Document: NUREG-0800
Document ID: 93695235-ba5b-4bfb-be93-d9aec2460bd0
Document Type: srp
Title: STEAM AND FEEDWATER SYSTEM MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0631/ML063190016.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.3.6
CFR Part: 
CFR Title: 

Content:
the review is not discussed in other safety evaluation report sections) the staff's 10.3.6-9 Revision 3 - March 2007 evaluation of the ITAAC, including design acceptance criteria (DAC), as applicable, and interface requirements and combined license action items relevant to this SRP Section. V. IMPLEMENTATION The staff will use this SRP section in performing safety evaluations 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apply to reviews of applications submitted six months or more after the date of issuance of this SRP section, unless superseded by a later revision. VI. REFERENCES 1. 10 CFR 50.55a, "Codes and Standards." 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 35, "Emergency Core Cooling." 4. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." 5. Regulatory Guide 1.37, "Quality Assurance Requirements for Cleaning of Fluid Systems and Associated Components of Water-Cooled Nuclear Power Plants." 6. Regulatory Guide 1.50, “Control of Preheat Temperature for Welding of Low-Alloy Steel.” 7. Regulatory Guide 1.71, "Welder Qualification for Areas of Limited Accessibility." 8. Regulatory Guide 1.85, "Design, Fabrication, and Materials Code Case Acceptability, ASME Section III ." 9. NSAC-202L-R2, “Recommendations for an Effective Flow Accelerated Corrosion Program,” Electric Power Research Institute, Palo Alto, CA, April 8, 1999. 10. ANSI Standard N45.2.1-1973, "Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants."