Document: NUREG-0800
Document ID: 949ca18d-b0e4-4b54-9ca9-fdb657988111
Document Type: srp
Title: Revision 5 - March 2007
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0706/ML070660170.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7
CFR Part: 
CFR Title: 

Content:
l protection interaction Subsection 4.7 Subsections 6.6 and 6.3 Auxiliary features Subsection 4.5 Subsection 5.12 Power sources Subsection 4.5 Subsection 8 Separation of protection and control systems should be considered in the review of all sections of Chapter 7 of the SAR to confirm that all interfaces between control systems and protection systems have been properly identified and addressed. (n) GDC 25, “Protection System Requirements for Reactivity Control Malfunctions” “The protection system shall be designed to assure that specified acceptable fuel design limits are not exceeded for any single malfunction of the reactivity control systems, such as accidental withdrawal (not ejection or dropout) of control rods.” Applicability - The RTS and reactivity control system interlocks identified in SAR Chapter 15 as required to assure that specified acceptable fuel design limits are not exceeded for any single malfunction of the reactivity control systems. Review Methods - Confirmation that the protection system is designed for an appropriate spectrum of reactivity control system malfunctions is addressed in the review of protection system design basis requirements as discussed in IEEE Std. 279-1971 and IEEE Std. 603-1991. SRP Appendix 7.1-B Subsection 3 and SRP Appendix 7.1-C Subsection 4 provide review guidance for this topic. The evaluation of conformance with this requirement should be addressed in the review of Section 7.2 of the SAR. (o) GDC 28, “Reactivity Limits” “The reactivity control systems shall be designed with appropriate limits on the potential amount and rate of reactivity increase to assure that the effects of postulated reactivity accidents can neither (1) result in damage to the reactor coolant pressure boundary Appendix 7.1-A-21 Revision 5 - March 2007 greater than limited local yielding nor (2) sufficiently disturb the core, its support structures or other reactor pressure vessel internals to impair significantly the capability to