Document: NUREG-0800
Document ID: 29ea352c-081e-469e-95b8-7278f6da64ce
Document Type: srp
Title: FRACTURE PREVENTION OF CONTAINMENT PRESSURE BOUNDARY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0636/ML063600407.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.7
CFR Part: 
CFR Title: 

Content:
ittle fracture, and that the probability of rapidly propagating fracture will be minimized, so that the requirements of General Design Criteria 1, 16, and 51 will be met. This conclusion is summarized as follows (provide the finding that applies): Based on its review, the staff finds that the ferritic materials of the reactor containment pressure boundary were (or will be where appropriate) acceptably tested and demonstrated to meet the fracture toughness requirements for Class MC components as specified in Article NE-2300 of ASME Code Section III, Division 1 or Class CC components as specified in Article CC-2520 of ASME Code Section III, Division 2. OR For ferritic reactor containment pressure boundary materials that were not fracture toughness tested, based on the licensing process review of the applicant's available fracture toughness data, metallurgical characterizations of the materials of interest developed from their fabrication and thermal histories, and correlations of metallurgical histories with fracture toughness data presented in NUREG-0577 and ASME Code Section III, Summer 1977 Addenda, Subsection NC, the conclusion is made that the fracture toughness of the materials of the reactor containment pressure boundary meet the fracture toughness requirements invoked for ASME Code Section III Class 2 materials effective with the Summer 1977 Addenda. 6.2.7-7 Revision 1 - March 2007 For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff's evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10