ML20136D052

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Proposed Tech Spec Table 4.1.1 Re Min Check,Calibr & Test Frequency for Protective Instrumentation
ML20136D052
Person / Time
Site: Oyster Creek
Issue date: 11/16/1985
From:
GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20136D013 List:
References
NUDOCS 8511210215
Download: ML20136D052 (1)


Text

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TAKE 4.1.1 MInDese CNEcr. CALImanTIfm ame TEST reEguEECT FIN PWTECTIVE INSTEMMENTATIon Instrument channel Check Calibrate last h 4s (Aonlies to Test and calibration) 1.

Migh tractor Pressure.

mA 1/3 me.

mote 1 By appitcation of test pressure 2.

High Drymell Pressure (Scram) mA 1/3 mo.

note 1 By appitcation of test pressure 3.

Low teactor Water" Level note 3 1/3 me.

Note 1 By appitcation of test pressure 4.

Low-tom Water Level note 3 1/3 me.

mote 1 By appitcation of test pressure 5.

utch Water Level in Scram uA 1/3 me.

Note 1 By varying level in switch coluuris Discharge volane 6.

Low-Low-tom Water Level uA 1/3 mo.

Note 1 By app 1tcation of test pressure 7.

uteh Flow in Main Steamitne 1/d 1/3 me.

mote 1 By appitcation of test pressure a.

Lou Pressure in Main Steamitne aA 1/3 me.

mote 1 By appitcation of test pressure 9.

High Drywell Pressure 1/d 1/3 me.

mote 1 By appitcation of test pressure (Core Cooling) 18.

Main Steam Isolation Valve (Scram) mA mA 1/3 me.

By eueretsing valve II.

AP90 Level uA 1/3 d uA Output adjustment using operattonal type heat balance during power operation APgM Scram Trips Note 2 1/d.

1/d.

Using butit-in caltbration equipment durine poner operatton 12.

AP9t God Blocks note 2 1/3 me.

1/mo.

Upscale and downscale 13.a. High Radiation in Main Steam 1tne 1/s 1/3 me.

1/s4.

Using butit-in calibration equipment during po=er operation

b. Sensors for 13(a) mA Each refuel NA Ustne enternal radiation source ing outage WOTE T: Intttally once/me, thereaf ter according to Fig. 4.1.1. with an interval not less than one month nor more than three months.

WOTE 2: At least daily during reactor poner operation. the reactor neutron flum peaking factor shall be estimated and the flow-referenced APen scram and rod block setttngs shall be adjusted, if necessary as spectfled in Section 2.3 Spectftcations (1) (a) and (2) (a).

NOTE 3: A daily channel check will be performed using RE ZIA and B to verify reactor mater level instrtmuentation header

.a.

operabtitty. This is valte from novomeer S.1985 to the restart from the lie outage. Otherwise, a datly channel y

check ts re wired.

La seassaa 8511210215 851116 PDR ADOCK 05000219 p

PDR

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