Document: NUREG-0800
Document ID: 6cac2015-4823-4421-9a34-1ee7f23d1ec2
Document Type: srp
Title: or ESFAS — Section 7.3):
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0525/ML052500512.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.2
CFR Part: 
CFR Title: 

Content:
ables and commands necessary to maintain the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems within prescribed operating ranges during plant shutdown. Therefore, we find that the DCSs employed by the reactor control system satisfy the requirements of GDC 13. DCSs have been provided to support instruments and controls within the control room to allow actions to be taken to maintain the nuclear power unit in a safe condition during shutdown, including shutdown following an accident. Therefore, we conclude that the DCSs employed by the reactor control system satisfy the requirements of GDC 19. Additional evaluation findings applicable to all DCSs that support diverse I&C systems functions (Section 7.8): Based upon our review of DCS performance and diversity between the DCSs that support ATWS mitigation functions and DCSs that support RTS functions, the Staff finds that the DCS meets the requirements of 10 CFR 50.62. Based on our review, we conclude that DCSs used in the diverse I&C system, taken in context with other provisions of the design, transmit the variables and commands necessary to maintain the fission process, the integrity of the reactor core, the reactor coolant pressure boundary, and the containment and its associated systems within prescribed operating ranges during plant shutdown. Therefore, we find that the DCSs employed by the diverse I&C system satisfy the requirements of GDC 13. DCSs have been provided to support instruments and controls within the control room to allow actions to be taken to maintain the nuclear power unit in a safe condition during shutdown, including shutdown following an accident. Equipment at appropriate locations outside the control room is also supported by the DCS design to achieve (1) prompt, hot shutdown of the reactor, and Rev. 4 — June 1997 SRP 7.9-10 (2) subsequent cold shutdown of the reactor. Therefore, we conclude that the DCSs