ML19318B973

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Proposed Tech Spec Interpreting Term Operable as Applied to Various Tech Spec Requirements
ML19318B973
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 06/24/1980
From:
DUKE POWER CO.
To:
Shared Package
ML15223A601 List:
References
NUDOCS 8006300364
Download: ML19318B973 (1)


Text

6 G

1.2.7 Refueling Operation An operation involving a change in core geometry by manipulation of fuel or control rods when the reactor vessel head is removed.

1.2.8 Startup The reactor shall be considered in the startup mode when the shutdown margin is reduced with the intent of going critical.

1.3 OPERABLE A system, subsystem, train, component or device shall be considered OPERABLE when it is capable of performing its intended safety functions. Implicit in this definition shall be the assumption that all essential auxiliary equip-ment required in order to assure performance of the safety function is capable of performing its related support function (s). Auxiliary equipment includes but is not limited to normal or emergency electrical power sources, cooling and seal water, instrumentation and controls, etc.

If either the normal or emergency power to system, subsystem, train, component or device is not available it is considered OPERABLE for the purpose of satisfying the require-ments of its applicable Limiting Condition for Operation, provided:

(a) the alternate power source is available, and (b) the reduncant system is operable.

1.4 PROTECTIVE INSTRUMENTATION LOGIC l.4.1 Instrument Channel An instrument channel is the combination of sensor, wires, amplifiers and output devices which are connected for the purpose of measuring the value of a process variable for the purpose of observation, control and/or protection.

An instrument channel may be either analog or digital in nature.

1.4.2 Reactor Protective System The reactor protective system is shown in Figures 7-1 and 7-6 of the FSAR.

It is that combination of protective channels and associated circuitry which forms the automatic system that protects the reactor by control rod trip.

It includes the four protective channels, their associated instrument channel inputs, manual trip switch, all rod drive protective trip breakers and activating relays or coils.

1.4.3 Protective Channel A protective channel as shown in Figure 7-1 of the FSAR (one of three or one of four independent channels, complete with sensors, sensor power supply units, amplifiers and bistable modules provided for every reactor protective saf ety parameter) is a combination of instrument c1'nnels forming a single digital output to the protective system's coincidene logic. It includes a shutdown bypass circuit, a protective channel bypas. circuit and reactor trip module and provision for insertion of a dummy bistable.

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