May 19 - 22, 8 a.m. to 5 p.m.|
** Earn 30 PDHs **
While not an in-depth review of design, fabrication, inspection, quality assurance, or other technical requirements, every Subsection in Section III is covered in sufficient detail to provide an understanding of the Code processes and methodology, including the ASME Accreditation processes. The Course provides valuable and useful information about the Nuclear Code for nuclear regulators, technical organizations, nuclear generating facility owners, equipment and material organizations, installers, and authorized inspection agencies.
The course also provides insights into the regulatory significance and application of Section III and other ASME Codes included in the USNRC's regulation 10CFR 50.55a, the regulatory significance of Code Cases and Code Inquiries, and a discussion on the use of Code alternatives, as permitted by the NRC's regulations. Participants will also learn about the USNRC's 10CFR Part 21 and 10CFR50.55(e) reporting requirements.
Reference material includes background material on the development of the ASME Boiler and Pressure Vessel Code, a summary of the Subsections of the ASME Boiler and Pressure Vessel (B&PV) Code, Section III, the ASME Accreditation process, and the course presentation material.
You Will Learn To:
- Describe the contents of Section III, including its current scope and exclusions
- Explain how the Code is adopted by NRC and its regulatory significance
- Describe NRC's acceptance of Code Cases
- Explain the reporting requirements of NRC's 10CFR Part 21 and 10CFR50.55(e)
- Describe the functions performed by Authorized Inspection Agencies and Authorized Nuclear Inspectors
- List the Quality Assurance requirements as they apply to Material Organizations and N-Certificate holders
- Explain the use and significance of ASME Code Stamps and the new ASME Code Stamp
- Describe the Process for ASME Accreditation
- List the responsibilities of various ASME Certificate Holders
- Describe the purpose of the different Code Data Reports and their required signatories
- Explain how Section III, interfaces with Sections II, V, and IX
- Explain how the ASME Code is becoming a global standard
- Relate future trends in nuclear power development
Who Should Attend
Mechanical and mechanical system design engineers, plant systems engineers, and QA and inspection personnel. 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.
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
Module 5 Nuclear Accreditation
Module 6 Technical Bases for Section III
Module 7 Subsection NB Class 1 Components
Module 8 Subsection NC Class 2 Components; Section III, ND Class 3 Components; Section III, NE Class MC Components
Module 9 Section III, NF Supports; NG Core Support Structures; NH Class 1 Components Elevated Temperature Service; Appendices
Module 10 Section II, Materials; Section V, Nondestructive Examination (NDE); Section IX, Welding & Brazing Qualifications; Nuclear Quality Assurance (NQA-1)
Module 11 Trends for the future
Gene Imbro 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.
For the last 17 years, with the USNRC, Mr. Imbro held senior management positions and was involved in the resolution of numerous and varied issues across many technical disciplines. He has also served on many technical standards writing committees sponsored by the American Society of Mechanical Engineers (ASME) and the American Nuclear Society (ANS). For the last 20 years, Mr. Imbro has actively participated on ASME Committees dealing with pressure boundary design and repair, operations and maintenance, and nuclear quality assurance. He received a Certificate of Recognition from ASME in 2008. In 2007, he participated along with a multi-national group on an International Atomic Energy Agency (IAEA) committee developing a generic systems safety classification standard that would be applicable to all reactor types.
Through his participation in the Nuclear Energy Agency sponsored Multi-National Design Evaluation Program (MDEP), Mr. Imbro gained some familiarity with the regulatory frameworks and practices of some other countries, including France, England, Korea, Japan, Canada, South Africa and Finland. For the two-years immediately prior to his retirement, Mr. Imbro held the position of Deputy Director, Division of Construction Inspection and Operational Programs in the Office of New Reactors. Following his retirement from the U.S. Nuclear Regulatory Commission in Feb of 2008, Mr. Imbro has performed consulting work for the NRC, other foreign regulators, and reactor vendors. 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.
Idaho Innovation Center
2300 N. Yellowstone Hwy., Ste. 100
Idaho Falls, ID 83401
|Kid Friendly: No|
|Dog Friendly: No|
|Wheelchair Accessible: Yes!|