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:
3: review of the radiological dose consequence analysis for the release of containment atmosphere prior to closure of containment isolation valves in lines providing a direct path to the environs. 12. Section 16.0: review at the operating license stage of proposed technical specifications for operability and leakage-rate testing of isolation barriers and closure time for containment isolation valves. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. 1 Locked-closed isolation valves are defined as sealed closed barriers (see SRP Acceptance Criteria II.6). 2A simple check valve is not an acceptable automatic isolation valve for use outside containment. 6.2.4-4 Revision 3 - March 2007 II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. General Design Criterion (GDC) 1, as it relates to designing, fabricating, erecting, and testing safety-related SSCs to quality standards commensurate with the importance of the safety functions to be performed. 2. GDC 2, as it relates to designing safety-related SSCs to withstand the effects of natural phenomena such as earthquakes, tornadoes, hurricanes, floods, tsunami, and seiches without loss of capability to perform safety functions. 3. GDC 4, as it relates to designing safety-related SSCs to accommodate the effects of and to be compatible with environmental conditions associated with normal operation, maintenance, testing, and postulated accidents, and as it relates to the requirement that these SSCs shall be appropriately protected against dynamic effects, including the effects of missiles, pipe whipping, and discharging fluids. 4. GDC 16, as it relates to reactor containment and associated systems, establishing an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment. 5. GDC 54, as it relates to the requirement that piping systems