Document: NUREG-0800
Document ID: c9fa37cd-0598-4030-8a78-8302ff93c8b4
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1235/ML12353A354.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.7.2
CFR Part: 
CFR Title: 

Content:
Draft Revision 4 - December 2012 Section 3.7.2, will be reviewed in accordance with the acceptance criteria given in the SRP Section 3.7.2, Revision 1, dated July 1981. VI. REFERENCES 1. 10 CFR Part 50, “Domestic Licensing of Production and Utilization Facilities.” 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 3. 10 CFR Part 50, Appendix S, “Earthquake Engineering Criteria for Nuclear Power Plants.” 4. 10 CFR Part 52, “Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants." 5. 10 CFR Part 100, Subpart A, "Evaluation Factors for Stationary Power Reactor Site Applications before January 10, 1997 and for Test Reactors.” 6. 10 CFR Part 100, Subpart B, "Evaluation Factors for Stationary Power Reactor Site Applications on or After January 10, 1997.” 7. 10 CFR Part 100, Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants.” 8. ASCE/SEI 43-05, “Seismic Design Criteria for Structures, Systems, and Components in Nuclear Facilities.” American Society of Civil Engineers, 2005. 9. DC/COL-ISG-01, “Interim Staff Guidance on Seismic Issues Associated with High Frequency Ground Motion in Design Certification and Combined License Applications.” May 19, 2008. 10. Miller, C.A.; Costantino, C.J.; and Philippacopoulos, A.J.; "High Soil-Structure Damping Combined with Low Structural Damping," 7th Structural Mechanics in Reactor Technology (SMiRT) Paper K 10/10, Chicago, IL, 1985. 11. NUREG/CP-0054, "Proceedings of the Workshop on Soil-Structure Interaction,” Bethesda, MD, June 16-18, 1986. 12. NUREG/CR-1161, "Recommended Revisions to Nuclear Regulatory Commission Seismic Design Criteria," May 1980. 13. RG 1.60, "Design Response Spectra for Seismic Design of Nuclear Power Plants." 14. RG 1.70, “Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants.”