Document: NUREG-0800
Document ID: 853719df-a6ea-408b-8d43-5956155abc38
Document Type: srp
Title: and 8.3.2.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1007/ML100740246.pdf
Revision Date: 2023-06
Chapter: 8
Section ID: 8.3.1
CFR Part: 
CFR Title: 

Content:
conditions outside the nuclear power unit associated with normal operation, maintenance, testing, and postulated accidents by adequate plant design. 3. The applicant has met the requirements of GDC 5, "Sharing of Structures, Systems, and Components," with respect to sharing of circuits of the preferred power system between units. Each circuit has sufficient capacity to operate the engineered safety features for a design basis accident on one unit and those systems required for concurrent safe shutdown on the remaining units. 4. The applicant has met the requirements of GDC 17, "Electric Power Systems," with respect to the offsite power system's (a) capacity and capability to permit functioning of structures, systems, and components important to safety; (b) provisions to minimize the probability of losing electric power from any of the remaining supplies as a result of, or coincident with, the loss of power generated by the nuclear power unit or loss of power from the onsite electric power supplies; c) physical independence of circuits; and (d) availability of circuits. The preferred power system consists of at least two physically independent circuits routed from the electrical grid system by transmission lines to the onsite power distribution system. At least one circuit will be available within a few seconds following a loss of coolant accident and is considered an immediate access circuit. Each circuit is designed and located so as to minimize to extent practical the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. Each circuit has been sized with sufficient capacity to supply all connected loads. Each circuit can be made available to the onsite power system, assuming loss of the onsite ac standby power supplies and loss of the other offsite circuit, to ensure that fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded. The switchyard is arranged such that