11th International Conference on CANDU® Maintenance and ...It is a privilege to fill the role of...

Delivering Clean Energy through CANDU® Life Extension

Conference Sponsor & OrganizerCNS Nuclear Operations and Maintenance and Design and Materials Divisions

October 1-4, 2017

Toronto Marriott Downtown Eaton Centre Hotel

Toronto, ON Canada

F I N A L P R O G R A M

11th International Conference on CANDU® Maintenance and Nuclear Components

The full-scale mock-up reactor at Ontario Power Generation’s Darlington training and tooling facility. Photo Credit: Ontario Power Generation

S P O N S O R S A N D E X H I B I TO R SThe CMNCC 2017 Organizing Committee gratefully acknowledges the support of our sponsors and exhibitors.

SPONSORS

EXHIBITORS

Host Sponsor

Conference Organizing Committee 2

Message from the Conference General Chair 3

Message from the Honorary Chair 4

Student Participation Program 5

CNS Membership 5

Audio/Video Recording Policy 5

Documented Questions & Answers 5

Conference Proceedings 5

Copyright 5

Exhibit Floor Plan 6

Program-at-a-Glance 7

Program Details 8

CANDU Configuration Overview Course 8

Plenary 1A: Long Term Asset Management Plans and Strategies 9

Plenary 1B: Long Term Asset Management Plans and Strategies cont’d 11

Post-Fukushima Strategies - 1 14

Advances in Inspection and Monitoring Techniques - Specialized Tools 15

Aging Management - Major Components 16

Post-Fukushima Strategies -2 17

Advances in Inspection and Monitoring Techniques - New Monitoring Techniques 19

Aging Management - Steam Generators 20

Utility Engagement Panel on Maintenance 22

Plenary 2A: Supply and Training of Qualified Staff for the Utilities and their Service Providers 23

Staffing Challenges and Innovative Solutions 26

Plant Management 27

Maintenance Management 28

Plenary 2B: Margin Management 30

Condition Assessment, Life Assessment and Refurbishment 33

Strategies to Mitigate Component Degradation 34

Material Properties and Degradation 36

Plenary 3A: Proactively Managing Obsolescence 38

Plenary 3B: Executing Maintenance 40

Integrity of Structures and Components 44

Fuel Channel Life Management 45

OPEX 46

Plant Performance 48

Component Corrosion and Corrosion Control 49

Sponsor and Exhibitor Company Profiles 50

Author Index 62

TA B L E O F CO N T E N TS

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Honorar y Chai rShane Ryder, Vice President Fleet Maintenance and Operations, Ontario Power Generation

Conference General Chai rAman Usmani, Amec Foster Wheeler

Conference Co-Chai rsKamal Verma, SNC Lavalin/Candu Energy Inc.Polad Zahedi, Ontario Power Generation

Plenar y Program Chai rKeith Stratton, Stratton Consulting Inc.

Plenar y Program Adv isorsJacques Plourde, Nuclear Insurance Association of CanadaPaul Spekkens, Kinectrics Inc.Paul Thompson, NB Power

Plenar y Program CommitteeRuth Burany, Kinectrics Inc.Graham MacDonald, Ontario Power GenerationHerb Schmid, Bruce PowerDerek Mullin, NB Power

Technical Program & Proceedings Co-ChairsMetin Yetisir, Canadian Nuclear LaboratoriesKrish Krishnan, CANDU Owners Group

Technical Program CommitteeStephen Yu, SNC Lavalin/Candu Energy Inc.Ken Kirkhope, Canadian Nuclear Safety Commission

Uti l i t y Engagement Chai rPolad Zahedi, Ontario Power Generation

Uti l i t y Engagement TeamBrandon Lambert, Bruce PowerDavid Meldrum, Canadian Nuclear LaboratoriesGraham MacDonald, Ontario Power GenerationNick Preston, Ontario Power Generation (retired)

Conference TreasurerMohinder Grover, M.S. Grover & Associates

Assist ing the Conference TreasurerJohn Roberts, JGRchem Inc.

Sponsorship & Exhib i ts Co-Chai rsKris Mohan, WiznucleusMo Fadaee, Ryerson University

Assisting the Sponsorship & Exhibits Co-ChairsAndrew Ali, Amec Foster WheelerRuth Burany, Kinectrics Inc.

Publ ic i t y Chai rPeter Easton, Eastworks Consulting

Assist ing the Publ ic i t y Chai rMo Fadaee, Ryerson University

Industr y L ia ison Chai rRon Oberth, Organization of Canadian Nuclear Industries

CANDU® Owners L ia ison Co-Chai rsMacit Cobanoglu, CANDU Owners GroupDon Wilson, CANDU Owners Group

Assisting the CANDU® Owners Liaison Co-ChairsNalini Valliere, CANDU Owners Group

CANDU® Course Chai rGraham MacDonald, Ontario Power Generation

Student Program Chai rRevi Kizhatil, BWXT Canada Ltd.

Adv isorsJacques Plourde, Conference Senior Advisor, Nuclear Insurance Association of CanadaDaniel Gammage, Conference Senior Advisor, Amec Foster WheelerPeter Ozemoyah, Conference Senior Advisor, Tyne EngineeringKen Smith, Financial Advisor, formerly AECL and NRCanMohamed Younis, Financial Advisor, Amec Foster Wheeler

Conference Regist rarBob O’Sullivan, CNS Office Managerc/o AMEC NSS Ltd.4th Floor, 700 University AvenueToronto, ON M5G 1X6Tel: (1) 416-977-7620Email: [email protected]

Conference Administ ratorElizabeth Muckle-JeffsThe Professional EdgeNorth America Toll-Free: 1-800-868-8776International: 1-613-732-7068Email: [email protected]

CO N F E R E N C E O RG A N I Z I N G CO M M I T T E E

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M E S S AG E F RO M T H E CO N F E R E N C E G E N E R A L CH A I ROn behalf of the Canadian Nuclear Society, my Conference Co-Chairs, Kamal Verma and Polad Zahedi, and the entire CMNCC 2017 Organizing Committee, it is my great honour as Conference General Chair to welcome you to the 11th International Conference on CANDU® Maintenance and Nuclear Components.

This ‘flagship’ conference has brought together subject matter experts from operating utilities and service providers under the banner of Delivering Clean Energy through CANDU® Life Extension.

CMNCC 2017 will generally follow the same approach as previous CANDU maintenance conferences, but with broadened scope to include all major components found in nuclear power plants worldwide. You will see that the conference program has been built around the needs and interests of the operating utilities, where the utilities identify issues of importance to them and service providers undertake to find solutions. It will focus on the future, while making use of past and present experience with successful refurbishment and life

extension initiatives to ensure that CANDU nuclear power plants continue to achieve world-class performance and provide safe, reliable and clean energy in Canada and where CANDU reactors operate around the world.

I am pleased to acknowledge our conference sponsors, in particular Ontario Power Generation as the host sponsor and to thank Shane Ryder for serving as Honorary Chair and helping to ensure that the focus of the conference remains on developing innovative approaches to improving plant maintenance productivity.

We have a very robust industry presence by our exhibitors whose products and services address the wide-ranging needs of the operating utilities in the areas of NDE, engineering, plant maintenance and life extension services. Be sure to take time to stop by every exhibit booth, introduce yourself to the company’s representatives, explain to them your areas of interest, your needs and ideas, and get to know more about these leaders of our industry.

In addition to the very informative and relevant plenary sessions, technical program and luncheon speakers that feature presentations by senior industry participants and stakeholders, this year’s conference includes some new events and networking opportunities.

On Sunday the very popular CANDU® Course is back by popular demand and course participants are eligible for Continuing Education Units in the context of the Engineering Institute of Canada Continuing Education program.

A new addition to this year’s conference is Mix & Mingle, co-sponsored by the North America Young Generation Nuclear (NAYGN) and Women in Nuclear Canada (WiN-Canada) on Sunday afternoon. Participants will learn about both organizations, and hear from inspirational speaker Alex DeLorey, who will recount his experiences while aspiring to become the next Canadian Astronaut.

The CNS Utility Engagement Team has been an integral part of the Organizing Committee in developing the Utility Engagement Panel on Maintenance on Monday evening. A panel of maintenance representatives from Ontario Power Generation, Bruce Power, NB Power and Canadian Nuclear Laboratories have identified key maintenance issues that will be the basis for interactive discussion intended to incubate solutions that will address them.

A highlight of the conference will be the CANDU® Around the World networking dinner on Tuesday evening. This will be an excellent opportunity for discussion in a relaxed environment and for connecting with past colleagues and many new faces, including our Student Program participants who are the future of our industry.

Plan to participate fully during the conference, including during the question and discussion periods. The Q&A will be recorded and documented in the conference proceedings.

I encourage you to become actively engaged over the next three days and be part of solution to the challenges and opportunities of Delivering Clean Energy through CANDU® Life Extension now and into the future.

Sincerely, Aman Usmani, Conference General Chair

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It is a privilege to fill the role of Honorary Chair on behalf of Ontario Power Generation, the host sponsor of the 11th International Conference on CANDU Maintenance and Nuclear Components.

This conference offers all of us in the Canadian nuclear industry an opportunity to come together to share our knowledge, experience and vision of future opportunities to advance the industry with innovative approaches to nuclear plant and component maintenance. I also hope all who attend take the time to meet new colleagues and discover the many exciting initiatives underway across the industry that support improvements to plant reliability and overall competitiveness of the nuclear fleet and associated facilities.

The Canadian nuclear industry is very busy these days with refurbishment and major component replacement planning underway at many sites. Plant operators need to ensure the refurbished plants are ready to operate for many years safely and reliably with total operating and maintenance costs that are competitive with other

available sources of power. Delivering on these performance expectations will require innovative maintenance programs that take advantage of new ways of solving maintenance and nuclear component challenges. The Canadian Nuclear Society community is key to helping devise improved means to address these challenges.

I appreciate the hard work done by the Organizing Committee, the presenters and exhibitors in preparing for this event and I am sure all who participate will find it a rewarding experience.

Welcome and please enjoy the conference!

Shane Ryder, Honorary Chair Vice President, Fleet Operations and Maintenance, Ontario Power Generation

M E S S AG E F RO M T H E H O N O R A RY CH A I R

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STUDENT PARTICIPATION PROGRAMThe Canadian Nuclear Society gratefully acknowledges Bruce Power, Canadian Nuclear Laboratories, NB Power and Ontario Power Generation for sponsoring the CMNCC Student Participation Program. Please welcome this year’s students:

Faraz Bohra, McMaster University

Bruce Gee, University of Waterloo

Matthew Grisebach, University of Waterloo

Ahmed Hameed, Ryerson University

David Kelly, McMaster University

Julie Kim, UOIT

Andre Laranjeiro, McMaster University

Monique Stuive, McMaster University

CNS MEMBERSHIPIf you are not already a member of the CNS, consider joining in order to obtain the reduced conference registration rate as well as the many other membership benefits. For details, go to the CNS website www.cns-snc.ca/cns/membership/

AUDIO/VIDEO RECORDING POLICYRecording of any sessions (audio, video, still photography, etc.) intended for personal use, distribution, publication or copyright is strictly prohibited.

Permission to record can only be provided after application to, and approval by, the Canadian Nuclear Society and by the individual author/presenter.

CONFERENCE PROCEEDINGSThe Conference Proceedings will be available on-line and a code to access the proceedings will be sent to conference participants by e-mail.

DOCUMENTED QUESTIONS & ANSWERSAll questions and answers will be documented and published in the Conference Proceedings. A student team will be present during each conference session to manage the process. Q&A forms will be provided to participants to record their questions immediately and legibly, and the speakers will in turn provide written responses. It is important that all questions and answers be in the hands of the Q&A team by the close of the conference.

COPYRIGHTCopyright for papers submitted to the 11th CNS International Conference on CANDU® Maintenance and Nuclear Components remains with the author; but the CNS may freely reproduce the papers in print, electronic or other forms. The CNS retains a royalty-free right to charge fees for such material as it sees fit.

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B1 Rolls-Royce Civil Nuclear Canada

B3/B4 Kinectrics Inc.

B5 Liburdi Automation Inc.

B6 ASI Group Ltd.

B7 BWXT Canada

B14 Pall Corporation

B15 Canadian Nuclear Laboratories

B16 Perma-Fix Environmental Services, Inc.

B17 LISEGA INC.

B18 UniTech Services Group

B8 Promation Nuclear

B10 Canadian Nuclear Partners

B11 Farris Pressure Relief Valves

B12 Unified Engineering.com Corp

B13 Westinghouse Electric Company LLC

B19 Tyne Engineering

B20 Organization of Canadian Nuclear Industries

F7 Black and MacDonald

F8 Laveer Engineering

F11 AMAG Inc.

F12 Areva Canada

F15 Lakeside Process Controls

F2 SWI

T1 CaNRisk – McMaster University

EXHIBITORS

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CMNCC 2017 PROGRAM-AT-GLANCES u n d a y , O c t o b e r 1 , 2 0 1 7

M o n d a y , O c t o b e r 2 , 2 0 1 7

T u e s d a y , O c t o b e r 3 , 2 0 1 7

W e d n e s d a y , O c t o b e r 4 , 2 0 1 7

09:30-10:00

07:00-17:00

07:00-17:00

07:00-17:00

07:00-17:00

07:30-08:15

07:30-08:30

07:30-18:30

08:30-10:00

10:00-10:30

15:00-15:30

17:00-18:30

07:00-17:00

17:30-18:30

07:00-17:00

07:30-15:10

10:30-12:00

18:30-21:00

07:30-08:30

10:00-10:3008:30-10:00

12:00-13:30

17:00

15:10-15:40

12:00-13:30

13:30-15:00

08:15-08:30

07:30-17:30

08:30-10:00

10:00-10:30

15:10-15:40

17:20

10:30-12:00

12:00-13:30

12:45-13:15

12:45-13:15

13:30-15:10Concurrent Sessions






10:00-15:00

15:00-19:00

15:00-17:00

17:30-19:30

CANDU® Course Check-in

Conference Registration Open


Speaker/Exhibitor Service Desk Open


Early Morning Refreshments

Early Morning RefreshmentsExhibits Open

Plenary 2A: Supply and Training of Qualified Staff for the Utilities and their Service Providers

Networking Break

Networking Break

Student/Mentor Poster Session


Networking Reception


Exhibits Open

Plenary 3B: Executing Maintenance

CANDU® Around the World Networking Dinner, Guest Speaker: The Hon. Glenn Thibeault, Minister of Energy

Early Morning Refreshments

Networking BreakPlenary 3A: Proactively Managing Obsolescence

Luncheon

Conference Concludes

Networking Break

Luncheon

Plenary 2B: Margin Management

Welcome and Opening RemarksExhibits Open

Plenary 1A: Long Term Asset Management Plans and Strategies

Networking Break

Networking Break

Adjourn

Plenary 1B: Long Term Asset Management Plans and Strategies, cont’dLuncheon

Luncheon Guest Speaker: Shane Ryder, Vice President, Fleet Operations and Maintenance, Ontario Power Generation

Luncheon Guest Speaker: Raj Verma, Vice President Major Accounts, Marketing and Business Development, SNC-Lavalin Nuclear

CANDU® Configuration Overview Course


NAYGN/WiN-Canada Mix & MingleWelcome Reception

Post Fukushima Strategies – 1

Staffing Challenges and Innovative Solutions

Condition Assessment, Life Assessmentand Refurbishment

Integrity of Structures and Components

OPEX

Post Fukushima Strategies – 2

Advances in Inspection and Monitoring Techniques – Specialised Tools

Maintenance Management

Strategies to Mitigate ComponentDegradation

Fuel Channel Life Management

Plant Performance

Advances in Inspection and Monitoring Techniques - New Monitoring Techniques

Aging Management – Major Components

Material Properties and Degradation

Component Corrosion and Corrosion Control

Aging Management – Steam Generators

Plant Management

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09:30-10:00CANDU® Course Check-in

10:00-15:00 CANDU® Configuration Overview Course

14:00-19:00Conference Registration Check-in

15:00-17:00NAYGN/WiN-Canada Mix and Mingle with Alex DeLorey, 2017 Canadian Astronaut Finalist

17:30-19:30Welcome Reception

09:30-10:00Course participant check-in

10:00Welcome and Introduction

Part 1 CANDU® Plant and Reactor Orientation

10:05Typical Plant Layout & Reactor Building OrientationGraham MacDonald, Ontario Power Generation

10:20CANDU® Reactor CoreStephen Yu, SNC-Lavalin Nuclear

Part 2 CANDU® Systems and Reactor Regulation

10:50Primary Heat Transport SystemPeter Caple, BWXT Canada Ltd

11:20Secondary (Steam) Heat Transport SystemPeter Caple, BWXT Canada Ltd.

11:35Reactor Regulating, Control and Safety SystemsGlenn Harvel, UOIT

12:00Other Process SystemsGlenn Harvel, UOIT

12:15 – 13:00Luncheon (provided)

13:00 – 15:00

Part 3 Plant Operations, Degradation and Maintainability

13:00Reactor Operation and ControlGraham MacDonald, Ontario Power Generation

13:20Major Degradation MechanismsPawel Trocki, BWXT Canada Ltd.

13:45Plant Chemistry Control & Degradation ManagementMaria-Lynn Komar, Kinectrics Inc.

14:10Maintenance and Maintainability PrimerGraham MacDonald, Ontario Power Generation

14:45Test and Review, CANDU® Configuration Overview Certificate Presentation and Course Feedback

15:00Adjourn

CANDU® Conf igurat ion Over v iew Course

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08:35Delivering the Nuclear PromiseKevin Pushee, Team Lead Delivering the Nuclear Promise, INPO

The US industry’s Delivering the Nuclear Promise (DNP) initiative has been ongoing since October 2015. Kevin Pushee of INPO will provide an update on industry progress in the implementation of DNP efficiency bulletins. Additionally, his presentation will discuss a few challenges associated with efficiency bulletin implementation, industry sharing and exchange of lessons learned, INPO’s role in preventing and monitoring for unintended consequences, and future DNP activities.

Kevin Pushee is the INPO Leader for the US Delivering the Nuclear Promise (DNP) initiative; a position he has held since July 2016. Mr. Pushee joined INPO in 2007 as a senior radiation protection (RP) evaluator and became the RP manager five years later. He also served as a plant monitoring leader in 2015-2016 prior to his appointment to the DNP organization. Before joining INPO, Mr. Pushee worked in the US nuclear power industry for 28 years. He began his career as a RP technician and later held the positions of radiological

engineer and RP manager. He holds a bachelor’s degree in nuclear technology from the University of the State of New York, a senior reactor operator certification, and is a member of the National Registry of Radiation Protection Technologists.

08:30Session Chair Opening Remarks

Session ChairRamzi Jammal, Executive Vice President and Chief Regulatory Operations Officer, Canadian Nuclear Safety Commission

Ramzi Jammal has worked for the Canadian Nuclear Safety Commission (CNSC) since 1998, holding progressively senior positions. He has accumulated over 35 years of experience in the nuclear industry, combining management skills with scientific expertise, and representing the CNSC in various international activities. These include the co-chairing of the IAEA Fukushima report, leading Canadian delegations to the Conventions of Nuclear Safety, and the Joint Convention on the Safety of Spent Nuclear Fuel Management and on the Safety of Radioactive waste management.

Currently, Mr. Jammal is the President of the Convention on Nuclear Safety as elected by the Contracting parties in 2016 and will continue the presidency until October 2018. He also sits on the IAEA Commission on Safety Standards. He was instrumental in the development and establishment of the IAEA Code of Conduct for the Safety and Security of Radioactive Sources, and the international categorization of radioactive sources. He also played a key role in ensuring that the recommendations of the International Commission on Radiation Protection complemented the CNSC’s regulatory needs.

As the Chief Regulatory Operations Officer, he led the development of the CNSC regulatory action plan in response to the Fukushima Daiichi accident.

07:30Early AM Refreshments

08:15Welcome and Opening RemarksAman Usmani, Amec Foster Wheeler, Conference General Chair

Shane Ryder, Ontario Power Generation, Honorary Chair

08:30-10:00

Plenary 1A: Long Term Asset Management Plans and StrategiesThis session will focus on how to achieve the full potential of nuclear power safely and reliability.

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08:55Long Term Asset Management PlanGary Newman, Chief Engineer, Senior Vice President of Engineering, Bruce Power

Nuclear Power Plant Life Extension is a key element of the strategy within Ontario to continue to provide base-load generation capacity to the electricity consumer for at least the next 50 years. These efforts have been underway for some time now recognizing the complexity of such an undertaking. It is without a doubt a great opportunity to have and the success of this major infrastructure investment, one of the largest in the world, is contingent upon the efforts of a multi-disciplinary team of professionals from a broad range of key stakeholders such as shareholders, market operators, vendors, regulators and the utilities. This series of slides provides an overview of the intensive work underway at Bruce Power to plan and execute the necessary activities to ensure that our units continue to operate safely, reliably and in a cost effective manner.

Mr. Gary Newman, M.A.Sc., P. Eng., is the Chief Engineer and Senior Vice President of Engineering at Bruce Power L.P. Bruce Power’s vision is to become Canada’s World Class Nuclear Operator, committed to providing safe, reliable, affordable, and environmentally sound electricity.

Mr. Newman was appointed to his current position in June 2008. He is the Design Authority for Bruce Power and carries responsibility for all Engineering activity at the Bruce Power L.P. site and is the current

Bruce Power representative on the CANDU Owners Group, Nuclear Safety Solutions and University Network of Excellence in Nuclear Engineering Board of Directors.

Mr. Newman joined Bruce Power in 2004 as the Department Manager of Equipment Life Cycle Engineering and prior to that was employed by AMEC - Nuclear Safety Solutions Ltd., Ontario Power Generation and originally joined Ontario Hydro in 1990.

09:35

Questions and Discussion

09:55Session Wrap-up

10:00-10:30Networking Break

09:15 Improved NPP PerformanceJason Wight, Director – Station Engineering, Pickering Nuclear, Ontario Power Generation

In 2016, the Pickering Nuclear Generating Station enjoyed one of the best years in the stations history. This strong performance has continued in 2017 and is characterized by historically low Forced Loss Rate, well managed outages, and record setting periods of continuous operation on several of the Pickering units. This performance stands in sharp contrast to that of the preceding ten years or so. This presentation will describe the contributors and causes of past performance shortfalls and how Ontario Power Generation has driven improvements in human and equipment performance during this period.

Jason Wight began his career with Ontario Power Generation at the Pickering Nuclear Generating Station (PNGS) in 2000, after graduating from McMaster University with a degree in Engineering Physics. He eventually progressed on to a variety of leadership positions including Section Manager of Rotating Equipment, Valve Programs, and Conventional Systems. He’s held Department Manager positions in Plant Design and Performance Engineering at Pickering, as well as the role of Design Authority at

Darlington. Jason broadened his expertise outside of engineering by taking on roles such as Outage Control Centre Manager and the Assistant Maintenance Manager at PNGS.

In August 2016, Jason became the Director, Station Engineering at Pickering. He is passionate about Leadership & Innovation. Jason is currently leading a Nuclear Fleet Initiative on Innovation & Technology to advance technological solutions within OPG’s nuclear fleet. In his role, he has created an innovation accelerator, called ‘X-LAB’. The goals of the accelerator are to create an environment that encourages and fosters creative thinking across OPG, drive the development of out-of-the-box solutions, engage and attract employees, drive efficiency improvements, and develop new revenue streams.

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10:30-12:00

Plenary 1B: Long Term Asset Management Plans and Strategies (cont’d)10:30Session Chair Opening Remarks

10:35Asset Management MethodologyRob Whalen, Senior Vice-President Engineering, Intellectual Property & Technology, SNC-Lavalin Nuclear

Long Term Asset Management (LTAM) is an important strategy to support safety, reliability, predictability and efficiency in operations. It is also key to maintaining the confidence of regulators, stakeholders as well as the general public. Utilities have made significant efforts and progress in improving equipment reliability and the industry has also gained experience with the benefits of having a proactive LTAM perspective. This includes benefits on short term equipment reliability and the ability to better integrate longer term actions into acomprehensive business plan. LTAM can also help the facility prioritize actions for systems and structures that do not have immediate safety implications, but are important to the long term operation of the plant.

IAEA, INPO AP-913, REGDOC 2.6.3 standards and other industry guidelines reflect a growing body of industry best practice that points to effective LTAM implementation. OEMs are incorporating this thinking into a more proactive design process to provide LTAM program elements as part of the original design supply. Utilities are looking at how these programs can lead to a more pro-active approach.

LTAM integrates the activities of groups throughout the station to manage the aging of plant assets, optimize asset operating life, and maximize the return on investment while maintaining safe and reliable operation.

The talk will consider aspects of successful LTAM strategies and plans from the operator as well as the OEM perspective and will enforce how both organizations can work together to achieve the desired results. It will discuss experiences in applying this thinking to operating station programs and application to new builds. It will also discuss how adopting an affective LTAM strategy can address regulatory and public concerns both while achieving the design life of stations as well as post-refurbishment life.

Rob Whalen is responsible for all engineering activities in SNC-Lavalin’s Nuclear business unit. In this capacity, he leads a team of over 800 nuclear steam plant and balance of plant engineers dedicated to the highest standards in the industry. Rob oversees all engineering activities including tooling and refurbishment tooling engineering as well as the development of CANDU® reactors.

Before joining SNC-Lavalin in 2015, Rob was most recently Vice President, Nuclear Engineering for Tennessee Valley Authority (TVA) in the United States. While there, he transformed the Nuclear

power group engineering from a reference source model to a highly valued technical team, while leading significant improvement in equipment reliability and resolution of significant historical regulatory issues. Rob was instrumental in building a strong technical conscience in the Engineering organization at TVA and in developing a strong and diverse leadership team focussed on collaborative leadership and industry best practices.

Rob brings a true operator’s viewpoint to SNC-Lavalin, with more than 30 years of commercial nuclear power plant experience. He has worked at four nuclear stations and also spent two years on assignment with INPO as a senior evaluator, supporting nuclear plant evaluations and assistance. His site experience includes responsibilities for site engineering, site maintenance and maintenance planning.

He holds a Bachelor of Science in Mechanical Engineering from Purdue University and an American National Standards Institute (ANSI) Senior Reactor Operator (SRO) certification from a US boiling water reactor site. Rob completed the Institute of Nuclear Power Operations (INPO) Senior Nuclear Plant Manager’s Program in 2007. Rob has been a member of the advisory boards of the University of Tennessee Knoxville and Auburn University in Alabama. He previously served in executive leadership roles on the US Boiling Water Reactor Owners Group and the Pressurized Water Owner’s Group, and served on the Electric Power Research Institute (EPRI) Nuclear Power Council.

Session ChairJason Lehtovaara, Team Lead, You Can Count On Me, Bruce Power

Originally from Thunder Bay Ontario Jason’s career began in Electrical Engineering at Ontario Hydro. Arriving at the Bruce Nuclear Power Development fresh out of the University of Western Ontario he and his wife relocated to Bruce County in 1990. His career has spanned 27 years at the Bruce Site where he witnessed “first hand” the transition from Ontario Hydro to Bruce Power.

He has held senior leadership positions throughout his career in Engineering, Projects, Operations, Work Management, Outage Management and Maintenance, including four years as the Division Manager for Outages and four years Division Manager Maintenance Production at Bruce B.

Jason’s current position is that of a team lead for a site improvement initiative called You Can Count On Me. It is a one year assignment to inspire and motivate Bruce Power’s vendor community to value organizational learning and establish elements

of a Human Performance Program. The goal is to reduce events and mitigate consequences during work preparation or execution. This role is challenging as it has many stakeholders to align and shift their thinking. Nuclear energy is unique and requires a different approach with regards to safety culture. The challenge being to get the complimentary workers to value and commit to high standards. That said, Jason views it as an excellent opportunity to test his leadership character and apply some political savvy in building strong partnerships and relationships with teams outside Bruce Power.

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11:15International Generic Aging Lessons Learned (IGALL) Programme for CANDU®/PHWR ReactorsKen Kirkhope, Senior Technical Specialist, Technical Support Branch, Canadian Nuclear Safety CommissionThe International Generic Ageing Lessons Learned (IGALL) Programme was developed by the International Atomic Energy Agency (IAEA) to assist Member States in ensuring that aging of structures, systems and components (SSCs) of nuclear power plants (NPPs) is well managed, so that safety levels are maintained during long-term operation. Canadian Nuclear Safety Commission (CNSC) staff have been strong supporters of the IGALL Programme since its beginning, and lead Canadian participation to ensure that it addresses current, proven best practices and knowledge on aging management for Canadian CANDU® NPPs. Participation in IGALL also helps to ensure that Canadian NPPs will benefit from international experience, proven practices, knowledge and lessons-learned from member states with CANDU / pressurized heavy-water reactor (PHWR) or light-water reactor technologies.

The purpose of this paper is to provide an overview of the IGALL Programme and to illustrate how it is applied to managing aging of mechanical, electrical and instrumentation and control (EI&C) components, and civil structures of CANDU NPPs. The aging management programs (AMPs), time-limited aging analyses (TLAAs) and aging management review (AMR) tables for mechanical, EI&C and structural SSCs of CANDU NPPs are described. The application of the IGALL programme for implementation and compliance with CNSC REGDOC-2.6.3, Aging Management, and REGDOC-2.3.3, Periodic Safety Reviews, is also discussed. Finally the paper outlines a few suggested areas for further enhancement of the IGALL programme.

Ken Kirkhope has been working for the Canadian Nuclear Safety Commission for over 20 years in various regulatory roles. He currently the Senior Technical Specialist in the Engineering Design Assessment Division, and leads the division’s activities with respect to licencing reviews, technical assessments, inspections and audits of nuclear power plants, with specialization in the areas of pressure retaining components, ageing management, long term operation.

He is the technical lead for the CNSC’s regulatory compliance program for RD-2.6.3

“Fitness for Service: Aging Management”. He was contributing author on several IAEA Safety Standards and Guides relating to nuclear power plant aging management, long term operation. He is currently the Chairperson of the Working Group on CANDU mechanical components for the IAEA International Generic Ageing Lessons Learned (IGALL) programme, and also serves on the Steering Committee.

Prior to his current position, he was a site inspector and CNSC Project Manager for the Point Lepreau CANDU-6 Refurbishment project. He is a member of the CSA N285A Technical Committee on Requirements for Pressure Retaining Systems & Components in CANDU Nuclear Power Plants.

He completed a Master’s in Mechanical Engineering from Carleton University. He is Chairperson of the Ottawa Branch of Canadian Nuclear Society since 2014.

10:55Strong PdM Program Mandatory for an Optimum Mix of Time-Based / Condition-Based MaintenanceOvidiu Gheorghiu, PdM Coordinator, Technical Division, CNE CernavodaThe commercial nuclear generation market has changed dramatically over the past several years. At the same time that standards for safe and reliable operation of nuclear stations have increased, natural gas prices, conservation efforts, green generation, and a slowing demand for additional electric generation have driven the need for nuclear generators to reduce operating costs. Reductions in budgets and available resources coupled with increased administrative requirements strain stations abilities to perform required maintenance. It is imperative moving forward that nuclear stations effectively manage costs without compromising safety and reliability in order to remain economically viable.

With Preventive Maintenance program costs representing a large portion of maintenance budgets, it is easy to focus solely on the reduction of the number of PM tasks, and therefore the related resource requirements, as a cost saving measure. The solution would be to replace PM tasks with CBM tasks wherever possible. The major difference is that in PM’s there is a list of components which will be replaced after a period of time while in CBM’s what and when must be replaced deficient components results from a diagnosis. A strong PdM program with high level expertise personnel is mandatory because it is obvious that the quality of diagnosis determines CBM process efficiency.

Ovidiu Gheorghiu is a professional Mechanical Engineer and has worked as an Maintenance Manager in several machines manufacturing entreprises.

Ovidiu work in nuclear industry as Training Coordinator for Maintenance Department at Cernavoda Nuclear Power Plant from 2001. From this position he lead the “Maintenance Trainig Center” project that is an important achivement in maintaining a high level of training for maintenance personnel.

In 2013 Ovidiu has been designated CBM Coordinator in the Technical Division having the

task of ensuring the transition from Time-Based Maintenace to a better mixt Time-Based / Condition-Based Maintenance, provided high level of equipment reliability with reasonable costs.

11:35Questions and Discussion11:55Session Wrap-up12:00-13:30Luncheon

12:45Luncheon Speaker: Shane Ryder, Vice President, Fleet Operations and Maintenance, Ontario Power Generation

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Review and Validation of Severe Accident Guidelines for Canadian NPPsNoreddine Mesmous, Canadian Nuclear Safety Commission

Fuel Channel Scanning Tool Elongation Measurement “Stem”Sukhpal Singh Dhaliwal, Andrew Hong and Satyanarayana Mallampalli, Ontario Power Generation

Low-Voltage Electrical Cable Condition: Approach to Remaining-Life PredictionsFabrice Guérout, Canadian Nuclear Laboratories

Considerations in Implementing Earthquake Design Extension Condition (DEC)Aman Usmani, Amec Foster Wheeler and Tarek Aziz, TSAziz Consulting Inc.

Strain and Vibration Monitoring of Nuclear Components using Fibre Optic SensorsMichel Gaudet, Kevin (Wenhai) Li and Metin Yetisir, Canadian Nuclear Laboratories

New Steam Generators for Embalse NGS – Replacement Cartridge Design, Manufacturing and Localization IssuesRalf Gold and Jerzy Parkitny, SNC-Lavalin Nuclear; Pablo Luna and Ricardo Sainz, Nucleoeléctrica Argentina S.A.

Post-Fukushima Strategies Implemented at CANDU Nuclear Power Plants - Part 2Lovell Gilbert, Bruce Power

FOSAR – Foreign Objects Search and RetrievalHolger Damies, Gerhard Nützel and Sebastian Popp, AREVA GmbH

Management of Aging Piping through Reasonable Assurance Assessments and Inspection PrioritizationAdam Roukema and Derek Newsom, Structural Integrity Associates, Inc.

Integrated In-Vessel Debris Blockage Testing for Pressure-Tube ReactorsQingwu Cheng, Canadian Nuclear Laboratories

Improved Radiation Monitoring and Decontamination Processes to Reduce Significant Radioactive Waste Costs via RecyclingKent Anderson, UniTech Services Group

The Role of Steam Generator Inspections in Life Cycle ManagementLaura Obrutsky, M&O Tech Inc.

Post-Fukushima Strategies Implemented at CANDU Nuclear Power Plants - Part 1Lovell Gilbert, Bruce Power

Qualified Field-Trialed Next-Generation Advanced Portable Polymer Tester for Improved Cable Condition Monitoring in NPPJason Deadman, Daniel Ho, Robert Jamieson and Narendra Sachdev, SNC Lavalin Nuclear

Ageing Management of Low Voltage Cables at Darlington Nuclear StationDavid Rouison, Kinectrics Inc.; Allan Ghaforian, Ontario Power Generation; Marzieh Riahinezhad, Kinectrics Inc.

Radiation Monitoring System for CFVS StacksSherri Hashemi, Nigel Reynolds and John Robinson, Tyne Engineering Inc.

Using Sub-GHZ Wireless Sensors for Nuclear Plant Process and Security MonitoringJason Hollern, Michael Liebenow, Xue Wang and Lee Watkins, AREVA Inc.; Jocelyn Perisse, AREVA NP; Christoph Duval, ARCYS

Steam Generator Service Solutions for Improving Plant EfficiencyHolger Damies and Gerhard Nutzel, AREVA GmbH

The Application of CNSC Fukushima Action Plan in the Design of Small Modular ReactorsMagdy El-Hawary and Noreddine Mesmous, Canadian Nuclear Safety Commission

Steel Pipe Wall Thickness Measurement by Pulsed Eddy CurrentKen Faurschou and Ross Underhill, Royal Military College; Jordan Morelli, Queen’s University; Thomas Krause, Royal Military College

Aging Management and Reliability of CANDU Steam Generators and Heat ExchangersMike Montazer, Bob Goel, Danyal Montazer and Carmen Fourar, CNG Nuclear

Advances in Ultrasonic Flow Measurement Technology for Nuclear ApplicationsVictor Janzen, Canadian Nuclear Laboratories; Alexander Gurevich, Srikrishnarajah Selvaratnarajah and Yuri Gurevich, AMAG Inc.

A Preliminary Three Dimensional CFD Model of the APR1400 Steam Generator Using ANSYSKrzysztof Zabrzycki and Aya Diab, KEPCO International Nuclear Graduate School

Proactive Source Term Monitoring at CANDU StationsYury Verzilov and David Trudell, Kinectrics Inc.

Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Tube Bundle – Tests in Air FlowPaul Feenstra and Teguewinde Sawadogo, Bruce Smith and Victor Janzen, Canadian Nuclear Laboratories; Helen Cothron, EPRI

Use of Gravity-Assisted Loop Heat Pipes for Passive Cooling of Spent Nuclear Fuel Pools During Station BlackoutAmir Sartipi, Rosa Elia Ortega Pelayo, Michel Gaudet and Changqing Zhang, Canadian Nuclear Laboratories

Specialized Tooling for Inspection of Calandria Relief DuctsAndrew Brooks, Bruce Power

Aging Management and Reliability of CANDU Primary Heat Transport System and FeedersMike Montazer, Bob Goel, Danyal Montazer and Carmen Fourar, CNG Nuclear

Networking Break

Adjourn

C O N C U R R E N T T E C H N I C A L S E S S I O N S

C O N C U R R E N T T E C H N I C A L S E S S I O N SPost Fukushima Strategies – 1 Advances in Inspection and Monitoring

Techniques - Specialised ToolsAging Management – Major Components

Post-Fukushima Strategies – 2 Advances in Inspection and MonitoringTechniques - New Monitoring Techniques

Aging Management – Steam Generators

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13:30 -15:10CONCURRENT TECHNICAL SESSIONSPost Fukushima Strategies – 1Session ChairNoreddine Mesmous, Canadian Nuclear Safety Commission

13:30Review and Validation of Severe Accident Guidelines for Canadian NPPsNoreddine Mesmous, Canadian Nuclear Safety Commission

Further enhancements to the existing severe accident management (SAM) program in CANDU® nuclear power plants (NPP) is an important activity in response to lessons learned from the Fukushima Daiichi nuclear event. In addition, verification and validation of the severe accident management guidance (SAMG) is crucial to assess its successful implementation and effectiveness in SAM.

In this view, Canadian Nuclear Safety Commission (CNSC) approach to assure SAM effectiveness includes:

• ImplementationofREGDOC-2.3.2“AccidentsManagement”requirements for SAM,

• complianceverificationofactionsrelatedtoSAM,

• evaluationofsite-specificSAMGimplementation,and

• verificationthatlessonslearnedareincorporatedintotheprograms.

In this presentation, CNSC regulatory oversight related to SAMG verification and validation will be discussed. This approach is seen as providing valuable evaluation and feedback to operating CANDU NPP utilities to improve and support decision making for increasing confidence in SAM effectiveness.

13:50Post-Fukushima Strategies Implemented at CANDU® Nuclear Power Plants – Part 1Lovell Gilbert, Bruce Power

The events which took place at Fukushima Daiichi Nuclear facility in Japan prompted NPP utilities to evaluate and enhance their ability to mitigate challenges caused by extreme external events and manage challenges caused by those events. One such challenge is an extended loss of onsite and offsite electrical power which results in the unavailability of reactor heat removal systems. As a preparatory measure for such events, NPPs in Canada have adopted the use of portable/mobile equipment to provide emergency power to critical monitoring instrumentation and key components and to provide cooling water to critical loads. This concept is similar to the US FLEX strategy developed by the Nuclear Energy Institute (NEI). In Canada the concept is referred to as the Emergency Mitigation Equipment (EME) strategy and is designed to prevent a Beyond Design Basis Accident (BDBA) from progressing to a severe accident (SA). This paper will discuss the EME strategies and their application at Canadian utilities.

If left unmitigated, the subsequent core damage from a loss of core cooling event will result in the pressurization of the containment envelope leading to an uncontrolled release of fission products to the surrounding environment. Therefore protection of the containment integrity is a key SA management objective and Canadian NPPs have developed implemented a number of diverse strategies in the plant designs (e.g., engineered safety features, EME, design changes specific for SA) to mitigate the potential containment challenges. This paper will discuss a number of the engineered safety features and design changes developed at Canadian utilities.

The buildup of hydrogen in the containment system following a SA has the potential to cause a very large explosion, if not property mitigated. As seen in Japan at the Fukushima Daiichi NPP, detrimental effects from the explosion caused significant damage to the containment system, allowing a pathway to the environment for radionuclides. To control hydrogen accumulation in the containment, Canadian utilities have implemented measures to control hydrogen concentration inside the containment. This paper will discuss the engineered safety features and design changes specific to hydrogen control in containment.

14:10Post-Fukushima Strategies Implemented at CANDU® Nuclear Power Plants – Part 2Lovell Gilbert, Bruce Power

14:30The Application of CNSC Fukushima Action Plan in the Design of Small Modular ReactorsMagdy El-Hawary and Noreddine Mesmous, Canadian Nuclear Safety Commission

In 2014, CNSC published a suite of updated regulatory documents that incorporate the lessons learned from the Fukushima Action Plan. To the extent practicable, the requirements and guidance provided in these documents are technology-neutral with respect to water-cooled reactors. For non-water cooled reactor, the principles behind the requirements remain applicable with the understanding that an applicant or licensee may put forward a case to demonstrate that the intent of a requirement is addressed by other means and demonstrated with supportable evidence. The wide range of non-water cooled reactor designs makes it impractical for CNSC to develop detailed regulatory documents specific to each design.

This paper addresses the potential application of CNSC Fukushima Action Plan, and the CNSC whitepaper on Design Extension Conditions, for the CNSC pre-licensing Vendor Design Reviews (VDR) performed for Small Modular Reactors (SMRs). SMRs include water cooled and more advanced designs. This paper provides: - Summary of CNSC VDR process; - Summary of relevant CNSC regulatory documents; - Summary of basic characteristics of SMRs designs including modularity, simplified design features, passive features and inherent safety features; - Examples of the safety intents in CNSC documents and how they can be shown to be satisfied for SMRs.

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14:50Use of Gravity-Assisted Loop Heat Pipes for Passive Cooling of Spent Nuclear Fuel Pools during Station BlackoutAmir Sartipi, Rosa Elia Ortega Pelayo, Michel Gaudet and Changqing Zhang, Canadian Nuclear Laboratories

Decay heat removal in a nuclear power plant’s spent fuel pool during an extended station blackout is a critical function, as demonstrated following the Fukushima Daiichi nuclear disaster in 2011 March. As the water level within these pools is reduced due to evaporation, the risk of fuel sheath melt/rupture and consequent fission product releases increases. The feasibility of removing heat generated through decay power by means of a gravity-assisted loop heat pipe system from a spent fuel pool is being examined at Chalk River Laboratories. Heat pipes offer passive heat removal, low maintenance, and high reliability that can be utilized to maintain spent fuel pools at sub-cooled temperatures to reduce evaporation losses. A small scale test rig was designed and built, with the performance and efficiency of such a system currently being studied. This paper provides a summary of the test rig design, setup and preliminary experimental results.

Advances in Inspection and Monitoring Techniques – Specialized ToolsSession ChairLaura Obrutsky, M&O Tech Inc.

13:30Fuel Channel Scanning Tool Elongation Measurement “STEM”Sukhpal Singh Dhaliwal, Andrew Hong and Satyanarayana Mallampalli, Ontario Power Generation

At Pickering NGS (Nuclear Generation Station), a mechanical (Linear Variable Differential Transducer LVDT/wheel) contact type STEM Tool is used to measure pressure tube axial elongation measurements at PNGS site. The raw data collected by STEM is integral for the monitoring and assessment of a pressure tube’s axial elongation and for evaluating the planned service life for both PNGS 1&4 and 5-8. Axial elongation is the life-limiting mechanism at PNGS stations and confirmation of on bearing operation is required for demonstration of fitness for service. The STEM Tool is held in the Fuelling Machine (F/M) snout to scan row-by-row of reactor face to perform the linear measurement between the E-face of End-fittings and F/M reference plane. As identified, the existing mechanical contact type PNGS STEM Tool has design limitations and made unintended contact with an end fitting during PNGS unit 1 Outage in 2015. Furthermore, the existing STEM Tool has experienced many mechanical failures and does not provide enough clearance for the expected end-of-life fuel channel elongation at PNGS site. Internal/external rigorous background reviews and investigation of all available designed STEM Tools was conducted and concluded that a design change similar to DNGS STEM Tool was required to meet the PNGS site requirements. The DNGS STEM Tool non-contact type uses an ultrasonic sensor (obsolete) which gives more clearance but is less accuratethanPNGSsystem.The“New”STEMToolnon-contacttypeuses laser triangulation sensor that are typically used in displacement and position monitoring applications where high accuracy, stability and lowtemperaturedriftarerequired.Theproposed“NEW”designSTEMtool will replace the old design to eliminate moving parts, contact with

end fittings, swap replacement time and clearance issues. This new STEM Tool design will simplify the critical FC elongation measurement process and would be applicable to all the CANDU® reactors.

13:50Qualified Field-Trialed Next-Generation Advanced Portable Polymer Tester for Improved Cable Condition Monitoring in NPPJason Deadman, Daniel Ho, Robert Jamieson and Narendra Sachdev, SNC Lavalin Nuclear

SNC-Lavalin Nuclear is developing the next generation of portable polymer tester for testing indenter modulus in accordance with the international standard IEC/IEEE 62582-2. The instrument also measures Recovery Time as an indicator of cable degradation. The latest prototype is based on initial tool development by Atomic Energy of Canada Limited. with enhancements made to the instrument’s usability and ergonomics. The Advanced Portable Polymer Tester (APPT) features single user operation, touch screen control, consistent automated cable clamping, measurement of Indenter Modulus and Recovery Time, improved human factors and immediate preliminary results information post-test.

SNC-Lavalin has collaborated with Canadian Nuclear Laboratories and NB Power to qualify the methodology used for operation of the APPT to ensure results obtained with the APPT predict accurately the cable ageing characteristics. As part of the development process the APPT has been field trialed at the Pt. Lepreau NGS and OPEX obtained has been incorporated into the design.

14:10FOSAR – Foreign Objects Search and RetrievalHolger Damies, Gerhard Nützel and Sebastian Popp, AREVA GmbH

The identification, location and retrieval of foreign objects is essential in order to maintain power plant integrity. It prevents risks related to loose part fretting but also potential damages caused by loose parts when circulating inside plant systems. Therefore visual inspection and FOSAR technologies strongly contribute to lifetime / aging management programs.

AREVA’S remote controlled combined inspection and search & retrieval solution combines the best of expertise and technology from our global resources to deliver the most cost-efficient, safe and reliable results.

We are committed to continual investing so our cutting edge technology can keep evolving. Our number one mission is to safely identify and remove foreign material out of plant systems while minimizing personnel radiation exposure in dose areas.

Our system contains positioning unit / feeding manipulator for tape deflection combined with specific cameras, lighting and very flexible modular FOSAR tools. This allows high maneuverability as well as rapid assembly and disassembly with low set-up times.

A set of easily exchangeable grippers for different FOSAR requirements (e.g. type, size, location of particles) covers a wide range of applications. Additional suction devices and magnets are available on specific demand. Special, highly qualified FOSAR personnel with up-to-date experience ensures optimum performance.

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14:30Steel Pipe Wall Thickness Measurement by Pulsed Eddy CurrentKen Faurschou and Ross Underhill, Royal Military College; Jordan Morelli, Queen’s University; Thomas Krause, Royal Military College

Non-destructive inspection of bulk wall loss in ferromagnetic steel pipe is a common requirement across multiple industries. In the nuclear industry, pulsed eddy current has potential applications for tile holes and balance of plant inspections where insulated pipe is present. Currently, inspection on this type of component is typically done with ultrasonic testing, which requires a coupling agent and removal of any insulation. Pulsed eddy current (PEC) technique does not require direct contact and has a larger spot size, thereby facilitating more rapid inspection. Three different types of PEC send-receive probes were examined for inspection of a section of steel pipe with a step wall reduction. PEC data was taken at different distances from the inner surface of the pipe so that sensitivity of wall loss measurement to liftoff (distance of the probe from the near surface) could be assessed. The PEC signal was analyzed by fitting the tail of the transient decay with an exponential curve, with curve fitting parameters correlated to wall thickness variation. An analytical model was developed and partially validated in order to examine a wider range of factors than is practical with a lab setup, such as probe parameters, and magnetic permeability and conductivity of the steel. The modelled data was also used to perform a sensitivity analysis on probe parameters in order to streamline further probe development and to determine optimal probe parameters for specific applications.

14:50Specialized Tooling for Inspection of Calandria Relief DuctsAndrew Brooks and Sahil Gupta, Bruce Power

This paper presents an overview of the specialized tooling developed for the purpose of full volumetric inspection and high pressure water jet cleaning from the inside diameter (ID) surface ofthe18”CalandriaReliefDucts(CRDs)attheBruceNuclearGenerating Station B (BNGS) (Unit 7).The Unit 7 CRDs have been degraded from transgranular chloride induced stress corrosion cracking (TGSCC). During the 2016 Unit 7 outage, there was specialized, first-of-a-kind tooling developed in order to inspect and clean the Unit 7 CRDs.

Aging Management – Major ComponentsSession ChairTracy Gendron, Canadian Nuclear Laboratories

13:30Low-Voltage Electrical Cable Condition: Approach to Remaining-Life PredictionsFabrice Guérout, Canadian Nuclear Laboratories

To obtain confirmation that many installed electrical cables do not need to be replaced in the context of nuclear plant extension programs can be of very large economic significance. A structured approach to assessing cable condition and determining the potential remaining life of electrical cables is proposed. The approach is based on testing retrieved cable insulation/jacket from operating or decommissioned plants.

13:50Ageing Management of Low Voltage Cables at Darlington Nuclear StationDavid Rouison, Kinectrics Inc.; Allan Ghaforian, Ontario Power Generation; Marzieh Riahinezhad, Kinectrics Inc.

Low voltage (LV) power, control and instrumentation cables are used in all systems essential to the safe and reliable operation of nuclear power plants. A number of CANDU® power plants are currently planning or going through refurbishment which will extend their life for another 30 to 40 years. This process is based on the replacement of major components and a detailed assessment of other assets to ensure their continued operation for the remaining life of the plant. The vast number of LV cables found in each nuclear plant does not allow full replacement to occur, therefore aging management programs have to be implemented to determine and monitor their condition. In this presentation, Darlington NGS and Kinectrics present key aspects of the Ontario Power Generation Cable Surveillance program. This program ensures the implementation of the Cable Condition Monitoring program which relies on the precise identification and characterization of LV cables insulation and jacket in key areas of the plant. The field assessment of these cables is based on material based techniques such as Near Infrared Spectroscopy (NIR) and indenter modulus. Sacrificial cables installed in the plant at its inception are also analyzed in the laboratory at regular intervals to provide further evidence of the condition of the cables. The implementation of the program is illustrated with results obtained in recent years on instrument and control cables in the field and in the laboratory. The test results have shown limited aging for most cables and support their continued operation.

14:10Management of Aging Piping through Reasonable Assurance Assessments and Inspection PrioritizationAdam Roukema and Derek Newsom, Structural Integrity Associates, Inc.

All US nuclear power plants have been inspecting and remediating buried piping as part of their required U.S. NEI 09-14 Guideline for the Management of Underground Piping and Tank Integrity response. Most US plants have entered into the next phase of NEI-09-14 and NRC guidance for committed and enduring programs in ensuring buried pipe integrity. As a large majority of buried piping inspections have been completed at US Plants and more are planned, the ability to prioritize and reduce cost of inspections based on risk becomes advantageous. In addition, the ability to disposition inspection resources based on expected degradation can help plants more cost effectively and efficiently manage the life and integrity of these critical assets.

The NEI 09-14 initiative provides guidance on how to group assets into risk classifications that dictate the required number of inspections and the locations of each inspection. Risk scores are based on the dynamic segmentation process, which relatively ranks the risk of each line based on risk significant parameters as defined by EPRI. If reasonable assurance can be demonstrated by the minimum required inspections for each group, additional scheduled inspections can be eliminated.

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The EPRI BPWorks, and SI MAPPro suite of programs automates the risk ranking process to provide an overall risk picture for all lines and systems. Further, the Reasonable Assurance module automates the risk groupings based on user selected inputs from the NEI 09-14 guidance, resulting in the ability to target inspections. If no severe indications are found during the minimal inspections process, reasonable assurance can be achieved and inspections can be eliminated.

This presentation will focus on how U.S. plants have been approaching buried piping inspection prioritizations and risk.

14:30Aging Management and Reliability of CANDU® Steam Generators and Heat ExchangersMike Montazer, Danyal Montazer, Bob Goel and Carmen Fourar, CNG Nuclear

The steam generators in the CANDU® and pressurized water reactor (PWR) plants are large heat exchangers that use the heat from the primary reactor coolant to make steam in the secondary side to drive steam turbine generators. The steam generators are shell-and-tube heat exchangers each with several thousands of tubes. The primary reactor coolant passes through the tubes and boils water on the outside of the tubes (secondary side) to make steam. The CANDU® design confines radioactivity from neutron activation or fission products to the primary coolant during normal operation of calandria.

Age related degradation effects in safety related systems of CANDU and other nuclear power plants should be managed to prevent safety margins from corrosion and eroding below the acceptable limits provided in plant design basis. The aging management process consists of three key elements: 1) selecting structures, systems, and components (SSCs) in which aging should be controlled; 2) understanding the mechanisms and rates of degradation in these SSCs; and 3) managing degradation through effective inspection, surveillance, condition monitoring, trending, record keeping, maintenance, refurbishment, replacement, and adjustments in the operating environment and service conditions of nuclear power plants.

In aging management and Steam Generator and Heat Exchangers reliability, among other factors, inspections and effective in-service surveillance are the essential aspect for ensuring the long- term safety and reliability of nuclear power plants (NPP). This paper presents the methodology towards ensuring that licensees operate and maintain their NPPs in a safe condition. There are programs that will enable existing or new steam generators to operate effectively for 40 years.

14:50Aging Management and Reliability of CANDU® Primary Heat Transport System and FeedersMike Montazer, Danyal Montazer, Bob Goel and Carmen Fourar, CNG Nuclear

The primary heat transport (PHT) system circulates pressurized heavy water coolant (D2O) through the reactor fuel channels to remove heat produced by fission in the uranium fuel. The heat is

carried by the reactor coolant to the steam generators, where it is transferred to light water to produce steam. The coolant leaving the steam generators is returned to the inlet of the fuel channels. The reliability and integrity of PHT Components and Feeder pipes are evaluated by Inspections and NDE technology. Failure of PHT system has direct effect on cooling and performance of the reactor. Age related degradation effects in safety related systems of CANDU and other nuclear power plants should be managed to prevent safety margins from corrosion and eroding below the acceptable limits provided in plant design basis. PHT equipment reliability is evaluated and followed by equipment reliability process top level diagram of AP913; that includes 1) scoping and identification of critical components, 2) performing monitoring, 3) corrective actions, 4) continuing equipment reliability improvement, 5) preventive management implementation, and 6) life cycle management.

In aging management and reliability of Primary Heat Transport System and Feeders, among other factors, inspections and effective in-service surveillance are the essential aspect for ensuring the long-term safety and reliability of nuclear power plants (NPPs). This paper presents the methodology towards ensuring that licensees operate and maintain their NPPs in a safe condition. There are programs that will enable existing or new steam generators to operate effectively for 40 years.

15:10 – 15:40 Networking Break

15:40 – 17:00CONCURRENT TECHNICAL SESSIONSPost-Fukushima Strategies – 2Session ChairLovell Gilbert, Bruce Power

15:40Considerations in Implementing Earthquake Design Extension Condition (DEC)Aman Usmani, Amec Foster Wheeler and Tarek Aziz, TSAziz Consulting Inc.

Lessons from the Fukushima accident have focused international attention on efforts in developing prevention and mitigation strategies for the accident scenarios beyond those design basis accidents (DBA) normally considered during the design of nuclear facilities. A subset of these beyond design basis accident (BDBA) scenarios is termed design extension conditions (DECs). The Canadian Nuclear Safety Commission (CNSC) is aligning with the international nuclear community especially IAEA to identify and adopt best practices as considerations regarding DECs. The CSA N289 series of Standards includes provisions to ensure that there are adequate margins in the nuclear power plant systems, structures and components (SSCs) to safely withstand beyond design basis earthquakes as well as DECs.

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16:00Radiation Monitoring System for CFVS StacksSherri Hashemi, Nigel Reynolds and John Robinson, Tyne Engineering Inc.

This paper describes Radiation Monitoring Systems (RMS) for a CANDU® Plant Containment Filtered Vent Systems (CFVS). The RMS proposed by Tyne Engineering will provide reliable stack monitoring for72hoursfollowinga“BeyondDesignBasisEvent”(BDB)event.Two designs are proposed by Tyne. Design 1-particulate, and iodine is sampled and noble gas is measured, and Design 2- gross gamma is measured by an adjacent-to-stack monitor. Tyne will provide Design 1 in accordance with ANSI N13.1-1999 for “SamplingandMonitoringReleasesofAirborneRadioactiveSubstancesfromtheStackandDuctsofNuclearFacilities”.Thiswill be achieved provided that velocity in the CFVS stack is within the range of stack velocity covered by ANSI code. Design 2 is based on an adjacent-to-stack gamma monitor providing overall gross gamma. As the noble gases are the major contributor to the stack discharge, they can be directly measured. Power is a significant issue as BDB accidents assume that no class IV or class III power is available. This option provides minimum power consumption as there is no need for a heater or a pump.

Monitoring is based on scintillation detector technology. The detector associated electronics are installed in a socketted module that attaches directly to the PMT. The compact configuration also allows for early analog to digital signal conversion and all signals being processed in a digital environment. Conventionally, a high-voltage power supply, a pre-amplifier, an amplifier, an analog to digital (A/D) converter and a Multi Channel Analyzer (MCA) are installed in a NIM (Nuclear Instrumentation Module) Rack which includes its own low voltage DC power supply to power the component boards installed inside. This configuration reduces the footprint and power consumption by eliminating the NIM rack.

16:20Integrated In-Vessel Debris Blockage Testing for Pressure-Tube ReactorsQingwu Cheng, Rul Xu and Metin Yetisir, Canadian Nuclear Laboratories

To investigate pressure-tube reactor in-vessel flow blockage during a simulated Loss-Of-Coolant Accident (LOCA) long-term core cooling operation, numerical simulations were performed for a pressure-tube reactor to understand its post-LOCA ECC flow in each fuel channel and the driving force between inlet header and outlet header. In addition, experiments were performed using a prototypical pressure tube with two dummy fuel bundles installed downstream of a reduced-scale strainer test rig. An end-fitting with a liner tube was connected to the pressure tube to simulate the actual fuel channel in a pressure-tube reactor. Particulate and fibrous debris simulating post-LOCA conditions were added to the strainer test rig. In addition, chemical reactants were also added to the test rig to simulate post-LOCA sump chemistry and to investigate the head loss effects of possible chemical precipitates. A total of five tests were performed, which included two thin bed tests, one full debris load tests and two chemical effects tests with full debris load. Bypassed debris from the strainer surface was observed to enter the fuel channel and accumulate inside the liner tube and on the fuel bundle endplates. Pressure drop due to the debris and chemical precipitates blockage across the fuel channel were measured and compared with the available driving force to determine whether sufficient flow would enter the pressure tube to remove decay heat. Preliminary testing results showed that the pressure tube head losses were not significant for the test conditions considered.

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Advances in Inspection and Monitoring Techniques - New Monitoring TechniquesSession ChairSteve Fluit, BWXT Canada Ltd.

15:40Strain and Vibration Monitoring of Nuclear Components using Fibre Optic SensorsMichel Gaudet, Kevin (Wenhai) Li and Metin Yetisir, Canadian Nuclear Laboratories

Fibre optic sensors, in which optical fibres are either used as the sensing element or used to relay the signal from these, are increasingly finding their way into industrial applications. Sensors intrinsic to a fibre optic strand, in which a fibre Bragg grating has been inscribed, offer several advantages. A single fibre can include multiple sensors or even distributed sensing capability, have minimal cross-section, low mass and not be affected by electro-magnetic fields. Low transmission losses within the fibre allow the signal can be carried considerable distances, and in some cases up to many kilometers.

Fibre optic sensors can be placed in locations previously considered inaccessible or difficult-to-access using conventional sensors. One example is the U-bend region of an on-power steam generator. In a program at Canadian Nuclear Laboratories (CNL), a fibre optic-based strain sensor is being developed, with the goal of eventually being deployed both as a research tool as well as a monitoring tool for components within the nuclear industry. To this end, a prototype tool has been tested, demonstrating that this technique can measure strain (ε) values as low as 2×10-6 m/m and vibration frequencies up to 1000 Hz. Up to 30 sensors can be engraved within a single fibre optic strand and interrogated simultaneously, with sensor spacing that can be customized.

Measurements were carried out with multiple sensing points within a single fibre optic strand, permitting strain values under a variety of conditions to be captured within the length of a vibrating cantilever test beam. The experience thus gained can then be applied to more complex systems such as steam generator U-bend tubes. This paper will present the operating principle of the instrument, as well as the test results.

16:00Using Sub-GHZ Wireless Sensors for Nuclear Plant Process and Security MonitoringJason Hollern, Michael Liebenow, Xue Wang and Lee Watkins, AREVA Inc.; Jocelyn Perisse, AREVA NP; Christoph Duval, ARCYS

Wireless technologies have been used in nuclear power plants for many years. Various systems utilize wireless technologies to perform their intended function. Some examples that have been employed include wireless security and Emergency Preparedness (EP) radios, Digital Enhanced Cordless Telecommunications (DECT) phone systems, wireless controllers for overhead cranes, and wireless business network Wi-Fi. With the exception of the security

and EP radios which tend to operate in the 800-900MHz range, most devices operate well above 1GHz. Because of the overall growth of wireless technology and devices, the increasing costs of employing traditional technologies, and the cost savings efforts that are being embraced by the nuclear industry worldwide, new wireless alternatives should be considered for cost reduction and advanced capability.

There are many advantages to deploying a sub-GHz sensor network within an industrial environment. Because sub-GHz frequencies can penetrate massive structures with less attenuation than higher GHz frequencies, it makes them an ideal candidate to employ plant-wide with less overall infrastructure to maintain. The type of networks employed for sub-GHz devices typically provides better signal strength and signal to noise ratios in areas of the plant where it is difficult to access or install permanent communications equipment. Some challenges exist with integrating new technology such as LTE-M and LoRa protocol based sensors into existing infrastructure, such as a Distributed Antenna System. Other challenges exist with battery consumption for wireless sensors versus data pull rates and data rate limitations.

There are many applications for sub-GHz wireless technology to include supplemental monitoring (I&C) of plant processes, security monitoring, remote tamper indication, operations monitoring (i.e. manual valve position indication), unmanned fire watch, etc. Many of the applications are intended to provide additional monitoring capability, provided capability for predictive maintenance, or reduce the overall time and expense of Operations and Maintenance of the plant.

16:20Improved Radiation Monitoring and Decontamination Processes to Reduce Significant Radioactive Waste Costs via RecyclingKent Anderson, UniTech Services Group

UniTech Services Group has been designing, manufacturing, and using custom radiation monitoring equipment to efficiently survey materials for recycling or reuse while significantly reducing the risk associated with traditional hand frisking. Additionally, they have developed and used custom decontamination processes that have allowed several million pounds of scaffolding and tooling to be released for unrestricted use back to the owners, or recycled as non-radioactive scrap metal. The combined effect of custom monitoring and decontamination processes has reduced significant volumes of radioactive waste in a low risk, cost effective, manner. This paper and presentation will highlight the processes and showcase the types of materials decontaminated. The intent is to make waste generators aware of new processes that could be applied to the waste materials stored in their vaults or generated as a result of major maintenance evolutions. The application of alternative workflows using custom monitoring technologies to handle high volumes of project generated LLRW (e.g. from reactor refurbishment or facility decommissioning) and their impact on project costs and schedules will also be discussed.

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16:40Advances in Ultrasonic Flow Measurement Technology for Nuclear ApplicationsVictor Janzen, Canadian Nuclear Laboratories; Alexander Gurevich, Srikrishnarajah Selvaratnarajah and Yuri Gurevich, AMAG Inc.

Ultrasonic techniques are widely used for a variety of diagnostic and monitoring purposes. The ability to transmit and receive signals through pressure boundaries, and their proven accuracy in measuring flow have made them essential to the nuclear industry, particularly for flaw detection and flow measurements.

We review the current use of ultrasonic technology in applications to nuclear power plants and report on recent advances in ultrasonic flow-measurement technology, including adaptations of cross correlation techniques and tests of specialized transducers. We suggest a number of potential but clearly achievable improvements in ultrasonic technology that could improve its usefulness to nuclear operators.

17:00Proactive Source Term Monitoring at CANDU® StationsYury Verzilov and David Trudell, Kinectrics Inc.

The radiation fields around the reactor components have a significant impact on the planning and execution of required maintenance and inspection activities; at the same time, they also carry the signatures of the various processes that reflect the state of health of the reactor components and systems. The variations in their spatial and radionuclide compositions are formed by corrosion of the carbon steel feeders, materials released by the movement of fuel along pressure tube surfaces during refueling, fuel failures, and wear of the various system components such as pump seals, valve hard facings and bearings. The monitoring of the radiation fields and detailed radionuclide characterization, station operation information and subsequent integration with reactor artifact data, and interpretation of the observed results are the vital modules of the source term monitoring (STM) program at CANDU stations. The results of the STM analysis allow for prediction of the future outage gamma fields and subsequent optimization of the radiation jobs during the maintenance and inspections activities through virtual job planning. Recent innovations and advancements in the STM program allow for 3D virtual reality job simulation for radioactive environments around various CANDU reactor components. Integrating the information on the radiation fields with station operational information is key to gaining an understanding of the cause and effect relationships of chemistry, operations, and system health of the various reactor systems in order to decrease the radiation fields. The information gained from the STM program also provides insights into the actual performance of the purification systems.

Aging Management – Steam GeneratorsSession ChairMichel Pettigrew, Ecole Polytechnique Montreal15:40New Steam Generators for Embalse NGS – Replacement Cartridge Design, Manufacturing and Localization IssuesRalf Gold and Jerzy Parkitny, SNC-Lavalin Nuclear; Pablo Luna and Ricardo Sainz, Nucleoeléctrica Argentina S.A.

Embalse Nuclear Generating Station (Central Nuclear Embalse) was placed in service in 1983 and the life extension outage is currently inprogress.EmbalseNGSisequippedwithfourverticalinverted“U”tube-type Steam Generators (SG) with integral preheater, I-800 tubes and carbon steel internals.

Between 2002-2006, NA-SA in consultation with AECL (now SNC-Lavalin Nuclear) assessed the potential for SG life extension; However, degradation of the tube supports (carbon steel broached plate) and U-bend supports due to Flow-accelerated corrosion (FAC) coupled with the plan to increase the plant power output during the life extension of the station, resulted in the strategic decision by NA-SA to replace the Steam Generators. As part of the localization program for major components required for Central Nuclear Embalse life extension program, NA-SA and SNC-Lavalin Nuclear (formely AECL) signed a cooperation and technology transfer agreement to evaluate the capabilities of local suppliers to manufacture the steam generators and steam generator tubing. The scope of the localization program for the Replacement Steam Generator (RSG) and Steam Generator Tubing included qualification of the following suppliers by AECL (now SNC-Lavalin Nuclear) under contract with NA-SA:

• IndustrialMetalurgicasPescarmonaSA(IMPSA)wasqualifiedasthe manufacturer and supplier of the replacement steam generator cartridges

• FabricaciondeAleacionesEspecialesS.A(FAE)asubsidiary of Combustibles Nucleares Argentinos Sociedad Anónima (CONUAR) was qualified as the manufacturer and supplier of the steam generator tubing.

The design documentation for the RSG was prepared by BWXT (Canada) under technology transfer contract to IMPSA. IMPSA developed applicable manufacturing drawings and procedures and manufactured four RSG cartridges. All RSG cartridges are now delivered to Embalse site. This paper concentrates on design and manufacturing challenges (successful qualification of local suppliers, pre-production qualification process etc.) encountered during the manufacturing phase of the project. All RSG cartridges are now delivered to Embalse site and installation is in progress.

16:00Steam Generator Service Solutions for Improving Plant EfficiencyHolger Damies and Gerhard Nutzel, AREVA GmbH

Long-term integrity and high performance of major plant systems and components like steam generators are of uppermost importance for the successful operation of any power plant.

AREVA is a provider of integrated high-technology services and maintenance tools for improving plant efficiency. AREVA provides such services and tools to customers worldwide and for various plant designs.

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The objective of AREVA’s integrated service and maintenance tool concept is to support operators to minimize corrosion damage and performance losses of water-steam cycle systems and components and thereby to maximize the availability and economic performance of the plant.

AREVA has an integrated approach for best long-term performance and reliable plant operation in the field of evolutionary services and maintenance tools, such as mechanical cleaning and inspection services for Steam Generator secondary side.

16:20The Role of Steam Generator Inspections in Life Cycle ManagementLaura Obrutsky, M&O Tech Inc.

A variety of degradation modes may challenge the integrity of steam generator (SG) tubing and therefore the stations’ reliability, capacity factor and cost effectiveness. One of the key life-management components for ensuring tube integrity, and thus protecting the safety of the public and the environment, while maintaining cost effective operation of Nuclear Power Plants (NPP), is inspection and monitoring aimed at timely detection and characterization of the degradation.

However, the role of Non-Destructive Evaluation (NDE) has evolved. In addition to the historical role of providing detection tools, current NDE technologies are used as diagnostic tools to gain knowledge that can be related to SG operational parameters. This additional information is often instrumental in tube integrity assessment decisions, fitness-for-service and operational assessments.

This paper discusses the evolution in the overall role of SG inspections and analyzes the motivations behind that evolution. It presents examples that illustrate the current scope of SG inspections as detection and diagnostic tools.

16:40A Preliminary Three Dimensional CFD Model of the APR1400 Steam Generator Using ANSYSKrzysztof Zabrzycki and Aya Diab, KEPCO International Nuclear Graduate School

Understanding complex flow within a nuclear Steam Generator (SG) requires advanced thermal-hydraulic analyses given the localized flow characteristics and associated two-phase flow phenomena. Such phenomena are usually studied using dedicated SG thermal-hydraulic pseudo multi-dimensional tools or by using generic system tools (e.g., lumped one- dimensional codes). However, dedicated codes such as ATHOS3® or CUPID®, require significant and complex model preparation primarily due to the complex geometry of the SG internal structures. On the other hand, lumped one-dimensional tools, such as RELAP5®/MELCOR®/CATHARE® are incapable of capturing the localized 3D flow characteristics associated with SGs. As such, application of Computational Fluid Dynamics (CFD) tools could be used to model the complex three-dimensional flow patterns relevant to SGs with good fidelity. However, modeling of two-phase flow phenomena, particularly those related to phase change (i.e. boiling and condensation), remains a challenge for the available CFD

tools. Thus models using these tools need to be complimented via the user defined function capability.

This study focuses on the development of a CFD model for APR1400® SG, suitable for modeling steady state conditions. ANSYS Fluent® is selected as the computational engine. This research is divided into three main stages of which the first is detailed here. Stage 1 is focused on the primary (tube) side representing the flow field by a porous medium with equivalent pressure drop. The secondary (shell) side is modeled as a heat sink. This is to be followed by Stage 2 modeling of the secondary side. This stage involves preparation of a User Defined File (UDF) that describes in detail the attendant physical models appropriate for the specific system conditions. The Stage 3 model would then integrate the primary and secondary sides into a single model. ANSYS-Fluent results using the Stage 3 model would be benchmarked to available APR1400® steam generator data as reported in the Standard Safety Analysis Report (SSAR).

The Stage 3 tool may then be used to analyze complex three-dimensional flow phenomena. For example: Fluid-Structure Interaction (FSI), tube fouling, and system response under (slow) reactor transients or accident conditions would be amenable to analysis using the ANSYS-FLUENT Stage 3 model as a foundation.

17:00Investigations of In-Plane Fluidelastic Instability in a Multi-Span U-Bend Tube Bundle – Tests in Air FlowPaul Feenstra and Teguewinde Sawadogo, Bruce Smith and Victor Janzen, Canadian Nuclear Laboratories; Helen Cothron, EPRI

The tubes in the U-bend region of a recirculating type of nuclear steam generator are subjected to cross-flow of a two phase mixture of steam and water. There is a concern that these tubes may experience flow-induced vibration, including the damaging effects of fluidelastic instability.

This paper presents an update and results from a series of flow induced vibration experiments performed by Canadian Nuclear Laboratories for the Electric Power Research Institute (EPRI) using the Multi-Span U-Bend test rig. In the present experiments, the main focus was to investigate fluidelastic instability of the U-tubes subjected to a cross-flow of air. The tube bundle is made of 22 U-tubes of 0.5 in (12.7 mm) diameter, arranged in a rotated triangular configuration with a pitch over diameter ratio of 1.5. The test rig could be equipped with variable clearance flat bar supports at two different locations to investigate a variety of tube and support configurations. The primary purpose of the overall project is to study the effect of flat bar supports on ‘in plane’ (‘streamwise’) instability in a U-tube bundle with realistic tube-to-support clearances or preloads, and eventually in two-phase flow conditions. Initially, the test rig was designed for tests in air-flow using an industrial air blower. Tests with two-phase Freon refrigerant (R-134a) will follow.

This paper describes the test rig, experimental setup, and the challenges presented by simulating an accurate representation of current steam generator designs. Results from the first series of tests in air flow are described.

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Utility Engagement Panel on MaintenanceFront-line maintenance workers are integral to plant maintenance and they need access to innovative approaches to improve maintenance productivity through automation, advanced technology and applications that provide them with essential information to execute their tasks efficiently and effectively.

The first Utility Engagement Panel on Maintenance is being held on Monday, October 2, 2017 from 17:30-21:00. This session is being held in workshop format and involves panelists who have identified key maintenance issues (current or foreseen in the future) as the basis for interactive discussion with solutions-oriented service providers, equipment vendors and CMNCC 2017 exhibitors to explore efforts that may be underway to address the issues.

Moderators:Edwin Chen, Director Structural Mechanics, Amec Foster Wheeler

Don Wilson, Director, Information Exchange, CANDU Owners Group

PanelistsKen Hamilton, Manager, Plant Maintenance, Ontario Power Generation

Jason Lehtovaara, Team Lead, You Can Count of Me, Bruce Power

Pierre Michaud, Manager, Programs Engineering, Point Lepreau NGS, NB Power

John Slade, Chief Engineer, Canadian Nuclear Laboratories

Agenda17:30–17:40 – Introduction

17:40–18:30 – Panelist presentations

18:30–19:10 – Networking Dinner (included)

19:10–20:00 – Panelist presentations

20:00–21:00 – Facilitated Q&A and discussion

21:00 - Adjourn

Sponsored by

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07:30Early AM Refreshments

08:30-10:00

Plenary 2A: Supply and Training of Qualified Staff for the Utilities and their Service ProvidersThis session explores, in a panel format, the issues and possible solutions to the challenges of developing and supplying the skills and trades required to support our nuclear industry for the years to come as it faces major refurbishment projects, and strives for world class performance of its facilities. The discussion will focus primarily on skills and trades needs as seen by the operating utilities, the vendors and the labour unions, and the role of the Ontario college network to meet those needs.

Panelists

Panel ModeratorDr. Ron Oberth, President, OCNI

Greg Cornett, Director, Training Programs, Ontario Power Generation

Greg is accountable for the effective design, scheduling and conduct of all work force initial and requalification training programs. Greg has vast experience in instructional systems design primarily using the Systematic Approach to Training (SAT) model, and has had direct involvement with World Association of Nuclear Operators (WANO) and International Atomic Energy Agency (IAEA) assessments and Area for Improvement (AFI) response strategies. Greg’s expertise includes commissioning, operations, project management, training and human performance.

Terry Armstrong, Vice President, Nuclear, E.S. Fox Ltd.

Mr. Armstrong commenced employment in the estimating department of E.S. Fox Ltd. in 1980. A change in career paths occurred in 1992 with his enrolment in law school at the University of Windsor. He received his Faculty of Law, Bachelor of Laws (LL.B.) in1995 and was called to the bar in 1997.

Upon his call to the bar in 1997, Mr. Armstrong began a private litigation practice until rejoining E.S. Fox Ltd. as General Counsel in late 2000. Mr. Armstrong’s focus within E.S. Fox Ltd. changed when he was appointed as Operations Manager for the ASLF Bruce A Units 3 & 4 Restart project.

He currently holds the position of Vice President Nuclear which includes overseeing work under the Extended Services Master Service Agreement with OPG as well as ongoing work at Bruce Power.

Terry currently holds the position of President of EPSCA (Electrical Power Systems Construction Association).

Dr. Ron Oberth has worked in the Canadian nuclear industry for more than 30 years at Ontario Hydro, Ontario Hydro International, Ontario Power Generation and the former AECL Reactor Division (now SNC-Lavalin/ Candu Energy). In June of 2011 Ron became president and CEO of the Organization of Canadian Nuclear Industries (OCNI) - an industry association that represents 180 private sector companies that supply equipment and services to CANDU and other nuclear power plants in Canada and offshore. His nuclear experience includes reactor safety, used fuel management, medical isotopes, and the marketing of CANDU reactors both domestically and internationally. Ron is a graduate of the University of Manitoba and the Rotman School of Business and received his PhD in aerospace propulsion from Princeton University.

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Bob Walker, Chair, Canadian Nuclear Workers Council

Apart from his current role with CNWP, Bob is a member of the Board of Directors of the Canadian Nuclear Association (CNA). In June of this year, he left the position of Sector Vice President – Nuclear with the Power Workers’ Union (PWU). Previously, Bob held Board positions with the Durham Region Labour Council, Durham Region Local Training Board and Bethesda House. His base position at Ontario Power Generation (OPG) is that of Supervising Nuclear Operator (SNO) at the Darlington Nuclear Generating Station.

Linda Franklin, President & CEO, Colleges Ontario

Linda joined Colleges Ontario in 2007. She has spearheaded a system wide marketing campaign on the value of college education, brought public attention to the impending skills shortage and led advocacy efforts to improve pathways for students.

Previously, Linda was CEO of the Wine Council of Ontario. There, she worked with government on legislation that dramatically improved the economics of the industry, allowing the number of wineries to rise from 20 to almost 200 today.

Linda’s early career included time as a partner in a consulting company, the head of communications for a regulatory body and for government MPPs, and Chief of Staff to an Ontario cabinet minister. She has an MA in journalism from Western University.

Kevin Baker, Principal & Dean, School of Skilled Trades, Apprenticeship & Renewable Technology, and Centre of Food, Durham College

Kevin Baker has been a senior administrator in the publicly-funded, post-secondary education system for over 16 years. He joined Durham College in April 2011 and assumed his current role as Whitby Campus principal and dean in July 2015. In that capacity, Baker oversees operations, planning and strategy for the campus and the schools of skilled trades, apprenticeship, renewable energy and the W. Galen Weston Centre for Food.

Prior to joining Durham College, Baker had roles as a campus administrator, general counsel and corporate secretary, and vice-president at College of the North Atlantic (CNA) in Stephenville, NL. He has also taught in the college and university systems for over 20 years.

Baker has a Bachelor of Arts and Master of Arts (Sociology) from York University, and a Juris Doctor from Osgoode Hall Law School in Toronto, Ontario.

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Luncheon Guest SpeakerRaj Verma, Vice President Major Accounts, Marketing and Business Development, SNC-Lavalin Nuclear Inc.

Raj Verma has recently rejoined SNC-Lavalin Nuclear as Vice President Major Accounts, Marketing and Business Development. Since 2001, Raj has had both technical and project management roles in the Canadian nuclear industry and has the good fortune of working with a number of the top CANDU suppliers, such as AECL, Promation Nuclear, Candu Energy, SNC-Lavalin and Kinectrics and providing services to OPG, Bruce Power, NB Power, SNN and KHNP. During this time, he led or was intimately involved in many maintenance initiatives such as Calandria Relief Duct Inspection, CanduClean, CT-Liss Gap Inspection, and CANDU refurbishment tooling design and build. From 2011 to 2014, Raj ran a mobile start-up – aajo – headquartered out of the MaRS Commons space in downtown Toronto. Raj received his Bachelor of Science in Engineering (Electrical Engineering) from the University of New Brunswick.

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A Collaborative Approach to Human Performance in Support of Maintenance Activities – A Vendor PerspectivePamela Tume, SNC-Lavalin Nuclear

Challenges during the Implementation of Cyber Security at Nuclear Power PlantsJeffrey Knight and Joseph Horn, ENERCON

Maintenance Optimization – Predictive vs. Preventive MaintenanceHolger Damies, Thomas Seitz, André Zander, Gerit Gloth, Peter Brückner, AREVA GmbH

Post Graduate Education and Training Programs for Nuclear ProfessionalsGeorge Bereznai, John Froats and Benjamin Rouben, UOIT

Methods and Facilities for Validation and System Integration Testing of Upgraded Legacy Shutdown SystemsAnqing Xing and Lawrence Lowndes, Candu Energy Inc.

Approaches to Identification of Functional Requirements and Development of Specifications for Digital I&C Systems UpgradesMehdi Tadjalli and Roger Wyatt, ENERCON

First Nation, Metis and Inuit (FNMI) ConsiderationsRozella Johnston, Bruce Power; Mike Ruysseveldt, Promation Nuclear

HITL-Guard: A Platform for Real-Time Tracking of Operator Situational Awareness in Control RoomsHarsh Singh, Ontario Power Generation; Qusay Mahmoud, UOIT

Advanced Techniques for Component Monitoring and Predictive Maintenance Program SupportMagnus Langenstein, Andy Jansky, David Walker, BTB Jansky GmbH

Succession Planning and Attracting Young Professionals to IndustryKaren Smith, Bruce Power

Reactor Area Bridge Fast Acting PlatformsEdward Veckie, Unified Engineering; Emily Ferreira and Jim Hanna, Bruce Power

Staffing Challenges and Innovative Solutions Plant Management Maintenance Management

10:30

11:10

10:50

11:30


Luncheon

10:30-11:50

12:00-13:30

12:45

Networking Break10:00-10:30

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10:30-11:50CONCURRENT TECHNICAL SESSIONSStaffing Challenges and Innovative SolutionsSession Co-ChairsGreg Cornett, Ontario Power GenerationJacques Plourde, Canadian Nuclear Society

10:30A Collaborative Approach to Human Performance in Support of Maintenance Activities – A Vendor PerspectivePamela Tume, SNC-Lavalin Nuclear

Vendor presence in both in-age and outage activities continues to be a norm in CANDU® Nuclear plants. Vendor contracts and management systems therefore need to be both flexible to respond to multiple client environments while providing assurance that the client-specific processes and behavioral expectations are met. Anotherwaytoviewthiscanbesimplyexpressedas“Itisessentialthatvendorslearnto“ThinklikeanOperator”“.

This paper will explore one vendor’s perspective to foster this learning through 1) Human Performance tools within its management systems; 2) 21st century technologies to aid human performance; 3) innovative multi-vendor and utility collaborations; and 4) fostering zipper-conversations to actively listen to both the vendor andclientvoiceinordertoensurethatto“ThinklikeanOperator”becomes the daily mindset on our journey of mutual success.

10:50First Nations, Metis and Inuit (FNMI) ConsiderationsMike Ruysseveldt, Promation Nuclear and Rozella Johnston, Bruce Power

The Canadian Nuclear Industry will face ongoing challenges of resourcing, particularly as Bruce Power and OPG both perform large scale programs such as Main Component Replacement and Refurbishments at the same time. This challenge could be mitigated by the increased engagement of our First Nations, Metis and Inuit representatives.

Bruce Power has established programs to engage Saugeen Nation directly and the vendor community will look to utilise their lessons learned to establish FNMI inclusion within their organisations. The OCNI is looking to take the lead on behalf of the vendor community in establishing new innovative programs and integrating with the BP/OPG initiatives.

11:10

Post Graduate Education and Training Programs for Nuclear ProfessionalsGeorge Bereznai, John Froats and Benjamin Rouben, UOIT

The majority of the engineers and scientists doing technical work in Canada’s nuclear industry have one or more degrees in a field other than nuclear science or engineering. Graduates of chemical, electrical and mechanical engineering programs are the most

frequent hires for entry level engineering positions, while graduates of other engineering programs are represented in lower numbers. With the exception of students who have taken nuclear courses as part of an engineering physics or a science program, knowledge of nuclear physics, or the impact of radiation on chemical and material properties, have not typically been studied. While the nuclear engineering degree and diploma programs that have been established since 2003 at the University of Ontario Institute of Technology (UOIT) in Oshawa have been graduating nuclear engineers, the vast majority of new engineering and science graduates hired into the nuclear industry continue to be from the traditional engineering programs. The companies and institutions that comprise Canada’s nuclear industry have relied on a combination of in-house and contracted training courses, as well as on-the-job training to impart the nuclear-specific information to the employees working in jobs that require such knowledge. Companies have been increasingly turning to universities such as UOIT and the ones that have partnered to form the University Network of Excellence in Nuclear Engineering (UNENE) to provide postgraduate degree and diploma programs in nuclear engineering. UOIT has also partnered with Ontario Power Generation (OPG) to deliver the Advanced Operations Overview for Managers (AOOM) training program. The AOOM program is an essential component of succession planning at OPG, and is attended by managers and senior technical experts with several years of utility experience. For recently graduated engineers hired into entry level positions, completion of a four course graduate diploma at UOIT is a required component of the initial training program.

11:30Succession Planning and Attracting Young Professionals to IndustryKaren Smith, Bruce Power

Attracting and developing current and future leaders is critical to our success and to ensure long-term sustainable operational excellence. Bruce Power’s Talent Management program includes robust and executable succession plans as a key component, is the foundation for our employee attraction and development programs. But this has not always been the case. During a 2013 review of our processes it was identified that the development of future leaders and successionplanningwereseenmoreas“HRprograms”andnotanarea of priority across the organization. This disconnect, and the fact that our metrics were not aligned with industry best practice, resulted in situations where internal candidates were not available to fill senior positions when organizational changes occurred. To address these gaps, Bruce Power undertook a set of initiatives, including benchmarking talent processes both within and outside the nuclear industry, a thorough review of positions to identify those considered critical to the organization and the establishment an overall Talent Management Review process which engaged leaders throughout the business and that was completed per annual plans.

Today, Bruce Power’s Talent Management has been identified as world class and the program incorporates the review of talent of over 1500 professional and management employees. We have more than 250 unique succession plans, including plans for approximately 60 identified critical positions. In 2016, 94% of our

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critical position vacancies were filled through planned moves and currently 488 employees are named on one more succession plan. There is confidence in our program from across the business and a strong focus on comprehensive and diverse development plans for all leaders, including our younger employees who may aspire to progress into a leadership role. This business focus on emerging leaders assists in recruitment activities of young high potential professionals considering a nuclear industry career.

Plant ManagementSession ChairPaul Spekkens, Kinectrics Inc.

10:30Challenges during the Implementation of Cyber Security at Nuclear Power PlantsJeffrey Knight and Joseph Horn, ENERCON

Requirements for the protection of digital computer and communications systems and networks for U.S. Nuclear Power Plants (NPPs) are documented in 10 CFR 73.54. Guidance to meet the requirements is provided by the Nuclear Energy Institute (NEI) in NEI 08-09Rev.6“CyberSecurityPlanforNuclearPowerReactors”andbytheNuclearRegulatoryCommission(NRC)inRG5.71“CyberSecurityProgramsforNuclearFacilities”.10CFR73.54requireslicenseestoimplement a Cyber Security Program as part of their Operating License. There are many challenges that need consideration during the application of these requirements. The list below captures some of these challenges:

· Realizing the full scope of critical digital components.

· Documenting the configuration of digital plant equipment.

· Employing alternate methods to achieve compliance

· Training/hiring staff to adequately implement the program.

· Obtaining Organizational Buy-In

Although there are challenges to overcome, the implementation of cyber security requirements at NPPs is essential to their safe and secure operation. Digital equipment is relied on now more than ever for plant operation, and as the use of digital equipment increases, so does the attack surface and risk of compromise. The implementation of a Cyber Security Program will help to address these risks and provide strategies for responding to events should they occur. The discussion below is meant to address challenges that come with the implementation of a Cyber Security Program at a NPP.

10:50HITL-Guard: A Platform for Real-Time Tracking of Operator Situational Awareness in Control RoomsHarsh Singh, Ontario Power Generation; Qusay Mahmoud, UOIT

The Human-in-the-Loop (HITL)-Monitor offers a non-intrusive means of monitoring operator situational awareness by measuring errors introduced by way of interactions between the operator and the Human Machine Interfaces (HMIs). Motivation for this application is partly in response to develop a system using computer vision to acquire data from legacy HMI devices common to industrial I&C

systems in control rooms, field mounted control panels, etc. in nuclear power plants, aviation and locomotive industry. Visual data acquisition for real-time monitoring of legacy HMI devices does not require the target indicator device to be digitized incurring expensive retrofits, nor causes any process or production downtime. Secondly, automatic validation of equipment status during maintenance and/or prior to returning to service, is also explored through this application. Nevertheless, severity of accidents caused due to operator errors can be reduced, if HITL errors are promptly discovered, trended and intervened upon.

11:10Methods and Facilities for Validation and System Integration Testing of Upgraded Legacy Shutdown SystemsAnqing Xing and Lawrence Lowndes, Candu Energy Inc.

In the Darlington design, each shutdown system consists of three Trip Computers, three Display/Test computers and a Monitor Computer. These computers are currently being upgraded due to hardware obsolesce and the associated maintenance burden. This paper describes the methods and facilities used to validate each individual computer and to perform system integration testing after each computer is successfully validated. A test computer with a specialized scripting tool/language is developed for both validation testing and system integration testing. In order to reduce engineering costs, the scripting tool/language is maintained backward compatible for re-use of scripts developed in the previous project. A purposely built test rig consists of computers under test that can be configured to any one of the three channels of a shutdown system, with the other two channels simulated using communication packet simulators. The test computer has extended I/O capability to drive inputs to all three computers and confirm the behavior of each individual computer as well as the behavior of the integrated system, eliminating the set of voltages sources and the panel of digital switches used in the previous project. Validation and system integration testing is performed by a team independent from the development team using a black-box approach and the testing is automated to the maximum extent practical. The test facilities/tools developed and qualified for this project can be easily adapted for use in future projects.

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Maintenance ManagementSession ChairKeith Stratton, Stratton Consulting Inc.

10:30Maintenance Optimization – Predictive vs. Preventive MaintenanceHolger Damies, Thomas Seitz, André Zander, Gerit Gloth, Peter Brückner, AREVA GmbH

The Long Term Operation Policy for nuclear plants poses new technical challenges on the power industry, since the plants need to be operated reliably for 50 and more years. It is therefore necessary to deal with the degradation behavior of equipment and its predictability in order to reduce maintenance costs and ensure high safety and high availability at the same time.

For this reason an effective maintenance strategy needs to be applied for the surveillance of possible aging effects and preventive measures need to be implemented to ensure the necessary technical basis for maintaining safety margins throughout the plant. Beside overall plant safety there is a special focus on reliable component operation what increases the demand for predictive maintenance solutions based on continuous surveillance and efficient monitoring.

10:50Advanced Techniques for Component Monitoring and Predictive Maintenance Program SupportMagnus Langenstein, Andy Jansky, David Walker, BTB Jansky GmbH

The large quantities of measurement information gathered throughout the Primary, Secondary and Cooling Water processes of a nuclear plant make the closing of the mass and energy balance nearly impossible without the help of advanced tools.

The BTB Jansky ProcessPLUS® Online System1 uses all redundant measurements within the process to continuously close mass and energy balances. The VDI 2048 standard ensures that the calculated results meet strict quality control standards thereby yielding the most accurate representation, with the lowest uncertainty, of plant conditions. ProcessPLUS® has been applied to all reactor types: BWR, PWR, VVER and CANDU®2.

All measured values within the plant are subject to distortions caused by avoidable, systematic or random errors. The Gaussian Correction Principle provides the optimum method of accounting for these measurement errors using proven mathematical/statistical methods.

Fundamental to the solution is use of all available measured variables, including redundant measurements, along with the respective variances and covariances. In addition the calculated true values of the measured variables must meet the boundary conditions of conservation of mass, energy and material balances.

VDI 2048 specifies the quality control criteria that must be met to ensure an accurate representation of both component and process behaviour.

Thehighqualitydataobtainedrepresentsthe“true”plantprocessstate with the highest confidence. This data can then be used as the reference for differentiating between instrument drift and process anomalies. Component performance is determined by quantification of internal leakages, non-condensable gases, fouling, etc. Instrument drift is quantified and can be trended over time.

The availability of quality assured reference data of all process variables in the Primary, Secondary and Cooling Water systems enables the plant to prioritize maintenance activities. Appropriate corrective action can be planned because the impact of problems can be accurately determined. Early detection of component degradation allows for maintenance intervention prior to failure thereby improving plant safety and availability.

In addition, this method is used for power recovery by application of asocalled“virtualflowmeter”whichprovidesreconciledfeedwaterflow and temperature data with significantly reduced uncertainty. Process Data Reconciliation is used for power recovery in Sweden, Germany, Switzerland, Japan, Hungary and the Netherlands.

11:10Approaches to Identification of Functional Requirements and Development of Specifications for Digital I&C Systems UpgradesMehdi Tadjalli and Roger Wyatt, ENERCON

Increasing challenges due to obsolete systems and components, as well as recent market conditions have driven the nuclear power plants (NPPs) owners to increase their focus on operation and maintenance cost reduction. Upgrading outdated Instrumentation and Control (I&C) systems to digital is considered an effective approach for reducing the O&M cost and increasing plants reliability. As most operating plants in the U.S. have already extended their license to 60 years (and several are preparing for the extension to 80 years), upgrade of the outdated 1960s and 70s technology becomes unavoidable. As existing analog systems age, maintenance personnel are tasked to repair rather than replace broken equipment. Although repair is often cheaper than replacement, multiple repairs on a singular component or module increases the risk of human error or the possibility that the item is damaged and cannot be repaired. Digital technologies, although constantly improving and evolving, often provide the flexibility of backward compatibility that eases the burden of obsolescence on the licensee. A significant lesson learned from the digital upgrades in U.S. NPPs, both safety and non-safety, it is critically importance of having a well-defined and detailed Functional Requirements Specification (FRS). Most Original Equipment Manufacturers (OEMs) will concur that one of the most important factors in reducing project cost is assuring that all requirements are well defined and complete prior to starting the project. A detailed and high quality Functional Requirements Specification is critical in documenting these requirements.

This paper provides some guidelines on development of functional and procurement specifications.

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11:30Reactor Area Bridge Fast Acting PlatformsEdward Veckie, Unified Engineering; Emily Ferreira and Jim Hanna, Bruce Power

n this highly regulated industry, developing and introducing the best tools to perform a function can pose a challenge. An innovative culture to develop safer more efficient systems can make existing products obsolete. This can be termed ‘Proactive Obsolescence’ and was incorporated by Bruce Power for maintenance access to the reactor area bridge in the reactor vault. Reactor maintenance requires a dedicated team of professionals to ensure safe, efficient work execution. Scaffolding has long provided a necessary function yet it introduces risks such as: foreign material entering the systems, working at heights on a temporary structure and radiation exposure for the workers installing and removing the scaffolding. Bruce Power personnel saw the need to minimize these risks and partnered with Unified Engineering to design and manufacture a mobile platform to eliminate the need for scaffolding. Bruce Power’s Human Factors and Operations / Engineering departments supported the design to ensure the best possible platform system. The scope was to design a platform with the following considerations:

•Initscompactedstatemustbeabletopassthroughtheairlock

•Bedeployedwithoutanytooling,hardwareorelectricalpoweredmotors/drives

•Beabletobeliftedinplacebyanoverheadcrane

•Bedeployedwith4personcrewin1½hourtimeframe

•Haveacoverageareaof16feetby10feet(fillingintherecessesin the bridge pit where accessibility is required)

•DesignbasedonHumanFactorsandForeignMaterialExclusionconsiderations

The result was a folding platform system that reduced 90 man hours of radiation exposure, ensured that FME was achieved, eliminated the issue of working at height, and achieved substantial reduction in reactor maintenance and deployment time. This project is an example of ‘Proactive Obsolescence’ and an example of how innovative thinking and partnering resulted in the elimination of several problems.

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13:30-15:00Plenary 2B: Margin ManagementThis session will focus on safely examining operating and design margins to improve operations.

13:30 Session Chair Opening Remarks

13:55Regulatory Perspective of Margin ManagementGerry Frappier, Director General, Power Reactor Regulation, Canadian Nuclear Safety Commission

This presentation will review how the regulator approaches the oversight of safety margin management. It will look at the regulatory basis for it and how it is viewed in design, safety analysis and Fitness for Service determination. Margin Management is a key approach to ensuring long term operation of reactors pose no unreasonable risks while allowing the use of more sophisticated analytical approaches, operational experience and results from research to optimize reactor operations.

Gerry Frappier started his career in Health Physics with Ontario Hydro working at the Pickering and Bruce Nuclear Generating Stations. He subsequently worked on aerospace, military projects and Nuclear Security and non proliferation.

In 2006 Gerry joined the Canadian Nuclear Safety Commission as Director General Security and Safeguards, where he was responsible for nuclear security, non-proliferation, international safeguards and emergency management. He also

spent several years as the Director General Assessment and Analysis responsible to provide the Commission with regulatory leadership and specialist advice in engineering, nuclear physics and safety assessments.

In 2016 Gerry became the Director General Power Reactor Regulation where he is responsible for the regulatory oversight of Nuclear Power Plants including the licensing and compliance oversight activities. Gerry is a physicist and a professional electrical engineer.

Session ChairPamela Tume, Director, Intellectual Property, Nuclear Security, HU and OPEX, SNC-Lavalin Nuclear Inc.

Pamela Tume is an established leader with more than 20 years of nuclear experience in project, engineering, compliance and corporate roles. Through this period she has learned to enable the power of many through the strengths of collaboration, active listening and support of human performance excellence. She has performed various leadership roles for integrated discipline engineering teams for Candu 6 refurbishments and services, and the sale and transition of the Commercial Reactor division to SNC- Lavalin. In her current capacity, she is provides expertise and consultancy services in the areas of Intellectual Property, Nuclear Security, Human Performance and Operations Experience. She is the technical adviser to patent office and legal counsel to manage the patent portfolio inclusive of the Atomic Energy of Canada Power reactor sector. As the Company Security Officer for Candu Energy, she is a key enabler of the Government of Canada security policy for New Power sector technologies. Pamela holds a Honors and Masers degrees in Physics and a Doctorate in Nuclear Engineering and was the beneficiary of National Defense and NSERC funding and a post-doctoral research fellowship.

13:35Utility Approach to Margin Management (Risk vs Benefit)David Tyndall, Senior Manager, Plant Design & Design Authority, Darlington Nuclear, Ontario Power Generation

This presentation will provide a utility’s perspective on Margin Management, from theory to practical implementation, discussing some of the programmatic considerations, behaviors required, and how the program is evolving and where it is heading in the future.

David Tyndall is the Senior Manager, Plant Design and Design Authority at Ontario Power Generation’s Darlington Nuclear Generating Station. David joined the Darlington team as the Senior Manager of Plant Design in September 2016, after spending the previous 10 years in positions of increasing authority within the Components and System Engineering organizations at the Pickering Nuclear Generating Station. He holds a bachelor’s degree in Electrical Engineering and

Management from McMaster University in Hamilton, Ontario, and is a licensed Professional Engineer in Ontario.

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14:15Fuel Channel Life ExtensionGary Newman, Chief Engineer, Senior Vice President of Engineering, Bruce Power

The Safe, Reliable and Cost Effective operation of the Ontario CANDU Reactors is a key element of the energy strategy for Ontario. The COG Fuel Channel Life Management Project is a co-funded initiative being undertaken by OPG, BP and CNL and is considered a key input to each utility’s Asset Management Program as well as in support of license renewal. This multi-year R&D project was undertaken to advance the industry understanding of key fuel channel assembly fitness-for-service material properties, modeling and methodologies for accelerated life-cycle conditions. In the limit the ultimate objective was to ensure that fuel channel assembly fitness-for-service could be demonstrated to at least 300,000 EFPH. As a key input to the asset management programs, this is also a key enabler for the Ontario Provincial Government Long-Term-Energy Plan (LTEP) where units at both OPG and BP must operate through to the 2030 time frame over which refurbishment of both the Darlington and Bruce Power reactors will be completed. In addition to successfully achieving these refurbishment targets, the understanding developed through this work will inform future operation of all CANDU reactors both domestically and internationally over the next 50 years as this critical base load generation capability continues to provide a safe, reliable low cost source of energy to the consumers. This initiative is expected to continue over the next three years and ultimately will be rolled back into the base COG R&D program given that development, refinement and sustaining efforts are expected to continue as part of the ongoing program. This program continues to contribute to the already considerable Industry R&D Knowledge basis while also transferring this understanding to the next generation of key Scientist and Engineering Staff as well as contributing to maintaining key laboratory capability within the Province of Ontario.

Mr. Gary Newman, M.A.Sc., P. Eng., is the Chief Engineer and Senior Vice President of Engineering at Bruce Power L.P. Bruce Power’s vision is to become Canada’s World Class Nuclear Operator, committed to providing safe, reliable, affordable, and environmentally sound electricity.

Mr. Newman was appointed to his current position in June 2008. He is the Design Authority for Bruce Power and carries responsibility for all Engineering activity at the Bruce Power L.P. site and is the current

Bruce Power representative on the CANDU Owners Group, Nuclear Safety Solutions and University Network of Excellence in Nuclear Engineering Board of Directors.

Mr. Newman joined Bruce Power in 2004 as the Department Manager of Equipment Life Cycle Engineering and prior to that was employed by AMEC - Nuclear Safety Solutions Ltd., Ontario Power Generation and originally joined Ontario Hydro in 1990.

14:35 Questions and Discussion

14:55 Session Wrap-up


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Safe Operation of NPPs – Canadian Regulatory Expectations for Condition Assessment in the Framework of PSRAli Omar, Sankar Laxman, Blair Carroll and Alexandre Viktorov, Canadian Nuclear Safety Commission

Remote Controlled Crud Removal by use of In-Pipe ManipulatorsHolger Damies, Florian Hudelmaier and Erich Seeberger, AREVA GmbH

A Statistical Approach for Evaluating Material Property Degradation in Fibreglass Reinforced Plastic Composite PipingOuajih Hamouda, Jason Kwan, Sang-hwan Kim, Ernie Mileta and Mike Stojakovic, Ontario Power Generation

Large Scale Feeder Removal on Darlington Unit 2 RefurbishmentKen Brown and Cameron Webb, Ontario Power Generation

Proposed Mitigation of the Reactor Inlet Header Temperature Increase in Bruce Power UnitsPreston Tang and Akash Bhatia, Bruce Power; David Zobin, Khurram Khan, Kurt Gilbride and Jefferson Tse, Amec Foster Wheeler

Micromechanics of Plasticity of Zr-2.5% Nb AlloyMd. Imran Khan and Robert J. Klassen, University of Western Ontario

Evaluation Methodology for the Pressure Tube Diameter Expansion Based on the Measured DataJong Yeob Jung, Korea Atomic Energy Research Institute

Strategies to Prevent the Increase of High Cycle Fatigue (Vibration) Piping FailuresAdam Roukema, Structural Integrity Associates, Inc.

Characterizing the Mechanical Properties of I Rod Removed from National Research Universal ReactorMichael Bach and Sterling St. Lawrence, Canadian Nuclear Laboratories

Life Cycle Management Evaluations of Safety Related Service Water Systems at Nuclear Power PlantsGeorge Licina, Adam Roukema and Peter Wood, Structural Integrity Associates, Inc.

Decontamination SolutionsHolger Damies, Sven Nothvogel and Sven Wegener, AREVA GmbH

Small-Scale Mechanical Testing of Nuclear Structural MaterialsColin Judge, Vineet Bhakhri, Chris Dixon and Clinton Mayhew, Canadian Nuclear Laboratories; Cameron Howard and Peter Hosemann, University of California Berkeley

Embalse Refurbishment: Update of ProgressRicardo Sainz, Gustavo Diaz and Patricia Salvetti, Nucleoelèctrica Argentina SA; Tim Freeman, SNC-Lavalin Nuclear Inc.

Nuclear Waste Parts Improvement Initiative Project (aka MRI#1 - Maintenance Readiness Initiative #1)Mioara Ibadula, Ontario Power Generation

Failure Analysis Examination of a Titanium Condenser TubePooya Delshad Khatibi and Erhan Ulvan, Acuren Group Inc.; Morteza Toloui and Alexander Di ilio, Ontario Power Generation

Condition Assessment, Life Assessmentand Refurbishment

Strategies to Mitigate ComponentDegradation

Material Properties and Degradation

15:30

16:10

15:50

16:30

16:50


Networking Break

Student/Mentor Poster Session

Networking Reception

CANDU® Around the World Networking DinnerGuest Speaker: The Hon. Glenn Thibeault, Minister of Energy

15:30-16:50

15:00-15:30

17:00

17:30

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T u e s d a y , O c t o b e r 3 , 2 0 1 7

15:30-16:50CONCURRENT TECHNICAL SESSIONSCondition Assessment, Life Assessment and RefurbishmentSession ChairXinjian Duan, SNC-Lavalin Nuclear

15:30Safe Operation of NPPs – Canadian Regulatory Expectations for Condition Assessment in the Framework of PSRAli Omar, Sankar Laxman, Blair Carroll and Alexandre Viktorov, Canadian Nuclear Safety Commission

It is the current practice of the Canadian Nuclear Safety Commission (CNSC) to expect the licensed operators to conduct a Periodic Safety Review (PSR) in support of the continued safe operation of their nuclear power facilities. One of the essential components of the PSR is the determination of the actual condition of structures, systems and components (SSCs) important to safety, including the confirmation that the existing aging management arrangement will assure fitness for service (FFS) of these SSCs for the continued operation, and the presence of records demonstrating evidence that activities and actions are undertaken to maintain SSCs important to safety fit for service.

This paper describes the regulatory expectations for the use of PSR in support of continued safe operation of a nuclear generating station. The paper specifically delineates the regulatory expectations regarding the necessary information required to maintain and report on the actual condition of SSCs important to safety, the arrangements (for example, programs, processes, procedures, instructions, tools) that the licensee must establish to maintain the FFS of these SSCs, and the database that supports the continual monitoring of the condition of these SSCs important to safety. Some lessons learned from the recent Canadian experience are presented and discussed.

15:50Evaluation Methodology for the Pressure Tube Diameter Expansion Based on the Measured DataJong Yeob Jung, Korea Atomic Energy Research Institute

The pressure tube of a CANDU® reactor is the most important part of the fuel channel because it passes through the calandria and contains the fuel bundles. However, measurements of the pressure-tube inside diameters at CANDU plants have shown that the diameters have been increasing over time. This phenomenon is due to the effects of irradiation by neutron flux, stress, and reactor operating temperatures over the plant life. This has been regarded as one of the principal aging mechanisms governing the heat transfer and hydraulic degradation of the heat transport system. The diametral expansion of the pressure tube results in the reduction of fuel cooling due to the increased bypass flow, increases the possibility of fuel dryout, and thus limits the operating power of the reactor. Therefore, an accurate prediction of the pressure tube diameter is very important in assessing the operational margin to dryout.

This study was focused on the modelling of expansion of the pressure tube diameter based on the operating conditions of the neutron flux and the temperature. It is well known that high temperature and neutron irradiation are the main parameters affecting pressure tube deformation. Accordingly, the pressure tube diameter expansion was modelled using the neutron flux and temperature distribution of each channel and each bundle as well as the measured diametral data of pressure tubes. From the measured data, a creep strain rate was derived for each measured channel and normalized flux and temperature data for each corresponding channel was specifically derived. Although the basic concept of the current modelling approach is simple, prediction results of the pressure tube diameter show very good agreement with the measured data.

16:10Large Scale Feeder Removal on Darlington Unit 2 RefurbishmentKen Brown and Cameron Webb, Ontario Power Generation

Darlington Refurbishment has just completed a major series to remove 960 feeders from Unit 2 on its refurbishment.

This work was performed by the Joint Venture (SNC Lavalin, AECON) with OPG support. The work was completed on schedule, and with zero personal contamination events. Overall dose collected was within budget. The feeders were packaged into waste containers and shipped off-site without incident. This result was made possible through a massive advance planning effort and field co-ordination effort.

The presentation includes video footage of the techniques used to protect workers from potential contamination uptakes. There are specific overpack containers designed and used specifically for this series. Worker hot hand-offs were successfully used to keep continuous vault work 24/7.

16:30Life Cycle Management Evaluations of Safety Related Service Water Systems at Nuclear Power PlantsGeorge Licina, Adam Roukema and Peter Wood, Structural Integrity Associates, Inc.

All US nuclear power plants are currently inspecting buried safety related piping as part of their required NEI-09-14 response. Prior service water system experience and those buried piping inspections have revealed a small number of pinhole leaks, both in above ground and in some excavated buried service water piping. All those leaks have been classified as weepers; and all of those leaks appear to be ID-initiated, suggesting that a large majority of issues with the buried safety related piping is and will continue to be ID-initiated.Structural Integrity Associates, Inc. (SI) has developed a Life Cycle Management (LCM) assessment approach that provides a method for quantitatively defining leaks, thinning, probability of at least one leak, etc. as a function of time to permit plants to plan for timely inspections, repairs, and/or refurbishments, considering ID degradation only. The case study presented in this paper identifies and prioritizes segments based on their degradation, provides an approach that can be used in conjunction with a separate

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alternatives analysis performed that defined methods for mitigation of the safety related service water systems, including buried portions of the piping. One goal was to produce results that would be amenable to financial analysis, based upon Net Present Value (NPV) computationsforalloptions,includingtheoptionto“DoNothing.”LCM evaluations have been used to prioritize and schedule inspections and replacement activities, for example, based upon segments that were identified as the greatest contributors to leaks or contributors to tmin violations after 40 years, 60 years, and 80 years of operation. The LCM also identified areas for improvement where further data would reduce the model’s uncertainty. The results from one case history show that the cumulative number of leaks is predicted to increase from approximately 20 now (in reasonable agreement with the number of known leaks in the in-scope systems), to approximately 30 by 2023, then to increase by 20 per decade, nearly 40 per decade, and 60 per decade thereafter for a total of more than 150 leaks by 2053, assuming no change to operation, chemistry, or treatments. Similarly, the number of tmin violations will increase dramatically, with the total tmin exceeding1400 by 2053.This paper provides an overview of the approach, discusses the driving factors considered by SI’s LCM model, describes the piping scope, outlines the input data collection requirements, highlights governing assumptions for the case history, summarizes LCM findings, illustrates potential value and impacts of results, and presents lessons learned for others’ use.

16:50Embalse Refurbishment: Update of ProgressRicardo Sainz, Gustavo Diaz and Patricia Salvetti, Nucleoelèctrica Argentina SA; Tim Freeman, SNC-Lavalin Nuclear Inc.

Following several years of detailed planning and preparation, the Embalse NPP (Córdoba Province, Argentina), was shut down on December 31, 2015 to embark on the execution phase of the Life Extension Project. Candu Energy engineering, tools and procedures previously used and successfully proven are being used to execute the retubing work. With this being the third CANDU6 retubing campaign, the processes and tooling have been further refined to minimize the critical path duration. NASA is leading the execution of the work with on-site support from Candu Energy technical advisors. The unit has been successfully defueled, drained and dried and did not experience tritium issues during the subsequent removal activities. The reactor component removal activities and inspection activities were completed on schedule. During the removal series, all irradiated reactor components removed were stored in on-site waste storage facilities, and permanent components were found to be in good condition for extended operation. The installation phase is underway starting with the calandria tube installation and there have been no major issues thus far.

This paper will provide an overview of the Embalse retubing activities, with particular emphasis on improvements developed and in some cases already executed, demonstrating how advancements in retubing techniques continue to be realized.

The paper will also include a reference to some others important refurbishment activities like a DCC computer replacement, turbine refurb and replacement including uprating, diesel generators replacement, and moderator heat exchanger replacement, safety systems modifications, among others.

Strategies to Mitigate Component DegradationSession ChairRalf Gold, Candu Energy Inc.

15:30Remote Controlled Crud Removal by use of In-Pipe ManipulatorsHolger Damies, Florian Hudelmaier and Erich Seeberger, AREVA GmbH

The Emergency Coolant Injection system is a critical special safety system that is poised to activate in the event that a Loss of Coolant Accident (LOCA) occurs within one of the units. Since there is not a continuous flow throughout the system, during the years of operation radioactive crud can built up in low points and valve internals in the system causing high dose rate areas. Due to the high field intensity (radiation dose rate at the crud up to 70 REM/hour) a cleaning can’t be done manually. Therefore remote controlled tooling must be used.

The AREVA solution is tailor made with specific equipment arrangement. The crud removal inside the ECI piping is performed completely remote controlled by application of proven AREVA in-pipe manipulator technology. An adjustable vacuum generator ensures a continuous high efficient crud removal via swiveling suction nozzle. The crud is transferred from the suction line straight into the water seal of the special water filter element. A swirl generator and a special strainer arrangement are ensuring a separation of the solid curd inside the water seal. Due to the gravitation effect the solid curd moves to the center of the cone bottom where the drain line is located. After remote controlled opening of the drain line the crud together with the water is discharged automatically to a shielded waste collection barrel. A special solid filter in the shielded barrel allows a separation of the water from the solid parts of the crud. The separated water can be re-used in the special water filter element.

15:50Strategies for the Increasing of High Cycle Fatigue (Vibration) Piping FailuresAndrew Crompton, Structural Integrity Associates, Inc.

As the age of systems, structures, and components, (SCCs) in the nuclear industry increase, so does the level of effort and cost to manage their ageing. Many of the CANDU® reactors in Canada are undergoing significant refurbishments and upgrades to turbines, pumps, and condensers, increasing the operating life and adding efficiency in an ever-challenging power generation market. Within the large engineering work packages for modifying these components, how often are vibration evaluations of affected small bore piping included? These small bore piping evaluations are being overlooked or improperly analyzed and the consequences, including loss of generation and increasing O&M costs, are trending into the red.

This paper will provide a framework for evaluation methods based upon the risk of failure and guidance regarding empirical testing methods to evaluate vibration susceptibility before, during, and after a modification. A discussion will also be provided on coupling empirical testing with analytical techniques to further quantify the potential for high cycle fatigue damage.

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16:10Proposed Mitigation of the Reactor Inlet Header Temperature Increase in Bruce Power UnitsPreston Tang and Akash Bhatia, Bruce Power; David Zobin, Khurram Khan, Kurt Gilbride and Jefferson Tse, Amec Foster Wheeler

The Reactor Inlet Header temperature has been increasing more rapidly in most CANDU® units, compared to the original aging predictions. Similar temperature increases have been observed in other reactor designs, e.g. PWR. The Reactor Inlet Header temperature is monitored and high temperature alarms are required to prevent operation outside the safe operating envelope as supported by the safety analysis. Elevated Reactor Inlet Header temperature above a certain value represents a level II impairment of both SDS1 and SDS2 and decreases margin to fuel sheath dryout for all accident cases. To prevent Reactor Inlet Header temperature alarms, temperature increase mitigated through changes in unit operating conditions which have caused power derates and a corresponding loss of production. In Bruce Power units, the Reactor Inlet Header Inner Zone temperature increase has been estimated at approximately 0.3°C/year. The main contributor to the increase is the fouling in the preheaters and steam generator due to magnetite deposits on tube inner surface, which reduces the heat transfer effectiveness and increases the Heat Transport temperature required. Corrective actions such as ID cleaning of the boiler and preheater tubes can be performed to recover lost heat transfer efficiency. However, boiler tube cleaning is expensive and has produced only mixed results. In one of Bruce Power Units Reactor Inlet Header Inner Zone temperature returned to the pre-cleaning value within as little as 3 years of operation. Multiple design modification alternatives were assessed for Bruce Power units based on their suitability, risk, economics and effectiveness in reducing the Reactor Inlet Header temperature with minimum system level impacts. Performance Evaluation of Plant System Efficiencies (PEPSE) software based model was used to evaluate the effect of design alternatives on the thermal cycle efficiency and possible increase in production. External bypass of high pressure feedwater heaters (on tube side) was selected as the best design alternative and detailed design work is in progress for its implementation.

16:30Decontamination SolutionsHolger Damies, Sven Nothvogel and Sven Wegener, AREVA GmbH

Efficient decontamination of NPP components is essential for reduction of dose rates below defined limits and removal of dust and corrosion particles (contamination) as well as surface coating.

Different equipment / tools are applied to prepare recurrent testing of components (like inside tank inspections), regular maintenance works (e.g. on pumps and valves) but also in terms of plant retrofit ormodernizationprogramstoallow“freerelease”ofthedismantledparts for further handling and disposal or recycling.

AREVA’s product portfolio provides 2 clean and time saving stationary decontamination solutions:

Decontamination Chambers:

• Differentsizes,fromgloveboxsizeforsmallerpartstolargeaccessible chambers equipped with a changing cabin

• Fordecontaminationofcomponentsorparts≤3t or diameter ≤1,5m or length ≤3m (special chamber sizes are possible)

• Possibilityofsemi-automaticdecontaminationincaseofhighdose rate

• Decontaminationonlywithdemineralisedwaterunderhighpressure > No secondary waste, nearly no surface removal

• PressurelevelofHighPressurePumpsisflexible(e.g.160to400barg) and will be chosen based on the decontamination task

• Possibilitytoworkwithadditionalchemicals

Cleaning Bathes:

• Suitableforsmallandsensitiveparts

• Equippedwithultrasonictransducers,ifneeded

Frequency and power level of ultrasonic transducers is flexible and will be chosen based on the decontamination task

• Possibilityofsemi-automaticdecontaminationincaseofhighdose rate

• Decontaminationonlywithdemineralisedwater(Nosecondarywaste, nearly no surface removal)

• Possibilityforadditionofchemicalsandheating

• SizeofCleaningBatheswillbeadaptedtothesizeandweightofthe components to be decontaminated

With our experience from implementation of different decontamination workshops worldwide we provide valuable and tailored customer solutions.

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16:50Nuclear Waste Parts Improvement Initiative Project (aka MRI#1 - Maintenance Readiness Initiative #1)Mioara Ibadula, Ontario Power Generation

The purpose of the MRI#1 project is to eliminate configuration management issues and to address parts obsolesces for approximately 350 systems installed at the Nuclear Waste Facilities within OPG. This will improve systems reliability and their capability to operate as per design intent.

Engineering services were contracted with the following mandate: - Maintain a qualified engineering project team that is self-sufficient in dispositioning component procurement and related engineering issues, dealing with the manufacturers to identify suitable component replacements.

Project Implementation Strategy

Phase 1: Retrieve design basis documentation of the installed systems to support component procurement and address configuration management issues;

Phase 2: Reconstitute design basis documentation (e.g. develop engineering changes, engineering briefs) to support parts procurement.

Project Completion Date - June 2018

Material Properties and Degradation SessionSession ChairMike Wright, Canadian Nuclear Laboratries

15:30A Statistical Approach for Evaluating Material Property Degradation in Fibreglass Reinforced Plastic Composite PipingOuajih Hamouda, Jason Kwan, Sang-hwan Kim, Ernie Mileta and Mike Stojakovic, Ontario Power Generation

The Pickering Nuclear Generating Station contains Fibreglass Reinforced Plastic composite piping and components in service since 1971. The Fibreglass Reinforced Plastic components are periodically inspected and analysed to ensure that any degradation experienced over time will not compromise structural integrity. A number of samples have been removed from service and subjected to laboratory tests to identify trends in the rate of material property degradation and possibly provide estimates of future performance. In this paper, we propose a statistical approach to evaluate possible trends in material property degradation over time, with a 36-inch Fibreglass Reinforced Plastic pipe used as a demonstrative example. The calculated elastic modulus is highly sensitive to variability in the tested material. The calculated flexural rigidity is less sensitive to variations in sample properties such as thickness and is therefore a better indicator of degradation trends over time. The results highlight the importance of improving the quality of the degradation trend data by carrying out repeat non-destructive tests on identical samples under tightly controlled test conditions and procedures.

15:50Characterizing the Mechanical Properties of I Rod Removed From National Research Universal ReactorMichael Bach and Sterling St. Lawrence, Canadian Nuclear Laboratories

The National Research Universal (NRU) reactor is a research reactor which has many roles, one of which is the generation of isotopes used for both medical and non-medical purposes. The vessel wall of the reactor used to contain the heavy water is made of Al 5052 alloy. After corrosion issues shutdown the reactor in 2009, a program was developed to examine the mechanical properties of the vessel wall and its fitness-for-service. It so happened that the iodine-125 (I-rod) material used to produce medical isotopes in the NRU that was removed in 1991 was also made out of the same Al5052 as the vessel wall. A recent research and development project was created to study the mechanical properties of the I-rod with varying thermal fluence levels which, could be used to assess the conditions of the NRU vessel. While in the NRU reactor, various locations on the I-rod was exposed to a range of thermal fluence from 0 to a maximum of 11.9 x 1022 n/cm2. The end of life thermal neutron fluence of the NRU vessel is estimated to be 2.2 x 1022 n/cm2 at 35 years of service. The goal of this project was to determine the fracture toughness along the various locations of the I-rod to determine if the mechanical properties changes due to different levels of irradiation exposure. From the experiment, the yield strength and UTS increased with thermal fluence value due to the radiation-induced Mg-Si precipitate strengthening and reduction in ductility. It was determined that the fracture toughness of the material decreased with increase fluence rates. In the irradiated materials, unstable crack jumps were detected however, SEM images of the fracture face showed signs of ductile fracture and not brittle fracture.

16:10Micromechanics of Plasticity of Zr-2.5% Nb AlloyMd. Imran Khan and Robert J. Klassen, University of Western Ontario

In this study micromechanical testing was carried out to obtain information regarding stress- strain response of Zr-2.5%Nb pressure tube material used in CANDU® nuclear reactors. Of particular interest is how the strength and ductility of the material changes as the size of the deforming volume decreases to dimensions in the micrometer range. This project intends to obtain such data for pressure tube material in the as-received and the ion-irradiation hardened conditions. Micropillars containing single α-phase grains and multiple grains were tested such that the effect of pillar diameter and crystal orientation on the flow stress and strain hardening coefficient could be assessed. The micropillars displayed a clear increase in flow stress with decreasing pillar diameter which reflects the length-scale dependence of the mechanical properties. Micro-compression data obtained from ion-irradiation hardened micropillars were compared with unirradiated micropillars. Irrespective of the irradiation condition, the flow stress of the single-crystal micropillars oriented along the axial direction of the pressure tube is lower than that of similar micropillars oriented along the transverse direction of the pressure tube. Micropillars were irradiated at two different temperatures (20°C and 300°C) to observe the effect of irradiation temperature

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on compressive strength of material. The obtained data clearly indicate that micropillars irradiated at 20°C display much higher compressive strength at 10% strain in comparison to the pillars irradiated at 300°C. A noticeable difference between the stress-strain curves of the pillars irradiated at different temperatures is that, for the low temperature irradiated pillars, the transition from elastic to plastic deformation is usually quite smooth whereas for the pillars irradiated at higher temperature strain jumps were observed.

16:30Small-Scale Mechanical Testing of Nuclear Structural MaterialsColin Judge, Vineet Bhakhri, Chris Dixon and Clinton Mayhew, Canadian Nuclear Laboratories; Cameron Howard and Peter Hosemann, University of California Berkeley

Material property changes due to harsh reactor environment conditions, such as neutron irradiation, high temperature, and heat transfer media, may limit the performance and the operating envelopes of all reactor types. Quantitative information on the material properties changes is needed to support on-going life extension/ life management efforts of the existing global fleet, as well as for design and development of future advanced reactor concepts. Testing of larger radioactive test specimens is challenging and expensive as it requires their handling and testing in shielded facilities. Testing smaller sized specimens has an advantage in terms of their reduced activity; hence safer handling and cost effectiveness. In this presentation, examples of various small-scale, ex-situ and in-situ SEM, mechanical testing techniques, being developed at CNL, and in collaboration with UC Berkeley will be discussed. The applications of nano/micro indentation, micro-compression and micro-tensile testing to acquire local and bulk properties measurement in structural nuclear materials are being explored, with an aim to extend their use to characterize radioactive specimens extracted from reactor components. In particular, small-scale mechanical testing of isolated interfaces in unirradiated and irradiated materials are used to investigate helium bubble embrittlement in Ni-based super alloys, and hydride embrittlement in zirconium alloys.

16:50Failure Analysis Examination of a Titanium Condenser TubePooya Delshad Khatibi and Erhan Ulvan, Acuren Group Inc.; Morteza Toloui and Alexander Di ilio, Ontario Power Generation

A distinctive form of degradation was observed in condenser tubes made from a commercially pure titanium alloy. Helium leak tests, Eddy Current inspections, and Borescope inspections conducted in the field revealed through wall cracking around the tube circumference in the affected tubes.

No indications of embrittlement due to titanium hydrates or defects were found in the microstructure of the failed section and Flattening Test results confirmed the high ductility of the failed tube. Metallurgical failure analysis revealed fatigue cracking at the location of the seam weld that led to tube failure. This was caused by vibration/movement of the tube during service. SEM examination revealed trans-granular cracking and the presence of striations on the opened crack surface of the titanium tube section, which is consistent with fatigue cracking.

17:00-18:30Student/Mentor Poster Session

17:30-18:30Networking Reception

18:30-21:00CANDU® Around the World Networking DinnerGuest SpeakerThe Hon. Glenn Thibeault, Minister of Energy

Glenn Thibeault was first elected to the Ontario legislature in 2015 as the MPP for Sudbury.

He was appointed Ontario’s Minister of Energy in June 2016. As Minister of Energy, Glenn is focused on ensuring all Ontarians have access to an affordable supply of clean, reliable energy. Beginning in Fall 2016, he is leading consultations across the province on Ontario’s renewed Long Term Energy Plan.

He previously served as Parliamentary Assistant to the Minister of the Environment and Climate Change, focusing on bringing forward the Climate Change Action Plan. Prior to entering provincial politics, Thibeault was the Member of Parliament for Sudbury and the Executive Director of the Sudbury United Way.

As a director with the United Way, he led many successful campaigns in support of community development. He has also been a volunteer with many not for profits, as well as with minor hockey and football leagues as a coach and official.

Thibeault was born and raised in Sudbury, and is a graduate of Cambrian College. He lives in Sudbury with his wife, Yolanda, and their two daughters.

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07:30 Early AM Refreshments

08:30-10:00

Plenary 3A: Proactively Managing ObsolescenceThis session is a specific aspect of asset management. It will focus on strategies and methodologies to deal with the provision of obsolete spare parts.


08:35Nuclear Utility Obsolescence Group (NUOG) ActivitiesSteve Ostrowski, Department Manager, Engineering Support Division, Bruce Power

This presentation provides an overview of the Nuclear Utility Obsolescence Group (NUOG). NUOG was formed in 2000 to create a platform for nuclear utilities to openly collaborate on obsolescence challenges, solutions and industry best practices. NUOG provides participants with tools that assist in identifying and solving obsolescence issues to improve parts readiness in order to reduce station risk and vulnerabilities associated with Equipment Reliability. In addition, NUOG’s relationship with other industry groups such as WANO IAEA, and COG has created synergies for wider collaboration and integration of solutions associated with Obsolescence Management.

Steve Ostrowski is an Engineering Support Division Department Manager with Bruce Power. Steve is responsible for Corporate and Station Management of Component Design and Design Programs, which includes ownership of Critical Spares and Obsolescence Management and is also the Corporate Function Area Manager responsible for Design Management, Engineering Change Control and Configuration Management. His experience

includes 26 years in Nuclear Power --- which includes 8 years at LaSalle Station, 5 years as an Engineering Consultant and 18 years at the Bruce Site. He graduated from Bradley University with a degree in Electrical Engineering. Steve has resided in Canada since 1999 and is a citizen of both the United States and Canada.

Session ChairJohn D’Angelo, Vice President, Engineering. and General Manager, Nuclear Parts & Engineered Services, Kinectrics Inc.

John D’Angelo M.S. Sc., P. Eng., is Vice President, Engineering, and General Manager of Kinectrics’ Nuclear Parts & Engineered Services business, the latter a position he has held since 2008. He assumed the role of Vice President, Engineering in 2015. He also manages the Kinectrics US Inc. operations.

Since joining Kinectrics in 1987, John Dhas held a variety of positions progressing from technical apprenticeship to senior management. He is currently responsible for a large portfolio of Kinectrics’ operations, which deal primarily with nuclear plant inspection tooling, maintenance and inspection services, nuclear equipment parts and components, environmental qualification, and civil and environmental engineering solutions.

John D’Angelo is also a registered Professional Engineer of Ontario.

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08:55Report on CANDU Owners Group Procurement Engineering Peer Group and Proactive Obsolescence Management Systems (POMs) ImplementationAndrew Allport, Procurement Engineering Specialist, Fix-It-Now, Point Lepreau NGS, New Brunswick Power

Obsolescence Management is becoming a leading issue while procuring replacement components for the Nuclear Industry. Utilities must evaluate the cumulative effects of both physical ageing and obsolescence to ensure plant operation remains safe and reliable; while continuing to be a feasible economic option for Power Generation. There are various tools and strategies to combat Obsolescence and this discussion will focus on the following key subjects:

· What is Obsolescence? What is the scale of Obsolescence impact?· How to tackle Obsolescence to mitigate its impact? · Identification, Prioritization, and Resolution of Obsolete Components. · What tools are available? · What are we doing about it? Examples of Obsolescence

Management at Point Lepreau.· Technical and Quality challenges with obsolete components at Point

Lepreau. How can your utility be different or similar from others?· How to ensure the design basis is maintained throughout the

Procurement of new or replacement components.· Identify the need for long term partners and strong vendor

relationships to combat obsolescence.· How do Industry OPEX/Collaboration and Proactive Obsolescence

programs help?

Andrew Allport (P. Eng.) is a Procurement Engineering Specialist currently forming part of NB Power Engineering Fix-It-Now (E-FIN) team at the Point Lepreau Nuclear Generating Station (PLGS). He is responsible for performing Engineering Equivalency Evaluations (and other design products) to support component replacement activities during running plant maintenance and/or FIN related work order priorities, ensuring safe and reliable plant operation.

A Procurement Engineering Specialist’s role is responsible for ensuring the Quality Assurance & Technical requirements are met are throughout the procurement process, including identification of Critical Characteristics for Design to ensure the plant design basis is preserved.

Andrew has a Bachelor of Science in Mechanical Engineering from University of New Brunswick.

Andrew has been working in the nuclear industry since 2009, including being seconded from Atlantic Nuclear Services (ANS) to Atomic Energy of Canada Limited (AECL) to provide technical support through the Refurbishment project at PLGS. Following the Refurbishment project he commenced work with Black and MacDonald as a Safety Advisor and would oversee the safe and efficient installation of the new Public Address system within the protected area of PLGS; also providing company Safety Audits to other Black and McDonald Industrial and Commercial sites all over New Brunswick ensuring NB Occupational Health and Safety Act compliance. He builds upon this experience working as a Procurement Engineering Specialist at PLGS to date.


09:15Reverse Engineering ChallengesPeter McLean, Senior Project Manager, Nuclear Products and Engineered Services, Kinectrics Inc.

The methodology of Reverse Engineering (RE) obsolete components is used to obtain a like for like replacement component when the existing component is no longer available for the original equipment manufacturer, and the cost / effort of a modification is not desired.

The main objectives of the RE process is to provide a replacement component that can be seamless installed into the parent system without the need to modify the system, revise the operating and maintenance procedures, or retrain the operators. The replacement component should be compatible with all other components in the system, fit into the existing panel cut-out, be supplied with all required mounting brackets / retrofit kits, utilize all existing electrical / process connections and provide a similar appearance to the legacy unit from a human factors perspective.

Based on our experience with Reverse Engineering projects the majority of projects fail due to inadequate technical specifications and not understanding the design requirement delta.

From our understanding and experience of the common pit-falls of the reverse engineering process, our approach is based on designing and qualifying the replace component to a set of critical characteristics for design derived from the component’s safety function, FMEA (Failure Mode Effects Analysis), legacy OEM product literature, and the customer’s specifications. The critical characterises are then review against the legacy technology employed in the obsolete component, the design requirements delta, available OPEX and the latest industry technology to derive a solution that will yield the highest reliability and value.

Peter McLean is the Service Line Leader for Reverse Engineering with Kinectrics, working in the Nuclear Parts and Qualification department. His primary focus is reverse engineering and manufacturing of obsolete components for the Canadian and US nuclear markets.

Peter has over 15 years’ experience in managing reverse engineering projects for the nuclear industry. His resume includes the design and qualification of various safety related instruments installed at many nuclear power plants.

Since 2012, he has been focused on developing Kinectrics Reverse Engineering program by building a dedicated reverse engineering team supported by the technical and capability depth of Kinectrics.

09:35Questions and Discussion



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10:30-12:00

Plenary 3B: Executing MaintenanceThis session will focus on initiatives to safely get work done at nuclear power plants.


10:35Crane Rehabilitation and ModernizationFred Wolsey, System Engineer, Cranes and Hoists, Bruce Power

As the CANDU® plants that were built in the 1970s and 1980s age and enter their Life Extension phase, their associated infrastructure must be considered as candidates for life extension as well. Typically the large overhead cranes in any power plant were used to build the equipment they now service. As such most turbine hall cranes have, for example had a longer service life than the turbine-generators themselves.

This paper and presentation will explore the problems encountered during Bruce 1&2 Restart with not refurbishing major cranes, including serious delays of critical path work. It will further present and evaluate the strategies that Bruce Power continues to employ to refurbish its fleet of overhead cranes that service the Turbines, Reactor, Spent Fuel Bays and Shops.

At Bruce Power, we have employed four distinct approaches to crane refurbishment: Refitting where the worn and obsolete components are replaced with new and different components; Rebuild where old components are replaced with similar new components with minor design changes; Replacement where the entire crane is changed out, oftenwithacapacityincrease,andthe“CreativeSolution”thatisrequired when the first three approaches will not work. It will look at Lessons Learned from these four different approaches and how each would be applicable elsewhere.

Thispaperwillalsodiscussthe“new”technologythatisbeingemployed to improve crane utility, including Variable Frequency Drive for crane motors.

Finally, the paper will also include a brief look ahead at how refurbishment work will fit in with Major Component Replacement (MCR) at Bruce Power.

Education: B.A.Sc. Mechanical Engineering, University of Waterloo, 1984, P.Eng (Ontario) 1989

• JoinedOntarioHydroin1985,Nanticoke (Fossil) GS.

• TransferredtotheBruceNuclearsite(then BNPD) in 1995.

• BecameResponsibleSystemEngineer(RSE) for cranes in 1996.

• ContributortotheoriginalOntarioHydroNuclear Crane Maintenance document (1997). Document Owner until OPG sold the BNPD (2001).

• FoundingmemberoftheEPRIHoisting,RiggingandCranesUsers’Group (HRCUG) in 2003. Current member of the HRCUG Steering Committee.

• ContributingEditoroftheBrucePowerRiggingandLiftingHandbook.

• ContributedtotheEPRISmallHoistGuide,LargeCraneGuide,Mobile Crane Guide and Rigging Handbook.

• MemberoftheCSAB167Committee(Producedthecurrentcranesafety standard B167-16).

• MemberoftheEPRITechnicalAdvisoryGroupthatiscreatingaCrane Program Guide as part of the Nuclear Promise.

Session ChairDaniel Gammage, Senior Engineer, Acting Manager, Amec Foster Wheeler

Daniel Gammage is a Senior Engineer and the acting Manager of Amec Foster Wheeler’s Steam Generator Assessment and Risk Informed Engineering Section. Daniel has worked in the nuclear industry since 2008, starting in the Life Cycle Engineering Group at B&W Canada (BWXT). His experience includes performing fitness-for-service assessments and component condition assessments, providing support to CANDU, PWR, and BWR utilities, and supporting R&D and OEM initiatives.

Daniel graduated from the University of Waterloo Honours Mechanical Engineering program with an option in Management Sciences (2008). Daniel is the current CNS President and has been involved in organizing and presenting at several conferences including Nuclear Plant Chemistry 2010, Steam Generator Conferences, CANDU Maintenance Conferences, INCC 2015, and various EPRI sponsored events.

Daniel currently holds the position of President of the Canadian Nuclear Society, and Chair of the Design & Materials Division for the CNS.

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10:55The Role of R&D in Support of Steam Generator Life Cycle StrategiesBob Tapping, Researcher Emeritus, Canadian Nuclear Laboratories

Since the early 1980s corrosion and fouling of steam generator (SG) components, especially tubing, has resulted in significant operational loss, maintenance and inspection requirements and regulatory attention. Although the tubing degradation was largely confined to PWR SGs tubed with Alloy 600, loss of function as a consequence of fouling and vibration were experienced more widely. CANDU SGs have also experienced many of the same degradation mechanisms as PWRs, and hence follow similar secondary side chemistry, support structure designs and inspection requirements. However because CANDU SGs are smaller than those typically found in PWRs, have smaller tube diameters, and have more primary side deposits, the CANDU community has had to develop some different and unique inspection and maintenance tools compared to those used in PWRs. CANDUs also have SGs tubed with one of three alloys, Alloys 400, 600 and 800, each with unique degradation characteristics and inspection requirements. These considerations impact CANDU SG management and addressing them has required significant technical input and support from R&D. This presentation will sketch the evolution of SG issues that have affected operation, maintenance and regulation, and demonstrate how, for CANDU SGs in particular, R&D has interfaced with designers, operators and regulators, and with external experts and sources, to develop tools and strategies for effective SG operation, including for long term continuation of operation.

Dr. Robert (Bob) Tapping is currently a Researcher Emeritus at the Canadian Nuclear Laboratories in Chalk River. Bob started his career at Chalk River in 1979, following two years at Alcan Research where he studied aluminum alloy degradation mechanisms. At Chalk River Bob has carried out R&D into the degradation of CANDU materials, with a significant focus on steam generator materials. He led the AECL R&D program on steam generators, when it was initiated in 1992. Bob retired in 2014 August, after 10

years as Director of the Components and Systems Division. Bob is a recognized authority on steam generator chemistry and materials, and has contributed to condition assessments of the steam generators at Point Lepreau, Gentilly-2, Wolsong-1, Bruce 1 and 2 and China’s Daya Bay, as well as being involved with assessments of a number of CANDU steam generator issues. Bob was also a contributor to the USNRC’s Proactive Materials Assessments, as well as a resource on the USNRC’s Tube Integrity Program.

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11:15Leveraging Technology to Improve Plant Maintenance, Training and Improve EfficiencyEd Lei, Fleet Maintenance Programs Manager, Ontario Power Generation

A presentation of some technology initiatives at OPG to improve maintenance activities and training.

1) Electronic Work Package (eWP): Up until a few months ago, all maintenance work was done by paper binders, which consists of procedures, drawings, work instructions and forms. These binders are being assembled the morning of execution and it takes times. We are now using tablets in Darlington in place of these paper binders. It saves assembly time and re-keying time after the job is done in the field. With WiFi going into the station, other benefits are limitless.

2) Electronic FME Logs (Foreign Material Exclusion): Eliminate the current paper logs. In a typical Turbine outage, the paper log is about 3 inches thick double sided. It is very difficult to read hand writings as well as reconcile everything that goes into the FME level 1 area and everything that comes out. We are working on a simple (user friendly) electronic solutions (and low cost) to make this paperless.

3) Scaffolding App: We have a licensing requirement to inspect our scaffolds monthly once it is built. And currently we are using Excel tracking ‘sheets’. This App is to wirelessly capture the inspection information to a live database. The side benefit is we will also have the inventory information.

4) Virtual Reality/Augmented Reality on Foreign Material Exclusion Dynamic Learning Activities (VR/AR FME DLA) tool: We are using VR/AR to enable students to do the JIT (Just In Time) training away from any classrooms or Mock up area. It makes training flexible and keeps it low cost (money and space).

The presentation will provide background to why these tools are created and the benefits of using them, and also the vision for adopting these new technologies in OPG Nuclear Maintenance.

Ed Lei, Ontario Power Generation Fleet Maintenance Programs Manager. Currently he is the technology initiatives Lead for OPG Maintenance organization. He has 10 years Mining (Automation Engineer), 10 years Automotive assembly (Maintenance Management) and 7 years Nuclear (Maintenance Management) experience. OPG Nuclear maintenance organization is one of the biggest maintenance organization in Ontario. OPG Nuclear plants have approximately 1500

skilled trades technicians between Pickering Nuclear Station and Darlington Nuclear Station. in the past 27 years, Ed has held varies roles in Engineering and Maintenance management and he is specialized in process improvement and drive efficiency gains within maintenance. Currently he is working on several initiatives, eWP (electronic Work Packages), Scaffolding App, VR/AR (Virtual Reality/Augmented Reality) for maintenance training/DLA’s (Dynamic Learning Activities) as well as Smart Procedures. These are all leading edge technologies that will help OPG Nuclear to reduce wait times, streamline maintenance processes, reduce cost and reduce and eliminate Human Performance Errors.

11:35Questions and Discussion


12:00-13:30Luncheon

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Calculation of Stress Intensity Factors Based on Through-Thickness Stress Data from ANSYS AnalysisJunjie Cao, BWXT Canada Ltd.

Pickering Unit-1 and -4 Fuel Channel ReconfigurationJeremy Thompson and Sid Tavares, Ontario Power Generation

Comparison of Predicted and Measured Data of Deformation of Pre-stressed ContainmentZdenek Bittnar, Petr Hlavacek and Borek Patzak, Czech Technical University in Prague; Jan Stepan, Energoprojekt

Fracture Protection of CANDU ZR-2.5NB Pressure Tubes with High Hydrogen Equivalent ConcentrationPreeti Doddihal, Douglas Scarth and Paula Mosbrucker, Kinectrics Inc.; Jessica Lam and Matthew Craven, Ontario Power Generation

Impact Analysis of CANDU Nuclear Waste Containers for a Hypothetical Drop AccidentLi Pan and Peter Zheng, BWXT Canada Ltd.; David Speer, Boris Nikic and Tom Carter, Bruce Power

Developing Optimum Single Fuel Channel Replacement Procedures with Anticipatory Piping Stress AnalysisOuajih Hamouda, Irfan Haq, Songyan Yang and Mike Stojakovic, Ontario Power Generation

Design and Analysis of Expansion Joint LinersDara O’Kane and Aman Usmani, Amec Foster Wheeler

Proximity Measurements of LISS Nozzles to CANDU Fuel Channels using the Eddy Current Gap ProbePerryn Bennett, Queen’s University / Royal Military College; Ross Underhill, Royal Military College, Jordan Morelli, Queen’s University and Thomas Krause, Royal Military College

A Mechanical Energy Approach to Predict Fretting-Wear Damage in Nuclear ComponentsMichel Pettigrew, Ecole Polytechnique Montreal; Victor Janzen, Canadian Nuclear Laboratories

Improved Fuel Bundle Disassembly Using Electrical Discharge MachiningRichard Meguerian and Jeffrey Hulcoop, Laveer Engineering; Ross Lewis, Bruce Power

Integrity of Structures and Components Fuel Channel Life Management

13:30

14:10

13:50

14:30

14:50


Networking Break

13:30-15:10

15:10-15:40

An Approach to Use the Operating Experience in the Refurbishment and the Design of New PlantsHelmy Ragheb, Safety Probe International

Advances in Plant Performance MonitoringStephen Woods and Raheel Naqvi, Ontario Power Generation

Treatment Optimization through Effectiveness MonitoringGeorge Licina, Robert Scholz and Erica Libra-Sharkey, Structural Integrity Associates, Inc.

Apparent Cause for Leakage in a Dry Storage ContainerCatherine Wang, Ryan Parcels, Jim Sato, Jim Carmichael and Tahir Iqbal, Ontario Power Generation

Overview of the High-Energy Line Break Assessment for CANDU ReactorsGordon Ozawa, Xinjian Duan, Michael Kozluk, Min Wang, Yihai Shi and Hui Wang, Candu Energy Inc.

Ultra-Low Chloride (ULC) Anion Ion Exchange Resin for Optimum Condensate PolishingCharles Kozora and Al Tavares, Graver Technologies

CRL Site Transition: Safe Shutdown and Readiness for Decommissioning of National Research Universal and Mo-99 Production FacilityJacques Vincelette and Angela Weaver, Canadian Nuclear Laboratories

Nuclear Facility High Performance and Mitigation of Risk – Common ObjectivesJacques Plourde, Nuclear Insurance Association of Canada

Electrosleeving ApplicationsLjubo Djordjic, Kinectrics Inc.; Gino Palumbo, Integran

Experience with the 0.05 Micron Absolute Rated Filters in the CVCS System of a PWR PlantKhalid Farooq, Pall Corporation; Wendy Walker, Pall Canada

Review of Zircaloy Oxidation Kinetics and Models in Air and Air-Steam MixtureMohamed Shawkat and Hisham Hasanein, Amec Foster Wheeler

OPEX Plant Performance Component Corrosion and Corrosion Control

15:40

16:20

16:00

16:40


Conference Concludes

15:40-17:00

17:00


13:30-15:10CONCURRENT TECHNICAL SESSIONSIntegrity of Structures and ComponentsSession ChairRevi Kizhatil, BWXT Canada Ltd.

13:30Calculation of Stress Intensity Factors Based on Through-Thickness Stress Data from ANSYS AnalysisJunjie Cao, BWXT Canada Ltd.

In this paper, an approach is developed to determine polynomial stress distributions across a shell based on through-thickness stress data from an ANSYS analysis. The polynomial stress distributions can be used to calculate stress intensity factors based on the requirements in different design codes. In ASME Code Section XI, Appendix A, polynomial stress distributions or linearized stresses over the flaw depth may be used to calculate the stress intensity factors for a flaw. Impacts on stress intensity factors by using polynomial stress distributions, and linearized stresses over the flaw depth or over the thickness are investigated based on the procedure in ASME Code Section XI. The results from using linearized stresses over the flaw depth are close to the results using polynomial stress distributions. Using linearized stresses over the thickness is un-conservative for a concave upward stress distribution with increasing slope across the thickness and conservative for a concave downward stress distribution with decreasing slope across the thickness.

13:50Impact Analysis of CANDU Nuclear Waste Containers for a Hypothetical Drop AccidentLi Pan and Peter Zheng, BWXT Canada Ltd.; David Speer, Boris Nikic and Tom Carter, Bruce Power

To refurbish a CANDU® reactor unit, Retube Waster Containers (RWCs) are required to contain medium level radioactive waste components. Two types of RWCs are designed for two types of waste components. The Abaqus finite element code is used to assess a hypothetical drop accident of the RWCs at the storage building from a height of 4 meters. Detailed finite element models are created to include the container body, lid, shielding panels, bolts and a slab-on-grade model. Nonlinear numerical simulations are performed for various drop orientations. The results are checked against both the functional acceptance criteria and the stress/strain based acceptance criteria.

14:10Comparison of Predicted and Measured Data of Deformation of Pre-stressed ContainmentZdenek Bittnar, Petr Hlavacek and Borek Patzak, Czech Technical University in Prague; Jan Stepan, Energoprojekt)

Concrete containment is the most important security barrier in a nuclear power plant (NPP). Therefore, the long-term behavior of this construction should be carefully analyzed. Several models have been developed to predict the long-term behavior of concrete structures.

Some are part of the standards. However, these are usually not sufficient to assess the long-term behavior of concrete containment of the NPP. The mechanical behavior of the containment at the Temelín nuclear power plant in the Czech Republic was analyzed [1, 2] and its long-term behavior was based on the data until 2003, i.e. after 3 years of operation of the 1st block. The containment of this power plant is very well equipped with sensors and is continuously monitored. In 2008, at the CONCREEP conference, Watanabe [3] published the results of long-term measurements of selected pre-tensioned bridges in Japan which exhibit significantly greater deflections than was declared in the project. The subject of this paper is to compare our 2004 forecast with current measured data after 16 years of operation of the NPP.

14:30Design and Analysis of Expansion Joint LinersDara O’Kane, Aman Usmani, Edwin Chen, Amec Foster Wheeler; Mugurel Oprea Veleriu, Cernavoda NPP

The expansion joints (EJ) are included in the piping systems to provide flexibility to accommodate displacements due to thermal expansion and other causes. Some EJs have internal liner to streamline flows and to also protect the EJ bellows convolutions from degradation. The EJ liners are not a pressure boundary components and therefore not subject to strict code requirements and analyses but are designed using the guidelines in the Expansion Joint Manufacturers Association (EJMA) standard . In some cases if the EJ liners are not properly sized and may be subject to reverse flow condition, the consequences can be very significant in terms of unexpected flow blockage due to failure of EJ liner in a piping system.

This paper describes the guidelines for designing the EJ liners, their failure modes and the analysis methodologies used to assess acceptability of the EJ liner designs.

14:50A Mechanical Energy Approach to Predict Fretting-Wear Damage in Nuclear ComponentsMichel Pettigrew, Ecole Polytechnique Montreal; Metin Yetisir, Nigel Fisher, Bruce Smith, Colette Taylor, Victor Janzen, Canadian Nuclear Laboratories

Fretting-wear damage between a vibrating structure and its supports is discussed in this paper. Typical components of concern are piping systems and pipe-supports, heat exchanger tubes and tube supports, and nuclear fuel bundles and fuel channels. Fretting-wear damage is related to the dynamic interaction between a structure and its supports. This interaction is conveniently formulatedintermsofaparametercalled“work-rate”topredictfretting-wear damage. Work-rate is simply the integral of contact force over sliding distance per unit time. Fretting-wear damage may be investigated from an energy point of view. It is essentially the mechanical energy or power dissipated through contact forces and sliding that causes fretting-wear damage. Development of a simple formulation that relates tube vibration response and fretting-wear damage is presented in this paper. Several practical examples and simple calculations are discussed.

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Fuel Channel Life ManagementSession ChairRuth Burany, Kinectrics Inc.13:30Pickering Unit-1 and -4 Fuel Channel ReconfigurationJeremy Thompson and Sid Tavares, Ontario Power Generation

For CANDU® reactors, pressure tube growth requires that one end of the Fuel Channel (FC) is fixed while the other is free to float on bearings. As the FCs run out of bearing length on the free end, two maintenance solutions exist: Reconfiguration reverses the fixed and free ends, allowing growth in the opposite direction, and Repositioning, which involves shifting FCs back towards the locked end, thus providing additional bearing length at the free end.

Pickering ‘A’ Large Scale Fuel Chanel Replacement (LSFCR) only installed Positioning Assemblies (PAs) on one side of the reactor, as end-of-life projections indicated that bearing length could be managed by Repositioning only. The opposite reactor face was left without PA installation to minimize risks associated with feeder clearances and additional unit outage.

With life extension of Pickering Unit-1 and -4 beyond 2014 however, available bearing travel was limited based on feeder clearances as the channels were shifted. To combat this dilemma, a new PA design was commissioned that allowed installation on each channel’s free end allowing for Reconfiguration.

While advantageous, the modified PA Reconfiguration presented significant challenges: major design modifications to the reactor, timely design and manufacturing of ASME code components, and critical development of tooling, methods and procedures.

A partial installation of these modified PAs in 2012 provided lessons-learned for working with the new PA designs. This OPEX was fully leveraged, and in 2015 Unit-1 Reconfiguration was completed successfully, followed by Unit-4 in 2016. Both Reconfiguration projects were executed with a composite team lead by OPG IMS.Both were completed safely, and within schedule, cost and dose targets.

This technical paper will review the salient reactor modification design considerations, the development of the execution methodology (tooling, procedures and training), and a survey of project results and OPEX applicable to future reactor maintenance projects.

13:50Developing Optimum Single Fuel Channel Replacement Procedures with Anticipatory Piping Stress AnalysisOuajih Hamouda, Irfan Haq, Songyan Yang and Mike Stojakovic, Ontario Power Generation

The replacement of a fuel channel is a maintenance procedure that is mandated as part of the periodic fuel channel inspection requirements. To accomplish a Single Fuel Channel Replacement during a planned outage, positioning assembly hardware must be removed from the target fuel channel as well as adjacent fuel channels to provide adequate working space. In addition, feeder pipes must either be disconnected or displaced a minimum distance from the target fuel channel. Piping and component stress analysis is required to determine the consequences of removing hardware and the tolerable amount of deflection on specified components. The analysis determines the movement limits for

feeders and end fittings to ensure that maintenance activities do not exceed component allowable stresses. By considering all potentially desirable combinations of maintenance configurations beforehand, optimum maintenance strategies can be devised by comparing the results of the stress analysis for specific configurations. This paper demonstrates the gains in efficiency that can be achieved during major reactor maintenance projects such as the Single Fuel Channel Replacement by adopting this collaborative approach.

14:10Fracture Protection of CANDU® ZR-2.5NB Pressure Tubes with High Hydrogen Equivalent ConcentrationPreeti Doddihal, Douglas Scarth and Paula Mosbrucker, Kinectrics Inc.; Jessica Lam and Matthew Craven, Ontario Power Generation

The core of a CANDU (CANada Deuterium Uranium) pressurized heavy water reactor includes horizontal Zr-2.5Nb alloy pressure tubes that contain the fuel. Pressure-temperature limits are used in CANDU reactors for normal operation heat-up and cool-down conditions to maintain margins against fracture. The pressure-temperature limits are determined by postulating a 20 mm long axial through-wall crack in the pressure tube and using a fracture toughness-based calculation procedure. Due to a corrosion reaction with the heavy water coolant, pressure tubes absorb high levels of deuterium in service, resulting in high levels of hydrogen equivalent concentration. Experiments have shown that high hydrogen equivalent concentration reduces the fracture toughness of pressure tube material at low temperatures below the normal operating temperature during reactor heat-up and cool-down. New fracture toughness curves that are applicable to material with high hydrogen equivalent concentration have been developed to address this issue. These curves are being used to develop new pressure-temperature limits for fracture protection of CANDU pressure tubes. The methodology for deriving the pressure-temperature limits for a CANDU Zr-2.5Nb pressure tube using the new fracture toughness curves is described in this presentation. Preliminary results of pressure-temperature limits for a CANDU reactor are also provided.

14:30Proximity Measurements of LISS Nozzles to CANDU® Fuel Channels using the Eddy Current Gap ProbePerryn Bennett, Queen’s University / Royal Military College; Ross Underhill, Royal Military College, Jordan Morelli, Queen’s University and Thomas Krause, Royal Military College

CANDU® (CANada Deuterium Uranium) nuclear reactors employ up to 400 horizontal fuel channels, each consisting of two initially concentric tubes. An outer calandria tube (CT) contains a smaller diameter pressure tube (PT) and the annulus space between the tubes, maintained by 4 spacers, is called the gap. Sag causes the tubes to become non-concentric and physical separation between the tubes ensures hydrides, which can lead to potential delayed hydride cracking of the PT, do not develop. Therefore, accurate measurements are required to ensure that contact between PT and CT is not imminent. The gap is monitored from within the PT using the gap probe, which is an eddy current based inspection probe operated at multiple frequencies. The proximity of remote perpendicular tubes, which run beneath the fuel channels, known as liquid injection shutdown system (LISS) nozzles, is a factor affecting

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gap measurement. The proximity of LISS nozzles confounds gap measurements and contact of the LISS nozzle could lead to fretting and deformation of the CT, due to moderator flow-induced vibrations in the LISS nozzle and CT. Proximity of LISS nozzle to CTs is currently measured optically and costs ~$1 million dollars per inspection campaign. Using gap probe measurements the effect of LISS nozzle proximity to the fuel channel was investigated experimentally and a relationship between eddy current response and LISS- PT proximity was obtained. When PT wall thickness, probe lift-off and PT resistivity variations are not present the observed relationship can be used to predict the LISS-PT proximity up to 25 mm with sub-millimetre accuracy. This method has the potential to provide LISS-CT proximity using existing gap measurement data. Obtaining the LISS nozzle proximity at multiple inspection intervals can provide an estimate of the time to LISS-CT contact, which could be used to optimize remediation schedules.

14:50Improved Fuel Bundle Disassembly Using Electrical Discharge MachiningRichard Meguerian and Jeffrey Hulcoop, Laveer Engineering; Ross Lewis, Bruce Power

Inspecting fuel bundles that have been removed from CANDU reactors is a common occurrence. The results of these inspections are used to ensure there is an adequate understanding of the fuel condition such that the assumptions in relevant safety and fitness-for-service assessments are demonstrated to be valid, and unexpected conditions are identified for trending and communication to interfacing system groups for assessment. When suspected fuel defects reside on the interior facing surfaces of the bundles, these cannot be easily viewed, if at all, with underwater vision systems. To facilitate more detailed inspection and investigation, a bundle must be disassembled.

The disassembly process is a time-consuming activity, typically utilizing manual tools (screwdrivers and pliers on long poles) which currentlynecessitatean“outside-in”disassemblyandbundledisposal through alternate nuclear waste stream given the change in bundle geometry. Presently, hard barriers do not exist to prevent excessive force and sheath contact with the current tools which could lead to a breach of the sheath as well as damage to the feature of interest – preventing the cause from being identified and mitigated. Moreover, the current approach requires multiple operators to coordinate manipulation of the bundle, observe tool interactions with the bundle, and handle the tools. A semi-automated, proof-of-concept system has been designed and built to support disassembly of a fuel bundle using electrical discharge machining (EDM). This process imparts no mechanical stress on the fuel components, minimizing the risk of damage to the desired evidence, allows selective removal of any element without removal of adjacent elements, and yields a partial bundle that still has integrity for disposal. The automated process, requires only a single operator to monitorthesystemwhileit“cuts”,reduceseffortforanddurationofbundle disassembly, decreases the likelihood of human performance errors and reduces waste requiring disposal.


15:40-17:00CONCURRENT TECHNICAL SESSIONSOPEXSession ChairDavid Meldrum, Canadian Nuclear Laboratories

15:40An Approach to Use the Operating Experience in the Refurbishment and the Design of New PlantsHelmy Ragheb, Safety Probe International

One of the key activities to be undertaken by the nuclear plant Operator to the proposed technical scope of a life extension project is the Periodic Safety Review (PSR).

The PSR includes an assessment of the current state of the plant to determine the extent to which the plant conforms to modern safety standards and practices. Through the PSR process, the Operator is expected to determine safety improvements that will reduce risk for long-term operation which result in changes including maintenance and/or replacement of equipment, design modifications, additional safety analysis or changes to the administrative and operating procedures.

Among the guiding principles in introducing improvements in refurbished plants, is that they should take into account the national and international operational experience (OPEX), research findings and new knowledge, and industry best practices. As well, in the case of a newly built plant, the regulator may require the designer to demonstrate that the newly proposed design incorporate the available operating experience.

In both cases, the Operator’s compliance would generally be aimed at establishing the existence and adequacy of an OPEX program and that there is a process for assessing the significance of operating experience from other plants and incorporating the lessons learned into improving safety performance.

However, a confirmation by the Operator that a feedback process exists does not in itself demonstrate HOW the OPEX information can be utilized to effectively determine the scope of refurbishment and optimize engineering solutions to prevent recurrence of failures and to bring the risk to a minimum. To feedback any kind of generalized lesson or guidance to the designer, pieces of the knowledge in the OPEX databases need to be synthesized. It is the synthesis of this knowledge that is the subject of the approach described in this study.

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16:00CRL Site Transition: Safe Shutdown and Readiness for Decommissioning of National Research Universal and Mo-99 Production FacilityJacques Vincelette and Angela Weaver, Canadian Nuclear Laboratories

On 2015 February 06, the Government of Canada announced that Canadian Nuclear Laboratories (CNL) will operate the National Research Universal (NRU) Reactor until 2018 March 31. At the conclusion of this period, the Reactor will be placed in a state of storage with surveillance until decommissioning. Since 2016 October, the Mo-99 Production Facility (MPF) has been in a stand-by mode with the ability to produce Mo-99, if needed, until the NRU Reactor is permanently shut down.

As part of CNL’s vision, the Chalk River site is being revitalized to create a modern, world class, national nuclear science and technology laboratory. This work involves the decommissioning of older facilities in order to make room for modern research facilities.

The turnover of nuclear facilities from an operating state to active decommissioning needs to be documented and managed to ensure Health, Safety, Security and Environmental (HSSE) risks are identified, and eliminated or effectively controlled. Regulatory requirements are driven by G 219, Decommissioning Planning for Licensed Activities, and N294-09, Decommissioning of Facilities Containing Nuclear Substances. Additional site-specific requirements are contained in a Licence Condition Handbook.

This paper will outline CNL’s process to attain readiness for the safe shutdown of NRU and MPF, and to enable the transfer of these facilities from Operations to Decommissioning. The safe shutdown activities include the revision of Operating procedures for new facility states, as well as the preparation of supplementary safety case documentation for transition and post-shutdown states.

Major milestones in the NRU Shutdown Plan include the defueling of the reactor, the drainage of the reactor vessel, and preparing the safety case for the fuel rod bays.

Major milestones for safe shutdown of MPF include the removal of processing equipment, decontamination of the hot cells, and shutdown of active ventilation. The Canadian Government’s commitment for the repatriation of Highly Enriched Material back to the United States also relates to the shutdown of NRU and MPF.

Documentation required for the turnover of permanently shut down facilities to the Decommissioning authority includes well-defined facility boundaries, plant configuration, and remaining radiation and environmental hazards. It must identify which components continue to perform a safety function, for the planning and execution of decommissioning activities.

The transfer certificate confirms the shut-down state, identifies remaining hazards, and formally transfers the responsibility for the maintenance, care, control and security of a facility from Operations to Facilities Decommissioning.

16:20Apparent Cause for Leakage in a Dry Storage ContainerCatherine Wang, Ryan Parcels, Jim Sato, Jim Carmichael and Tahir Iqbal, Ontario Power Generation

The last processing step before placing a Dry Storage Container (DSC) loaded with used fuel into interim storage at Ontario Power Generation (OPG) is the OPG-helium leak test. DSC 5149 failed its OPG-helium leak test with an unacceptable leak rate. After various methods of trouble shooting, it was diagnosed that the leak was from a weld defect on the outer shell. Leakage from outer shell indicates that there was also leakage from the containment boundary, which contains the used fuel and was backfilled with helium prior to leak testing. An Apparent Cause Evaluation (ACE) was performed; the results of the ACE investigation are presented in this paper.

Of the five possible causes identified in the investigation, the ACE pointed to two apparent causes: (1) Manufacturer’s helium leak test failed to detect the leak, and (2) Containment boundary was damaged during manufacturing, after the manufacturer’s helium leak test.

Investigation and validation included internal discussion and meetings with OPG staff involved with processing the DSC, meetings with the manufacturer to review details of the manufacturer-helium leak test and manufacturing process, and review of all relevant OPG and manufacturer documents and records for this DSC.

The ACE investigation identified no high probability issue that could lead to this type of defect. The manufacturer’s materials and manufacturing procedures have been examined, and deemed of sufficient quality and well planned. It was concluded that this was a“one-off”instance,andleakagefromaDSCcontainmentboundaryis not expected to reoccur.

16:40Experience with the 0.05 Micron Absolute Rated Filters in the CVCS System of a PWR PlantKhalid Farooq, Pall Corporation; Wendy Walker, Pall Canada

The use of finer, sub-micron absolute rated filters has been an effective, proven tool for the reduction of out-of-core radiation levels through the control of the corrosion and erosion product transport in PWR systems.

Left unchecked, these out-of-core particles are transported to the core thereby become activated and is transported to out of core piping, thus becoming the source term for almost all dose rates in the plant.

A PWR station in the US that was already using absolute rated sub-micron filters was interested in even finer grade filters to reduce occupational exposure through enhanced source term reduction. Until recently, the finest absolute rated filtration available in the industry was 0.1 micron rated at Beta 5000 removal efficiency. Pall recently 0.05 micron absolute rated filters that were installed at the power plant in its CVCS Letdown System Post Demineralizer side. The paper discusses the experience of the plant with the 0.05 micron absolute rated filters.

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Plant PerformanceSession ChairMohinder Grover, M.S. Grover and Associates

15:40Advances in Plant Performance MonitoringStephen Woods and Raheel Naqvi, Ontario Power Generation

Ontario Power Generation (OPG) plays a major role in helping Canada achieve its commitments under the Paris climate agreement as its nuclear fleet ensures Ontario’s electricity production is virtually free of greenhouse emissions. The nuclear industry is now required to optimize its existing stations by increasing equipment efficiency andbychasing“lostmegawatts”.Asaresult,therehasbeenatremendous increase in technologies that are designed to improve communications, sensors, analytics, interconnectivity and data visualization. This has paved the way for accurate equipment health monitoring in ways that were not possible before by enabling continuous monitoring and diagnosis of power plant assets via quick and effective identification of deteriorating equipment conditions and troubleshooting the cause of these conditions. This is called, Condition Based Monitoring (CBM).

To achieve this, OPG is establishing a fleet-wide CBM over the next 18 months which will greatly reduce the Operations & Maintenance (O&M) costs. This involves use of high performance diagnostic tools that can combine the power of on-line process data acquisition with advanced diagnostics methodologies. These tools will use analytical models based on thermodynamic principles and multi-parameter analysis combined with the knowledge of component diagnostic experts. CBM will reduce costly and error prone reoccurring maintenance and disassembling inspection activities.

The Federal climate change strategy highlights nuclear generation’s continued role in helping Canada meet its targets. In addition to reliable base-load generation, customers will also benefit from the long-term, lower and stable electricity prices offered by nuclear power. OPG is well positioned to provide the province with the clean, safe, reliable and cost-effective electricity it needs today, and to support its future electrification plans.

16:00Nuclear Facility High Performance and Mitigation of Risk – Common ObjectivesJacques Plourde, Nuclear Insurance Association of Canada

It just so happens that achieving world-class performance in a nuclear facility also reduces the risks that are of concern to insurers who underwrite nuclear liability and nuclear peril. Our objectives being the same, insurance inspections of the past have now become ‘surveys’ that are far more collaborative in nature. These surveys are performed by engineers and specialists with significant experience in the Canadian nuclear industry. Survey outcomes play a major role in determining insurability and establishing premiums. The Nuclear Insurance Association of Canada (NIAC), the Canadian nuclear insurance pool, boasts a team of three surveyors with more than 120 years of nuclear power plant experience. Their surveys touch on all aspects of a nuclear facility’s operation as defined by

international guidelines that have been written by surveyors from insurance pools around the world including Canada, and incorporate industry best practices. Nuclear liability insurance is concerned with the risk to the public from reactor operation, while nuclear peril insurance is concerned with casualties and equipment damage from radioactivity arising from a facility’s operation. The survey guidelines are therefore aligned to best address these risks:

•NuclearSafety,OperationsandThird-PartyLiability(NSO-TPL);•FireSafety(FP),insupportofNSO-TPL;•MachineryBreakdownPrevention(MB),insupportofNSO-TPL);and•NuclearSafetyCulture,insupportofalloftheabove.

Fire and Machinery Breakdown have been the focus of the conventional insurance industry for well over a century. In the nuclear context, they continue to be significant contributors to a much broader scope that includes such themes as organizational effectiveness, training, emergency preparedness, radiation protection, to name but a few. This presentation will walk you through a typical survey cycle, focusing on survey methodology and the interface with the facility operator.

16:20Overview of the High-Energy Line Break Assessment for CANDU® ReactorsGordon Ozawa, Xinjian Duan, Michael Kozluk, Min Wang, Yihai Shi and Hui Wang, Candu Energy Inc.

CANDU Safety Issue CSI-IH6 is one of 16 design and analysis issues for Canadian CANDU® reactors. CSI-IH6 is associated with Internal Hazards (IH) and in 2007 was originally categorized as a Category 3 issue, which are issues that are a concern in Canada and have measures in place to maintain safety margins, but the adequacy of these measures needs to be confirmed. The risk control measure for CSI-IH6 requires a systematic review of the dynamic effects (i.e., local effects from pipe whip and jet impingement) and environmental effects (e.g., humidity, temperature, radiation levels) of postulating high-energy piping breaks inside the reactor containment and identifying the consequences on plant safety, which may require potential design or process improvements. Candu Energy Inc. has performed such assessments for Bruce, Pickering, and the Point Lepreau Generating Station to support their request for the recategorization of CSI-IH6 from a Category 3 to a lower category. The purpose of the high-energy line break assessment (HELBA) is to systematically demonstrate that the design of the high-energy piping and safety systems inside the reactor building are in compliance with the best practices from modern industry standards and guidelines such as IAEA NS-G-1.11. Assessments of the high energy piping for the balance of plant have been performed for some units. Since its start in 2007, the HELBA methodology has dramatically evolved to address regulatory concerns, to adapt to unique station designs and layouts, and to meet specific client requirements. Some examples are presented in this paper. Most significantly, this work has assembled a qualified and experienced team that is capable of performing HELBA on operating stations and new designs.

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Component Corrosion and Corrosion ControlSession ChairPeter Ozemoyah, Tyne Engineering, Inc.

15:40Treatment Optimization through Effectiveness MonitoringGeorge Licina, Robert Scholz and Erica Libra-Sharkey, Structural Integrity Associates, Inc.

Essentially all industries include treatments with corrosion inhibitors, deposit control agents, and biocides as a part of their control of general corrosion, localized corrosion, fouling, and microbiologically influenced corrosion (MIC) in cooling waters and process waters. Most such treatments rely exclusively on monitoring the concentrations of the control chemicals rather than monitoring the effectiveness of those treatments. Inhibitors and biocides are expensive, can produce undesirable side effects as they interact with other chemicals, and will always be subject to effluent controls. Over-dosing of treatment chemicals, especially oxidizing biocides, will have undesirable side effects, including increased corrosion of piping, heat exchangers, and process equipment.This presentation provides results of biofilm monitoring at Exelon’s Peach Bottom Atomic Station, including biocide optimization efforts.

16:00Electrosleeving ApplicationsLjubo Djordjic, Kinectrics Inc.; Gino Palumbo, Integran

Different mechanisms of localized corrosion are present in power and process piping at nuclear plants. The inspection, monitoring, and repair of the corrosion affected areas are done during outages, regular or forced, and can be very costly; in certain cases, the unit might be de-rated, or the permanent shutdown of a reactor is required. The conventional repair methods such as mechanically expanded or welded sleeving might be unsuitable as they leave residual stresses, deformation, or alteration of the original material microstructure.Electrosleeve™ utilizes electrodeposition of a nanocrystalline nickel micro alloy on the internal surface of the piping. It is a non-intrusive and low-temperature process that applies a continuously bonded high strength inner tubular electroform having an average grain size of 100 nm. The electrosleeve provides superior thermal, mechanical, and creep performance with corrosion resistance being comparable to that of high purity nickel. The yield and tensile strength of the nanocrystalline structure is significantly higher than that of conventional wrought alloys, while maintaining good ductility and fracture toughness. The thickness of the plating layer depends on the overall thickness of the piping and regulatory requirements for a repair. Electrosleeve™ is capable of fully restoring the structural integrity of the affected area and rehabilitation of a pressure boundary.Ontario Hydro’s Technologies (OHT) originally developed this technology and it was first applied in 1994, at Ontario Hydro’s Pickering Nuclear Generating Station (PNGS) Unit 5 for a repair of steam generator (SG) tubing. Integran Technologies and Kinectrics are developing this technology to be more universal by applying the same principles on larger diameter piping. The process steps, current density, solution compositions, flow rates, and temperature are optimized for a particular problem. The repair is in-situ, and the NDE inspection is necessary to confirm adhesion and the structural integrity of the layer.

16:20Ultra-Low Chloride (ULC) Anion Ion Exchange Resin for Optimum Condensate PolishingCharles Kozora and Al Tavares, Graver Technologies

Ion exchange resins are an accepted and established water treatment method for condensate polishing for the removal of species prone to cause corrosion. The minimization of such species lead to the minimization of asset degradation from corrosion and thereby leads to potentially decreased maintenance and increased asset longevity.

The purity of the ion exchange resin itself has an impact on this goal. The presence of chloride is detrimental in high-purity water systems and the ion-exchange resin can be a source of the chloride ion. Chloride ions in high pressure steam cycle chemistry (PWRs) can be concentrated by a factor of 100-350X leading to increased conductivity and promotion of corrosive reactions. Thus, dependent upon the chloride maximum specification, even ion exchange resins can contribute to the chloride level in the condensate.

Historically, 40 years ago, chloride specification for ion exchange resins were as high as 5%. Currently, it is at 0.5% for typical condensate and 0.1% for nuclear grade. The Ultra-Low Chloride (ULC) Anion Ion Exchange Resin has a specification of 0.05% with actual values typically well below this specification.

The Ultra-Low Chloride (ULC) Anion Ion Exchange Resin is manufactured by Graver Technologies via a specific anion regeneration process which enables the new low chloride benchmark specification to be established. This new industry benchmark has been well-vetted for station improvements per multiple- year utilization of Gravex GR 1-9 US Ultra (uniform particle size) and Gravex GR-1-9 NG ULC (Gaussian particle size distribution) at both PWR and BWR stations, respectively, in the northeast and mid-Atlantic regions of the United States.

16:40Review of Zircaloy Oxidation Kinetics and Models in Air and Air-Steam MixtureMohamed Shawkat and Hisham Hasanein, Amec Foster Wheeler

There are several events in CANDU® reactor where the fuel bundles may be exposed to air or air/steam mixture. The available experimental programs investigating Zircaloy oxidation in air and air/steam mixture and identifying the main characteristics of the oxidation kinetics in both environments are reviewed. The oxidation correlations that describe the oxidation kinetics in air and air/steam mixture are also identified and discussed. Sheath and fuel temperatures are expected to be higher for bundles exposed to air than for bundles exposed to steam due to the differences between Zircaloy oxidation kinetics and heat of reaction. Oxidation kinetics are generally faster and the heat of reaction is higher in air than in steam. Under accident conditions, sheath oxidation in air/steam mixture is more likely than oxidation in air. The ratio between air and steam in the mixtures plays a major role in determining the mass gain and the oxide thickness for a given sheath temperature and oxidation time.

17:00Conference Concludes

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AREVA NP Canada Ltd. 9925 Brock Road, Pickering, ON L1W 2X9 www.canada.areva.com Contact: Kelly Pedersen, Sales & Marketing Specialist T: 905-421-2600 E: [email protected]

AREVA Canada, headquartered in Pickering with a regional office in Kincardine - is a major player as a services and engineering provider for the Canadian and global CANDU markets. As an actively engaged supplier member of COG, AREVA Canada is committed to being the leading Nuclear Service provider that exceeds our clients’ needs and expectations. We are proud to be deeply rooted in Canada for more than 50 years and are committedtoservingasAREVA’s“CANDUCentreofExcellence”andsinglepointofcontactfortheglobalCANDUmarket.Ourgoalistobringvaluetothe CANDU Nuclear Industry through Technology, Innovation and Collaboration.

Advanced Measurement & Analysis Group Inc. 2396 Dunwin Drive, Mississauga, ON L5L 1J9 www.amag-inc.com Contact: Alexander Gurevich, Engineering Scientist T: 905-607-6349 x31 E: [email protected]

Advanced Measurement & Analysis Group Inc. (AMAG) is a high-tech Canadian company that provides a variety of services related to improvement of plant performance in the power production and processing industries. The company was founded in 1993 by former Ontario Hydro employees with over 20 years’ experience in nuclear plant commissioning and performance improvement. The list of AMAG clients currently includes more than a hundred nuclear power plants in Canada, the United States, Europe, Asia, and South America.

AMAG main product is CROSSFLOW, a cross-correlation based non-intrusive ultrasonic flow measurement system used to provide reliable and accurate flow measurements. In the power production industry, the main applications of this technology are for reactor thermal power calibration by performing accurate boiler feedwater flow measurement and verification of reactor coolant flow in safety channels in CANDU reactors. CROSSFLOW is also used for various non-intrusive flow and temperature measurements in other components of nuclear power plants, such as total reactor coolant flow, emergency coolant pump flow, service water flow, and others. The main advantage of the CROSSFLOW is its ability to provide accurate and reliable flow and temperature measurement during normal plant operation without cutting the pipes. AMAG also performs measurements of neutron flux distribution and of feeder flow distribution during plant commissioning.

Amec Foster Wheeler 700 University Avenue, 4th Floor, Toronto, ON M5G 1X6 www.amecfw.com Contact: Gord Fountain, Vice President, Business Development T: 416-592-7000 E: [email protected]

Amec Foster Wheeler Nuclear Canada is a provider of services to nuclear utilities and related markets. With more than 40 years of experience and an in-depth knowledge of nuclear plant design and operation, Amec Foster Wheeler Nuclear Canada supports its clients through the entire nuclear life-cycle, from new build to operations, refurbishment and life extension and finally waste management and decommissioning.

Globally, Amec Foster Wheeler’s pedigree in the nuclear business can be traced back to 1955, involving the first applications of nuclear fission for commercial power generation. Amec Foster Wheeler has been involved with virtually every major commercial reactor technology and now designs, delivers and maintains strategic and complex assets through its 35,000 employees located in more than 55 countries worldwide.

C M N CC 2 017 S P O N S O R A N D E X H I B I TO R CO M PA N Y P RO F I L E S

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ASI Group Ltd. 250 Martindale Road, St. Catharines, ON L2S 0B2 www.asi-group.com Contact: Merry Dang, Sales and Marketing Manager T: 905-641-0941 E: [email protected]

ASI Group Ltd., is a full-service engineering and marine technology company comprised of two groups; ASI Marine, which offers a full range of under-water inspection, mapping and light construction services, and ASI Water which has extensive experience in design, build, and operation of drinking water and wastewater systems and mussel control operations.

Since 1987, ASI Marine has been a world leader in commercial and nuclear diving, having developed world-first techniques and services that have improved safety and equipment reliability. We specialize in underwater radiological environment diving for inspection, maintenance, and repair. In turn, this has led to the reduction of maintenance workload in nuclear plants and other industrial sites with underwater infrastructure. ASI Marine’s highly trained commercial dive team conduct detailed underwater inspection, repair, and maintenance operations both safely and efficiently. We ensure the necessary procedures and plans are in place to protect the safety of the dive team and facility in working in radiological environments. ASI Marine is committed to the radiation safety principal ALARA (as low as reasonably possible) and operates under strict Quality Control/Assurance guidelines.

ASI Water’s patented macrofouling service solution encompasses a comprehensive package which includes an initial facility risk assessment, biological monitoring, and site specific turnkey control programs designed to reduce the risk and cost of macrofouling infestation. ASI Water is recognized as the macrofouling industry leader specifically related to aquatic invasive species’ such as zebra mussels and quagga mussels. We have led the effort for nearly 27 years to develop and scale up novel macrofouling management protocols, beginning with an R&D initiative alongside Ontario Hydro in 1990. ASI Water currently provides mussel control programs for over 40 industrial and water treatment facilities throughout the Great Lakes Region.

Black and MacDonald 81 Osborne Road, Courtice, ON L1E 2R3 www.blackandmcdonald.com Contact: Jim Whyte, ESMSA Operations Manager T: 647-749-3613 E: [email protected]

Black & McDonald was founded in 1921 as a partnership between William J. McDonald and William R. Black, primarily engaged in residential wiring. In the early years, when they often traveled from one job to the next on foot, Black & McDonald established its long-standing commitment to fairness, quality, its people, and its clients. Today, the company is the fourth generation of McDonald family ownership, providing multi-trade construction and maintenance services to clients across North America.

Black & McDonald is a prime multi-trade contractor providing a full range of electrical, mechanical, utility and maintenance services to commercial, industrial, utility and government clients. The company is registered and licensed to do business in all provinces and territories, operating out of a network of over 25 offices across Canada and the United States, with over 5,500 employees.

Black & McDonald’s depth of experience has made us the partner of choice across a wide range of industries including power generation. Our man-agement team invested in the development of our people, determine to make our highly-experienced tradespeople renowned as the best in their industries. With over 95 years of lessons learned, we are able to consistently apply that knowledge – meeting our customers’ most demanding chal-lenges, in their most critical environments.

The company’s multi-trade services for nuclear facilities include construction projects, extensive plant maintenance and modification services, and emergency support. Our leaders are experienced in integrated projects and partnerships; key personnel have significant power generation expertise; and employees are long-term and highly qualified. Best practices are upheld company-wide from the corporate level to the tradesperson. Together, our personnel maintain our steadfast commitment to global leadership in Health & Safety, Quality, Performance, and Client Satisfaction.

At Black and McDonald, we remain proud of our past, advanced in our capabilities, and driven to deserve our reputation.

Bruce Power 177 Tie Road, Tiverton, ON N0G 2T0 www.brucepower.com Contact: Brandon Lambert, Executive Assistant to the Chief Nuclear Officer T: 519-361-2673 x11577 E: [email protected]

Formed in 2001, Bruce Power is an electricity company based in Bruce County, Ontario. We are powered by our people. Our 4,200 employees are the foundation of our accomplishments and are proud of the role they play in safely delivering clean, reliable, low-cost nuclear power to families and businesses across the province. Bruce Power has worked hard to build strong roots in Ontario and is committed to protecting the environment and supporting the communities in which we live.

Bruce Power is a partnership among TransCanada Corp., OMERS Infrastructure Management Inc. (a trust established by the Ontario Municipal Employees Retirement System), The Power Workers’ Union and The Society of Energy Professionals. Over 90% of employees also own a part of the company.

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BWXT Canada Ltd. 581 Coronation Blvd., Cambridge, ON N1R 5V3 www.bwxt.com Contact: Natalie Cutler, Manager of Communications & Government Relations T: 519-620-5288 E: [email protected]

BWXT Canada Ltd. (BWXT Canada) has over 60 years of expertise and experience in the design, manufacturing, commissioning and service of nuclear power generation equipment. This includes CANDU ® and Pressurized Water Reactor steam generators, nuclear fuel and fuel components, critical plant components, parts and related plant services. Headquartered in Cambridge, Ontario, BWXT Canada has approximately 850 employees at locations in Cambridge, Peterborough, Toronto and Arnprior, Ontario. BWXT Canada is a subsidiary of BWX Technologies, Inc. (NYSE:BWXT). BWXT is a leading supplier of nuclear components and fuel to the U.S. government; provides technical, management and site services to support governments in the operation of complex facilities and environmental remediation activities; and supplies precision manufactured components, fuel and services for the commercial nuclear power industry. Learn more at www.BWXT.com.

Canadian Nuclear Laboratories 286 Plant Road, Chalk River, ON K0J 1J0 www.cnl.ca Contact: Denys Elliot, Marketing Specialist T: 613-584-3311 x45262 E: [email protected]

Canadian Nuclear Laboratories (CNL) is Canada’s premier nuclear science and technology laboratory, dedicated to developing peaceful and innovative applications from nuclear technology through its expertise in physics, metallurgy, chemistry, biology, and engineering. We address global issues across the nuclear lifecycle – reactors and fuels, waste management, nuclear safeguards – and develop novel medical isotopes and devices. CNL’s Chalk River Laboratories represent the largest single complex within Canada’s science and technology infrastructure. The site contains several licensed nuclear facilities, including the National Research Universal (NRU) reactor and more than 50 other unique facilities and laboratories. Highly skilled employees deliver a range of nuclear services – ranging from research and development, design and engineering to specialized technology development, waste management and decommissioning.

Canadian Nuclear Partners 700 University Avenue, Toronto, ON M5G 1X6 [email protected] Contact: Greg Thede, Director, Business Development T: 416-592-3227 E: [email protected]

Management Expertise• ProjectManagementtoprovideturn-keyservices;• Leadershipinnuclear,hydroandthermalplantoperations;• Strategicleadershipinoperationsanddecision-making;• Nuclearregulatoryandlicensing;• Workmanagementandoutagemanagement.

Technical and service expertise• Innovativeinspectiontoolingdevelopment,operationandmaintenance;• Inspectionservices(fuelchannels,NonDestructiveExamination,phasedarray,specializedtroubleshooting,nuclear reactor feeders,piping,heat

exchangers, steam generators);• Nuclear reactor maintenance (single fuel channel replacement, calandria tube replacement, reactor component troubleshooting, irradiated

component transfer, inspection delivery system technical support, pressure tube sampling);• Machinedynamicsandcomponentintegrity(vibrationmonitoring,diagnostics,balancingandanalysis);• Plantlifecycleplanning;• Inspectionandmaintenanceengineering;• Nuclear,hydroandthermalplantrefurbishmentandrepurposing;• Nuclear,hydroandthermalplantdecommissioning;• Nuclearwastemanagement;• Diveservices.

• Drone&UAV(unmannedArialVehicles)InspectionServices

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Canadian Nuclear Safety Commission P.O. Box 1046, Station B, 280 Slater Street, Ottawa, ON K1P 5S9 www.nuclearsafety.gc.ca T: 1-800-668-5284 (in Canada) T: 613-995-5894 (outside Canada) E: [email protected]

The Canadian Nuclear Safety Commission (CNSC) regulates the use of nuclear energy and materials to protect the health, safety and security of Canadians and the environment; to implement Canada’s international commitments on the peaceful use of nuclear energy; and to dissem¬inate objective scientific, technical and regulatory information to the public.

The CNSC was established in 2000 under the Nuclear Safety and Control Act (NSCA) and reports to Parliament through the Minister of Natural Resources. The CNSC was created to replace the former Atomic Energy Control Board (AECB), which was founded in 1946.

Under the NSCA, the CNSC’s mandate involves four major areas:

• regulationofthedevelopment,productionanduseofnuclearenergyinCanadatoprotecthealth,safetyandtheenvironment;

• regulation of the production, possession, use and transport of nuclear substances, and the production, possession and use of prescribedequipment and prescribed information;

• implementation of measures respecting international control of the development, production, transport and use of nuclear energy and substances, including measures respecting the non-proliferation of nuclear weapons and nuclear explosive devices; and

• disseminationofobjectivescientific,technicalandregulatoryinformationconcerningtheactivitiesofCNSC,andtheeffectsontheenvironment, on the health and safety of persons, of the development, production, possession, transport and use of nuclear substances.

The CNSC’s Commission Tribunal has up to seven appointed permanent members whose decisions are supported by CNSC staff. These employees review applications for licences according to regulatory requirements, make recommendations to the Commission, and enforce compliance with the NSCA, regulations, and any licence conditions imposed by the Commission.

E.S. Fox Limited P.O. Box 1010, 9127 Montrose Road, Niagara Falls, ON L2E 7J9 www.esfox.com Contact: Terry Armstrong, Vice President, Nuclear T: 905-708-8908 E: [email protected]

E.S. Fox has been a key supplier to the Canadian nuclear industry since the early 1970’s. Fox’s Quality Management System is registered to ISO 9001 by Bureau Veritas and is the minimum standard for the work we perform. We manufacture and install nuclear parts and components under supplemen-tary Quality Assurance programs CSA N285; CSA N286; and CSA Z299. We also hold numerous other certifications including ASME B31.1 and B31.3, ASME Section VIII Div 1 & 2, ASME Section III: N, NA, NPT, NS, all of which are listed on our website under Project Controls in the QA/QC section.

E.S. Fox also holds certifications in both ISO14001 Environmental and 18001 Health and Safety. Our comprehensive Corporate Safety Program and commitment to the safety of our workforce is unwavering. Rigorous implementation of our Safety Program along with management’s dedication to a culture of safety has enabled us to achieve COR Certification in Ontario, Alberta and New Brunswick, and COR equivalencies in Saskatchewan and Newfoundland and Labrador.

With over four decades of experience, E.S. Fox has the expertise and capacity to be the single source solution for fabrication, construction and main-tenance services to the Canadian nuclear industry.

Farris/Great Lakes Industrial Controls 880 Upper Canada Drive, Sarnia, ON N7W 1A4 www.greatlakesic.com Contact: Gary Jensen, President T: 800-546-0705 E: [email protected]

Great Lakes Industrial Controls proudly represents Farris pressure relief valves in the Provinces of Ontario and Manitoba. Farris is a world leader in the design and production of a wide range of spring-loaded and pilot-operated pressure relief valves. They are used as safety devices to prevent over-pres-surization of vessels, pipelines, and equipment in both the Conventional and Nuclear Power Generation Industries.

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Kinectrics Inc. 800 Kipling Ave. Unit 2, Toronto, ON M8Z 5G5 Contact: Cheryl Tasker-Shaw, Marketing and Training Manager T: 416.207.6000 x5970 E: cheryl [email protected]

With over 100 years of proven expertise in providing advanced technical support for major North American generating stations, Kinectrics is uniquely qualified to provide engineering, testing and certification services for the nuclear industry.

Our capabilities include a full range of services for Nuclear Parts Qualification (NPQ) and Inspection and Maintenance Systems (IMS). The Kinectrics IMS department provides leading-edge inspection tooling for nuclear including CWEST, TRUSTIE™, CIGAR and ANDE. Kinectrics’ Nuclear Parts and Equipment Qualification business delivers reliable, effective services for Commercial Grade Dedication (CGD), Reverse Engineering (RE) from a new dedicated Kinectrics RE facility and machining / prototyping of genuine nuclear replacement parts and components.

Kinectrics is an accredited full-service resource for the nuclear industry. Our Generation Life Cycle Management (GLCM) business provides radioactive materials and analytical chemistry testing, materials characterization, nuclear waste management, environmental technologies, emissions monitoring and other specialized capabilities.

GLCM facilities include a Radioactive Materials Lab, Corrosion Testing Lab, and a large, dedicated Decontamination and Refurbishment Facility.

Kinectrics’ Candesco Division is also available to support nuclear waste management, decommis¬sioning, nuclear safety, human factors, and industry licensing requirements.

Complementing these offerings is Kinectrics’ training initiative, which features a wide variety of industry-related courses.

Kinectrics’ staff of over 400 engineers, scientists and highly-qualified technical personnel, working in state-of-the-art facilities, can provide nuclear operators with the life cycle management solutions and innovative products needed to maintain optimal operations and reliable, cost-effective plant performance.

Lakeside Process Controls

2475 Hogan Drive, Mississauga, ON L5N 0E9 www.lakesidecontrols.com Contact: Nadre Mark, Event Coordinator T: 905-412-0500 E: [email protected]

Since 1952, Lakeside Process Controls Ltd. has been providing innovative automation solutions with superior customer service. Lakeside is an employ-ee-owned Canadian company that operates as the exclusive Local Business Partner of Emerson Process Management in Ontario (excluding the Ottawa Valley), Manitoba, and the Kivalliq region of Nunavut.

Lakeside’s mission is to create customer value by providing the best solutions to fulfill our customers’ process automation challenges, through creativity, reliability, productivity, teamwork, professionalism and dedication. Lakeside’s solutions range from devices that measure and relay diverse physical and chemical conditions, devices that control flow of materials, networks that transmit event related information, to process control systems that collect information and trigger necessary actions to ensure continued operations, based on the logic defined for the process being automated.

There is constant pressure to cut costs, increase output, reduce energy use, and improve safety and emissions, all with fewer experienced workers than ever before. That is why companies turn to Lakeside for technologies, services and expertise to solve pressing problems to keep their operations running better, longer, and safer than ever before.

Laveer Engineering 3070 Mainway, Unit 12, Burlington, ON L7M 3X1 www.LAVEER.ca Contact: Richard Meguerian, Program Manager T: 905-861-1200 E: [email protected]

Laveer Engineering Limited has a team of engineers and project managers with extensive project experience. The organization has worked on successful first-of-a-kind tooling and field execution projects with unique constraints associated with nuclear. In addition to our design capability, Laveer offers a range of services that dovetail our team’s experience.

Projects can range from playing a narrowly defined role such as a technical reviewer to being a full-scale, start-to-finish supplier involved in all aspects of project development, execution, and completion.

Turn-key design services focused on mechanical and electrical design of components and assemblies in the areas of welding, machining and inspec-tion. Integrating proven practices and standards with our innovative approach, Laveer can deliver a design package tailored to your unique requirements. Laveer can produce ruggedized designs including limited space/limited access applications.

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Liburdi Automation Inc. 1230 South Service Road, Stoney Creek, ON L8E 5C4 www.liburdi.com Contact: Kathy Nelson, Market Development/Trade Show Manager T: 905-689-0734 E: [email protected]

For over 40 years Liburdi has been a leader in high reliability equipment and processes for orbital tube and pipe welding. Our GoldTrack® systems have been used in the Nuclear Industry since the 1970s for construction and maintenance of all types of reactors. Liburdi offers the best in equipment supply, weld development, procedure qualification, technical support and project management.

Liburdi manufactures and markets a complete line of welding power supplies and heads for GTAW, GMAW, FCAW, PAW and LAW applications. We design and build custom engineered systems to address the unique needs of the nuclear industry. This includes:

• remotelydeployedandoperatedsystems,• highradiationresistantsystems,• multi-processsystems(ie.welding,grindingandinspection),and• specialtysystemsforlowclearanceapplications.

In addition to welding equipment design and fabrication, Liburdi offers technical, project management and field execution services. Being a CSA N285.0 Certificate holder, puts us in a unique positon to support the Canadian Nuclear Sector with capabilities ranging from welding procedure qualification to full project management and execution.

Liburdi is a global company with headquarters located in Canada, with sales and technical support in North America, Europe and Asia.

LISEGA INC. 370 E Dumplin Valley Road, Kodak, TN 37764 www.lisega.com Contact: Dave Dutrow, Nuclear Sales Manager T: 865-206-8942 E: [email protected]

Manufacturer of pipe supports for the power industry. We provide both the product and engineering services to support power plants with all of their piping support needs.

Canadian Nuclear Energy Infrastructure Resilience under Systemic Risk (CaNRisk) JHE-301, 1280 Main Street West, Hamilton, ON L8S 4L8 www.canriskcreate.ca Contact: Wael El-Dakhakhni, Program Director T: 905-929-1912 E: [email protected]

The CaNRisk NSERC-CREATE program aims at providing Canada with the next generation of experts in seismic safety assessment and resilience enhancement of nuclear power plants (NPP) following a unique interdisciplinary system-level focuses approach. The program focuses on quantifying the probability of failure of critical structures, systems, and components in NPP reactor safety systems under different levels of seismic hazard.

The CaNRisk-CREATE program also focuses on minimizing the environmental risk of spent nuclear fuel to be permanently stored within the planned Canadian Deep Geologic Repository. The CaNRisk-CREATE interdisciplinary academic training is integrated with hands-on industrial internship and professional development experiences to facilitate effective transition of the program trainees to the workforce in Canada and worldwide.

North America Young Generation in Nuclear (NAYGN) www.naygn.org/regions/canada/ Contact: Andrew Ali, Canadian Affairs Chair E: [email protected]

North American Young Generation in Nuclear (NAYGN) was established in 1999 by seven young professionals. These young professionals wanted to create an organization that provided professional development, public information, knowledge transfer, recruiting and networking opportunities for the next generation of nuclear leaders.

NAYGN provides opportunities for a young generation of nuclear enthusiasts to develop leadership and professional skills, create life-long connections, engage and inform the public, and inspire today’s nuclear technology professionals to meet the challenges of the 21st century.

Fueled by volunteers, the organization has grown to include dozens of continental committees and over a hundred local chapters facilitated by a board of directors affectionately known as The Core. This structure allows the organization to be flexible and serve a wide variety of members. The organization has conducted hundreds of thousands of hours of activities to educate the public and provided development opportunities at the local, regional, national and continental level.

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NB Power 515 King Street, PO Box 2000, Fredericton, NB E3B 4X1 www.nbpower.com

Organization of Canadian Nuclear Industries 1550 Kingston Road, Suite 219, Pickering, ON L1V 1C3 www.ocni.ca Contact: Marina Oeyangen, Director of Operations T: 905-839-0073 E: [email protected]

The Organization of Canadian Nuclear Industries (OCNI) is the leading and trusted voice of the Canadian nuclear supply chain, actively promoting the production of safe, clean and reliable nuclear electricity. Founded in 1979, OCNI is an association of more than 200 leading Canadian suppliers to the nuclear industry in Canada and abroad.

OCNI’s four strategic priorities are to:

• Strengthenlinkagesbetweenmembercompaniesandutilities;• Increasesupplierreadinessforrefurbishment/MCRprojectsinOntario;• Developinternationalopportunitiesformembercompanies;• AdvocatewithgovernmentandthepublicforanexpandedrolefornuclearpowerinCanada

OCNI member companies collectively employ more than 12,000 highly skilled and specialized people who manufacture major equipment and compo-nents and provide engineering services and support to the 19 operating CANDU nuclear power plants in Canada as well as to CANDU and LWR plants in offshore markets. OCNI companies also work on medical and industrial applications of nuclear technology.

Ontario Power Generation Ontario Power Generation 889 Brock Road, Pickering, ON L1S 3J2 www.opg.com Contact: Shane Ryder, Vice President Fleet Operations & Maintenance

T: 905-839-6746 X 5306 E: [email protected]

Ontario Power Generation produces about two thirds of the electricity that powers Ontario’s homes and businesses. We’re an important part of many communities, with 12,000 employees working at 73 power plants across the province.

OPG owns and operates the Pickering and Darlington Nuclear Power Stations located in Durham Region. The two stations have 10 reactors with a combined generating capacity of about 6,600 megawatts. The electricity produced by our nuclear stations is virtually free of climate change and smog-causing emissions. OPG is committed to operating in a safe, efficient, open and environmentally-responsible manner.

Pall Corporation 25 Harbor Park Drive, Port Washington, NY 11050 www.pall.com Contact: Keith Webb, Power Generation Vertical Marketing Manager T: +44 (0)2392 3338437 / Cell: +44 (0)78089 12331 E: [email protected]

Pall Corporation is a global company solving complex contamination, separation and purification problems.

Pall Power Generation serves the power generation markets around the world. With a broad line of products and services, Pall can help you improve fluid quality and increase profitability by optimizing the performance of plant equipment.

Pall can design, manufacture, and install economical, integrated systems as well as service them. State-of-the-art media design, application experience and unsurpassed removal efficiencies have made Pall the world standard in nuclear safety, control, radioactive waste treatment and fuel pool clean-up.

For many years, Pall filtration systems have been used in the most sensitive nuclear applications of PWR coolant systems. Today, the cleanest plants use Pall nuclear grade filters to reduce the out of core radiation levels and reduce overall personnel exposure. The fine ratings program is a step by step reduction of filtration level down to 0.05 micron in order to decontaminate the coolant systems progressively, ensuring better operation, easier maintenance and reduced exposure.

Pall is the ideal partner for the nuclear power generation industry.

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Perma-Fix Canada Inc. 1 Yonge Street, Suite 1801, Toronto, ON M5E 1W7 www.perma-fix.com Contact: Tammy Monday, Vice President, Waste Services Sales and Business Development T: 865-342-7613 E: [email protected]

Perma-Fix Canada Inc. provides commercial and government customers with safe, compliant, and environmentally responsible nuclear and waste remediation, management, and treatment services. Our team provides turnkey solutions to our clients’ challenges through various offerings including project management, environmental restoration, operational services, radiological protection, and waste management. These offerings consist of the following:

Decontamination, decommissioning, and demolition of facilities, structures, and sites contaminated with radiological and hazardous materials, including:

• Structureandsitecharacterisation,includingradiologicalsurveyingandassessment

• Structureandopenlanddecontamination,dismantling,demolition,andrelatedplanningandplan

• Development(includinghealthandsafety,radiologicalcontrol,environmentalcompliance,qualitycontrol,workplans,etc.)

• Structureandsitepreparation

• Radiologicalandhazardousmaterialsabatement

• Radiologicalcontrolandprotection

• Aboveandbelowgroundremovaloftanks,piping,foundations,structuralcomponents,etc.

• Soilandwastecharacterisation,excavation,sorting,andsegregation

• Siterestoration

Waste management, including:

• RadiologicalandhazardousmaterialscharacterizationRadiologicalandhazardousmaterialstransportation(includingbrokering,packagingandshipping support)

• LLRW,mixedwaste(wastecontainingbothhazardousandlow-levelradioactivematerials),hazardousandindustrialmaterials/wastecharacter-isation, processing, treatment, and disposal

PwC Canada 18 York Street, Site 2600, Toronto, ON M5J 0B2 www.pwc.com Contact: Helen Bremner, Partner, Strategy &, Energy & Utilities T: 403-509-7404 E: [email protected]

PwC provides power and utility companies with assurance, tax, consulting and deals services. For more than 100 years, we’ve used our knowledge and experience to develop tailored solutions for our clients, helping them build public trust and deliver the value they’re looking for.

Delivering results in this new energy era means transforming your business and implementing innovation from strategy through execution. We offer deep expertise and advisory capabilities in a variety of functions including Enterprise Work/Asset Management and capital projects. We will help you antic-ipate the challenges and set you on the path to achieving operational excellence.

We work with 5800 partners and staff across Canada and belong to a trusted network of advisors worldwide, including over 5300 dedicated utilities people.

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Promation Nuclear 2767 Brighton Road, Oakville, ON L6H 6J4 www.promation.com/nuclear-division/ Contact: Anna Masarik, Manager of Proposals T: 416-801-2278 E: [email protected]

Promation is a leading designer and manufacturer of high-quality tooling, automation, and robotic systems. It is a privately owned Canadian Corporation supported by three divisions- Nuclear, Automotive, and Industrial. With a strong commitment to excellence and strict conformance to quality manage-ment programs, Promation has been successful in delivering custom equipment and engineered turnkey systems to global customers for nearly 20 years. Promation offers a wide range of capabilities in design and technology for tooling and as a machine developer, integrator and builder of indus-trial manufacturing systems.

For Promation, ‘Delivering Expertise’ is more than a tagline- it reflects the approach to every engagement. By providing the full scope of services necessary to research, develop, engineer, test and build custom solutions, Promation yields maximum benefits to the customers ensuring highest quality and performance on-time, on-schedule and on-budget, while catering to the unique requirements of each industry. Promation focuses its efforts in providing consultancy and project management services and is supported by a team with robust skills and a collective engineering experience of 500 years in respective fields.

Promation also takes pride in their superiority in the robotic industry by deploying robotics in multiple divisions and improving the efficiency in the operations. Many years of experience, coupled with proficient project management skills, advanced technology, engineering expertise and continuous business improvements are some of the driving factors that contributes to Promation’s proven capabilities.

SNC-Lavalin Nuclear 2285 Speakman Drive, Mississauga, ON L5K 1G8 www.snclavalin.com/en/nuclear Contact: Barbara Hooley, Senior Advisor, Marketing Communications T: 416-252-5315 x 54505 E: [email protected]

About SNC-Lavalin

Founded in 1911, SNC-Lavalin is a global fully integrated professional services and project management company and a major player in the ownership of infrastructure. From offices around the world, SNC-Lavalin’s employees are proud to build what matters. Our teams provide comprehensive end-to-end project solutions – including capital investment, consulting, design, engineering, construction, sustaining capital and operations and maintenance – to clients in oil and gas, mining and metallurgy, infrastructure and power. On July 3, 2017, SNC-Lavalin acquired Atkins, one of the world’s most respected design, engineering and project management consultancies.

Our Nuclear Services

We oversee new-build nuclear power plants, major refurbishments, and life extensions, and offer specialized services in safety analysis, environmental qualification, metrology/spatial analysis, geotechnical investigations, decommissioning and waste management services. We are also involved in both nuclear steam plant (NSP) and balance of plan (BOP) projects.

Our knowledgeable team of nuclear power experts, offer a catalogue of engineering and field services, an extensive range of plant life management and steam generator maintenance programs, and tooling for boiling water reactors (BWRs) and pressure water reactors (PWRs).

Rolls-Royce Civil Nuclear Canada Ltd. 678 Neal Drive, Peterborough, ON K0J 6X7 www.rolls-royce.com Contact: Sinisa Milidrag, Sales Manager T: 705-743-2708 X222 E: [email protected]

Rolls-Royce Civil Nuclear Canada Ltd. is a 100% nuclear engineering and custom equipment supply company. Our projects cover the full life cycle of a typical nuclear power plant from new build, to inspection, maintenance, refurbishment, and waste handling. Since 1974, we have provided nuclear components, process systems, remote handling equipment and waste storage containers to Canadian, US and International clients. Our commitment to the nuclear industry is demonstrated by our multi-tiered Quality Assurance Program that addresses the needs of the most demanding nuclear codes and standards that include CSA Z299.1, ASME Section III (including NQA-1), as well as 10CFR50 Appendix B.

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SWI 2300 Yonge Street, Suite 1800, Toronto, ON M4P 1E4 www.swi.com Contact: Ed Mischkot, Vice President, Energy T: 416-932-4582 E: [email protected]

SWI is an information technology consulting firm committed to providing dependable software and engineering services for high impact projects in the financial and energy sectors, in addition to specialized solutions for the nuclear industry. For over three decades, SWI has maintained a strong reputa-tion for deep industry knowledge and extensive experience in architecting and implementing complex IT systems. SWI provides a full range of consulting services, including custom software development and integration, project management, and strategic planning in industries where dependability and business continuity are critical.

SWI is a subsidiary of Alithya, one of Canada’s leading strategy and information technology consulting firms. Comprised of over 1500 specialized consultants, Alithya guides and assists clients in their pursuit of innovation and excellence. With multiple offices in Canada, France and The United States, Alithya serves a variety of industries including financial services, telecommunications, energy, transportation, health care and government services. As an Alithya company, SWI has gained an enhanced set of capabilities and now offers a wider array of expertise and services to our clients.

We believe that by building long-term partnerships with our clients based on trust and a shared commitment to excellence, we can accomplish great things. For more information, visit www.swi.com

Tyne Engineering Inc. 730 Darlene Court, Burlington, ON L7L 5V1 www.tyne-engineering.com Contact: Vince Robinson, President T: 289-288-0490 E: [email protected]

Located in Burlington Ontario, Tyne Engineering has over 30 years of experience in the design and manufacture of complex engineering systems in the fields of process engineering, mechanical engineering, and Instrumentation and Controls for the nuclear and tritium-handling industries.

Experience has come from extensive work in the following areas:

• Nuclearpowerplantcontrolandinstrumentationsystems.• Instrumentationandelectroniccircuitdesign.• Skid-mountedmodularizedsystemsofhighcleanliness,lowleakage,hightemperature/cryogenictemperature.• Tritiumhandlingandradiationmonitoringequipment.• Purchasing,qualification,reverseengineeringofobsolete/hard-to-findnuclearcomponents.• Sitework(construction,installation,commissioning,service)

This has led to a company that:

• Iscosteffective(lowoverhead,mixoflaborrates)• Isflexibleandresponsive• HasnumerousstaffwithspecializedknowledgewhohaveworkedatNuclearPowerStations• Hasawiderrangeofexpertisethatareinnovative&practical(numerouspatentableitems)• Frequentlypartnerswithlargerfirmsforlargerscopeprojects

Tyne designs, fabricates and tests its products in its manufacturing facility located in Burlington, Ontario, Canada. With its sets of Quality Assurance Procedures and Workmanship that meet applicable Codes and Standards, Tyne is well suited for Commercial Grade Dedication (CGD) and Reverse-Engineering.

Within Canada, Tyne has been involved in various process design work with Candu Energy, OPG, Bruce Power, NB Power, CNL, and others. Products include SDS2 power supplies, Cover Gas Analysis carts, PHT oxygen Content Analysis carts, In-Core Amplifiers, Handheld and Wall-Mount Tritium Monitors, Getter Beds, Electrolyzers, and more.

Tyne has also performed work in USA, Korea, China, India, Rumania, Germany, France, and England, just to name a few.

59

Unified Engineering.com Corp. 171 Niagara Street, Hamilton, ON L8L 6A8 www.unifiedengineering.com Contact: Edward Veckie, Vice President T: 905-523-1700 E: [email protected]

Since 1980, Unified Engineering has built its reputation as a rapid response custom manufacturing and engineering company. As a team of licensed Professional Engineers, Technicians, and Trades we are able to provide practical solutions under quick turnaround times while ensuring quality. Our services expand to structural/pressure boundary analysis.

UniTech Services Group 138 Longmeadow Street, Suite 202, Longmeadow, MA 01106 www.unitechcdn.com Contact: Kent Anderson, Director, Canadian Operations T: 413-348-3826 E: [email protected]

UniTech Services Group began business in 1957 and was the first licensed nuclear laundry facility. UniTech’s US Locations include: Springfield MA, Royersford PA, Barnwell SC, Macon GA, Oakridge TN, Santa Fe NM, Ontario CA, and Richland WA. They service 70% of the operating reactors and 90% of the Department of Energy/Department of Defense sites in the US. Our European facilities (located in the UK and one in The Netherlands) service customers in Germany, France, Sweden, The Netherlands, Scotland, England, and Switzerland. UniTech designs, builds, and operates the most advanced, automated radiological monitoring equipment available in the world. In fifty years, we have never stopped an outage due to a shortage of protective clothing. We log over one million miles annually transporting protective clothing and have never had an incident in transit that has resulted in releasing radioactivity to the environment.

UniTech is the world’s largest supplier of nuclear protective clothing, accessories and services that are designed to provide our customers with cost effective protection for their workers with minimal generation of radioactive waste. We provide the following services: radiological laundering of protec-tive clothing, decontamination and testing of respirators, and the decontamination of tools & equipment (scaffolding, hand tools, portable HEPA vacuums, etc.) which allows for reuse as non-radioactive, or for recycling as non-radioactive scrap metal. We also provide turnkey lease and laundering services for all types of PPE. No project is too big or too small. We use 3 of our licensed decontamination facilities in the US to support Canada. We make hundreds of shipments annually and have a CNSC WNSL to support export. We can manage materials and risk from the customer site to our US facilities and as appropriate, return. Our Reduce, Reuse, and Recycle services cut costs, waste volumes, and overall risk.

Westinghouse 1000 Westinghouse Drive, Cranberry Township, PA 16066 www.westinghouse.com Contact: Craig Nitchman, Customer Account Manager T: 412-396-9878 E: [email protected]

Westinghouse provides electric utility companies around the world with the most reliable, dependable nuclear power plants, nuclear fuel, plant automation and operating plant products and services. Innovation has been the cornerstone of Westinghouse Electric Company since it was founded by George Westinghouse in 1886. Today, Westinghouse is the engine of innovation for the nuclear industry, fueled by our team of 12,000 employees globally.

At Westinghouse, we are solely focused on nuclear energy technology. Our vision is simple – to be the first to innovate the next technology, practice or solution that helps us help customers generate safer, cleaner, more reliable energy for more people and a better planet. No other company is more focused on helping utilities around the world reduce dose, enhance safety, improve outage performance and reduce maintenance costs.

When the era of nuclear energy began more than 50 years ago, we were there. Today, we’re leading the way with a new generation of nuclear technology, helping the world meet growing electricity demand with safe, clean, and reliable nuclear energy.

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Women in Nuclear Canada 150 Eglinton Ave. E., Suite 402, Toronto, ON M4P 1E8 www.wincanada.org Contact: Carly Silberstein, Executive Director T: 416.915.3020 x101 E: [email protected]

WiN (Women in Nuclear) is a world-wide association of women working professionally in various fields of nuclear energy and radiation applications.

WiN-Canada was formed in early 2004 and has been working to support the objectives of WiN-Global and emphasize and support the role that women can and do have in addressing the general public’s concerns about nuclear energy and the application of radiation and nuclear technology. WiN-Canada also works to provide an opportunity for women to succeed in the industry through initiatives such as mentoring, networking, and personal development opportunities.

Globally, the goal of WiN is to make the public aware, especially women, of the benefits of nuclear and radiation applications and of the safety that ensures protection of the public and the environment.

WiN’s principle objectives are:

1. To develop a dialogue with the public to promote awareness around the factual contribution to people and society from nuclear technologies.

2. To contribute to knowledge and experience exchange among members and chapters.

3. To promote career interest in nuclear engineering, science, technology, the trades and other nuclear-related professions, especially among women and young people.

While many of the members of WiN are employed in the nuclear energy sector, WiN-Canada welcomes members from industries who use nuclear and radiation technologies, such as hospitals and medical facilities, mining, academic and research institutions, the wider electricity sector, and the suppliers to all of these diverse industries. WiN-Canada believes its value resides in having a diverse membership representing not only skilled and technical disciplines, but also welcomes members who support the industry such as lawyers, accountants, financial professionals, sales, administration, etc.

Members of WiN all have one thing in common: they want the general public to have a better understanding of nuclear and radiation issues. WiN is open to men who support the organization’s goals.

For more information on WiN-Canada goals and objectives and guiding principles please visit our website at www.wincanada.org.

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Allport, Andrew . . . . . . . . . . . . . . . . . . . . .38

Anderson, Kent. . . . . . . . . . . . . . . . . . . . .19

Aziz, Tarek. . . . . . . . . . . . . . . . . . . . . . . . .17

Bach, Michael . . . . . . . . . . . . . . . . . . . . .36

Bennett, Perryn. . . . . . . . . . . . . . . . . . . . .45

Bereznai, George . . . . . . . . . . . . . . . . . . .26

Bhakhri, Vineet . . . . . . . . . . . . . . . . . . . . .37

Bhatia, Akash . . . . . . . . . . . . . . . . . . . . . .35

Bittnar, Zdenek . . . . . . . . . . . . . . . . . . . . .44

Brooks, Andrew. . . . . . . . . . . . . . . . . . . . .16

Brown, Ken. . . . . . . . . . . . . . . . . . . . . . . 33

Cao, Junjie . . . . . . . . . . . . . . . . . . . . . . . .44

Carmichael, Jim . . . . . . . . . . . . . . . . . . . .47

Carroll, Blair . . . . . . . . . . . . . . . . . . . . . . .33

Carter, Tom . . . . . . . . . . . . . . . . . . . . . . . .44

Chen, Edwin . . . . . . . . . . . . . . . . . . . . . . .44

Cheng, Qingwu . . . . . . . . . . . . . . . . . . . . .18

Cothron, Helen . . . . . . . . . . . . . . . . . . . . .21

Craven, Matthew. . . . . . . . . . . . . . . . . . . .45

Damies, Holger . . . . . . . . 15, 20, 28, 34, 35

Deadman, Jason. . . . . . . . . . . . . . . . . . . .15

Delshad Khatibi, Pooya . . . . . . . . . . . . . . .37

Dhaliwal, Sukhpal Singh . . . . . . . . . . . . . .15

Di ilio, Alexander. . . . . . . . . . . . . . . . . . . .37

Diab, Aya . . . . . . . . . . . . . . . . . . . . . . . . .21

Diaz, Gustavo . . . . . . . . . . . . . . . . . . . . . .34

Dixon, Chris . . . . . . . . . . . . . . . . . . . . . . .37

Djordjic, Ljubo . . . . . . . . . . . . . . . . . . . . .49

Doddihal, Preeti . . . . . . . . . . . . . . . . . . . .45

Duan, Xinjian . . . . . . . . . . . . . . . . . . . . . 48

Duval, Christophe . . . . . . . . . . . . . . . . . . .19

El-Hawary, Magdy . . . . . . . . . . . . . . . . . . .14

Farooq, Khalid . . . . . . . . . . . . . . . . . . . . .47

Faurschou, Ken. . . . . . . . . . . . . . . . . . . . .16

Feenstra, Paul . . . . . . . . . . . . . . . . . . . . .21

Ferreira, Emily. . . . . . . . . . . . . . . . . . . . . .29

Fisher, Nigel . . . . . . . . . . . . . . . . . . . . . . .44

Fourar, Carmen. . . . . . . . . . . . . . . . . 17, 18

Frappier, Gerry . . . . . . . . . . . . . . . . . . . . .30

Freeman, Tim . . . . . . . . . . . . . . . . . . . . . .34

Froats, John . . . . . . . . . . . . . . . . . . . . . . .26

Gaudet, Michel . . . . . . . . . . . . . . . . . 15, 19

Ghaforian, Allan . . . . . . . . . . . . . . . . . . . .16

Gheorghiu, Ovidiu . . . . . . . . . . . . . . . . . . .12

Gilbert, Lovell . . . . . . . . . . . . . . . . . . . . . .14

Gilbride, Kurt . . . . . . . . . . . . . . . . . . . . . .35

Gloth, Gerit. . . . . . . . . . . . . . . . . . . . . . . .28

Goel, Bob. . . . . . . . . . . . . . . . . . . . . 17, 18

Gold, Ralf . . . . . . . . . . . . . . . . . . . . . . . . .20

Guérout, Fabrice . . . . . . . . . . . . . . . . . . . .16

Gupta, Sahil . . . . . . . . . . . . . . . . . . . . . . .16

Gurevich, Alexander . . . . . . . . . . . . . . . . .20

Gurevich, Yuri . . . . . . . . . . . . . . . . . . . . . .20

Hamouda, Ouajih . . . . . . . . . . . . . . . 36, 45

Hanna, Jim. . . . . . . . . . . . . . . . . . . . . . . .29

Haq, Irfan. . . . . . . . . . . . . . . . . . . . . . . . .45

Hasanein, Hisham . . . . . . . . . . . . . . . . . .49

Hashemi, Sherri . . . . . . . . . . . . . . . . . . . .18

Hlavacek, Petr. . . . . . . . . . . . . . . . . . . . . .44

Ho, Daniel . . . . . . . . . . . . . . . . . . . . . . . .15

Hollern, Jason. . . . . . . . . . . . . . . . . . . . . .19

Hong, Andrew . . . . . . . . . . . . . . . . . . . . . .15

Horn, Joseph . . . . . . . . . . . . . . . . . . . . . .27

Hosemann, Peter . . . . . . . . . . . . . . . . . . .37

Howard, Cameron . . . . . . . . . . . . . . . . . . .37

Hudelmaier, Florian. . . . . . . . . . . . . . . . . .34

Hulcoop, Jeff . . . . . . . . . . . . . . . . . . . . . .46

Ibadula, Mioara . . . . . . . . . . . . . . . . . . . .36

Iqbal, Tahir . . . . . . . . . . . . . . . . . . . . . . . .47

Jamieson, Robert . . . . . . . . . . . . . . . . . . .15

Jansky, Andy . . . . . . . . . . . . . . . . . . . . . . .28

Janzen, Victor . . . . . . . . . . . . . . . 20, 21, 44

Johnston, Rozella . . . . . . . . . . . . . . . . . . .26

Judge, Colin . . . . . . . . . . . . . . . . . . . . . . .37

Jung, Jong Yeob . . . . . . . . . . . . . . . . . . . .33

Khan, Khurram . . . . . . . . . . . . . . . . . . . . .35

Khan, Md. Imran. . . . . . . . . . . . . . . . . . . .36

Kim, Sang-hwan . . . . . . . . . . . . . . . . . . . .36

Kirkhope, Ken. . . . . . . . . . . . . . . . . . . . . .12

Klassen, Robert J. . . . . . . . . . . . . . . . . . . .36

Knight, Jeffrey . . . . . . . . . . . . . . . . . . . . . .27

Kozluk, Michael . . . . . . . . . . . . . . . . . . . 48

Kozora, Charles . . . . . . . . . . . . . . . . . . . .49

Krause, Thomas . . . . . . . . . . . . . . . . 16, 45

Kwan, Jason . . . . . . . . . . . . . . . . . . . . . . .36

Lam, Jessica. . . . . . . . . . . . . . . . . . . . . . .45

Langenstein, Magnus . . . . . . . . . . . . . . . .28

Laxman, Sankar . . . . . . . . . . . . . . . . . . . .33

Lei, Ed . . . . . . . . . . . . . . . . . . . . . . . . . . .42

Lewis, Ross . . . . . . . . . . . . . . . . . . . . . . .46

Li, Kevin (Wenhai). . . . . . . . . . . . . . . . . . .19

Libra-Sharkey, Erica . . . . . . . . . . . . . . . . .49

Licina, George . . . . . . . . . . . . . . . . . 34, 49

Liebenow, Michael . . . . . . . . . . . . . . . . . .19

Liu, Yong Chang . . . . . . . . . . . . . . . . . . . .12

Lowndes, Lawrence. . . . . . . . . . . . . . . . . .27

Luna, Pablo . . . . . . . . . . . . . . . . . . . . . . .20

Mahmoud, Qusay . . . . . . . . . . . . . . . . . . .27

Mallampalli, Satyanarayana . . . . . . . . . . .15

Mayhew, Clinton . . . . . . . . . . . . . . . . . . . .37

McLean, Peter. . . . . . . . . . . . . . . . . . . . . .39

Meguerian, Richard. . . . . . . . . . . . . . . . . .46

Mesmous, Noreddine . . . . . . . . . . . . . . . .14

Mileta, Ernie . . . . . . . . . . . . . . . . . . . . . . .36

Montazer, Danyal . . . . . . . . . . . . . . . 17, 18

Montazer, Mike . . . . . . . . . . . . . . . . . 17, 18

Morelli, Jordan . . . . . . . . . . . . . . . . . 16, 45

Mosbrucker, Paula . . . . . . . . . . . . . . . . . .45

Mugurel Oprea, Valeriu . . . . . . . . . . . . . . .44

Naqvi, Raheel. . . . . . . . . . . . . . . . . . . . . .48

Newman, Gary . . . . . . . . . . . . . . . . . 10, 31

Newsom, Derek . . . . . . . . . . . . . . . . . . . .16

Nikic, Boris. . . . . . . . . . . . . . . . . . . . . . . .44

Nothvogel, Sven . . . . . . . . . . . . . . . . . . . .35

Nutzel, Gerhard. . . . . . . . . . . . . . . . . . . . .20

Nützel, Gerhard. . . . . . . . . . . . . . . . . . . . .15

Obrutsky, Laura. . . . . . . . . . . . . . . . . . . . .21

O’Kane, Dara . . . . . . . . . . . . . . . . . . . . . .44

Omar, Ali . . . . . . . . . . . . . . . . . . . . . . . . .33

Ortega Pelayo, Rosa Elia . . . . . . . . . . . . . .15

Ostrowski, Steve . . . . . . . . . . . . . . . . . . . .38

Ozawa, Gordon . . . . . . . . . . . . . . . . . . . . .48

Palumbo, Gino . . . . . . . . . . . . . . . . . . . . .49

Pan, Li . . . . . . . . . . . . . . . . . . . . . . . . . . .44

Parcels, Ryan . . . . . . . . . . . . . . . . . . . . . .47

Parkitny, Jerzy . . . . . . . . . . . . . . . . . . . . . .20

Patzak, Borek . . . . . . . . . . . . . . . . . . . . . .44

Perisse, Jocelyn . . . . . . . . . . . . . . . . . . . .19

Pettigrew, Michel. . . . . . . . . . . . . . . . . . . .44

Plourde, Jacques . . . . . . . . . . . . . . . . . . .48

Popp, Sebastian . . . . . . . . . . . . . . . . . . . .15

Pushee, Kevin. . . . . . . . . . . . . . . . . . . . . . .9

Ragheb, Helmy . . . . . . . . . . . . . . . . . . . . .46

Reynolds, Nigel. . . . . . . . . . . . . . . . . . . . .18

Riahinezhad, Marzieh . . . . . . . . . . . . . . . .16

Robinson, John. . . . . . . . . . . . . . . . . . . . .18

Rouison, David . . . . . . . . . . . . . . . . . . . . .16

Rouben, Benjamin . . . . . . . . . . . . . . . . . 26

AUTHOR INDEX

62

Roukema, Adam . . . . . . . . . . . . . 16, 34, 35

Ruysseveldt, Mike . . . . . . . . . . . . . . . . . . 26

Sachdev, Narendra . . . . . . . . . . . . . . . . . 15

Sainz, Ricardo . . . . . . . . . . . . . . . . . 20, 34

Salvetti, Patricia . . . . . . . . . . . . . . . . . . . 34

Sartipi, Amir . . . . . . . . . . . . . . . . . . . . . . 15

Sato, Jim . . . . . . . . . . . . . . . . . . . . . . . . 47

Sawadogo, Teguewinde . . . . . . . . . . . . . . 21

Scarth, Douglas . . . . . . . . . . . . . . . . . . . 45

Scholz, Bob . . . . . . . . . . . . . . . . . . . . . . 49

Seeberger, Erich . . . . . . . . . . . . . . . . . . . 34

Seitz, Thomas . . . . . . . . . . . . . . . . . . . . . 28

Selvaratnarajah, Srikrishnarajah . . . . . . . 20

Shawkat, Mohamed . . . . . . . . . . . . . . . . 49

Shi, Yihai . . . . . . . . . . . . . . . . . . . . . . . . 48

Singh, Harsh. . . . . . . . . . . . . . . . . . . . . . 27

Smith, Bruce . . . . . . . . . . . . . . . . . . 21, 44

Smith, Karen . . . . . . . . . . . . . . . . . . . . . 26

Speer, David. . . . . . . . . . . . . . . . . . . . . . 44

St Lawrence, Sterling . . . . . . . . . . . . . . . 36

Stepan, Jan . . . . . . . . . . . . . . . . . . . . . . 44

Stojakovic, Mike . . . . . . . . . . . . . . . . 36, 45

Stoyanov, George . . . . . . . . . . . . . . . . . . 12

Tadjalli, Mehdi . . . . . . . . . . . . . . . . . . . . 28

Tang, Preston . . . . . . . . . . . . . . . . . . . . . 35

Tapping, Robert . . . . . . . . . . . . . . . . . . . 41

Tavares, Al . . . . . . . . . . . . . . . . . . . . . . . 49

Tavares, Sid . . . . . . . . . . . . . . . . . . . . . . 45

Taylor, Colette . . . . . . . . . . . . . . . . . . . . . 44

Thompson, Jeremy . . . . . . . . . . . . . . . . . 45

Toloui, Morteza . . . . . . . . . . . . . . . . . . . . .37

Trudell, David . . . . . . . . . . . . . . . . . . . . . .20

Tse, Jefferson . . . . . . . . . . . . . . . . . . . . . .35

Tume, Pamela. . . . . . . . . . . . . . . . . . . . . .26

Tyndall, David . . . . . . . . . . . . . . . . . . . . . .30

Ulvan, Erhan. . . . . . . . . . . . . . . . . . . . . . .37

Underhill, Ross . . . . . . . . . . . . . . . . . 16, 45

Usmani, Aman . . . . . . . . . . . . . . . . . 17, 44

Veckie, Edward . . . . . . . . . . . . . . . . . . . . 29

Verzilov, Yury . . . . . . . . . . . . . . . . . . . . . . 20

Viktorov, Alexandre . . . . . . . . . . . . . . . . . 33

Vincelette, Jacques. . . . . . . . . . . . . . . . . 47

Walker, David . . . . . . . . . . . . . . . . . . . . . 28

Walker, Wendy . . . . . . . . . . . . . . . . . . . . 47

Wang, Catherine . . . . . . . . . . . . . . . . . . . 47

Wang, Hui . . . . . . . . . . . . . . . . . . . . . . . 48

Wang, Min . . . . . . . . . . . . . . . . . . . . . . . 48

Wang, Xue . . . . . . . . . . . . . . . . . . . . . . . 19

Watkins, Lee. . . . . . . . . . . . . . . . . . . . . . 19

Weaver, Angela . . . . . . . . . . . . . . . . . . . . 47

Webb, Cameron . . . . . . . . . . . . . . . . . . . 33

Wegener, Sven . . . . . . . . . . . . . . . . . . . . 35

Whalen, Rob. . . . . . . . . . . . . . . . . . . . . . 11

Wight, Jason. . . . . . . . . . . . . . . . . . . . . . 10

Wolsey, Fred . . . . . . . . . . . . . . . . . . . . . . 40

Wood, Peter . . . . . . . . . . . . . . . . . . . . . . 34

Woods, Stephen . . . . . . . . . . . . . . . . . . . 48

Wyatt, Roger . . . . . . . . . . . . . . . . . . . . . . 28

Xing, Anqing . . . . . . . . . . . . . . . . . . . . . . 27

Xu, Rui . . . . . . . . . . . . . . . . . . . . . . . . . . 18

Yang, Songyan . . . . . . . . . . . . . . . . . . . . 45

Yetisir, Metin. . . . . . . . . . . . . . . . 18, 19, 44

Zabrzycki, Krzysztof . . . . . . . . . . . . . . . . . 21

Zander, Andre . . . . . . . . . . . . . . . . . . . . . 28

Zeng, Zhaojing . . . . . . . . . . . . . . . . . . . . 12

Zhang, Changqing. . . . . . . . . . . . . . . . . . 15

Zheng, Peter . . . . . . . . . . . . . . . . . . . . . . 44

Zobin, David . . . . . . . . . . . . . . . . . . . . . . 35

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