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
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CFR Title: 

Content:
tance 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 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR Part 50, §50.55a, Codes and Standards. 2. 10 CFR Part 50, Appendix A, General Design Criterion 1, “Quality Standards and Records.” 3. 10 CFR Part 50, Appendix A, General Design Criterion 16, “Containment Design.” 4. 10 CFR Part 50, Appendix A, General Design Criterion 51, “Fracture Prevention of Containment Pressure Boundary.” 5. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 6. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, “Class MC Components,” American Society of Mechanical Engineers. 7. ASME Boiler and Pressure Vessel Code, Section III, Division 2, “Code for Concrete Reactor Vessels and Containments,” American Society of Mechanical Engineers. 8. ASME Boiler and Pressure Vessel Code, Section III, Division 1, Summer 1977 Addenda, Subsection NC, “Class 2 Components”, American Society of Mechanical Engineers. 9. NUREG-0577 Revision 1, “Potential for Low Fracture Toughness and Lamellar Tearing on PWR Steam Generator and Reactor Coolant Pump Supports,” USNRC, October 1983. 6.2.7-8 Revision 1 - March 2007 10. Regulatory Guide 1.26, “Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power