Document: NUREG-0800
Document ID: b2d15b43-96b5-4876-877d-f6ba1944c6d7
Document Type: srp
Title: INTERLOCK SYSTEMS IMPORTANT TO SAFETY
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A092.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.6
CFR Part: 
CFR Title: 

Content:
ions, the staff concludes that appropriate interlocks are provided to maintain an appropriate design margin to assure that acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. Therefore, the staff finds that the interlock systems satisfy the requirements of General Design Criteria 10, 15, 16, 28, 33, 34, 35, 38, 41, and 44. Based on the review of interlock system status information, initiation capabilities, and provisions to support safe shutdown, the staff concludes that information is provided to monitor interlocks over the anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety. Appropriate controls are provided for interlock initiation and bypass. The interlocks appropriately support 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 interlock systems satisfy the requirements of GDC 13 and 19. The staff conducted a review of these systems and finds that they comply with the reliability guidance of (IEEE Std 279-1971 or IEEE Std 603-1991). Based on this review, the staff finds that the redundancy requirements of General Design Criteria 34, 35, 38, 41, and 44 have been met. The review included the identification of those systems and components for the interlock systems that are designed to survive the effects of earthquakes, other natural phenomena, abnormal environments, and missiles. Based on 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