Document: NUREG-0800
Document ID: 0bc22ae4-5c52-4b2a-bb94-6d323cffe8b8
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070335.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
ods and computer programs used for the design and analysis of seismic Category I Code Class 1, 2, 3, and CS structures, and non-Code structures within the present state-of-the-art limits and by having design control measures which are acceptable to assure ensure the quality of the computer programs. For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff’s evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.35 3.9.1-9 DRAFT Rev. 3 - April 1996 V. IMPLEMENTATION The following is intended to provide guidance to applicants regarding the NRC staff's plan for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 36 cases in which the applicant proposes acceptable alternative methods for complying with specified portions of the Commission's regulations, the methods described here will be used by the staff in its evaluation of conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.37 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guide.38 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and 39 Reports." 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against National Phenomena." 3. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 4. 10 CFR Part 50, Appendix A, General Design Criterion 15, "Reactor Coolant System