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Overview of Codes and Standards for
Nuclear Power Plants
PD633 ASME Standards Course
This course introduces mechanical and civil engineers to ASME, its
codes and standards and the ASME Boiler and Pressure Vessels
(B&PV) Code as it applies to nuclear facilities. It provides an overview
of Sections III and XI of the B&PV Code as well as the Guides for the
Operation and Maintenance for Nuclear Power Plants. This course also
reviews Sections II, V and IX as they apply to nuclear facilities.
This course also discusses the NQA-1 Quality Assurance for Nuclear
Facility Applications Standard. Other topics include a brief history of the QME-1 and OM.
B&PV Code, the ASME Boards and Committees (including the Board
on Nuclear Codes and Standards), international activity in the area of
nuclear codes and ASME Nuclear Accreditation.
You Will Learn To
• Describe the scope of ASME codes and standards applicable to
construction of pressure-retaining components
• Explain the purpose, organization and requirements in Sections III and
XI of the ASME Boiler and Pressure Vessel (B&PV) Code, including the
requirements and process for ASME Nuclear Accreditation
• Explain the purpose, organization and requirements of NQA-1 Quality
Assurance for Nuclear Facility Applications and the OM Standards and
Guides for the Operation of Nuclear Power Plants
• Describe the purpose, organization and requirements in Sections II, V
and IX as they apply to nuclear facility construction
Who Should Attend
Engineers and managers involved in the design, analysis, and
construction of nuclear facilities as well as operations and maintenance,
quality assurance and quality control programs, inspection, procurement,
product design, process engineering and project management
Instructor William K. (Ken) Sowder
3 Days, 2.3 CEUs, 23 PDHs
Member $2,255 / List Price $2,355
ASME Book of Interest
Containment Structures of US Nuclear
Power Plants
Hansraj Ashar
332 pp ISBN: 9780791860175
Print Book Member $149 / List Price $199
Order Number: 860175
Toward Consistent Design Evaluation of
Nuclear Power
Piping by Nonlinear Finite Element Analysis
(2015)
Lingfu Zeng, Lennart Jansson and Nils-Erik Wiberg
80 pp ISBN: 9780791861042
Print Book Member $79 / List Price $99
Order Number: 861041
GET MORE INFORMATION AT ASME.ORG
Visit go.asme.org/NAtraining
Design in Codes, Standards & Regulations
for Nuclear Power Plant Construction
PD632 ASME Standards Course
The course provides details of the ASME Section III Division 1 code NUCLEAR � PUBLIC COURSES
requirements and their technical basis for the design of piping, pumps,
valves and vessels in nuclear power plants. Topics include overview
of the ASME Section III design requirements, methods of analysis and
qualification criteria for each type of component, design by rule, design
by analysis and qualification by testing, and supplementary requirements
imposed by regulation (regulatory guides, standard review plan, etc.).
The course also covers related ASME codes and standards such as B16,
Each student will receive complementary copies of BPVC Section
III - Rules for Construction of Nuclear Facility Components - Division
1 - Subsection NC: Class 2 Component and BPVC Section III - Rules for
Constructions of Nuclear Facility Components-Subsection NCA - General
Requirements for Division 1 and Division 2.
You Will Learn To
• Identify Regulatory requirements and explain how they affect the
contents of a Section III, Division 1 Component Design Specification
• Define requirements and loads and develop the contents of an ASME
Section III Design Specification to ensure that a Section III Division
1 Component Design Specification contains the minimum ASME
requirements
• Apply the methods and criteria for design-by-rule and design-by-
analysis, and the relationship between rules and analysis, such as
using finite element methods
• Apply the NC-3000 design rules and analyses in conjunction with the
“design-construction interfaces” in NC-1000, -2000, -4000, -5000,
-6000, -7000, -8000
• Apply the process and analysis and qualification for the Design,
Operating Levels A, B, C and D and Test loadings and determine
or explain how the results are reported in a Section III Division 1
Component Design Report
• Describe key differences and similarities between Class 1, 2 and 3
Components
Who Should Attend
Engineers, managers and quality personnel and inspectors involved
in the design, analysis or fabrication of components or structures for
nuclear power plants.
Instructors George Antaki or Greg Hollinger
4 Days, 3 CEUs, 30 PDHs
Member $2,750 / List Price $2,850
See pages 4–10 for dates and locations of ASME Public Courses
delivered in the USA during Spring 2018.
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