Section XI: Rules for Inservice Inspection and Tests of Nuclear Power Plant Components


This chapter discusses the general requirements of Section XI of the ASME Boiler and Pressure Vessel Code that are applicable to all Code Classes of components, including steel vessels, piping, pumps, and valves, as well as concrete structures. It identifies the limits of applicability of Section XI—that is, elements that are within and elements that are outside the scope of the Code. Interfaces with any applicable regulatory requirements are addressed, and use of Code Editions and Addenda and Code Cases is explained. In addition, this chapter describes periodic nondestructive examination and pressure testing used to ensure the integrity of components (other than containment vessels) within the scope of the Code’s jurisdiction. The requirements of nondestructive examination (NDE) are specified, ranging from personnel qualification to the overall conduct of the examinations, as are the types of NDE required, including sample expansion, and the frequency of examinations required, such as from the detection of defects. Periodic pressure testing and pressure tests following repair/replacement activities are addressed, although the latter are addressed in Chapter 28 of this book. The responsibilities and Quality Assurance (QA) Program requirements of the different entities involved in the examination and testing of a nuclear power plant are also addressed in this chapter. Controversial issues and topics of current concern, including the applicability of recent United States Nuclear Regulatory Commission (USNRC) Generic Letters and Information Notices, are addressed, and ways in which the reader can use recent Section XI revisions to his or her advantage are described. As a benefit to the reader, this chapter references some published ASME interpretations to explain how the Code requirements can be applied to commonly-encountered problems.

29.4Article IWA-1000: Scope and Responsibility
29.5Article IWA-2000: Examination and Inspection
29.6IWA-2300: Qualifications of Nondestructive Examination Personnel
29.7Mandatory Appendix VII: Qualification of Nondestructive Examination Personnel for UT
29.8IWA-2400: Inspection Program
29.9IWA-2420: Inspection Plans and Schedules
29.10IWA-2430: Inspection Intervals
29.11IWA-2440: Application of Code Cases
29.12IWA-2500: Extent of Examination
29.13IWA-2600: Weld Reference System
29.14Subsections IWB/IWC/IWD/IWE/IWF/IWL: Requirements for Class 1, 2, 3, MC, and CC Components and Supports
29.15Exemptions from the Examination Requirements
29.16Class 1, 2, and 3 Components and Their Supports Exempt from Examination
29.17Class MC Components and Liners of Class CC Components Exempt from Examination
29.18Portions of Reinforced Concrete Containment Vessels and Their Posttensioning Systems Exempt from Examination
29.19IWF-1300: Component Support Examination Boundaries
29.20IWB/IWC/IWD/IWE/IWF-2000: Examination and Inspection
29.21Combining Preservice Examinations with Construction Code Shop and Field Examinations
29.22IWE-2300: Visual Examination, Personnel Qualification, and the Responsible Individual
29.23IWL-2300: Visual Examination, Personnel Qualification, and the Responsible Engineer
29.24IWB/IWC/IWD/IWE/IWF/IWL-2400: Inspection Schedule
29.25IWL-2400: Inspection Schedule
29.26IWB/IWC/IWD/IWE/IWF-2420: Successive Inspections
29.27IWB/IWC/IWD/IWE/IWF-2430: Additional Examinations
29.28IWB/IWC/IWD/IWE/IWF-2500: Examination and Pressure Test Requirements
29.29Unique Aspects of Containment Vessel Examination
29.30IWL-2500: Examination Requirements
29.31Unique Aspects of the Component Support Examination
29.32IWA-5000: System Pressure Tests
29.33IWA-5110: Periodic System Pressure Tests
29.34IWA-5120: System Pressure Tests for Repair/Replacement Activities
29.35IWA-5200: System Test Requirements
29.36IWA/IWB/IWC/IWD-5220: Test Pressurization Boundaries
29.37IWA-5240: Visual Examination
29.38IWA-5250: Corrective Action
29.39IWA-5260: Instruments for System Hydrostatic Tests
29.40IWA-5300: Test Records
29.41IWA-6000: Records and Reports
29.42IWA-6300: Retention
29.43Risk-Informed Inservice Inspection
29.44High-Temperature Gas-Cooled Reactors

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