Document: NUREG-0800
Document ID: 6813459c-4e76-4630-8395-e948ff46c2b3
Document Type: srp
Title: and 7.5 of the SAR.  The review of this requirement should be coordinated
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159A207.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.4
CFR Part: 
CFR Title: 

Content:
tter than the minimum required performance, as conservatism in setpoint calculations, or by system features that make the protection or control systems more fault tolerant. Margin may also be credited in many places and there will naturally be tradeoffs between margin in the reactor design, margin in performance analysis assumptions and methods, and margin in the I&C design. The reactor systems and I&C reviewers should work together to understand the margins provided in the applicant’s design and to confirm there is reasonable assurance that adequate margin is provided. Appendix 7.1-A-17 Draft Revision 6 – August 2015 (g) GDC 16, “Containment Design” “Reactor containment and associated systems shall be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to ensure that the containment design conditions important to safety are not exceeded for as long as postulated accident conditions require.” Applicability - ESF I&C systems. Review Methods - GDC 16 imposes functional requirements on ESF I&C systems to the extent that they support the requirement that the containment provide a leak tight barrier. Relevant I&C functions might include, for example, initiation of containment isolation, removal of radioactive material from the containment atmosphere (e.g., containment spray), or containment environmental control (e.g., containment spray or containment cooling). The review should confirm that the I&C systems provide the functions, performance, and reliability necessary to support the containment system safety function. This review is coordinated with the organization responsible for the review of containment systems. (h) GDC 19, “Control Room” “A control room shall be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions, including loss-of-coolant accidents.