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:
however, to ensure these COL action items are addressed during a COL application, they should be added to the DC FSAR. For review of a COL application, the scope of the review is dependent on whether the COL applicant references a DC, an early site permit (ESP) or other NRC approvals (e.g., manufacturing license, site suitability report or topical report). For review of both DC and COL applications, SRP Section 14.3 should be followed for the review of ITAAC. The review of ITAAC cannot be completed until after the completion of this section. IV. EVALUATION FINDINGS The reviewer verifies that the applicant has provided sufficient information and that the review and calculations (if applicable) support conclusions of the following type to be included in the staff's safety evaluation report. The reviewer also states the bases for those conclusions. For the reasons set forth above, the staff concludes that the structural integrity of the reactor vessel is acceptable and meets the requirements of General Design Criteria 1, 4, 14, 30, 31, and 32 of Appendix A of 10 CFR Part 50; the requirements of 10 CFR Part 50, Appendix B; the requirements of 10 CFR 50.60 and associated Appendices G, and H; the requirements of 10 CFR 50.55a; and for PWRs, the requirements of 10 CFR Revision 2 - March 2007 5.3.3-8 50.61. This conclusion is based on the staff's review of the safety analysis report (SAR), conducted in accordance with the following standard review plan sections, and supplemented by the acceptance criteria of SRP Section 5.3.3: (1) SRP Section 5.2.3, “Reactor Coolant Pressure Boundary Materials.” (2) SRP Section 5.2.4, “Reactor Coolant Pressure Boundary Inservice Inspection and Testing.” (3) SRP Section 5.3.1, “Reactor Vessel Materials.” (4) SRP Section 5.3.2, “Pressure-Temperature Limits and Pressurized Thermal Shock.” (5) SRP Section 3.13, “Threaded Fasteners - ASME Code Class 1, 2, and 3.” We have reviewed all factors contributing to the structural