

3

0

Oral question-ning

2.1

Lesson RW-12.02.1

World practice of decommissioning

2

2

2.2

Lesson RW-12.02.2

National practice of decommissioning

1

1

3

Module RW-12.03

Regulatory and safety issues of NPP decommissioning

5

5

0

Oral question-ning

3.1

Lesson RW-12.03.1

The regulation of decommissioning

3

3

3.2

Lesson RW-12.03.2

Safety analysis at decommissioning

2

2

4

Module RW-12.04

NPP decommissioning project management

6

3

3

Oral question-ning

4.1

Lesson RW-12.04.1

Theoretical basis for the decommissioning project management

3

2

1

4.2

Lesson RW-12.04.2 Conducting the SWOT-analysis of a decommissioning project

3

2

1

5

Module RW-12.05

Technological issues of NPP decommissioning projects

6

5

1

Oral question-ning

5.1

Lesson RW-12.05.1

Technological issues of decommissioning projects

6

5

1

6

Module RW-12.06

Economics of NPP decommissioning

3

3

Oral question-ning

6.1

Lesson RW-12.06.1

Economics of decommissioning

3

3

 

7

Module RW-12.07

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

5

5

0

Oral question-ning

7.1

Lesson RW-12.07.1

Social aspects of decommissioning

2

2

7.2

Lesson RW-12.07.2

Managing human resources in decommissioning projects

3

3

8

Module RW-12.08

Analysis of the world practice in NPP decommissioning

3

1

2

Oral question-ning

8.1

Lesson RW-12.08.1

Analysis of the world practice of decommissioning

3

1

2

9

Final examination

1

1

1

Written test

 

Total

36

28

8

 

19. Development and implementation of integrated programmes on remediation of uranium production legacy sites
# Module, topics Hours of training Control
Total Training forms
Lecture Workshop Individual work
1 Introduction the environmental assessment and remediation in areas affected by uranium production legacy sites 22 16 6 0 Oral questioning
1.1 Environmental impacts of uranium production 2 1 1
1.2 Conceptual Site Model for uranium production legacy sites 6 4 2
1.3 Radioactivity and radiation. Behavior of radionuclides in the environment 2 2
1.4 System of radiological protection 2 2
1.5 Safety culture in remediation programmes 2 2
1.6 Regulatory framework for remediation programmes 3 2 1
1.7 Interaction with regulatory bodies 2 1 1
1.8 Involvement of stakeholders 3 2 1
2. Remediation planning for uranium production legacy sites 12 9 3 0 Oral questioning
2.1 Environmental remediation: terms, concepts, phases 2 2
2.2 Data collection for uranium legacy site 2 2
2.3 Remediation purposes 2 2
2.4 Planning process for remediation programmes 4 2 2
2.5 Training of the personnel 2 1 1
3. Implementation of the remediation programmes 21 15 6 0 Oral questioning
3.1 Overall management for remediation programmes 2 2
3.2 Development and realization of monitoring strategies in compliance with remediation criteria 6 4 2
3.3 Safety assurance and safety control programme 2 2
3.4 Soil and groundwater remediation techniques, tools, and methods 4 2 2
3.5 Waste management 3 1 2
3.6 Cost estimate 2 2
3.7 Report on completion of  a remediation programme 2 2
4. Post-remediation management at uranium production legacy  sites 16 8 4 4 Oral questioning
4.1 Post-remediation monitoring 2 2
4.2 Data management 2 2
4.3 Long-term stewardship, institutional control, liability management 2 2
4.4 National good practices (study cases)  in remediation of uranium production legacy sites 8 4 4
4.5 World good practices (study cases)  in remediation of uranium production legacy sites 2 2
5. Final control 1 1 Written test
6. Total 72 48 19 5  
20. General aspects of WWER technology. Russian computer codes for safety assessment
No Topics Total,hours Including Exam  form
Lectures Practice
1 Layout of NPP with WWER-type reactor 8 8 0
2 WWER Safety Systems 8 6 2
3 Analytical Simulator  WWER-1000 24 2 22
3.1 Introduction to the simulator of WWER-1000 2 2 0
3.2 Practice on the WWER-1000 simulator 22 0 22
4 WWER fuel 30 22 8
4.1 Chemical composition, types and basic operational characteristics of nuclear fuel. Fuel behavior under irradiation. Modern technical requirements for nuclear fuel 8 8 0
4.2 WWER fuel. The use of burnable absorber 4 4 0
4.3 Nuclear fuel fabrication techniques. Perspective fuel types 12 10 2
4.4 Technological scheme of nuclear fuel fabrication: from the powder to fuel. Tech Tour to MSZ. 6 0 6
5 Personnel Management for NPP with WWER-type Reactor 4 4 0
6 Computer codes for safety assessment 44 28 16
6.1 Codes and computational tasks 4 4 0
6.2 Russian computer codes for safety assessment 8 8 0
6.3 Status of MCU code. A modular structure of MCU code. Input data, geometry, source and tally description. Sample problems and practice 32 16 16
7 Management issues of NPP with WWER 24 4 20
7.1 Reactor Island 8 2 6
7.2 Turbine Island 8 2 6
7.3 NPP under the operation. Technical Tour to NPP 8 0 8
8 Deterministic safety analysis in severe accident analysis. Computer code SOCRAT 36 20 16
8.1 Getting started with SOCRAT modeling: general description of SOCRAT and modeling of thermal hydraulics
8.2 Modeling of core degradation 8 4 4
8.3 Modeling of the late stage of a severe accident (in-vessel and ex-vessel stages) 8 4 4
8.4 Modeling of fission products build-up, release, transport and deposition 8 6 2
8.5 Examples of practical application of SOCRAT code in resolving the safety issues 4 2 2
9 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. 36 28 8
9.1 RSES (State Unified System of Prevention and Response to Emergence Situations). Russian emergency response systems to radiation hazards. 12 12 0
9.2 Computer codes for the justification of radiation safety for population and the environment. International experience. Classification 16 16 0
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) 4 0 4
9.4 Examples of the use of software packages to predict radiation situation after the accident at Fukushima 4 0 4
Test 2 0 2
Total 216 122 94
21. Methodology and Practices for Industrial Involvement

Course was piloted on May 27, 2015

# Modules Total, hours Including
lectures Practice/self-study
       
1 Industry Procurement Standard 14 8 6
1.1 WWER design. Safety issues 4 4
1.2 The ROSATOM’s concept for procurement 8 2 6
1.3 Unified industry procurement standard of the State Corporation “Rosatom” (UIPS) 2 2
2 Industrial Involvement and Procurement. Technical Tour to ZiO Podolsk 16 8 8
2.1 Basic principles of design, manufacturing and supply of equipment 8 4 4
2.2 Industrial Involvement and procurement 8 4 4
3 Becoming a knowledgeable customer: build up the technical competences for owner/operator 4 4
3.1 Build up technical competences For owner/operator at the pre-construction stage 2 2
3.2 Build up technical competences For owner/operator at the stage of NPP construction, operation and commissioning 2 2
4 Technical Tour to Novovoronezh NPP 8 4 4
4.1 Operation and construction activities of NV NPP 4 4
4.2 NPP personnel training 4 4
5 Technical Tour to JSC Atomenergoremont 4 4
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 2 2
5.2 Maintenance personnel training 1 1
5.3 Licenses of safety authorities for responsible works and production activities in the nuclear industry and power engineering 1 1
6 NPP Maintenance Staffing   6 1 5
7 Training on Industrial Involvement and Staffing 18 6 12
7.1 Local market analysis for suppliers of goods and services for the NPP construction needs 2 2 4
7.2 Development of specifications for suppliers. Procurement procedures 2 2 4
7.3 Staffing of contractors and subcontractors 2 2 4
8 Test 2 2
  Total 72 35 37
22. Quality Management and Quality Assurance

Course was piloted on June 22 – July 04, 2015

# Modules Total, hours Including
Lectures Practice/self-study
1 The QM system of ROSATOM 4 4
1.1 The Quality Management System of the ROSATOM. The main activities of the ROSATOM QMS. 2 2
1.2 QMS development directions 2 2
2 The legislation of the Russian Federation in the field of QA&QM. Specific issues 4 4  
2.1 Fundamentals and scope of the standard series ISO 9000 1 1
2.2 The legislation of the Russian Federation in the field of QA&QM. Specific issues 3 3
3 Integrated QMS of JSC “Concern Rosenergoatom” 4 4
3.1 Quality assurance during NPP construction 2 2
3.2 Quality assurance system during NPP startup and adjustment works 2 2
4 Quality Control Organization on the NPP Construction Site 4 4
4.1 Concept of QMS Implementation in the Directorate of NPP during construction 2 2
4.2 Organization and description of the QMS process 2 2
5 Nondestructive control 8 8  
5.1 Nondestructive control and technical diagnostics 4 4
5.2 Resource management equipment of methods nondestructive control and technical diagnostics 2 2
5.3 Economic indicators use nondestructive control of equipment 2 2
6 Tech tour to Research Institute of Introscopy and National Research University MPEI 8 8
6.1 The latest trends in the field of non-destructive testing. MSIA SPECTRUM 4 4
6.2 Visit to NDC laboratory of MPEI 4 4
7 The organization of incoming inspection of  the documents, equipment and expediting during construction phase on NPP site 4 4  
7.1 The organization of incoming inspection of the documents and equipment. 3 3
7.2 The organization of expediting construction and installation work 1 1
8 Project management with the use of Microsoft Office Project 8 2 6
8.1 Project management framework using  Microsoft Office Project 2010 2 2
8.2 Project management Cases. 6 6
9 Planning and quality control of work on the NPP pre-construction phase 8 2 6
9.1 Case 1. Initial and boundary condition definition 2 2
9.2 Project management Cases. 6 6
10 Planning and control quality of work on the NPP construction and installation work phases 6 2 4
10.1 Case 2. Initial and boundary condition definition 2 2
10.2 Project management Cases. 4 4
11 Tech tour to Leningrad NPP 8 8
11.1 NPP under construction 4 4
11.2 NPP personnel training 4 4
12 Tech tour to TK OMZ-Izhora (Izhorskiy Zavod) 4 4
13 Final test 2 2
  Total 72 34 38
23. Stakeholder Involvement
# Modules

Total

hours

Including

 

Form of control
lectures practice
1

Module SI01

Basic elements of SI

8 6 2 Oral questioning
1.1

Lesson SI01.1

International and national requirements and recommendations for SI

2 2
1.2

Lesson SI01.2

Outline of SI programme

2 2
1.3

Lesson SI01.3

General approaches to the SI strategy and plan development

2 2  
1.4

Lesson SI01.4

Practical exercise “Stakeholder matrix”

2   2  
2

Module SI02

Organization’s activities in the area of  SI

5 3 2 Oral questioning
2.1

Lesson SI02.1

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

1 1
2.2

Lesson SI02.2

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

1 1  
2.3

Lesson SI02.3

Risk management of the SI programme implementation.

1 1
2.4

Lesson SI02.4

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

2   2
3

Module SI03

Methods and instruments for   SI

9 6 3 Oral questioning
3.1

Lesson SI03.1

SI principles

1 1
3.2

Lesson SI03.2

Methods and instruments of involvement

2 2
3.3

Lesson SI03.3

Collaboration between the newcomer and vendor countries

1 1
3.4

Lesson SI03.5

Youth involvement

1 1
3.5

Lesson SI03.5

Russian experience

2 2
3.6

Lesson SI03.6

Practical exercise “Methods and instruments of involvement”

2   2  
3.7

Lesson SI03.7

Practical exercise “Youth involvement”

1   1  
4

Module SI04

Risk communication

4 3 1 Oral questioning
4.1

Lesson SI04.1

Hazards and risks associated with the nuclear power

1 1
4.2

LessonSI04.2

Risk perception and public acceptance of risks

1 1
4.3

Lesson SI04.3

Public communication on the risks associated with the nuclear power

1 1
4.4

Lesson SI04.4

Practical exercise: “Risk communication”

1   1  
5

Module SI05

Information center

4 2 2 Oral questioning
5.1

Lesson SI05.1

Information center goals and structure

1 1
5.2

Lesson SI05.2

Methods and instruments used in the information center

1 1
5.3

Lesson SI05.3

Practical exercise “Visit to Information Centre”

2 2
6

Module SI06

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

4 2 2 Oral questioning
6.1

Lesson SI06.1

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

1 1
6.2

Lesson SI06.2

Communication with the international organizations and neighboring countries.

1 1
6.3

Lesson SI06.3

Practical exercise “Scenario for public hearings”

2 2
7 Final examination 2 2 Written test
  Total: 36 25 11