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:
ratus and to determine if valve leakage is within acceptable limits. Piping in the RCIC system passes through the containment boundary, and is provided with isolation valves and integrity verification capabilities. Containment isolation and leak detection, 5.4.6-9 DRAFT Rev. 4 - April 1996 as required by GDC 54, provide high level of assurance that the containment will perform its safety function in the event of a postulated accident and will maintain the capability to prevent significant uncontrolled release of radioactivity. 7. 10 CFR 50.63 invokes explicit requirements on the plant regarding the capability to ensure that the core is cooled in the event of a station blackout for a determined duration. The RCIC system provides decay heat removal from the reactor core. Its design capability to operate regardless of a-c power source availability enables performance of the decay heat removal function to support the plant in coping with a station blackout. Regulatory Guide 1.155 identifies methods acceptable for complying with the requirements of 10 CFR 50.63. Compliance with this Regulatory Guide and 10 CFR 50.63 provides assurance that the RCIC system is capable of performing its intended function in the event of a station blackout. III. REVIEW PROCEDURES The procedures below are used during the construction permit (CP) review to assure that the design criteria and bases and the preliminary design as set forth in the preliminary safety analysis report meet the acceptance criteria given in subsection II. For the operating license (OL) review, the procedures are used to verify that the initial design criteria and bases have been appropriately implemented in the final design as set forth in the final safety analysis report. The OL and design certification (DC) review also includes the 73 proposed technical specifications, to assure that they are adequate in regard to limiting conditions of operation and periodic surveillance testing. Upon request from the primary