training & development
PD184 - BPV Code, Section III, Division 1: The Code and Regulation

PD184 - BPV Code, Section III, Division 1: The Code and Regulation

Date & Location   Member Price List Price Qty

Chicago, IL, USA
May 14, 2018 - May 17, 2018




Length: 4 days    CEUs: 3.00    PDHs: 30.00

This course is a comprehensive overview of Section III, Division 1, including interfaces with Sections II, V, IX, XI, NQA-1, and US NRC regulations, and regulatory guidance.  The course explains the Section III requirements and processes, including the requirements for design, quality assurance, third-party oversight by the Authorized Inspection Agency, and the duties and responsibilities of N, NA, 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, and the Quality Assurance Program requirements for Material Organizations and ASME Certificate Holders.  The course includes an overview of the classification of nuclear components, and the use of Code Cases and Inquiries.

Each participant will receive a copy of ASME B&PVC, Section III, Subsection NCA: General Requirements for Division 1 and Division 2.

You Will Learn To:
 - Describe the scope and requirements of Section III
 - Explain how Section III interfaces with Sections II, V, IX, XI and NQA-1
 - Explain the purpose of Code Cases and their use by regulatory bodies
 - 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 ASME Code Stamps and the new ASME Certification Mark
 - Describe the ASME Accreditation Process, and duties and responsibilities for N, NA, NPT Certificate Holders
 - Describe new initiatives being considered by Section III to assist international users
 - Describe future global trends for nuclear generation of electric power

Please click HERE to view the course outline.

Who Should Attend
Managers, engineers, quality assurance and inspection personnel involved in the design, fabrication and installation of components in nuclear facilities.  Experienced and entry-level personnel who want to gain an understanding of Section III of the ASME Boiler and Pressure Vessel Code and its application in nuclear facilities.

For venue information, please click HERE.

Please click HERE to register for this course in Europe.

  • Course Type: Public Course
  • Course Number: PD184
  • Language: English
Final invoices will include applicable sales and use tax.


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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