Zwentendorf Nuclear Power Plant Training (ZNPPT)

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CLASSROOM LECTURES DELIVERED BY UNIVERSITY PROFESSORS, NUCLEAR INDUSTRY EXPERTS AND STAFF FROM THE INTERNATIONAL ATOMIC ENERGY AGENCY (IAEA);

HANDS ON TRAINING AT THE ZWENTENDORF NUCLEAR POWER PLANT (ZNPP); AND

EXPERIENTIAL LEARNING CONSISTING OF INTERACTIONS WITH INDUSTRY LEADERS.

NPPT will provide students with a unique experience by providing full and unrestricted access to the ZNPP. The plant is situated in the picturesque countryside of Tullnerfeld, Austria, a 45 minute drive from the capital Vienna. The plant was built in 1978, was ready to operate, but was never commissioned nor fueled due to a policy decision of the Austrian Government. As a one-of-a-kind facility it allows unrestricted access to all parts of the plant including the reactor internal structures.

We provide Nuclear Power Plant Training (NPPT) program at Zwentendorf Nuclear Power Plant to nuclear engineering s t u d e n t s / n u c l e a r workforce. The NPPT program is designed to bring a group of nuclear engineering experts from research, academia and the industry to deliver a unique and robust program. The NPPT program is based on a multitier approach. It includes:

The centre provides comprehensive training in management, operation, maintenance and technical support necessary to develop a highly skilled workforce for a Nuclear Power Plant (NPP) and as such is often used as a training centre for the IAEA, European Commission (EURATOM), the United States Nuclear Regulatory Commission and regulators / operators from various countries.

OBJECTIVES

The objective of the training program is to offer radiation free hands-access to various plant components / structures / systems and develop nuclear acumen among participants through training modules and workshops.

The training modules at Zwentendorf NPP provide opportunity for:

• Understanding of activities associated with various stages of nuclear power plant through which it has to pass to see daylight

• Learning of internationally accepted provisions for nuclear safety, nuclear security, safeguards and obligations

• Access to various NPP structures, systems and components

• Understanding the functioning of various electrical, mechanical and instrumentation & control systems and associated troubleshooting

• Understanding of various engineering safety features for ensuring nuclear, fire, physical and industrial safety at NPP and provisions for precluding any breach to nuclear security.

• Understanding the licensing methodology and procedures for various stages of NPP and principles of quality assurance and technology management

• Understanding of activities of Regulatory Body, inspection methodology and associated procedures

• Understanding of role of emergency preparedness and safety culture for ensuring NPP safety

• Understanding of active safeguards provisions and additional protocols by International Atomic Energy Agency in member states

Outline of Training CoursesCOURSE NAME DURATION: 1 WEEK FOR EACH COURSE

DESCRIPTION OF THE COURSE

SPECIFIC TOPICS PLANT WALKDOWN

Nuclear Law

Basic principles of international law

Types of legal instruments

The physical protection /essential elements of safeguards measures will be shown during the walkdown outside and inside the plant.

n Binding instruments such as Conventions, Agreements and Treaties

n Non-binding instruments such as Codes of Conduct and Concept of Soft Law

n UN Security Council Resolutions, UN Charter, Chapter VII Resolutions

Areas of and Actors inInternational Nuclear Law

n Incorporation into national law, Different constitutional approaches

n Principles of International Nuclear Law

n Nuclear Safety, Security, Safeguards, Liability

n 3S concept and synergies between different areas

n IAEA, OECD/NEA, EURATOM, ABACC

International Nuclear Safety Law

n Convention on Nuclear Safety

n Conventions on Early Notification of a Nuclear Accident and on Assistance in the case of a Nuclear Accident including the IAEA emergency response network.

n Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste management

n Overview of IAEA Safety Standards and Missions (IRRS, NRSW,)

International Nuclear Security Law

n Convention on the Physical Protection of Nuclear Material

n UN Security Council Resolutions 1373 and 1540

n INFCIRC/225/Rev.4

n Overview of IAEA Security Guidelines and Missions (INSServ, IPPAS)

International Nuclear Non-Proliferation Law n Nuclear Non-proliferation Treaty

n Comprehensive Test Ban Treaty

n Nuclear Terrorism Convention

n Regional Nuclear Weapons Free Zones

n IAEA Safeguards

— Safeguards system

— Item-specific safeguards (INFCIRC/66/Rev.2)

— Comprehensive Safeguards (INFCIRC/153 (corrected)

— Additional Protocol (INFCIRC/540 (corrected)

n IAEA SSAC Missions

Other initiatives (Zangger Committee, Nuclear Suppliers Group)

Licensing Procedures & Methodology

Introduction to regulatory bodies

n Regulatory body, Infrastructure, Staffing and Technical Competence

To understand general layout and Regulatory Inspection of NPP System, Structures and Components (SSCs)

License procedures for lifecycle of NPP

n Involvement of Stakeholders, Site Permits, Design certification, Reviews, Safety Evaluation Report, Construction Permits, Commission Permit and Operation Permits.

Introduction to reactor types

BWR, PWR, CANDU, ABWR, AP1000, EPR , AGR, PHWR, APR 1400, VVER, ESBWR and GENERATION IV

The different designs and functionalities will be described. The future trends will also be presented.

Throughout the course differences of the other reactors types to the BWR will be pointed out.

Measurements of nuclear material in the nuclear power plant

Neutron Measurements

Gamma Measurements

The principles of the gamma and neutron measurements of fresh fuel and spent fuel will be presented. The different measurement equipment & techniques like the HLLNC, AWCC, etc. will also be described.

Strategic locations for measurements will be pointed out.

Site Selection

Introduction to site selection process

n Planning of site selection activities, Work control and site evaluation,

Identify and explain the features relevant/ important to site selection and safety aspects.

n Data collection and evaluation, report preparation and site finalization

Basic requirements for site selection and study of siting activities

n Geotechnical, Geological, Hydro-geological, Seismicity and Meteorological studies,

n External Events due to Natural Phenomena -

n Earthquakes and Surface Faulting, Geological Hazards, Meteorological, Flooding, Shoreline and Riverbank Erosion

Impact of external events n Human induced external events - Aircraft Crash, Chemical Explosion etc.

NPP Radiological impact study

n Activity dispersion through atmospheric pathways,

A visit to the IAEA Emergency Preparedness Center

n Activity dispersion through surface water,

n Radiation dose evaluation

Emergency preparedness n Feasibility of implementation of Off-site emergency planning

Seismic Data with Possible Scenarios

Overview of seismic studies

n Principles of Seismic Margin Analysis (SMA) and Seismic Probabilistic Safety Analysis (SPSA)

To explain some systems / structures and component designs. Sensitive seismic issues.Seismic evaluation

methodologies

Quality Management

Concept of Quality Management

n Various Quality Management Systems To explain QA requirements for different systems and components for example Nuclear Steam Supply System (NSSS), Turbine, Generator, Pumps etc.

Quality Assurance during Design & Construction

n Vendor Surveillance, Specifications checks,

Quality Assurance during Maintenance & Operations

n Applicable Codes and Standards

Quality Assurance for record keeping

n Quality Procurement Specifications – Quality Evaluation activity, Quality Audit, Quality Surveillance, Quality Inspection, Quality document review

Practical approaches for implementing standards and codes

n Operation, Maintenance, Testing, In-service Inspection and Technical Operation Control Procedures

n Preventive and Predictive Maintenance, Temporary and Permanent Modification

Nuclear Safety

Introduction to Nuclear safety

n Objective, Breach of nuclear safety in NPP Accident

Get familiar with different safety systems:Primary Containment Air Locks, Isolation Valves (PCIVs), Air Temperature Low-Low Set (LLS) Valves, Residual Heat Removal (RHR) Containment Spray System, Penetration Valve Leakage Control System (PVLCS), Main Steam Isolation Valve (MSIV),

Nuclear safety criteria n Containment of radioactive releases

Reactor safety analysis n Safety Barriers

Safety systems n Principle sources, Significant Events at NPPs,

Operating Experiences in safety

n The “International Nuclear Event Scale"

Classification of accidents n Design Basis Accidents, Beyond Design Basis Accidents, External Accident due to natural Causes

Dispersion of radioactive releases

n Dispersion Phenomena, Evaluation Techniques

COURSE NAME DURATION: 1 WEEK FOR EACH COURSE

DESCRIPTION OF THE COURSE

SPECIFIC TOPICS PLANT WALKDOWN

Classification of components

n Classification on the basis of Safety Functions, Leakage Control System (LCS), Suppression Pool, Hydrogen Ignitors, Drywell Purge System, Secondary Containment Isolation Valves (SCIVs), Standby Gas Treatment (SGT) System, Drywell Air Lock, Drywell Isolation Valves, Drywell Vacuum Relief System, Reactor Vessel Head, Sealing Feature, Bolting Features, Installation, Support Penetrations

Nuclear Safety (Contd.)

Failure mechanisms n Classification of pressure components on the basis of mechanical complexity

Introduction to engineered safety features

n Classification on the basis of resistance to external impacts

n Classification on the basis of I & C systems based on their safety functions

n Classification on the basis of Quality Assurance requirements

n Reactor Pressure Vessel, Piping, Pump, Valves, Containment System

n General characteristics, IAEA criteria, US general design criteria, EUR criteria

n Probabilistic Safety Analysis (PSA) and Deterministic Safety Analysis (DSA)

Instrumentation & Control Systems

Overview of nuclear instrumentation systems

Process instrumentation

Reactivity Measurement

Control rod drive mechanism

Control room panels

Operator information systems

Reactor protection systems

n Neutronic Instrumentation Walkdown:Emergency Core Cooling Systems (ECCS),Leak Detection And Isolation System (LDS),RHR System, Recirculation Flow Control System, High Pressure Core Flooder(HPCF) System, Automatic Depress-urizationSubsystem (ADS), Reactor Core IsolationCooling (RCIC) System, Safety Valve Control System, Turbine Bypass Control System,

n Source and Intermediate Range Detector, Radiation Counters, Pressure Transmitter, Temperature Probes,

n Pressurize Heater Controller, Reactor Trip Breaker, Traversing In-core Probe System, Multi-channel Analyzer, Spectroscope, Sensor, Controllers, Rod Position Indication System, Alarms and Enunciators, Control valves

n Instrumentation and control associated with ECCS, LDS, HPCF, RCIC

n I & C associated with Automatic depressurization system and recirculation flow control

Plant Engineering

Reactor design features

Reactor components

Fuel design features

Operational physics

Thermal Hydraulics

Reactor safety

Safety barriers

Reactor controls

Containment design & system

Core spray system

Suppression pools

Auto blow down system

Accident prevention provisions

Fuel handling facilities

Accident mitigation

n Core internals, functions of core internals Internals such as grid, control rods, control blades, neutron monitors, core barrel, recirculation pumps, jet pumps, moisture separators,reactor vessel head, sealing feature, bolting features, installation, support penetrations, fuel bundle, channel, flow path, design of fuel, control rod system line up and its functioning in field, containment spray system, line up and operation in field, suppression pool, its link with core spray and containment system, spent fuel pool system design.

n Reactor materials

n Different types of fuel, fuel design, fuel failures,

n Coolant flow

n Fission process, neutron transport concept,

n Nuclear design, kinematics and control

n Heat transport system

n Engineered safety features, Design basis evaluations,

n Spent fuel handling,

n Diesel Generators, LPCI, HPCI, ECCS,

n Containment cooling, power supplies, RHR

n Function of control rods, Adjuster rods,

n Liquid poison shut down system

n Inherent safety features

n Reactor Protection System, Shutdown Cooling System

Plant Operations & Maintenance

Principles of Operations & Maintenance

Training NPP personnel

Performance criteria

n Organizational Structure, Staffing, Competency See Nuclear Safety, Plant Engineering sections and I&Cn Competency and Licensing

n Performance Monitoring and Control Requirements,

n Procedures

Outline of Training CoursesCOURSE NAME DURATION: 1 WEEK FOR EACH COURSE

DESCRIPTION OF THE COURSE

SPECIFIC TOPICS PLANT WALKDOWN

Plant Operation and Maintenance (Contd.)

Supervision & Responsibility

Operations Management

Shift Management

Technical specifications

Outage management

Plant life management

Principles of operations

Spent fuel management

n Activities in Control Room,

n Technical Workshops and Interfaces

n Responsibilities, Authorization and Communications

n Limiting Conditions and Allowable Deviations

n Trending, Monitoring Evaluations

n Configuration Management Requirements

n Testing, Staffing, Inspections

n Performance Evaluation of various Approaches

n Information Collection and Benchmarking

Radiation Protection & Environmental Monitoring

Radiation protection procedures

Monitoring instrumentation

Dose budgeting

Introduction to off-normal incidents

Environmental monitoring techniques

Planning for highly radioactive jobs

n Workplace monitoring, A visit to CTBTO Monitoring System / SEIBERSDORF Laboratories

n Area radiation monitoring

n Survey techniques n Air monitoring techniques for particulates of

different size,

n Control of exposures, Iodine characterization, Contamination monitoring techniques

n Area Monitoring Instrumentation, Stack Monitoring Instrumentation

n ALARA ( As Low As Reasonably Achievable)

n Wide spread contamination, High air activity

n Sampling plan for onsite and off-site,

n Sampling and measurements of environmental samples,

n Laboratory procedures

n Contamination monitoring techniques

Radiation Emergency Planning & Response

Requirements for infrastructure for emergency response

A visit to the IAEA Emergency Response Unit

Safety CultureCode of conduct, Nuclear Industry Operating Organization Culture and Ethics

Note: Training courses could be tailor-made as per Client’s requirements

E. Emergency power diesel building

C. Decontamination building and solid materials storage

D. Workshop

B. Machinery building7. Turbine (high-pressure portion)8. Turbine (low-pressure portion)9. Condenser10. Interim reheater11. Supply water container12. Generator

A. Reactor building1. Safety vessel2. Reactor pressure vessel3. Personnel lock4. Fuel rod basin with a flood room5. Storage for new fuel rods6. Fuel rod changing machinery

PLAN FOR WALKDOWN

COURSE NAME DURATION: 1 WEEK FOR EACH COURSE

DESCRIPTION OF THE COURSE

SPECIFIC TOPICS PLANT WALKDOWN

About Zwentendorf NPP Training CentreThe Zwentendorf Nuclear Power Plant in Austria is a 723 MWe Boiling Water Reactor (BWR) plant situated in the picturesque countryside of Tullnerfeld, just an hour long drive from the International Atomic Energy Agency (IAEA) in Vienna. The plant was built in 1978, was ready to operate, but was never commissioned due to a policy decision of the Austrian Government.

RIENTEC, along with the plant owners EVN Liegenschaftsverwaltung GmbH, has established this plant as a training centre that offers unrestricted and radiation free

Contact:

Dr. Kaluba CHITUMBOTel: +43 (0) 6769319989

Email : k.chitumbo@rientec.com Info@rientec.com

Website : www.rientec.com

accessibility, which is not available in an operating NPP. The centre provides a realistic environment for hands-on training in the areas of management, operation, maintenance and technical support of a nuclear power plant to develop a highly skilled workforce for the global nuclear industry.

About RIENTECRIENTEC GmbH is a Vienna, Austria headquartered company, with competencies underpinned in nuclear energy related services and technologies. RIENTEC is resourced by some of the finest members in the nuclear industry consisting of academia and practitioners, and staff from international agencies. We bring subject matter experts for each of the services.