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:
priate) 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. OR33 DRAFT Rev. 1 - April 1996 6.2.7-6 For ferritic reactor containment pressure boundary materials that were not fracture toughness tested, Bbased on the licensing process review of the 34 applicant's available fracture toughness data, metallurgical characterizations of the materials of interest developed from their fabrication and thermal histories,35 and correlations of metallurgical histories with fracture toughness data presented in NUREG-0577 and ASME Code Section III, SUMMERSummer 1977 36 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."37 The staff concludes that reasonable assurance has been provided that the materials of the reactor containment pressure boundary, under operating, maintenance, testing and postulated accident conditions, will not undergo brittle fracture, 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.38 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.39 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications