Document: NUREG-0800
Document ID: 56b685cb-9a03-4a1a-a356-fa81af405cb6
Document Type: srp
Title: REACTOR COOLANT PRESSURE BOUNDARY INSERVICE INSPECTION AND TESTING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340602.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.2.4
CFR Part: 
CFR Title: 

Content:
Code con- stitutes an acceptable basis for satisfying in part the requirements of General Design Criterion 32. The staff concludes that the inservice program is acceptable and.meets the inspection and testing requirements of General Design Criterion 32 and 10 CFR Part 50, Section 50.55a. This conclusion is based on the applicant's or licensee's meeting the requirements of the ASME Boiler and Pressure Vessel Code, Section XI, as reviewed by the staff and determined to be appropriate for this application. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regard- ing the NRC staff's plan for using this SRP section. Except in those cases in which the applicant or licensee proposes an acceptable alternative method for complying with the specified portions of the Commission's regulations, the methods described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules are defined in Section 50.55a of 10 CFR Part 50. Rev. 1 - July 1981 5.2.4-6 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 32, "Inspection of Reactor Coolant Pressure Boundary." 2. ASME Boiler and Pressure Vessel Code, Section III, "Nuclear Power Plant Components," and Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," Division 1, "Rules for Inspection and Testing of Components of Light-Water Cooled Plants," American Society of Mechanical Engineers. Rev. 1 - July 1981 5.2.4-7