ASME Section III: Rules for Construction of Nuclear Power Plant Components
Introduction
ASME Section III: Rules for Construction of Nuclear Power Plant Components
Course Objectives:
You Will Learn To:
- Describe the scope and requirements of Section III
- Describe how Section III is used by the USNRC
- Describe the differences in requirements between Class 1, 2 and 3 components
- Describe the Scope of Sections II, V, IX, XI and NQA-1 and how they interface with Section III
- Explain the purpose of Code Cases and Code Interpretations and their use by the USNRC
- 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 Certificate holders
- Explain the significance of the ASME Certification Mark
- Describe the ASME Accreditation Process, and duties and responsibilities for N, NA, NPT Certificate Holders
- Describe new initiatives being considered by the Section III Standards Committee
- Describe future global trends for nuclear generation of electric power
Who Should Attend
Entry level and experienced engineers and personnel employed by suppliers of nuclear systems and components, and operating nuclear power generation facilities that wish to gain a more in-depth understanding of Section III and how it is applied in the design and construction of components for nuclear power generation facilities.
Course Outline:
Introduction to ASME & the Boiler and Pressure Vessel Code
- Overview of a Pressurized Water Reactor
- The ASME Code and Regulatory Agencies -- US NRC
- Section III Division 1 Scope, Components, Classes NCA, NB, NCD, NE, NF, NG
Subsection NCA Requirements
- NCA-1000 Scope
- NCA-2000 Classification and "Importance to Safety" (Class 1, 2, 3, MC, CS, NS)
- NCA-3000 Duties and Responsibilities and Section XI Inservice Inspection
- NCA-4000 QA and NQA-1
- NCA-5000 Authorized Inspection, 7000 Reference Standards
- NCA-8000 Certification and Stamping and Nuclear Accreditation
- NCA-9000 Glossary
Subsection NB - Construction of Class 1 Components
- Section III Basis
- NB-1000 Introduction
- NB-2000 Materials and BPVC Section II Parts A, B, C, D
- NB-3000 Design (Vessels, Pumps, Valves, Piping)
- NB-4000 Fabrication/Installation and BPVC Section IX Welding/Brazing Qualifications
- NB-5000 Nondestructive Examination (“NDE”) and BPVC Section V NDE
- NB-6000 Testing
- NB-7000 Overpressure Protections, (8000 Certification and Stamping)
NCD Class 2&3 Components (Vessels, Pumps, Valves, Piping, Storage Tanks)
NF Supports and NG Core Support Structures
NE Class MC (“Metal Containment”)
Course Wrap-up
- ASME Nuclear Accreditation
- Computer Usage responsibility – ASME NQA-1 3-400 and Subpart 2.7
- ASME Section XI, Division 1: Rules for Inservice Inspection and Testing of Components of Light Water-Cooled Plants
- US Nuclear Regulation Guides and Laws
- Review learning outcomes