Document: NUREG-0800
Document ID: 6a2cfd91-f202-4240-9d1c-0e5ba76660e5
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550066.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
TESTING REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of component integrity issues related to reactor coolant pressure boundary Secondary - Organization responsible for component integrity issues related to reactor vessels. I. AREAS OF REVIEW Components that are part of the reactor coolant pressure boundary (RCPB) must be designed to permit periodic inspection and testing of important areas and features to assess their structural and leaktight integrity. Inservice inspection (ISI) programs are based on the requirements of 10 CFR 50.55a, “Codes and Standards,” in that Code Class 1 components, as defined in Section III of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereinafter “the ASME Code”), meet the applicable inspection requirements set forth in Section XI of the ASME Code, “Rules for Inservice Inspection of Nuclear Power Plant Components.” Inservice inspection includes a pre-service examination prior to initial plant startup as required by Subsubarticle NB-5280 of Section III, Division 1, of the ASME Code, “Rules for Construction of Nuclear Facility Components. The specific areas of review are as follows: 1. System Boundary Subject to Inspection. The ISI program for those portions of the RCPB consisting of Code Class 1 components, other than steam generator tubes, is reviewed. 5.2.4-2 Revision 2 - March 2007 2. Accessibility. The descriptive information that pertains to the general and specific provisions for access to components covered by the ASME Code, Section XI, is reviewed. In addition, the remote access equipment needed to perform inspections in a radiation field or areas not readily accessible to inspection personnel is reviewed. 3. Examination Categories and Methods. The descriptive information that pertains to Section XI of the ASME Code, Subsection IWA, “General Requirements,” and Subsection IWB, “Requirements for Class 1 Components of Light-Water Cooled Power