Document: NUREG-0800
Document ID: 96ddbfc8-7fd0-4a33-9fbe-144d653b6e9f
Document Type: srp
Title: REACTOR CORE ISOLATION COOLING SYSTEM (BWR)
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070433.pdf
Revision Date: 2023-06
Chapter: 5
Section ID: 5.4.6
CFR Part: 
CFR Title: 

Content:
tion is normally made up by the feedwater system, supplemented by inleakage from the control rod drive system. If the feedwater system is inoperable, the RCIC turbine-pump unit starts automatically or is started by the operator from the control room. The water supply for the RCIC system comes from the condensate storage tank, with a secondary supply from the suppression pool. The review of the RCIC system includes the system design bases, design criteria, description, and the points noted below. The RSB SRXB is responsible for performing the technical review of the RCIC system in the 4 following areas: 1. The piping and instrumentation diagrams are reviewed to determine that the system is capable of performing its intended function and of being preoperationally and operationally tested. 2. The degree of separation of the RCIC system from the high pressure core spray (HPCS) system, or the high pressure coolant injection (HPCI) system, or the high pressure core flooder (HPCF) system is reviewed for protection against common mode failure of 5 redundant systems. 3. The process flow diagram is reviewed to confirm that the RCIC system design parameters are consistent with expected pressures, temperatures and flow rates. 4. The complete sequence of operation is reviewed to determine that the system can function as intended and that the system is capable of manual operation. 5. The system is reviewed for compliance with the applicable requirements of NUREG-0737 (Reference. 13 ). 6 7 Review Interfaces:8 The SRXB also performs the following reviews under the SRP sections indicated:9 1. As part of its primary review responsibility for SRP Section 3.12 (proposed), the SRXB reviews the design of the RCIC system for evolutionary light-water reactor designs to verify, to the extent practical, that low-pressure portions of the RCIC that interface with the RCS will withstand full RCS pressure. If designing the RCIC with an ultimate rupture strength capable of withstanding full RCS