INSC Programme 2017
EuropeAid/136877/DH/SER/Multi
project MC3.01/14
Training and Tutoring for experts of the NRAs and their TSOs for developing or strengthening their regulatory and technical capabilities
Training Module 4
Regulatory Control of Nuclear Site-Inspection on I&C System and Electrical Systems
2 – 6 October, 2017
Rome, Italy
Introduction
A 5 day training module covering the design, conduct, reporting and follow up of inspection programmes for reactor electrical systems and instrumentation and control systems. It addresses activities undertaken by the regulatory authority to assure compliance with safety requirements during design, manufacture/fabrication, construction, installation and testing, commissioning and operation phases of the nuclear power plant lifetime. It includes design, conduct, reporting and follow up of regulatory inspection programmes during these phases. The module is made up of presentations, exercises and key issue discussion sessions and is presented by internationally recognised experts from European nuclear regulatory authorities and international organisation.
The training is intended for professionals involved in regulatory processes related to the design, construction, commissioning and operations of nuclear power plants and research reactors. Firstly, it is intended to create an understanding of compliance assurance activities undertaken by the regulatory authority, second the importance to safety of reactor electrical systems and instrumentation and control systems and their consideration in the safety assessment process and third the design, conduct, reporting and follow up inspection processes. It covers the design, construction, commissioning and operational phases and the regulatory interaction, inspection and follow-up during these phases of project development.
Participants will require a basic knowledge of nuclear installation technology, nuclear and radiation safety and nuclear regulatory processes.
Educational objective
The objective of this training module is to provide trainees with an understanding of regulatory compliance assurance activities and their application to reactor electrical systems and instrumentation and control systems during design, manufacture, construction, installation, commissioning and operation. The training will address the design, conduct and follow up of inspection programmes for these activities giving trainees an understanding of how regulatory processes work in practise.
Training course description
Including the general introduction, the module will consist of 5 days of training, which will cover the following subjects:
- The basis and role of inspection in the overall licensing process
- The importance to safety of reactor electrical systems and instrumentation and control systems
- Design, conduct, reporting and follow up of inspection programmes for SSCs during design, manufacture, construction, testing, commissioning and operation
The table below shows the subjects that will be covered during the 5 day course. A number of practical exercises will take place during the week in which participants will work in groups to address issues related to the subject matter being presented. Each day will have a summary session to enable general feedback and discussion of the topics covered during the day. A round table discussion session will take place at the end of the module to address issues identified by participants, which will be followed by a multiple choice test covering the material presented during the module. The module will be concluded with an evaluation of the module. At this time, the participants’ impressions of the module will be gathered and the satisfaction of the needs expressed on the first day of the training session will be reviewed. The lectures will be distributed to the participants in electronic format.
The course timetable, list of lecturers with their brief CV and the synopsis of the lectures are included hereafter. CVs of the lecturers in standard format are attached as separate files.
Timetable of the training module 4: Regulatory Control of Nuclear Site-Inspection on I&C System and Electrical Systems
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09:00-10:00 |
10:00-11:00 |
11:15-12:30 |
14:00-15:00 |
15:15-17:00 |
17:00-17:15 |
|
A – Monday |
A.1 Introduction to the course – basis and role of inspection in the overall licensing process Phil Metcalf |
A.2 Organisation and staffing of the regulatory body for inspection of I & C and electrical power systems Peter Hughes |
A.3 Regulatory review and assessment and the linkage to inspection Phil Metcalf |
A.4 Regulatory documentation Peter Hughes |
A.5 I&C Principles for Nuclear Facilities and Current Challenges Mauro Cappelli |
A.6 Summary |
|
B – Tuesday
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B.1 Safety requirements for electrical power systems for NPPs and research reactors Peter Hughes |
B.2 Analogue I&C Systems Mauro Cappelli |
B.3 Digital I&C Systems Mauro Cappelli
|
B.4 Identification and classification of SSCs and safety assessment Phil Metcalf |
B.5 Classification of I & C and electrical power systems Peter Hughes |
B.6 Summary |
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C – Wednesday
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C.1 Design guidelines for electrical power systems Peter Hughes |
C.2 Derivation of limits, controls and conditions and establishment of regulatory conditions of authorisation Phil Metcalf
|
C.3 Design, conduct, reporting and follow up of inspection processes associated with electrical power systems and components Peter Hughes |
C.4 Example inspection programme for electrical power systems Peter Hughes |
C.5 Group discussion on inspection of electrical power systems Peter Hughes, Mauro Cappelli |
C.6 Summary |
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D – Thursday
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D.1 . Design and software considerations for I & C systems
Peter Hughes |
D.2 Application of FPGA based technology for I&C systems Mauro Cappelli
|
D.3 Design, conduct, reporting and follow up of inspection processes associated with I & C systems and components Peter Hughes |
D.4 Example inspection programme for I&C systems Peter Hughes
|
D.5 Exercise |
D.6 Summary
|
|
E – Friday
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E.1 Topical issues with inspection of I & C and electrical power systems Peter Hughes, Mauro Cappelli |
E.2 Round table discussion Peter Hughes, Mauro Cappelli, Phil Metcalf |
E.3 Test
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E.4 Course evaluation and closure
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Contents of the training module 4; Regulatory Control of Nuclear Site-Inspection on I&C System and Electrical Systems
Day 1 – Regulatory approach to inspection, and compliance assurance
A.1 Introduction to the course – basis and role of inspection in the overall licensing process - Phil Metcalf
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants research reactors
Synopsis
The safety of nuclear installations has a high dependence on the design, manufacture, installation, testing, proper operation and maintenance of all structures, systems and components that are of importance to safety including electrical power and I & C systems and components that play a role in the safety of the facility. This training course deals with the regulatory approach to assuring compliance of all these elements with safety requirements. This presentation addresses the basic role of inspection in the nuclear licensing process and introduces the content and structure of the course.
A.2 Organisation and staffing of the regulatory body for inspection of I & C and electrical power systems - Peter Hughes
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants research reactors, organisation and staffing, nuclear regulatory authority Synopsis
Regulatory process associated with the inspection of structures, systems and components important to safety and in particular electrical power and I & C systems will be discussed, and the organisation and staffing of regulatory bodies to both develop and put in place these processes will be presented. Consideration will be given to the range of technical disciplines necessary, the timeframes involved, operator/regulator interaction and the integrated decision making process.
A.3 Regulatory review and assessment and the linkage to inspection - Phil Metcalf
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants research reactors, regulatory review, safety assessment
Synopsis
The regulatory review and assessment processes related to determining the adequacy of design, manufacture, installation, commissioning, operation and maintenance of all nuclear power plants structures, systems and components will be addressed. The identification of aspects that must be assured for safety purposes will be discussed and how a linkage is created with inspection activities undertaken to confirm that safety requirements will be fulfilled.
A.4 Regulatory documentation - Peter Hughes
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants research reactors, regulatory documentation
Synopsis
Licensees are required to document safety assessments of nuclear installations, derive operating technical specifications and establish surveillance and testing, in-service inspection, maintenance, radiation protection and other programmes. Operating procedures must also be developed to comply with operation technical specifications and to implement the control programmes. All these documents are subject to review and various levels of approval by the regulatory authority. An overview will be presented of the required documentation.
A.5 I&C principles for nuclear facilities and current challenges - Mauro Cappelli
Key words nuclear safety, principles for instrumentation and control systems, nuclear power plants research reactors
Synopsis
The lecture gives a general overview of instrumentation and control topics for nuclear applications. Why a plant must be monitored? Why a plant must be controlled? The answer to these questions gives rise to the introduction of sensors and physical actuators, and to the concept of control and closed loop control systems. The lecture provides a comprehensive, yet introductory description of many aspects of modern nuclear instrumentation and control. A particular focus will be on the significance of I & C systems for safety and the challenges posed by I & C technology. I & C systems will be described in terms of their physical, functional and lifecycle features. A brief overview will be presented of all I & C product phases (design, qualification, supply chain commissioning, training, operations and maintenance, modernization). Finally, the lecture outlines the potential challenges to be faced when a new technology must be introduced (safety, security and licensing driven issues).
Day 2 – Importance to safety of electrical systems and I & C systems
B.1 Safety requirements for electrical power systems for NPPs and research reactors - Peter Hughes
Key words nuclear safety, electrical power systems, nuclear power plants, research reactors, safety requirements Regulatory inspection processes for I & C systems
Synopsis
This presentation will describe the electrical systems at NPPs (and research reactors). The safety requirements that are applicable to electrical power systems will be identified and discussed. The application of the graded approach to safety requirements for research reactors will be covered. The role of codes and standards, the design considerations that arise for nuclear safety and the design considerations that arise for electrical design will also be covered. The safety requirements for the design bases for the electrical power systems will be introduced and the considerations that the regulator needs to give to developing a suitable inspection plan.
B.2 Analogue I&C Systems - Mauro Cappelli
Key words nuclear safety, analogue instrumentation and control systems, nuclear power plants research reactors
Synopsis
The objective of the lecture is to provide a basic review of electronic design techniques and to learn how to treat sensors, actuators and analogue signals. This is a fundamental step for addressing the more advanced issues. The basic building blocks for electronic circuits: active and passive components, signal conditioning, power control, cabling, basics of electromagnetic compatibility. The presentation covers how to design electronic circuits manually using mental calculations, and how to design and simulate electronic circuits using software tools and potential accident scenarios. Signal processing for analogue sensors is addressed together with power amplifier for physical actuators. The analogue computer is discussed covering PID regulators. Limits for analogue I&C are covering: dynamic, signal to noise ratio and bandwidth.
B.3 Digital I&C Systems - Mauro Cappelli
Key words nuclear safety, digital instrumentation and control systems, nuclear power plants research reactors
Synopsis
The objective of the lecture is to develop a positively critical view of digital technology addressing why digital is substituting analogue I&C. An overview of analogue and digital sensors and actuators is provided and analogue to digital and digital to analogue conversion techniques are discussed. A/D and D/A converters as control systems building blocks are addressed together with digital signal processing basic building blocks. The digital computer as a closed loop controller is discussed and real time computer concepts explained. Well known and typical catastrophic design errors for digital I&C systems are covered.
B.4 Identification and classification of SSCs and safety assessment - Phil Metcalf
Key words nuclear safety, nuclear power plants, research reactors, structures systems and components important to safety, safety classification
Synopsis
Different structures, systems and components play different roles in providing nuclear safety. These roles are of varying levels of importance and as such there is considerable value in classifying such structures systems and components with a view to identifying the importance of their safety role and thus the degree of effort that should be expended in assuring their assigned safety functions will be fulfilled. Amongst other aspects the classification scheme determines the degree of inspection and assurance that should be applied to the different safety classes. The presentation discusses the approach to classification of structures systems and components.
B.5 Classification of I & C and electrical power systems - Peter Hughes
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants, research reactors, safety classification
Synopsis
Electrical power and I & C systems and component falling under the classification of those SSCs important to safety require particular consideration within the SSC classification scheme. Such classification for I&C systems depends on the role played by the system and this presentation will discuss the various roles played by I & C systems and how these are dealt with by the classification methodology.
Day 3 – Regulatory inspection processes for electrical systems
C.1 Design guidelines for electrical power systems - Peter Hughes
Key words nuclear safety, electrical power systems, design guidelines, nuclear power plants, research reactors
Synopsis
This presentation will discuss the implementation of the electrical power systems design basis which have been covered earlier in lecture B1. The design of the electrical power systems needs to consider anticipated electrical faults and those that challenge the continuity of supplies on the power station e.g. Station Blackout. This presentation will cover the design provisions that lead to defence in depth and robustness in electrical power systems and consider failure mechanisms that might undermine their reliability e.g. common cause failure. The presentation will draw out the type of information that a regulator needs to identify for effective regulatory assessment and inspection.
C.2 Derivation of limits, controls and conditions and establishment of regulatory conditions of authorisation - Phil Metcalf
Key words nuclear safety, instrumentation and control systems, electrical power systems nuclear power plants, research reactors, regulatory control, limits and conditions, conditions of licence
Synopsis
Based on the classification of structures systems and components and their importance to safety it is necessary to ensure that all safety principles and requirements are fulfilled in respect of design, manufacture, installation, commissioning and operation. This presentation discusses the important elements in this regard and the establishment of operational limits controls and conditions – again based on the importance to safety of the individual structures systems and components. It also addresses the regulatory authorization process and the associated conditions of authorization. The degree of regulatory effort to be expended in this phase based on safety classification considerations will also be discussed.
C.3 Design, conduct, reporting and follow up of inspection processes associated with electrical power systems and components - Peter Hughes
Key words nuclear safety, electrical power systems, nuclear power plants research reactors, regulatory inspection
Synopsis
This presentation will discuss the development and implementation of regulatory inspection and other compliance assurance activities primarily for the design and manufacturing phases. These are aimed to provide a good level of assurance that design processes are undertaken competently and that manufacturing processes will ensure that the items will be manufactured as designed and assessed to be fit for purpose and providing the necessary safety functions.
C.4 Example inspection programme for electrical power systems - Peter Hughes
Key words nuclear safety, electrical power systems, nuclear power plants research reactors, regulatory inspection
Synopsis
This presentation will build on the development of the inspection plan in C.3 to provide examples of regulatory inspection programmes. The example are based on regulatory programmes for the inspection of electrical systems for new build and for operating power stations. The purpose of the example is to show how a regulatory body must plan its activities over the various lifecycle phases of the power programme to ensure that regulatory decisions are timely and effective.
Day 4 – Regulatory inspection processes for I & C systems
D.1 . Design and software considerations for I & C systems - Peter Hughes
Key words nuclear safety, instrumentation and control systems, software, design guidelines, nuclear power plants, research reactors
Synopsis
NPP engineering is complex involving many technical disciplines and correct information is necessary at appropriate times in a project for each discipline to ensure that the designs are delivered as required. For systems important to safety, a structured development process with conservative design measures and sound engineering practice is needed and this applies to I & C systems and components important to safety. In addition, computer based systems are of increasing importance to safety in NPPs as their use has rapidly increased. They are used both in safety related applications, such as some functions of the process control and monitoring systems, as well as in safety critical applications, such as reactor protection or actuation of safety features. The dependability of computer based systems important to safety is of prime interest and must be ensured. This presentation discusses these issues import to design of I & C systems and the software used in such systems.
D.2 Application of FPGA based technology for I&C systems - Mauro Cappelli
Key words nuclear safety, instrumentation and control systems, field programmable gate arrays, nuclear power plants, research reactors
Synopsis
This presentation is mainly organized as a case study. Participants will work on minor tasks related to the assessment of I & C from a regulatory perspective and they will shortly present their findings. The objective of the exercise is to explain FPGA, a novel technology based on programmable devices. Advances over CPUB based systems as well as limitations of FPGA technology in the context of I & C applications will be covered and the genesis of FPGA technology. The (anti)economy of FPGA circuits will be addressed and where FPGA wins and where it loses: comparison with standard programmable micro controllers and computer based control systems. FPGA devices as glue logic and ASIC alternative will be covered as well as mixed signal (analogue) FPGA components. Design and simulation software tools for FPGA will be addressed together with the low level layer: the CLB, the intermediate layer: VHDL and Verilog. The high level: functional block representation (e.g. LabVIEW) will also be addressed.
D.3 Design, conduct, reporting and follow up of inspection processes associated with I & C systems and components
Peter Hughes
Key words Regulatory processes, nuclear safety, radiation safety, accidents, existing situations, abandoned facilities, orphaned sources
Synopsis
This presentation will discuss the actual development and implementation of regulatory inspection and other compliance assurance activities for all phases of reactor lifecycle form the design and manufacturing phases through commissioning and operation. These are aimed to provide a good level of assurance that design processes are undertaken competently and that manufacturing processes will ensure that the items will be manufactured as designed and assessed to be fit for purpose and providing the necessary safety functions. It also deals with the initial contact with the operating management, arrangements for access to the various areas of the plant necessary, entrance meetings and conduct of the inspections. It deals with interactions during the inspection and the initial reporting of finding to the power station management. The documenting of findings is addressed and the categorization of finding in terms of significance and the need for corrective action and follow-up. The documentation of findings and the follow-up and close out of issues identified is covered. The presentation will be complemented by an example inspection programme.
Day 5 – Course summary, test and evaluation
E.1 Topical issues with inspection of I & C and electrical power systems
Peter Hughes, Mauro Cappelli
Synopsis
This session will deal with topical issues associated with the inspection of electrical power and I & C systems and components identified from recent experience feedback. The significance of events and implications for regulatory inspection programmes will be discussed.
E.2. Round table discussion - Peter Hughes, Mauro Cappelli, Phil Metcalf
Synopsis
This session enables issues related to regulatory inspection of electrical power and I&C systems identified by participants to be discussed in depth in an open forum.
E.3 Test
The course will conclude with a multiple choice test covering all the topics presented during the week.
E.4 Course evaluation and closure
Synopsis
The session deals with feedback from the test and overall evaluation of the course by students and lecturers.
List of lecturers of training module 4: Regulatory Control of Nuclear Site-Inspection on I&C System and Electrical Systems
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Lecture / Workshop / Excursion |
Lecturer / Company |
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A.1 Introduction to the course – basis and role of inspection in the overall licensing process |
Phil Metcalf, IRSN France |
|
A.2 Organisation and staffing of the regulatory body for inspection of I & C and electrical power systems |
Peter Hughes, Consultant UK |
|
A.3 Regulatory review and assessment and the linkage to inspection |
Phil Metcalf, IRSN France |
|
A.4 Regulatory documentation Peter Hughes |
Phil Metcalf, IRSN France |
|
A.5 I&C Principles for Nuclear Facilities and Current Challenges |
Mauro Cappelli, ENEA Italy |
|
B.1 Safety requirements for electrical power systems for NPPs and research reactors |
Peter Hughes, Consultant UK |
|
B.2 Analogue I&C Systems |
Mauro Cappelli, ENEA Italy |
|
B.3 Digital I&C Systems |
Mauro Cappelli, ENEA Italy |
|
B.4 Identification and classification of SSCs and safety assessment |
Phil Metcalf, IRSN France |
|
B.5 Classification of I & C and electrical power systems |
Peter Hughes, Consultant UK |
|
C.1 Design guidelines for electrical power systems |
Peter Hughes, Consultant UK |
|
C.2 Derivation of limits, controls and conditions and establishment of regulatory conditions of authorisation |
Phil Metcalf, IRSN France |
|
C.3 Design, conduct, reporting and follow up of inspection processes associated with electrical power systems and components |
Peter Hughes, Consultant UK |
|
C.4 Example inspection programme for electrical power systems |
Peter Hughes, Consultant UK |
|
C.5 Group discussion on inspection of electrical power systems |
Peter Hughes, Mauro Cappelli |
|
D.1 . Design and software considerations for I & C systems |
Peter Hughes, Consultant UK |
|
D.2 Application of FPGAI based technology for I&C systems |
Mauro Cappelli, ENEA Italy |
|
D.3 Design, conduct, reporting and follow up of inspection processes associated with I & C systems and components |
Peter Hughes, Consultant UK |
|
D.4 Example inspection programme for I&C systems |
Peter Hughes, Consultant UK |
|
E.1 Topical issues with inspection of I & C and electrical power systems |
Peter Hughes, Mauro Cappelli |
|
E.2 Round table discussion |
Peter Hughes, Mauro Cappelli, Phil Metcalf |
|
Multiple-choice test Discussion of the results. Feedback of the module, possible improvement for future training courses
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Short career summary of the lecturers
Mauro Cappelli is a researcher at ENEA, Frascati Research Center, and the former Head of Design and Experimental Engineering Laboratory in the ENEA Casaccia Research Center in Rome. He has a Laurea degree in Electrical Engineering from the University of Perugia, a PhD in Electrical Engineering from La Sapienza University of Rome, a Master in Nuclear Safety at the University of Pisa and a Master in Fusion Science and Engineering at the University of Rome Tor Vergata. After a postdoc at the University of Salento, he worked as a Training Manager in the field of Defense Control Management Systems at Elsag Datamat (a Finmeccanica Company), where he led a team of over twenty teachers for the training of around one hundred of trainees (officers and petty officers of the Italian Navy). Afterwards, he joined ENEA where he has been working on Control Systems, Human-Computer Interfaces and Simulations tools. He is involved in many working groups and projects dealing with I & C as the Italian representative (IAEA, OECD-NEA, NATO, Halden Reactor Project, Jules Horowitz Reactor, INL). In 2011 he was Visiting Researcher at IRSN and worked at the SOFIA Simulator Laboratory. He has a post-laurea degree in Technological Teaching. From 2008 to 2013 he was Contract Professor of Computer Science Systems at La Sapienza University of Rome, and since 2014 he has been invited to teach courses on I&C systems at the University of L’Aquila. He is currently a Contract Professor at the University of L’Aquila, where he teaches a Course called Laboratory of Control System Engineering and Technology. He is the author of more than fifty papers on Electronics and Nuclear Safety. He has been Track Co Chair at ICONE 2013 (Track on Instrumentation and Control), Chengdu (China), Track Chair at ICONE 2014 (Track on Instrumentation and Control), Prague (Czech Republic), Track Co-Chair at ICONE 2015 (Track on New Reactors), Charlotte (USA), Track Co-Chair at ICONE 2016 (Track on New Reactors), Shanghai (USA). He has been the ENEA scientific secretary, and since 2013, the ENEA scientific coordinator of INSN Projects.
Peter Hughes has thirty-five years of experience in the nuclear industry having worked in the operational, design, safety analysis, regulatory and international safety areas. He holds an honours degree in energy technology from the University of Aston, UK and an MSc in electrical power engineering and economics from the University of Manchester, UK. He commenced his career as Assistant Engineer Operation at Trawsfynydd NPP in 1981 progressing to Second Engineer with the CEGB in 1983. He joined the Sizewell B Team in 1987 for three years then moving to Spectrum Engineering Corporation in Canada for a two-year period. In 1992 he joined the UK nuclear regulatory authority (currently ONR) and progressed to the level of Principal Inspector. During his tenure with the ONR he was twice seconded to the IAEA for separate periods of two and three years. At the IAEA he was Section Head; Safety Assessment. Part of his experience with the IAEA involved development of the international safety standards relating to I & C systems important to safety. He is chartered member of the UK Institute of Engineering and Technology and a member of the Federation Europeenne Associations Nationales d'Ingenieurs. He has has French, Welsh and German language skills.
Phil Metcalf is an independent nuclear and radiation safety consultant with BBM Consulting, Austria. He has degrees in nuclear and applied physics (Bachelor) and radiation safety (Master) and worked for the South African National Nuclear Regulator for 28 years where he was deputy general manager. He was head of the IAEA radioactive waste and spent fuel safety unit for 10 years. He chaired various IAEA committees including the Waste Safety Standards Committee and the Radiation Protection Training and Education Committee. He has been involved in the development of internationals safety standards for radiation protection, radioactive waste and spent fuel safety and legal and regulatory infrastructure and in over 100 technical assistance missions for the IAEA. He lectures on IAEA training courses in various countries and regions around the world and has lectured at the Universities of Milan and Munich (technical) and EC summer schools on radioactive waste and decommissioning safety. He is a past president of the International Radiation Protection Association and the South African Radiation Protection Society.
