ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations (Virtual Classroom)
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Length: 11 days CEUs: 3.00 PDHs: 30.00
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Course Schedule: This course is offered over the following eight days: June 7 -10 and 14-17, 2021, commencing at 9:30 AM and ending at 1:30 PM Eastern, each day, with breaks scheduled throughout.
This course is a comprehensive overview of Section III, Division 1, including interfaces with Sections II, V, IX, XI, and NQA-1. The course explains how Section III is implemented by the US NRC in its regulations, and regulatory guidance. The course also explains the Section III requirements and processes, including the requirements for design, determination of safety classification for components, quality assurance, third-party oversight by the Authorized Inspection Agency, and the duties and responsibilities of N, NA, NV and NPT certificate holders.
Students are presented with an overview of the technical bases for Section III, Class 1, design-by-analysis, the ASME Accreditation process, the requirements for the Authorized Inspection Agency, the duties and responsibilities of the Authorized Nuclear Inspector, and the Quality Assurance Program requirements for Material Organizations and ASME Certificate Holders. The course explains the Section III process for Code Cases and Code Inquiries.
Course Materials
Participants have digital access to ASME B&PVC, Section III, Subsection NCA, during the course and a downloadable version of the course presentation.
You Will Learn To:
- Describe the scope and requirements of Section III
- Describe how Section III is used by the USNRC
- Describe the differences in requirements between Class 1, 2 and 3 components
- Describe the Scope and Requirements of Sections II, V, IX, XI and NQA-1 and how they interface with Section III
- Explain the purpose of Code Cases and Code Interpretations and their use by the USNRC
- Describe the purpose of Code Data Reports
- Describe the third-party oversight functions performed by Authorized Inspection Agencies and the role of the Authorized Nuclear Inspector
- Describe the Quality Assurance Program required for Material Organizations and the Quality Assurance Program required for Certificate holders
- Explain the significance of the ASME Certification Mark
- Describe the ASME Accreditation Process, and duties and responsibilities for N, NA, NPT Certificate Holders
- Describe new initiatives being considered by the Section III Standards Committee
- Describe future global trends for nuclear generation of electric power
Who Should Attend
Entry level and experienced engineers and personnel employed by suppliers of nuclear systems and components, and operating nuclear power generation facilities that wish to gain a more in-depth understanding of Section III and how it is applied in the design and construction of components for nuclear power generation facilities.
Topics Covered
- Module 1 – Introduction to ASME Boiler and Pressure Vessel Code
- Module 2 – The ASME Code and the Interface with US Nuclear Regulatory Commission (NRC)
- Module 3 – Overview of a Pressurized Water Reactor \\
- Module 4 – Section III, Division I Subsection NCA Articles 1000 & 2000
- Module 5 – Section III, Division I Subsection NCA Articles 9000 & 8000, 3000 - 3700
- Module 6 – NCA-3800
- Module 7 – NCA-4000, 5000, 7000
- Module 8 – Nuclear Accreditation
- Module 9 – Technical Bases for Section III
- Module 10 – Subsection NB Class 1 Components
- Module 11 – Subsection NC Class 2 Components; Section III, ND Class 3 Components; Section III, NE Class MC Components
- Module 12 – Section III, NF Supports; NG Core Support Structures;
- Section III Appendices
- Module 13 – Section II, Materials; Section V, Nondestructive Examination (NDE); Section IX, Welding & Brazing Qualifications; Nuclear Quality Assurance (NQA-1)
- Module 14 – Trends for the future
Gene Imbro, P.E., has worked in the commercial nuclear power industry since 1969 and has a broad knowledge of light water reactor (LWR) designs and operation. He began his nuclear career with Combustion Engineering, a nuclear steam supply system vendor, and was involved with the design of the reactor coolant and accident mitigation systems. Mr. Imbro also worked for an architect/engineering firm as a systems designer for balance of plant and other A/E supplied systems and, for the United States Nuclear Regulatory Commission (USNRC) retiring in early 2008 after 33 years of service. During his last 17 years with the US NRC, Mr. Imbro held senior management positions including, Chief, Quality Assurance Branch, Deputy Director, Division of Engineering and Deputy Director, Division of Construction Inspection and Operational Programs.
For the last 30 years, Mr. Imbro has actively participated on ASME Nuclear Standards Committees including Sections III and XI, the ASME Operations and Maintenance Code and NQA-1. These committees are responsible for pressure boundary design, inspection, repair and replacement of components, component readiness for service, and nuclear quality assurance. He received a Certificate of Recognition from ASME in 2008 for his contribution to the Society. Following his retirement from the U.S. Nuclear Regulatory Commission.
Mr. Imbro has performed consulting work for the NRC, foreign regulators, and the World Nuclear Association and ASME in the area of Small Modular Reactors. Most recently, he has been teaching courses to foreign nuclear regulatory bodies on topics including reactor siting, nuclear quality assurance, nuclear codes and standards and reactor regulation. Mr. Imbro earned his BS in Mechanical Engineering at the Polytechnic Institute of New York University and his MS in Mechanical Engineering at Stanford University. Mr. Imbro is also a Registered Professional Engineer in New York State.
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