Document: NUREG-0800
Document ID: c9c204f0-a162-491c-8c25-ee0418212f29
Document Type: srp
Title: PRESSURE-TEMPERATURE LIMITS, UPPER-SHELF ENERGY, AND PRESSURIZED
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380185.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.2
CFR Part: 
CFR Title: 

Content:
tion apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision.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 52.47, “Contents of Applications.” 2. 10 CFR 50.55a, “Codes and Standards.” 3. 10 CFR 50.60, “Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation.” 4. 10 CFR 50.61, “Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.” 5. 10 CFR Part 50, Appendix A, General Design Criterion 1, “Quality Standards and Records.” 6. 10 CFR Part 50, Appendix A, General Design Criterion 14, “Reactor Coolant Pressure Boundary.” 7. 10 CFR Part 50, Appendix A, General Design Criterion 31, “Fracture Prevention of Reactor Coolant Pressure Boundary.” 8. 10 CFR Part 50, Appendix A, General Design Criterion 32, “Inspection of Reactor Coolant Pressure Boundary.” 5.3.2-15 Revision 2 - March 2007 9. 10 CFR Part 50, Appendix G, “Fracture Toughness Requirements.” 10. 10 CFR Part 50, Appendix H, “Reactor Vessel Material Surveillance Program Requirements.” 11. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants.” 12. 10 CFR 52.97, “Issuance of Combined Licenses.” 13. ASME Boiler and Pressure Vessel Code, Section III, including Appendix G, “Protection Against Nonductile Failure,” American Society of Mechanical Engineers. 14. ASME Boiler and Pressure Vessel Code, Section XI, Division 1, Appendix G, “ Fracture Toughness Criteria for Protection Against Failure,” American Society of Mechanical Engineers. 15. Branch Technical Position BTP 5-3, “Fracture Toughness Requirements”. 16. ORNL/NRC/LTR-03/03, “Tabulation of Thermally-Induced Stress Intensity Factors (KIT) and Crack Tip Temperatures for Generating P-T Curves per ASME Section XI - Appendix G.” 17. Regulatory Guide 1.99, “Radiation Embrittlement of