Document: NUREG-0800
Document ID: 638ddb22-e6d2-4b69-855f-e55482aae718
Document Type: srp
Title: STEAM AND FEEDWATER SYSTEM MATERIALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070583.pdf
Revision Date: 2023-06
Chapter: 10
Section ID: 10.3.6
CFR Part: 
CFR Title: 

Content:
quirements of ANSI Standard N45.2.1-1973, "Cleaning of Fluid Systems and Associated Components During Construction Phase of Nuclear Power Plants." If austenitic stainless steel is utilized, the review includes appropriate findings from SRP Section 5.2.3, "Reactor Coolant Pressure Boundary Materials," for material selection and fabrication process controls for stainless steel.43 For design certification reviews, the findings will also summarize, to the extent that the review is not discussed in other safety evaluation report sections, the staff's evaluation of inspections, tests, analyses, and acceptance criteria (ITAAC), including design acceptance criteria (DAC), site interface requirements, and combined license action items that are relevant to this SRP section.44 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using the SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 45 cases in which the applicant proposes an acceptable alternative 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. 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.46 Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES47 91. 10 CFR Part 50, 50.55a , "Codes and Standards." 48 12. 10 CFR Part 50 , Appendix A, General Design Criterion 1, "Quality Standards and 49 Records." 103. 10 CFR Part 50 , Appendix A, General Design Criterion 35, "Emergency Core 50 Cooling." 114. 10 CFR Part 50 , Appendix B, "Quality Assurance Criteria for Nuclear Power Plants and 51