Document: NUREG-0800
Document ID: ce3522a1-5c42-492a-95d7-9087534cf63c
Document Type: srp
Title: STABILITY OF SLOPES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070270.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.5
CFR Part: 
CFR Title: 

Content:
onding primary branch.16 2.5.5-3 DRAFT Rev. 3 - April 1996 II. ACCEPTANCE CRITERIA The applicable rules and basic acceptance criteria pertinent to the areas of this section of the Standard Review Plan are: 1. 10 CFR Part 50, 50.55a, "Codes and Standards." This rule requires that structures, 17 systems, and components shall be designed, fabricated, erected, constructed, tested, and inspected in accordance with the requirement of applicable codes and standards commensurate with the importance of the safety function to be performed. 2. 10 CFR Part 50, Appendix A: (a) General Design Criterion 1 (GDC 1) - "Quality Standards and Records." This 18 criterion requires that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. It also requires that appropriate records of the design, fabrication, erection, and testing of structures, systems, and components important to safety shall 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 19 Natural Phenomena." This criterion requires that 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. (c) General Design Criterion 44 (GDC 44) - "Cooling Water." This criterion 20 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. 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,