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:
eview of component integrity issues related to reactor vessels (secondary reviewer), and the organization responsible for review of chemical engineering issues (secondary reviewer), assess pressurizer materials under SRP Section 5.2.3. 6. Reactor Core Isolation Cooling System (BWR) / Isolation Condenser System [ESBWR]) A. The organization responsible for the review of thermal-hydraulic systems in BWRs assesses the reactor core isolation cooling system / isolation condenser system under SRP Section 5.4.6. B. The organization responsible for the review of the BWR and PWR emergency core cooling system (primary reviewer), and the organization responsible for the review of other systems and technical areas related to the BWR and PWR emergency core cooling systems (secondary reviewer), evaluate the ESBWR isolation condenser system under SRP Section 6.3, since this system is part of the emergency core cooling system. 5.4-8 Revision 2 - March 2007 7. Residual Heat Removal System / Passive Residual Heat Removal System [ALWR] / Shutdown Cooling Mode of the Reactor Water Cleanup System [ESBWR] The organization responsible for review of reactor thermal-hydraulic systems in PWRs and BWRs reviews the residual heat removal system under SRP Section 5.4.7. 8. Reactor Water Cleanup System [BWR] / Reactor Water Cleanup/Shutdown Cooling System [ESBWR] A. The organization responsible for review of chemical engineering issues reviews the design parameters and features provided to ensure proper operation of the reactor water cleanup system under SRP Section 5.4.8, “Reactor Water Cleanup System (BWR).” B. The organization responsible for the review of instrumentation and controls assesses the instrumentation and control aspects to confirm conformance to the acceptance criteria in SRP Sections 7.1, “Instrumentation and Controls - Introduction,” and Section 7.6, “Interlock Systems Important to Safety,” and Branch Technical Positions in SRP Appendix 7-A. 9. Reactor Coolant System