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
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CFR Title: 

Content:
imary reviewer), and the organization responsible for the review of atmospheric dispersion estimates (secondary reviewer), assess the steam generator response to various postulated accidents under SRP Section 15.0.3, “Design Basis Accident Radiological Consequence Analyses For Advanced Light Water Reactors,” and various other SRP Sections of Chapter 15. 3. Reactor Coolant System Piping and Valves A. The organization responsible for review of reactor thermal-hydraulic systems in PWRs or BWRs reviews the piping and instrumentation diagrams, process flow features, and equipment arrangements of RCS piping and valves. B. The organization responsible for mechanical engineering reviews assesses the design and analysis, and the preoperational testing, of the RCS piping, and associated piping supports, under SRP Section 3.12, “ASME Code Class 1, 2, and 3 Piping Systems, Piping Components and Their Associated Supports.” C. The organization responsible for review of component integrity issues related to reactor coolant pressure boundary (primary reviewer), the organization responsible for review of component integrity issues related to reactor vessels (secondary reviewer), and the organization responsible for review of chemical engineering issues (secondary reviewer), assess reactor coolant piping materials, including valves, under SRP Section 5.2.3. D. The organization responsible for the review of component integrity issues related to reactor coolant pressure boundary (primary reviewer), and the organization responsible for the review of component integrity issues related to reactor vessels (secondary reviewer), evaluate periodic inspection and testing of ASME Code Class 1 RCS piping and valves (other than steam generator tubes) to assess their structural and leaktight integrity. These evaluations are performed under SRP Section 5.2.4. E. The organization responsible for the review of reactor coolant pressure boundary leakage detection reviews design features,