Document: NUREG-0800
Document ID: e40387bd-a6d6-49ae-a11b-6d22124df03a
Document Type: srp
Title: Each calculated spectrum of the artificial time history is considered to envelop the
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070317.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.0
CFR Part: 
CFR Title: 

Content:
e with the acceptance criteria given in the SRP Section 3.7.1, Revision 1, dated July 1981.63 VI. REFERENCES 41. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection 64 Against Natural Phenomena." 2. 10 CFR Part 100, Appendix A, "Seismic and Geologic Siting Criteria for Nuclear Power Plants." 53. Regulatory Guide 1.60, "Design Response Spectra for Nuclear Power Plants." 34. Regulatory Guide 1.61, "Damping Values for Seismic Analysis for Nuclear Power Plants." 5. Regulatory Guide 1.84, "Design and Fabrication Code Case Acceptability, ASME Section III, Division 1."65 6. SECY-93-087, "Policy, Technical, and Licensing Issues Pertaining to Evolutionary and Advanced Light-Water Reactor (ALWR) Designs," April 2, 1993; SRM-93-087 issued on July 21, 1993.66 17. NUREG/CP-0054, "Proceedings of the Workshop on Soil-Structure Interaction," Bethesda, Maryland, NUREG/CP-0054, June 16-18, 1986. 67 88. NUREG/CR-1161, D. W. Coats, "Recommended Revisions to Nuclear Regulatory Commission Seismic Design Criteria," NUREG/CR-1161, May 1980. 68 79. NUREG/CR-3509, M. Shinozuka, T. Mochio, and E. F. Samaras, "Power Spectral Density Functions Compatible with NRC Regulatory Guide 1.60 Response Spectra," NUREG/CR-3509, June 1988. 69 610. NUREG/CR-5347, A. J. Philippacopoulos, "Recommendations for Resolution of Public Comments on USI A-40, Seismic Design Criteria," NUREG/CR-5347, AprilJune 70 71 1989. 911. ASCE Standard 4-86, "Seismic Analysis of Safety-Related Nuclear Structures and Commentary on Standard for Seismic Analysis of Safety-Related Nuclear Structures," American Society of Civil Engineers, September 1986. 12. ASME Boiler and Pressure Vessel Code, Section III, "Rules for Construction of Nuclear Power Plant Components," Division 1, Appendix N, "Dynamic Analysis Methods," American Society of Mechanical Engineers.72 S0( ) 2 F ( ) 2 2 TD 3.7.1-13 DRAFT Rev. 3 - April 1996 ....................(1) APPENDIX A TO SRP SECTION 3.7.1 SPECIFICATION FOR MINIMUM