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:
17.0. 18 3. The Civil Engineering and Geosciences Branch (ECGB) reviews surveillance programs to verify inclusion of erosion/corrosion monitoring of steam and feedwater system materials as part of its primary review responsibilities for SRP Section 6.6.19 For those areas of review identified above as being reviewed as part of the primary review responsibility under other SRP Sectionsof other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary branch. 20 II. ACCEPTANCE CRITERIA The applicable rules and basic acceptance criteria pertinent to the areas of this section of the Standard Review Plan are: A1. 10 CFR Part 50, §50.55a - Codes and Standards 21 This rule requires that structures, systems, and components shall be designed, fabricated, erected, constructed, tested, and inspected in accordance with the requirements of applicable codes and standards commensurate with the importance of the safety function to be performed. (Ref. 1). 22 B2. 10 CFR Part 50, Appendix A: 1a. General Design Criterion 1 - "Quality Standards and Records." This criterion requires that structures, systems, and components important to safety shall be designed, fabricated, erected, and tested to quality standards commensurate with the importance of the safety functions to be performed. It also requires that appropriate records of the design, fabrication, erection, and testing of structures, systems, and components important to safety shall be maintained by or under the control of the nuclear power unit licensee throughout the life of the unit. (Ref. 2) 23 2b. General Design Criterion 35 - "Emergency Core Cooling." This criterion 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. It also requires that the system will have containment capabilities to DRAFT Rev. 3 -