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:
discharging fluids that may result from equipment failures and from events and conditions outside the nuclear power unit...” Applicability - All I&C safety systems and supporting data communication systems. Review Methods - The environmental and missile design bases for I&C systems important to safety should be provided for each system in Chapter 7 of the SAR. The design bases should identify those systems and components that are qualified to accommodate the effects of environmental conditions and that are Appendix 7.1-A-14 Draft Revision 6 – August 2015 protected from the dynamic effects of missiles, pipe whipping, and discharging fluids. If systems or components are qualified to survive the environmental effects of postulated accidents for limited periods of time, the bases for limited operability should be provided. The review of equipment qualification for environmental conditions should be conducted in accordance with the guidance provided in SRP Appendix 7.1-B, Subsection 4.4 and SRP Appendix 7.1-C, Subsection 5.4. The I&C systems needed for severe accidents must be designed so there is reasonable assurance they will operate in the severe accident environment for which they are intended and over the time span for which they are needed. They need not be subject to additional environmental qualification requirements. The review of this requirement should be coordinated with the organization responsible for review of environmental qualification. (d) GDC 10, “Reactor Design” “The reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to ensure that specified fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.” Applicability - I&C protection and control systems. Review Methods – The evaluation of I&C system contributions to the design margin for reactor core and coolant systems should be a part of the review