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:
ations for steam generators is performed under SRP Section 5.4.2.1, “Steam Generator Materials.” 5. The review of surveillance programs to verify inclusion of FAC monitoring of steam and feedwater system materials is performed under SRP Section 6.6, “Inservice Inspection of Class 2 and 3 Components.” The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50.55a, "Codes and Standards,” which requires that SSCs shall be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed. 2. 10 CFR Part 50, Appendix A, GDC 1, "Quality Standards and Records," which requires that SSCs important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. Where generally recognized codes and standards are used, they shall be identified and evaluated to determine their applicability, adequacy, and sufficiency and shall be supplemented or modified as necessary to assure a quality product in keeping with the required safety function. GDC 1 also requires that appropriate records of the design, fabrication, erection, and testing of SSCs important to safety shall be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit. 3. 10 CFR Part 50, Appendix A, GDC 35 - "Emergency Core Cooling," which requires that a system be provided to supply abundant emergency core cooling such that damage to reactor core components is minimal following any loss of reactor coolant. GDC 35 also requires that the system will have containment capabilities to assure that the emergency core cooling function can be accomplished, assuming a single failure. For pressure- containing