Document: NUREG-0800
Document ID: dd687b37-3f26-4512-91d8-633ddb655821
Document Type: srp
Title: DATA COMMUNICATION SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1602/ML16020A097.pdf
Revision Date: 2023-06
Chapter: 7
Section ID: 7.9
CFR Part: 
CFR Title: 

Content:
h regard to control and protection system interactions. Therefore, the staff finds that the DCS satisfies the requirements of GDC 24. Based on the review of all the above, the staff concludes that the DCS satisfies the requirements of GDC 29. The staff’s conclusions noted above are based on the requirements of (IEEE Std 279-1971 or IEEE Std 603-1991) with respect to the design of the DCS. Therefore, the staff finds that the DCS satisfies the requirement of 10 CFR 50.55a(h) with regard to (IEEE Std 603-1991 or IEEE Std 279-1971). Additional evaluation findings applicable to all DCSs that support the following functions: safe shutdown systems (SRP Section 7.4), information systems important to safety (SRP 7.9-12 Revision 6 - August 2016 Section 7.5, “Information Systems Important to Safety”), or interlock systems important to safety (SRP Section 7.6, “Interlock Systems Important to Safety”): Based on the staff’s review, the staff concludes that DCSs used in the [safe shutdown system, information systems important to safety, or 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, the staff finds 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. Data communications systems 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