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:
lity 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 our review, we conclude that DCSs used in the [safe shutdown system, information systems important to safety, and interlock systems important to safety], 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 (safe shutdown system, information systems important to safety, or interlock systems important to safety) satisfy the requirements of GDC 13 and the Staff Requirements Memorandum on SECY-93-087 item II.T. 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 (2) subsequent cold shutdown of the reactor. Therefore, we conclude that the DCSs employed by the (safe shutdown system, information systems important to safety, or interlock systems important to safety) satisfy the requirements of GDC 19. Additional evaluation findings applicable to all DCSs that support control system functions (Section 7.7): Based on our review, we conclude that DCSs used in the reactor control 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