Document: NUREG-0800
Document ID: 9b735916-a58a-4bd3-b7e0-826b84cb6e43
Document Type: srp
Title: FRACTURE PREVENTION OF CONTAINMENT PRESSURE BOUNDARY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070465.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.7
CFR Part: 
CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Materials and Chemical Engineering Branch (EMCB)(MTEB) 1 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 capability of enclosing the reactor system and of providing a final barrier against the release of radioactive fission products attendant to postulated accidents. This SRP section reviews fracture prevention of the reactor 2 containment pressure boundary materials. The review of the reactor containment system is addressed further within the context of General 3 Design Criterion (GDC) 51 of Appendix A of 10 CFR Part 50 and Section III, Division 1,4 Subsection NE of the ASME Boiler and Pressure Vessel Code (Reference 8) , as endorsed by 10 5 CFR Part 50, and stated byreflected in Standard Review Plan (SRP) Section 3.8.1, "Concrete 6 7 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 vessel, and (b) all 8 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. 1 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 DRAFT Rev. 1 - April 1996 6.2.7-2 provide a pressure boundary in the performance of the containment function under the operating, maintenance, testing and postulated accident conditions cited by GDC 51. Within this context, typically reviewed are the ferritic materials of components such as freestanding containment vessels, equipment hatches, personnel airlocks,