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:
, manual initiation capabilities, and provisions to support safe shutdown, the staff concludes that information is provided to monitor the RTS over the anticipated ranges for normal operation, for the anticipated operational occurrences, and for the accident conditions as appropriate to assure adequate safety. Appropriate controls are provided for manual initiation of reactor trip. The RTS appropriately supports actions to operate the nuclear power unit safety under normal conditions and to maintain it in a safe condition under accident conditions. Therefore, the staff finds that the RTS design satisfies the requirements of General Design Criteria 13 and 19. Based on the review of system functions, the staff concludes that the RTS conforms to the design bases requirements of (IEEE Std 279-1971 or IEEE Std 603-1991) and 10 CFR 50.34(f). The RTS conforms to the guidance of RG 1.105. Based upon this review and coordination with those having primary review responsibility for the accident analysis, the staff concludes that the RTS includes the provision to sense accident conditions and anticipated operational occurrences in order to initiate reactor shutdown consistent with the accident analysis presented in Chapter 15 of the SAR and evaluated in the SER. Therefore, the staff finds that the RTS satisfies the requirements of GDC 20. The RTS conforms to the guidelines for periodic testing in RG 1.22, “Periodic Testing of Protection System Actuation Functions,” and RG 1.118, “Periodic Testing of Electric Power and Protection Systems.” The bypassed and inoperable status indication conforms to the guidelines of RG 1.47, “Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems.” The RTS conforms to the guidelines of the single-failure criterion 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