Page 55 - 2017_NAmer_Spring_TD_eCatalog

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 and 3 piping, pumps, valves and vessels in nuclear power plants.
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
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 N A-1 uality
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 A end
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 2,1 0 List Price 2,2 0
See pages 90–95 for dates and locations of ASME Public Courses
delivered in the USA during Spring 2017.
Visit go.asme.org/ENAcourses
Design in Codes, Standards and
Regulations for Nuclear Power Plant
Construction
PD632 ASME STANDARDS COURSE N UC LE A R Public Courses
The course provides details of the ASME Section III Division 1 code re-
quirements and their technical basis for the design of Class 1, 2
Topics include an 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.
Supplementary requirements imposed by regulation (regulatory guides,
standard review plan, etc.) will also be covered. The course also
discusses related ASME codes and standards such as B16, QME-1
and OM.
Each participant will receive complimentary copies of BPVC Section
III - Rules for Construction of Nuclear Facility Components - Division
1 - Subsection NB-Class 1 Components 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
• Explain how to ensure that design specifications contain the minimum
ASME requirements and how they relate to design input to a Design
Report
• Describe the methods and criteria for design by analysis and apply
pressure design equations
• Explain how to design input loads and develop the contents of an
ASME Section III Design Specification
• Explain the process and analysis and qualification for extreme loads
• Describe the design rules for the design of vessels, pumps, valves
and piping systems
Who Should A end
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, Greg Hollinger
4 Days, 3 CEUs, 30 PDHs
Member 2,67 List Price 2,87
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