Document: NUREG-0800
Document ID: 7d53889c-d236-4e84-9579-a2beb4716167
Document Type: srp
Title: SEISMIC CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070296.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.1
CFR Part: 
CFR Title: 

Content:
assifying those plant 31 features that should be designed to withstand the effects of the SSE. Regulatory Guide 1.151 provides guidance with regard to seismic design requirements and classification of safety-related instrumentation sensing lines.32 Regulatory Guide 1.143 provides guidance used to establish the seismic design requirements of radioactive waste management SSCs to meet the requirements of GDCs 2 and 61 as they relate to designing these SSCs to withstand earthquakes. The guide identifies several radioactive waste SSCs requiring some level of seismic design consideration.33 Technical Rationale:34 The technical rationale for application of the above acceptance criteria to seismic classification is discussed in the following paragraphs. 1. Compliance with General Design Criterion 1 and 10 CFR Part 50, Appendix B, require that SSCs important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. GDC 1 requires, in part, that a Quality Assurance Program be established and implemented in order to provide adequate assurance that SSCs important to safety will satisfactorily perform their safety functions. 10 CFR 50, Appendix B, establishes quality assurance program requirements for the design, construction, and operation of SSCs important to safety. The requirements of 10 CFR 50, Appendix B apply to activities affecting the safety-related functions of those SSCs, including those SSCs defined by the guidance of Regulatory Guide 1.29 as seismic Category I SSCs. Specifying and using proven quality standards and requirements for the design of SSCs important to safety minimizes the potential for failures of those SSCs, including seismic Category I SSCs, that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. 2. Compliance with General Design Criterion 2 requires that nuclear power plant SSCs