1. Scope
1.1 At the onset of an accident, certain protective actions (e.g., reactor trip, emergency core cooling actuation, containment isolation) are designed to be performed automatically. Specific CSA Standards cover the systems that perform these actions. ,, However, the operator has an increasing role to play as time progresses in managing the outcome of the event. Instrumentation is then required to monitor and display the necessary post- accident information within the CANDU nuclear power plant. ,, 1.2 Instrumentation addressed by this Standard is that which enables the operator to: (a) Assess the post-accident conditions of the plant and determine the nature and course of the accident; (b) Determine whether or not the safety-related systems have performed or are performing their required protective actions; (c) Monitor the plant characteristics required to follow the effects of the accident; (d) Determine the appropriate actions that need be performed and monitor the results of these actions, including the need to initiate the off-site emergency procedures. ,, 1.3 This instrumentation will provide plant operators with the information deemed necessary for the performance of their role in bringing the plant to and maintaining it in a safe condition following an accident.
1.4 This Standard provides the requirements for the design, manufacture, installation, and qualification of this instrumentation.
| File Size : | 1
file
, 1.6 MB |
| Number of Pages : | 19 |
| Published : | 06/01/2000 |
