IEEE 497-1977

This standard applies to the design of instrumentation to monitor and display required post accident conditions within the nuclear power generating station. Instrumentation addressed by this document includes that which enables the operator to: (1) identify the accident to the degree necessary for him to perform his role; (2) assess whether or not safety systems are accomplishing the required safety functions (for example, cooling the core, controlling containment pressure, etc); (3) determine when conditions exist that require specified manual actions and monitor the results of those actions; and (4) follow the course of the accident to determine whether or not conditions are evolving within prescribed limits. This document does not include criteria for instrumentation used only to monitor status, maintenance, or degradation of individual items of safety system equipment during the post accident period

The purpose of this standard is to provide the minimum design criteria for permanently installed instrumentation used to provide the operator with information that may be necessary to perform his role in bringing the plant to and maintaining it in a safe condition following the accidents identified in the Design Basis.

New IEEE Standard - Superseded. The protection of nuclear power plants following a design basis event is provided automatically by the protection systems as defined by IEEE Std 279-1971 (ANSI N42.7-1972), Criteria for Protection Systems for Nuclear Power Generating Stations, and by required specified manual actions. Following the automatic initiation of the protection systems, the operator has the responsibility of bringing the nuclear power plant to and maintaining it in a safe condition. The operator requires specific information to assist him in fulfillling this role. The scope of this document is limited to the design criteria for the monitoring display instrumentation required b y the operator during the post accident period.