Document: NUREG-0800
Document ID: a569dbdc-1bfb-4a16-b103-db6e01d735e7
Document Type: srp
Title: STABILITY OF SLOPES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070730607.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.5
CFR Part: 
CFR Title: 

Content:
t to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. It also requires that 2.5.5-3 Revision 3 - March 2007 appropriate records of the design, fabrication, erection, and testing of structures, systems, and components important to safety be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit. (b) General Design Criterion 2 (GDC 2), "Design Bases for Protection Against Natural Phenomena," as it relates to consideration of the most severe of the natural phenomena that have been historically reported for the site and surrounding area, with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated. (c) General Design Criterion 44 (GDC 44), "Cooling Water," requires that a system 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. (d) For ESP applications, GDC are not applicable. However, the GDC 2 requirement to identify site characteristics that consider the most severe of the natural phenomena that have been historically reported for the site and surrounding area and with sufficient margin for the limited accuracy, quantity, and period of time in which the historical data have been accumulated is specifically identified in 10 CFR 52.17(a)(1)(vi). 3. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Processing Plants,“ establishes quality assurance requirements for the design, construction, and operation of those 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. 4. 10 CFR Part 50, Appendix S, “Earthquake Engineering