Document: NUREG-0800
Document ID: a2f24e8d-bc9b-4cc9-91c8-556b80541349
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0704/ML070430402.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
on 3 - March 2007 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, Appendix A, General Design Criterion (GDC ) 1, which requires, in part, that components important to safety be designed, fabricated, erected, and, tested to quality standards commensurate with the importance of the safety functions to be performed. 2. GDC 2, which requires, in part, that components important to safety be designed to withstand seismic events without loss of capability to perform their safety functions. 3. GDC 14, which requires that the reactor coolant pressure boundary be designed, fabricated, erected and tested so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. 4. GDC 15, which requires that the reactor coolant system and associated auxiliary, control and protection systems be designed with sufficient margin to assure that the design conditions of the reactor coolant pressure boundary are not exceeded during any condition of normal operation, including anticipated operational occurrences. 5. 10 CFR Part 50, Appendix B, Section III, as it relates to quality of design control. 6. 10 CFR Part 50, Appendix S, as it relates to the suitability of the plant design bases for mechanical components established in consideration of site seismic characteristics. 7. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed inspections, tests, analyses, and acceptance criteria (ITAAC) that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and