Document: NUREG-0800
Document ID: e6a79bdb-930d-4b57-91b9-39db4d8a76f1
Document Type: srp
Title: ENGINEERED SAFETY FEATURES MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190010.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.1.1
CFR Part: 
CFR Title: 

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of DC applications and license applications submitted by applicants pursuant to 10 CFR Part 50 or 10 CFR Part 52. Except when the applicant proposes an acceptable alternative method for complying with specified portions of the Commission’s regulations, the staff will use the method described herein to evaluate conformance with Commission regulations. The provisions of this SRP section apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. Implementation schedules for conformance to parts of the methods discussed herein are contained in the referenced regulatory guides. Acceptable repairs and upgrades are described in the referenced generic letter for previously accepted materials and welds that 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. 6.1.1-15 Revision 2 - March 2007 VI. REFERENCES 1. 10 CFR 50.55a, “Codes and Standards.” 2. 10 CFR Part 50, Appendix A, General Design Criterion (GDC) 1, “Quality Standards and Records.” 3. 10 CFR Part 50, Appendix A, GDC 4, “Environmental and Dynamic Effects Design Bases.” 4. 10 CFR Part 50, Appendix A, GDC 14, “Reactor Coolant Pressure Boundary.” 5. 10 CFR Part 50, Appendix A, GDC 31, “Fracture Prevention of Reactor Coolant Pressure Boundary.” 6. 10 CFR Part 50, Appendix A, GDC 35, Emergency Core Cooling. 7. 10 CFR Part 50, Appendix A, GDC 41, Containment Atmosphere Cleanup.” 8. 10 CFR Part 50, Appendix B, “Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants,” Criterion IX, “Control of Special Processes,” and Criterion XIII, “Handling, Storage and