Document: NUREG-0800
Document ID: 22884f18-189e-46a8-81b2-45db11edf145
Document Type: srp
Title: SYSTEM QUALITY GROUP CLASSIFICATION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1422/ML14227A641.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.2.2
CFR Part: 
CFR Title: 

Content:
ds Institute, ANSI B96.1, “Specification for Welded Aluminum-Alloy Field-Erected Storage Tanks.” 4. American Petroleum Institute, “Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage Tanks,” American Petroleum Institute Standard 620, Sixth Edition, American Petroleum Institute Standard 650, Sixth Edition, Revision 1, “Welded Steel Tanks for Oil Storage.”. 5. American Society of Mechanical Engineers, ASME BPV Code, “Section III, Division I, Nuclear Power Plant Components.” New York, NY. 6. American Society of Mechanical Engineers, ASME BPV Code, “Section VIII, Division 1, Pressure Vessels,” New York, NY. 7. American Water Works Association, AWWA D100, “AWWA Standard for Steel Tanks-Standpipes, Reservoirs, and Elevated Tanks for Water Storage.” 8. Nuclear Energy Institute, NEI 97-04, “Guidance and Examples for Identifying 10 CFR 50.2, Design Bases,” Revised Appendix B, November 2000. 9. U.S. Code of Federal Regulations, “Codes and Standards.” § 50.55a, Chapter 1, Title 10, “Energy.” 10. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 1, “Quality Standards and Records.” 11. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization,” Part 50, Chapter 1, Title 10, “Energy,” Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants.” 12. U.S. Nuclear Regulatory Commission, BTP 3-1, “Classification of Main Steam Components Other than the Reactor Coolant Pressure Boundary for BWR Plants.” 13. U.S. Nuclear Regulatory Commission, BTP 3-2, “Classification of BWR/6 Main Steam and Feedwater Components Other than the Reactor Coolant Pressure Boundary.” 14. U.S. Nuclear Regulatory Commission, “Codes and Standards and Other Guidance Cited in NRC