Document: NUREG-0800
Document ID: f5ae448a-20e3-4127-90a9-888a9b291921
Document Type: srp
Title: REACTOR VESSEL INTEGRITY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340640.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.3.3
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Content:
es that the basic criteria are met in each review area covered by this SRP section. Although he will not normally be responsible for the basic reviews of all of these areas, he will consult with those responsible for basic review of the other areas to determine that all areas are individually acceptable. He then reviews each area again, considering the information presented in other areas that interrelate with it, as discussed in subsection II above. Because the reviewer is familiar with the specific procedures used by the reactor vendor, he can readily pick out any differences from past practice. He will evaluate these in detail, consulting with other KTEB members as appropriate. IV. EVALUATION FINDINGS The reviewer verifies that sufficient information is provided to satisfy the requirements of this SRP section, and that the completeness and technical adequacy of his evaluation will support conclusions of the following type, to be included in the staff's safety evaluation report: The staff concludes that structural integrity of the reactor vessel is acceptable and meets the requirements of General Design Criteria 1, 4, | 5.3.3-5 Rev. 1 - July 1981 14, 30, 31, and 32 of Appendix A of 10 CFR Part 50; the requirements of Appendices B, G, and H of 10 CFR Part 50; and the requirements of Section 50.55a of 10 CFR Part 50. 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, "RCPB Materials." (2) SRP Section 5.2.4, "RCPB Inservice Inspection and Testing." (3) SRP Section 5.3.1, "Reactor Vessel Materials." (4) SRP Section 5.3.2, "Pressure-Temperature Limits." We have reviewed all factors contributing to the structural integrity of the reactor vessel and conclude there are no special considerations that make it necessary to consider potential reactor vessel failure for this plant.