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:
ational and critical startup 20 test programs as part of its primary review responsibility for SRP Section 14.2. 6. The MEB EMEB reviews the RCIC system to assure that it has the proper seismic and 21 quality group classification as part of its primary review responsibility for SRP Sections 3.2.1 and 3.2.2. 7. The RCIC is to be enclosed in a seismic Category I structure or building. The design adequacy of this structure or building is evaluated by the Structural and Geotechnical Engineering Branch (SGEB) Civil Engineering and Geosciences Branch (ECGB) as 22 part of its primary review responsibility for SRP Sections 3.3, 3.4, 3.5, 3.7, and 3.8 3.3.1, 3.3.2, 3.4.2, 3.5.3, 3.7.1, 3.7.2, 3.7.3, 3.8.1, 3.8.3, 3.8.4 and 3.8.5.23 8. The Containment Systems Branch (CSB) Containment Systems and Severe Accident Branch (SCSB) reviews the RCIC system, as part of its primary review responsibility 24 for SRP Sections 6.2.2, 6.2.4 and 6.2.6 to confirm that the design is compatible with the 25 containment system and can be isolated. SCSB also reviews the containment heat removal capability and the suppression pool suction strainers as part of its review responsibility for SRP Section 6.2.2.26 9. The Instrumentation and Control Systems Branch (ICSB)Instrumentation and Controls Branch (HICB) , as part of its primary review responsibility for SRP Section 7.3 and 27 28 7.4, evaluates the adequacy of controls and instrumentation of the RCIC system with regard to the required features of automatic actuation, remote sensing and indication, and remote control. DRAFT Rev. 4 - April 1996 5.4.6-4 10. The Power Systems Branch (PSB)Electrical Engineering Branch (EELB) , as part of its 29 primary review responsibility for SRP SectionChapter 8.3 , evaluates the adequacy and 30 reliability of offsite and emergency onsite power, the sufficiency of battery capacity, and the use of d-c power only to support operation of specified systems/subsystems, and the plant's capabilities to cope with a Station