Description
ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations
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| Settings | ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations remove | ASME BPV Code, Section VIII, Division 1: Design and Construction remove | ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations remove | B31.8 Gas Transmission & Distribution Piping System remove | Fundamentals of Pumps and Their Selection for Optimum System Performance remove | Comparison of Global Quality Assurance and Management System Standards Used for Nuclear Applications remove |
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| Name | ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations remove | ASME BPV Code, Section VIII, Division 1: Design and Construction remove | ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations remove | B31.8 Gas Transmission & Distribution Piping System remove | Fundamentals of Pumps and Their Selection for Optimum System Performance remove | Comparison of Global Quality Assurance and Management System Standards Used for Nuclear Applications remove |
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| Price | 50.00 EGP | 700.00 EGP | 700.00 EGP | 4,800.00 EGP | 250.00 EGP | 6,000.00 EGP |
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| Description | The course explains how Section III is implemented by the US NRC in its regulations, and regulatory guidance. The course also explains the Section III requirements and processes, including the requirements for design, determination of safety classification for components, quality assurance, third-party oversight by the Authorized Inspection Agency, and the duties and responsibilities of N, NA, NV and NPT certificate holders. | |||||
| Content | ASME BPV Code Section III, Division 1: Rules for Construction of Nuclear Facility Components and USNRC Regulations | This course is a comprehensive introduction to the requirements of Section VIII, Division 1 including background, organization, design, materials, fabrication, inspection, testing and documentation of pressure vessels. It covers the more commonly applied subsections and paragraphs, and includes a practical discussion of individual problems and situations. Designed primarily for beginners, experienced vessel designers who would like to update their knowledge of the Code will also benefit from attending. | This course is a comprehensive overview of Section III, Division 1, including interfaces with Sections II, V, IX, XI, and NQA-1. The course explains how Section III is implemented by the US NRC in its regulations, and regulatory guidance. The course also explains the Section III requirements and processes, including the requirements for design, determination of safety classification for components, quality assurance, third-party oversight by the Authorized Inspection Agency, and the duties and responsibilities of N, NA, NV and NPT certificate holders. | The course introduces the requirements of the ASME B31.8 – Gas Transmission and Distribution Piping Systems Code. It covers the scope of B31.8, including its history, the types of systems to which it applies, its organization, and the intended use of the Codebook. | This course covers the nature of pumps and valves and how they interact for optimum system performance. It will help participants develop a full understanding of how pumps and valves work, covering selection, installation, operation, maintenance, and trouble shooting. During the course participants receive guidance in making cost-effective decisions on the sizing of a pipeline diameter and tips for avoiding poor system operation. | Upon completion of this intermediate-level course, managers, engineers and program developers will have a better understanding of the major international Nuclear Quality Assurance Standards and how they relate and interact.This online, instructor-supported course is designed for engineers, managers and quality personnel who are or will be directly or indirectly involved in manufacturing, fabrication and examination of components or structures for nuclear power facilities. |
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