Document: NUREG-0800
Document ID: 632e6c59-03bd-4648-b0b3-e8b2efd6fa04
Document Type: srp
Title: CONTAINMENT ISOLATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0703/ML070380197.pdf
Revision Date: 2023-06
Chapter: 6
Section ID: 6.2.4
CFR Part: 
CFR Title: 

Content:
the release of fission products (e.g., fuel cladding, reactor coolant pressure boundary, containment) are not maintained throughout the event and its recovery period. The containment isolation system, including its provisions for control, indication, and performance under loss/restoration of power conditions, is instrumental in maintaining integrity of the containment barrier without undue interference with flow paths essential for cooling the reactor core. Compliance with 10 CFR 50.63 and the positions of RG 1.155 in the performance of the containment isolation system for an SBO, therefore adds defense in depth against unacceptable 6.2.4-13 Revision 3 - March 2007 offsite radiological consequences if both offsite and onsite emergency AC power systems fail by maintaining containment integrity for such an event. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The procedures provide guidance on review of the containment isolation system. Portions of the review may be done generically for aspects of containment isolation common to a class of containments or by adoption of the results of previous reviews of plants with essentially the same containment isolation provisions. Upon request from the primary reviewer, other reviewers provide input for the areas of review stated in subsection I of this SRP section. The primary reviewer uses such input as required to complete this review. 1. The reviewer determines acceptability of the containment isolation system by comparison of the system design criteria to the design requirements for an engineered safety feature. The quality