Document: NUREG-0800
Document ID: 611e1a8a-5fb2-4d1d-8b0e-7561bc7e46ac
Document Type: srp
Title: SEISMIC AND DYNAMIC QUALIFICATION OF MECHANICAL AND ELECTRICAL EQUIPMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340654.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.10
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CFR Title: 

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down earthquake, postulated accidents, and loss-of-coolant accidents. This program constitutes an acceptable basis for satisfying the applicable requirements of GOC 2, 4, 14 and 30 of Appendix A to 10 CFR 50 and paragraphs XI of Appendix B to 10 CFR 50 and VI(a)(1) and (2) of Appendix A to 10 CFR 100 as they relate to qualification of equip- ment. The applicant's equipment qualification file also constitutes an acceptable basis for satisfying the requirements of GOC 1 of Appendix A to 10 CFR 50 and paragraph XVII of Appendix B to 10 CFR 50. At the OL stage, the review should provide justification for a finding similar to that above with the phrase "will be implemented" modified to read Uhas been implemented." V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plan for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained In the referenced regulatory guides. 3.10-13 Rev. 2 - July 1981 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena.' 3. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Missile Design Bases." 4. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 5. 10 CFR Part 50, Appendix A, General Design Criterion 30, "Quality of Reactor Coolant Pressure Boundary." 6. 1O CFR Part 50, Appendix B. "Quality Assurance Criteria For Nuclear Power Plants and Reprocessing Plants." 7. 10 CFR 100, Appendix A, "Seismic and Geologic Siting