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:
issues related to reactor vessels (secondary reviewer), evaluate the inservice inspection program for ASME Code Class 1 RCS pressure relief devices / reactor coolant depressurization systems to assess their structural and leaktight integrity. These evaluations are performed under SRP Section 5.2.4. J. The organization responsible for the review of transient and accident analyses for PWRs/BWRs reviews RCS performance during anticipated operational occurrences and postulated accidents under SRP 15.6.1, and other various SRP Sections of Chapter 15. 10. Reactor Coolant System Component Supports A. The organization responsible for mechanical engineering reviews assesses methods of analysis (e.g., seismic and vibratory loadings, and dynamic analyses), and structural integrity of RCS (and subsystem) component supports under SRP Sections 3.9.1, 3.9.2, and 3.9.3. 5.4-10 Revision 2 - March 2007 B. The organization responsible for the review of component performance and testing reviews the functional design and qualification provisions and IST programs for certain safety-related dynamic restraints (snubbers) typically designated as Class 1, 2, or 3 under Section III of the ASME Code under SRP Section 3.9.6. The review may include other dynamic restraints not categorized as ASME Code Class 1, 2, or 3 if the staff considers them to be safety related. 11. Pressurizer Relief Discharge System The organization responsible for the review of reactor thermal-hydraulic systems in PWRs reviews the pressurizer relief tank (or one or more components and/or systems that perform functions similar to those of the pressurizer relief tank system) under SRP Section 5.4.11, “Pressurizer Relief Tank. 12. RCS High-Point Vents The organization responsible for the review of reactor thermal-hydraulic systems in PWRs and BWRs reviews the RCS high-point vents under SRP 5.4.12, “Reactor Coolant System High [Point] Vents.” 13. Main Steam Line, Feedwater, and Auxiliary Feedwater Piping A.