Document: NUREG-0800
Document ID: 8981f423-79ff-42f4-9d5d-f0aa9777b60e
Document Type: srp
Title: STABILITY OF SLOPES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340606.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.5
CFR Part: 
CFR Title: 

Content:
safety-related portions of the system shall be designed to withstand the effects of earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions. (Ref. 3) (c) General Design Criterion 44 - "Cooling Water." This criterion requires that a system shall be provided with the safety function of transferring the combined heat load from structures, systems, and components important to safety to an ultimate heat sink under normal operating and accidental conditions. (Ref. 4) 3. 10 CFR Part 50 Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." This appendix establishes quality assurance requirements for the design, construction, and operation of those 2.5.5-2 Rev. 2 - July 1981 structures, systems, and components of nuclear power plants that prevent or mitigate the consequences of postulated accidents that could cause undue risk to the health and safety of the public. (Ref. 5) 4. 10 CFR Part-100, "Reactor Site Criteria." This part describes criteria which guide the evaluation of the suitability of proposed sites for nuclear power and testing reactors. (Ref. 6) 5. 10 CFR Part 100, Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants." These criteria describe the nature of the investi- gations required to obtain the geologic and seismic data necessary to determine site suitability and identifies geologic and seismic factors required to be taken into account in the siting and design of nuclear power plants. (Ref. 7) .The following regulatory guides provide information, recommendations, and guidance and in general describe a basis acceptable to the staff that may be used to implement the requirements of 10 CFR Part 50, §50.55a; 10 CFR Part 50, Appendix A, General Design Criteria 1, 2, and 44; 10 CFR Part 50, Appendix B; 10 CFR Part 100; and 10 CFR Part 100, Appendix A. 1. Regulatoy Guide 1.27, "Ultimate Heat Sink for Nuclear Power Plants." This