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:
ation valves manually before resetting the isolation signals is not an acceptable method for meeting this design requirement. 20. In meeting 10 CFR 50.34(f)(2)(xv) purging requirements, the regulatory guidance of BTP 6-4, "Containment Purging During Normal Plant Operations," should be used to establish compliance with this regulation. 21. RG 1.155, "Station Blackout," Regulatory Position C.3.2.7, provides guidance for meeting the requirements of the SBO rule, 10 CFR 50.63(a)(2), for containment isolation valves and valve position indication. 22. 10 CFR Part 50, Appendix K, provides guidance for the determination of the extent of fuel failure (source term) in the radiological calculations. Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 1. GDC 1, "Quality Standards and Records," requires that safety-related SSCs be designed, fabricated, erected, and tested to quality standards commensurate with the safety functions performed. This SRP section defines appropriate reliability and performance standards for the design of the containment isolation system. These standards reflect the importance of forming an essentially leak-tight barrier to prevent the release of fission products in an accident. RG 1.26 specifies quality standards applicable to containment isolation system components. This SRP section also contains TMI-related requirements for 6.2.4-10 Revision 3 - March 2007 containment isolation dependability, containment purging/venting during plant operation, and purge/vent valves. Compliance with GDC 1 requirements provides reasonable assurance that the containment isolation system will perform its safety function and prevent the release of radioactive materials to the environment. 2. GDC 2, "Design Bases for Protection Against Natural Phenomena," requires that safety-related SSCs be designed to withstand the effects of natural