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:
. The reviewer materials of construction information, addresses the information provided by the applicant for the the components of interest. Such information should consist of drawings, piping system diagrams and related supplemental ASHE Code Data Reports and certified material test reports. For those ferritic materials for which fracture toughness data are unavailable, or are inappropriate, the reviewer addresses the applicant's assessment of their fracture toughness based on a metallurgical characterization developed from a review of how these materials were fabricated and what thermal history they experienced during fabrication. The reviewer addresses the applicant's correlation of this information with the fracture toughness data presented in NUREG-0577 and ASME Section III, Summer 1977 Addenda, Subsection NC. The reviewer addresses the applicant's justification of the acceptability of these materials within the context of the criteria for Class 2 materials as stated in the Summer 1977 Addenda, ASME Code Section III. The reviewer verifies that the Class 2 requirements of the Summer 1977 Addenda of ASME Section III code have been met by the applicant. IV. EVALUATION OF FINDINGS The reviewer verifies that information provided by the applicant through construction drawings, piping system diagrams and related supplemental information, ASME Code Data Reports and certified material test reports, is sufficient to support the statements and conclusions in the staff's safety evaluation report: 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