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Nuclear Piping Systems BPV Code,
Section III and B31.1: Design, Integrity-
Operability Assessment and Repairs
PD615 ASME Standards Course
This course provides information and instruction on the design, analysis,
and qualification of nuclear power plant piping systems that are
consistent with the ASME Boiler and Pressure Vessel Code, Section III,
Division 1, Subsections NB/NC/ND, as well as the parallel requirements
of ASME B31.1 for nuclear power plants. The methods and criteria
described throughout the course apply to new systems, as well as
modifications or repairs to existing systems.
The course also addresses the integrity assessment of degraded
nuclear piping systems (wall thinning and crack damage) using the
methods and criteria of ASME XI, operability assessment per NRC
Inspection Manual and piping repairs per ASME XI and ASME PCC-2.
The course covers (a) the code and regulatory requirements, (b) the
technical and historical basis of the requirements, and (c) best industry
practices for the correct and cost-effective design, analysis and integrity Boiler and Pressure Vessel Code.
assessment.
Each student will receive a copy of the book, Nuclear Power Plant Safety
and Mechanical Integrity: Design and Operability of Mechanical Systems,
Equipment and Supporting Structures, by George Antaki and Ramiz
Gilada
You Will Learn To
• Describe Class 1, Class 2/3, and B31.1 nuclear piping design
requirements
• Explain the differences between Class 1, Class 2/3, and B31.1
• Describe the NRC regulatory requirements related to ASME III and
B31.1 piping systems
• Evaluate normal operating loads (pressure, weight, thermal expansion)
• Evaluate postulated design loads (seismic, waterhammer, vibration,
pipe break, etc.)
• Determine how to make the correct and cost-effective decisions in
the design and modification of nuclear piping
• Evaluate corroded (wall-thinning) nuclear piping
• Evaluate crack-like flaws in nuclear piping
• Assess operability of piping systems for abnormal conditions
Who Should Attend
Engineers involved in the design, analysis, and qualification of ASME
Boiler and Pressure Vessel Code, Safety Class 1, 2 & 3 piping systems,
and ASME B31.1 for nuclear power plants.
Participants are expected to have at least one year of experience in the
design, maintenance, or operation of a nuclear power reactor facility.
Instructor George Antaki
3 Days, 2.3 CEUs, 23 PDHs
Member $2,255 / List Price $2,355
See pages 4–10 for dates and locations of ASME Public Courses
delivered in the USA during Spring 2018.
Visit go.asme.org/NAtraining
BPV Code, Section III, Division 1: NUCLEAR � PUBLIC COURSES
The Code and Regulation
PD184 ASME Standards Course
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. The course presents 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 Subsection NCA, General
Requirements for Division 1 and Division 2 of Section III of the ASME
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
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.
Instructor Gene Imbro
4 Days, 3 CEUs, 30 PDHs
Member $2,750 / List Price $2,850
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