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:
ign Criterion 16, as it relates to the prevention of the release of radioactivity to the environment.19 For components which also may beperform 1 other pressure-retaining functions important to safety in addition to comprising a part of the containment pressure boundary (e.g., part of the reactor coolant pressure boundary), the provisions of 10 CFR Part 50, §50.55a are also applicable. These aspects are considered in other SRP sSections such as 5.2.3.20 3. General Design Criterion 51, as it relates to the reactor containment pressure boundary being designed with sufficient margin to assure that under operating, maintenance, testing, and postulated accident conditions (1) its ferritic materials behave in a nonbrittle manner and (2) the probability of rapidly propagating fracture is minimized. 6.2.7-3 DRAFT Rev. 1 - April 1996 To meet the requirements of GDC 1, 16 and 51, ferritic containment pressure boundary materials should meet the fracture toughness criteria and requirements for testingfor Class 2 components identified in Article NE-2300 of Section III, Division 1 of the ASME Code or, for materials that were not fracture toughness tested as discussed below, the fracture toughness criteria for Class 2 components identified in the Summer 1977 Addenda tothe Summer 1977 Addenda of Section 21 III, Division 1, Subsection NC (Reference 7) of the ASME Code. These criteria were selected 22 to provide for a uniform review, consistent with the safety function of the containment pressure boundary within the context of Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants." The consistency is developed in that the containment system is addressed in the licensing review process as an engineered safety feature, as is, for example, the emergency core cooling system. Regulatory Guide 1.26 is silent with respect to the containment pressure boundary, but does assign Group B