Document: NUREG-0800
Document ID: 91fee075-c567-438d-bf9f-47be3177b457
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070453.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

Content:
the applicant proposes an acceptable alternate method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations.110 The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.111 Implementation schedules for conformance to parts of the methods discussed herein are contained in the referenced Rregulatory Gguides. Acceptable repairs and upgrades are 112 described in the referenced Generic Letter for previously accepted materials and welds which do not meet NUREG-0313, Revision 2 recommendations related to material specifications and post weld treatments for stress corrosion cracking resistant piping installations. NUREG-0313, Revision 2 recommendations for stress corrosion cracking resistant installations will be used by the staff for evaluation of IGSCC susceptible portions of ESF piping in new BWR applications.113 VI. REFERENCES 1. 10 CFR Part 50, Appendix A, "General Design Criteria," and Appendix B, "Quality Assurance Requirements for Nuclear Power Plants and Fuel Reprocessing Plants."114 DRAFT Rev. 2 - April 1996 6.1.1-18 1. 10 CFR Part 50, Section 50.55a, "Codes and Standards."115 2. 10 CFR Part 50, Appendix A, General Design Criterion 1, "Quality Standards and Records." 3. 10 CFR Part 50, Appendix A, General Design Criterion 4, "Environmental and Dynamic Effects Design Bases." 4. 10 CFR Part 50, Appendix A, General Design Criterion 14, "Reactor Coolant Pressure Boundary." 5. 10 CFR Part 50, Appendix A, General Design Criterion 31, "Fracture Prevention of Reactor Coolant Pressure Boundary." 6. 10 CFR Part 50, Appendix A, General Design Criterion 35. "Emergency Core Cooling." 7. 10 CFR Part 50, Appendix A, General Design Criterion 41, "Containment Atmosphere Cleanup."116 8. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants