Document: NUREG-0800
Document ID: 071299b4-6786-484c-b8f0-a2f5a4af09d8
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A357.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.3
CFR Part: 
CFR Title: 

Content:
ing, determination of the number of earthquake cycles, interaction of other systems with seismic Category I systems, and evaluation of multiply-supported equipment. Meeting these requirements provides assurance that seismic Category I subsystems will be adequately designed to withstand the effects of earthquakes, and thus, will be able to perform their intended safety function. 2. 10 CFR Part 100, Subpart A, which is applicable to power reactor site applications before January 10, 1997, refers to appendix A of this part for seismic criteria. 10 CFR Part 100, A provides definitions for the OBE and the SSE, and requires that the engineering methods, used to ensure that the required safety functions are maintained during and after the vibratory ground motion associated with the SSE, involve the use of either a suitable dynamic analysis or an appropriate qualification test methodology. 10 CFR Part 100, Appendix A requires that the applicable levels of vibratory ground motion corresponding to the OBE and the SSE are properly defined, and that adequate methods are used to demonstrate that SSCs important to safety can withstand the seismic and other concurrently applied loads. 10 CFR Part 100, Subpart B, which is applicable to power reactor site applications on or after January 10, 1997, refers to 10 CFR 100.23 of this part for seismic criteria. 10 CFR 100.23 describes the criteria and nature of investigations required to obtain the geologic and seismic data necessary to determine the suitability of the proposed site