Document: NUREG-0800
Document ID: 4a96f7f8-16d2-41a4-a436-12b528d783d7
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190008.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
CFR Part: 
CFR Title: 

Content:
ns 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulations and regulatory guide. VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR 50.60, “Acceptance Criteria for Fracture Prevention Measures for Light-water Nuclear Power Reactors for Normal Operation.” 3. 10 CFR 50.61, “Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.” Revision 2 - March 2007 5.3.3-10 4. 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records.” 5. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases.” 6. 10 CFR Part 50, Appendix A, GDC 14, “Reactor Coolant Pressure Boundary.” 7. 10 CFR Part 50, Appendix A, GDC 30, “Quality of Reactor Coolant Pressure Boundary.” 8. 10 CFR Part 50, Appendix A, GDC 31, “Fracture Prevention of Reactor Coolant Pressure Boundary.” 9. 10 CFR Part 50, Appendix A, GDC 32, “Inspection of Reactor Coolant Pressure Boundary.” 10. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 11. 10 CFR Part 50, Appendix G, “Fracture Toughness Requirements.” 12. 10 CFR Part 50, Appendix H, “Reactor Vessel Material Surveillance Program Requirements.” 13. Regulatory Guide 1.99, Revision 2, “Radiation Embrittlement of Reactor Vessel Materials.” 14. ASME Boiler and Pressure Vessel Code, Sections II, III, V,