ML19312B952

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Proposed Replacement Page W/Original Tech Spec 1.2.8 Deleted Re Definition of Refueling Period as Time Between Normal Refuelings of Reactor,Not to Exceed 18 Months W/O Prior NRC Approval.Remaining Specs Renumbered
ML19312B952
Person / Time
Site: Oconee  
Issue date: 03/12/1975
From:
DUKE POWER CO.
To:
Shared Package
ML19312B946 List:
References
NUDOCS 7911270735
Download: ML19312B952 (2)


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TABLE OF CONTENTS Section Page TECHNICAL SPECIFICATIONS g g,

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DEFINITIONS 1-1 1.1 RATED POWER l-1 1.2 REACTOR OPERATING CONDITIONS 1-1 1.2.1 Cold Shutdown 1-1 a

1.2.2 Hot Shutdown 1-1 1

1.2.3 Reactor Control 1-1 1.2.4 Hot Standby 1-1 1.2.5 Power Operation 1-1 1.2.6 Refueling Shutdown 1-1 1.2.7 Refueling Operation 1-2 1.2.8 Startup 1-2 1.3 OPERABLE 1-2 1.4 PROTECTIVE INSTRUMENTATION LOGIC 1-2 1.4.1 Instrument Channel 1-2 1.4.2 Reactor Protective System 1-2 1.4.3 Protective Channel 1-2 1.4.4 Reactor Protective System Logic l-3 1.4.5 Engineered Safety Features Svstem 1-3 1.4.6 Degree of Redundancy 1-3 1.5 INSTRUMENTATION SURVEILLANCE l-3 1.5.1 Trip Test 1-3 1.5.2 Channel Test 1-3 1.5.3 Instrument Channel check 1-3 i

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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 component or system is operable when it is capable of performing its intended function within the required range.

The component or system shall be considered to have this capability when:

(1) it satisfies the limiting conditions for operation defined in Specification 3, and (2) it has been tested periodically in accordance with Specification 4 and has met its performance requirements.

1.4 PROTECTIVE INSTRUMENTATION LOGIC 1.4.1 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 une of four independent channels, complete with sensors, sensor power supply units, amplifiers and bistable modules provided for every reactor protective safety parameter) is a combination of instrument channels forming a single digital output to the protective system's coincidence logic.

It includes a shutdown bypass circuit, a protective channel bypass circuit and reactor trip module and provision for insertion of a dummy bistable.

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