Document: NUREG-0800
Document ID: 5691df7d-390d-4ce8-953e-bbdb0a812705
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1515/ML15159B086.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
in RG 1.53, “Application of the Single-Failure Criterion to Safety Systems,” which endorses IEEE Std 379, “IEEE Standard Application of the Single- Failure Criterion to Nuclear Power Generating Station Safety Systems.” Based on the review, the staff concludes that the RTS satisfies the requirement of (IEEE Std 279-1971 or IEEE Std 603-1991) with regard to the system reliability and testability. Therefore the staff finds that the RTS satisfies these requirements of GDC 21. The RTS conforms to the guidelines in RG 1.75, “Criteria for Independence of Electrical Safety Systems,” for the protection system independence. Based on the review, the staff concludes that the RTS satisfies the requirement of (IEEE Std 279-1971 or IEEE Std 603-1991) with regard to the systems independence. Therefore, the staff finds that the RTS satisfies the requirements of GDC 22. 7.2-8 Draft Revision 6 – August 2015 Based on the review of the failure modes and effects analysis for the RTS, the staff concludes that the system is designed to fail into a safe mode if conditions such as disconnection of the system, loss of energy, or postulated adverse environment are experienced. Therefore, the staff finds that the RTS satisfies the requirements of GDC 23. Based on the review of the interfaces between the RTS and plant operating control systems, the staff concludes that the system satisfies the requirements of (IEEE Std 279-1971 or IEEE Std 603-1991) with regard to control and protection system interactions. Therefore the staff finds the RTS satisfies the requirements of GDC 24. Based on the review of the RTS, the staff concludes that the system satisfies the protection system requirements for malfunctions of the reactivity control system such as accidental withdrawal of control rods. Chapter 15 of the SAR and SER address the capability of the system to ensure that fuel design limits are not exceeded for such events. Therefore, the staff finds that the RTS satisfies the