Document: NUREG-0800
Document ID: 4851d1d8-cf40-4a04-920b-1e59a44d3f2e
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1608/ML16088A068.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
d for fatigue analysis of appropriate components are provided. 4. The review of the consideration given to minimize degradation of materials due to corrosion based upon the environmental conditions to which equipment will be exposed is performed under SRP Section 6.1.1, “Engineered Safety Features Materials.” 3.9.1-3 Revision 4 –December 2016 5. The design of ASME BPV Code Class 1, 2, and 3 components, component supports, and core support structures is reviewed under SRP Section 3.9.3, “ASME Code Class 1, 2, and 3 Components, and Component Supports, and Core Support Structures.” The design of reactor vessel internal components is reviewed under SRP Sections 3.9.4, “Control Rod Drive Systems,” and 3.9.5, “Reactor Pressure Vessel Internals.” 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. Title 10 of the Code of Federal Regulations (10 CFR) Part 50, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criterion” (GDC) 1, “Quality Standards and Reports,” as to the requirement that SSCs be designed, fabricated, erected, and, tested to quality standards commensurate with the importance of the safety functions to be performed. 2. GDC 2, “Design Bases for Protection against Natural Phenomena,” as to the requirement that SSCs be designed to withstand seismic events without loss of capability to perform their safety functions. 3. GDC 14, “Reactor Coolant Pressure Boundary,” as to the requirement that the reactor coolant pressure boundary (RCPB) 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, “Reactor Coolant System Design,” as to the requirement that the reactor coolant system