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:
in DCs) included in the referenced DC. Additionally, a COL applicant must address requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC. Review Interfaces Other SRP sections interface with this section as follows: 1. Review of the material characteristics of the RCPB and the reactor vessel, including fracture toughness properties and the material surveillance program, is performed under SRP Sections 5.2.3 and 5.3.1. 5.3.2-3 Revision 2 - March 2007 2. Review of the overpressure protection system for consistency with the P-T limits in Appendix G to 10 CFR Part 50 is performed under SRP Section 5.2.2. 3. Review of the peak reactor vessel wall fluence for the design life of the plant is performed under SRP Section 4.3. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.55a, as it relates to quality standards for the design, fabrication, erection, and testing of SSCs important to safety. 2. 10 CFR 50.60, as it relates to compliance with the requirements of Appendix G to 10 CFR Part 50. 3. 10 CFR 50.61, as it relates to fracture toughness criteria for PWRs relevant to PTS events. 4. General Design Criterion (GDC) 1, found in Appendix A to 10 CFR Part 50, as it relates to quality standards for design, fabrication, erection, and testing. 5. GDC 14, as it relates to ensuring an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture of the RCPB. 6. GDC 31, as it relates to ensuring that the RCPB will behave in a nonbrittle manner and that the probability of rapidly propagating fracture is minimized. 7. GDC 32, as it relates to the reactor vessel materials surveillance program. 8. Appendix G to 10 CFR Part 50, as it relates to material testing and fracture toughness. 9. 10