Document: NUREG-0800
Document ID: 0c20c24d-a707-4c10-8846-1c59c835bac5
Document Type: srp
Title: -
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16029A367.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.2.1
CFR Part: 
CFR Title: 

Content:
Draft Revision 4 – April 2016 The referenced regulatory guides include implementation schedules for conformance to parts of the method discussed herein. VI. REFERENCES 1. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section II, “Materials Specifications,” New York, NY. 2. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section III, “Rules for Construction of Nuclear Facility Components,” New York, NY. 3. American Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Section IX, “Welding and Brazing Qualifications,” New York, NY. 4. American Society for Testing and Materials (ASTM) A-708, “Standard Recommended Practices for Detection of Susceptibility to Intergranular Corrosion in Severely Sensitized Austenitic Stainless Steel,” West Conshohocken, PA. 5. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 1, “Quality Standards and Records.” 6. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 4, “Environmental and Dynamic Effects Design Bases.” 7. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 14, “Reactor Coolant Pressure Boundary.” 8. U.S. Code of Federal Regulations, “Domestic Licensing of Production and Utilization Facilities,” Part 50, Chapter 1, Title 10, “Energy,” Appendix A, “General Design Criteria for Nuclear Power Plants,” General Design Criterion 15, “Reactor Coolant System