Document: NUREG-0800
Document ID: 0a15bfe3-b20f-42c5-a9ae-f05462e14c42
Document Type: srp
Title: REACTOR TRIP SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A059.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
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Content:
s for the RTS designed to survive the effects of earthquakes, other natural phenomena, abnormal environments and missiles. Based upon the review, the staff concludes that the applicant or licensee has identified those systems and components consistent with the design bases for those systems. Sections 3.10 and 3.11 of the SER address the qualification programs to demonstrate the capability of these systems and components to survive these events. Therefore, the staff finds that the identification of these systems and components satisfies the requirements of GDC 2 and 4. Based on the review of RTS status information, 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 7.2-8 Revision 6 – August 2016 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