ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations (Virtual Classroom)

Length:  days  CEUs:   PDHs: 

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.