ML19262C690

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Revised Tech Specs 3.5.1.7 & 3.5.1.8 for Reactor Trip Circuitry
ML19262C690
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 06/06/1979
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19262C672 List:
References
NUDOCS 8002150409
Download: ML19262C690 (5)


Text

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ATACHMENT 2

REFERENCE:

ITEM 3 REVISED JUNE 6,1979 SUBMITTAL.

800215,o V Og

3.5.1.7 The following Reactor Trip circuitry shall be operable as indicated:

1.

Reactor trip upon loss of Main Feedwater shall be operable (as determined by Specification 4.1.a items 2 and 36 of Table 4.1-2) at greater than 5% reactor power.

(May be bypassed up to 10% reactor pswer. )

2.

Reactor trip upon Turbine Trip shall be operable (as determined by Specification 4.1.a, items 2 and 42) at greater than 5% reactor power.

(May be bypassed up to 20% reactor power.)

3.

If the requirements of Specifications 3.5.1.7.1 or 3.5.1.7.2 cannot be met, restore the inoperable trip within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or bring the plant to a hot shutdown condition.

3.5.1.8 The Decay Heat Removal system isolation valve closure tetpoints 2

shall be equal or less than 340 psig for one valve and equal to or less than 400 psig for the second valve in the suction line.

The relief valve setting for DHR system shall be equal to or less than 450 psig.

Amendment 2 42a

for protective action from a digital ESAS subsystem will not cause that subsystem to trip. The fact that a module has been removed will be con-tinuously annunciated to the operator. The redundant digital subsystem is still sufficient to indicate complete ESAS action.

The testing schemes of both the RPS and the ESAS cneb:e complete system testing while the reactor is operating.

Each channel is capable of being tested independently so that operation of individual channels may be eval-uated.

Reactor trips on loss of all main feedwater and on turbine trips will sense the start of a loss of GTSG heat sink and actuate earlier than other trip signals. This early actuation will provide a lower peak RC pressure dur-ing the initial over pressurization following a loss of feedwater or tur-bine trip event. The LOFW trip may be bypassed up to 13L to allow suf-ficient margin for bringing the MFW pumps into use at approximately 7%.

The Turbine Trip trip may be bypassed up to 20% to alles sufficient margin for bringing the turbine on line at approximately 15%.

The Automatic Closure and Isolation Systen. (ACI) is designed to close the Decay Heat Removal System (DHRS) return line isolation valves when the Reac-tor Coolant System (RCS) pressure exceeds a selected fraction of the DHRS design pressure or when core flooding system isolation valves are opened.

The ACI is designed to permit manual operation of the DiRS return line isolation valves when permissive conditions exist.

In addition, the ACI is designed to disallow manual operation of the valves when permissive conditions do not exist.

Power is normally supplied to the control rod drive meccanisms from two separate parallei 480 volt sources. Redundant trip devices are employed in each of these sources.

If any one of these trip devices fails in the untripped state on-line repairs to the filed device, when practical will be made, and the remaining trip devices will be tested.

Four hours is ample time to test the remaining trip devices and in many cases make or.-

line repairs.

The Steam Line Break Instrumentation and Control System (SL3iC) is de-signed to automatically close the Main Steam Block valves and the Main Feedwater Isolation valves upon loss of pressure in eitner of the two 4

main steam lines.

The SLEIC is also designed to be reset from its trip pcsition only when the systen, is shut down or the Main Steam line pressure is below 650 psig.

l4 REFERENCE FSAR, Section 7.1 Amendment 4 43a

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