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:
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 mater als effective with the Summer 1977 Addenda." 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 6.2.7-3 Rev. 0 - July 1981 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. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described.herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides and NUREGs. VI. REFERENCES 1. 10 CFR Part 50 Appendix A, General Design Criterion 1, "Quality Standards and Records." 2. 10 CFR Part 50 Appendix A, General Design Criterion 16, "Containment Design." 3. 10 CFR Part 50 Appendix A, General Design Criterion 51, "Fracture Prevention of Containment Pressure Boundary." 4. ASME Code Section III, Summer 1977 Addenda, Subsection NC. 5. NUREG-0577, "Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant ump Supports," USNRC, October 1979 (Draft). 6. Regulatory Guide 1.26, "Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power