Document: NUREG-0800
Document ID: d28d123a-bc09-41b2-af11-f5cf31fb7c4e
Document Type: srp
Title: Compacted Fill.  In meeting the requirements of 10 CFR Part 50, the applicant should
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070730607.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.5.4
CFR Part: 
CFR Title: 

Content:
d dike analyses and, for the reasons given above, concludes that the design analyses contain margins of safety which adequately demonstrate that natural and manmade slopes will remain stable under SSE conditions and that safety-related earthwork will function reliably at the site to justify the soil and rock characteristics used in the design. The staff further concludes that the design analyses contain adequate margins of safety for construction and operation of the nuclear power plant and meets the requirements of 10 CFR Part 50, Appendix A (GDC 1, 2, and 44); Appendices B and S of 10 CFR Part 50; and 10 CFR 100.23. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR 50.55a, "Codes and Standards." 2. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 3. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 4. 10 CFR Part 50, Appendix A, General Design Criterion 44, "Cooling Water." 2.5.5-14 Revision 3 - March 2007 5. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 6. 10 CFR Part 100, "Reactor Site Criteria." 7. 10 CFR Part 50, Appendix S, "Earthquake Engineering Criteria for Nuclear Power Plants." 8. Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Power Plants." 9. Regulatory Guide 1.28, "Quality Assurance