Document: NUREG-0800
Document ID: 14bfec68-f65b-4ef9-b3f0-2c7d5dd69324
Document Type: srp
Title: may not be complete.  The subsections within SRP Chapter 2.5.4 that are not
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100610449.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.5.4
CFR Part: 
CFR Title: 

Content:
ry of the site characteristics and parameters used for the plant: As set forth above, the applicant has presented and substantiated information to establish the geotechnical engineering aspects of the plant site. The staff has reviewed the information provided and, for the reasons given above, concludes that the applicant has performed sufficient investigations at the site to justify the soil and rock characteristics used in the design, and 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 (GDCs 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apply to reviews of applications submitted 6 months or more after the date of issuance of this SRP section, unless superseded by a later revision.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." 5. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 6. 10 CFR Part 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants." 7. 10 CFR Part 100, "Reactor Site Criteria." 8. RG 1.27, "Ultimate Heat Sink for Nuclear Power