Document: NUREG-0800
Document ID: 76e2cd41-eada-4a81-bc9e-1df5cf439180
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A637.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
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CFR Title: 

Content:
sis for withstanding the effects of natural phenomena. 3. The applicant has met the relevant requirements of GDC 14 and GDC 15 by demonstrating that the design transients and consequent loads and load combinations with appropriately specified design and service limits for Code Class 1 components, component supports, reactor core support structures, and reactor vessel internal components provide a complete basis for design of the reactor coolant pressure boundary for all conditions and events expected over the service lifetime of the plant. For DC and COL reviews, the findings will also summarize the staff’s evaluation of requirements and restrictions (e.g., interface requirements and site parameters) and COL action or information items relevant to this SRP section. In addition, to the extent that the review is not discussed in other SER sections, the findings will summarize the staff’s evaluation of the ITAAC, including design acceptance criteria, as applicable. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. American Society of Mechanical Engineers, BPV Code, Section III, Division I, “Nuclear Power Plant Components,” New York, NY. 2. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 1, “Quality