Document: NUREG-0800
Document ID: a416cfea-d766-4e80-9d15-6ac4918475fa
Document Type: srp
Title: REACTOR COOLANT SYSTEM COMPONENT AND SUBSYSTEM DESIGN
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070610167.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4
CFR Part: 
CFR Title: 

Content:
lass 1, 2, or 3 if the staff considers them to be safety related. J. The organization responsible for mechanical engineering reviews (primary reviewer), and the organization responsible for reviews of electrical engineering and instrumentation and controls (secondary reviewer), assess the methods of test and analysis used to ensure the function of valves (including valve operators), associated electrical equipment, and instrumentation and controls, under the full range of normal and accident loadings (including seismic). These assessments are conducted under SRP Section 3.10. K. The organization responsible for review of component integrity issues related to reactor coolant pressure boundary (primary reviewer), and the organization responsible for the review of materials engineering issues related to flaw evaluation and welding (secondary reviewer), assess materials of fabrication for RCS valves under SRP Section 10.3.6, “Steam and Feedwater System Materials.” L. The organization responsible for review of component integrity issues related to engineered safety features evaluate the compatibility of fluids with valve materials under SRP Section 6.1.1, “Engineered Safety Features Materials.” M. The organization responsible for review of the inspection, testing, evaluation, and repair of mechanical equipment and components assesses the inservice inspection of ASME Code Class 2 and Class 3 valves under SRP Section 6.6, “Inservice Inspection of Class 2 and 3 Components.” 4. Main Steam Line Flow Restrictions A. The organization responsible for mechanical engineering reviews assesses methods of analysis (e.g., seismic and vibratory loadings, and dynamic analyses), and structural and functional integrity of the main steam line flow restrictions under SRP Sections 3.9.1, 3.9.2, and 3.9.3. 5.4-7 Revision 2 - March 2007 B. The organization responsible for the review of transient and accident analyses for PWRs/BWRs reviews the functional requirements of the main