Document: NUREG-0800
Document ID: 9099ab75-0fb9-4fa1-a9f0-ccd7fd3b6c5a
Document Type: srp
Title: FRACTURE PREVENTION OF CONTAINMENT PRESSURE BOUNDARY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340707.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.7
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Materials Engineering Branch (MTEB) Secondary - None I. AREAS OF REVIEW The reactor containment pressure boundary relates to the reactor containment system. The reactor containment system design must include the functional capa- bility of enclosing the reactor system and of providing a final barrier against the release of radioactive fission products attendant postulated accidents. This SRP section reviews fracture prevention of the reactor containment pressure boundary materials. The reactor containment system is addressed within the context of General Design Criterion (GDC) 51 of Appendix A of 10 CFR Part 50 and Section III, Subsection NE of the ASME Boiler and Pressure Vessel Code, as endorsed by 10 CFR Part 50, and stated by Standard Review Plan (SRP) Section 3.8.1, "Concrete Containment" and SRP Section 3.8.2, "Steel Containment." The reactor containment system, as addressed in the NRC licensing review process, includes (a) the containment ves- sel, (b) all penetration assemblies or appurtenances attached to the containment vessel, all piping, pumps and valves attached to the containment vessel, or to penetration assemblies out to and including the pressure boundary materials of any valves required to isolate the system and provide a pressure boundary for the containment function.' The reactor containment pressure boundary, as addressed in the NRC licensing review process, consists of those ferritic steel parts of the reactor containment system which sustain loading and provide a pressure boundary in the performance of the containment function under the operating, maintenance, testing and 'For components which also may be part of the reactor coolant pressure boundary, the provisions of 10 CFR Part 50, §50.55a are also applicable. These aspects are considered in SRP Section 5.2.3. Rev. 0 - July 1981 USNRC STANDARD REVIEW PLAN Standard review plans are prepared for the guidance of the Office of Nuclear Reactor Regulation staff