Document: NUREG-0800
Document ID: f689fb6d-4711-4972-b900-1b2001877b19
Document Type: srp
Title: TSUNAMI HAZARDS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1819/ML18190A200.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.6
CFR Part: 
CFR Title: 

Content:
of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. 2.4.6-19 Revision 4 - September 2018 VI. REFERENCES 1. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 2, “Design Bases for Protection against Natural Phenomena.” Part 50, Title 10, “Energy.” 2. U.S. Code of Federal Regulations, Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 44, “Cooling Water.” Part 50, Title 10, “Energy.” 3. U.S. Code of Federal Regulations, “Licenses, Certifications, and Approvals for Nuclear Power Plants,” Part 52. Title 10, “Energy.” 4. U.S. Code of Federal Regulations, “Reactor Site Criteria,” Part 100, Title 10, “Energy.” 5. U.S. Nuclear Regulatory Commission “Ultimate Heat Sink for Nuclear Power Plants.” Regulatory Guide 1.27. 6. U.S. Nuclear Regulatory Commission, “Seismic Design Classification.” Regulatory Guide 1.29. 7. U.S. Nuclear Regulatory Commission, “Design Basis Floods for Nuclear Power Plants.” Regulatory Guide 1.59. 8. U.S. Nuclear Regulatory Commission, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants,” Regulatory Guide 1.70. 9. U.S. Nuclear Regulatory Commission, “Flood Protection for Nuclear Power Plants,” Regulatory Guide 1.102. 10. U.S. Nuclear Regulatory Commission, “Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants,” Regulatory Guide 1.125. 11. U.S. Nuclear Regulatory Commission, “Combined License Applications for Nuclear Power Plants.” (LWR Edition), Regulatory Guide 1.206. 12. American National Standards Institute/American Nuclear Society, “Determining Design Basis Flooding at Power Reactor Sites,” ANSI/ANS-2.8-1992, [Historical technical reference].