ML20154C194

Proposed Tech Specs Table 15.4.1-1 Re Min Frequencies for Checks,Calibrations & Tests of Instrument Channels

ML20154C194
Person / Time
Site:	Point Beach
Issue date:	09/28/1998
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20154C190	List: ML20154C194 NPL-98-0768, Application for Amends to Licenses DPR-24 & DPR-27,adding Notation Definition Contained in TS Table 15.4.1-1, Min Frequencies for Checks,Calibrations & Tests of Instrument Channels, Per NUREG-1431
References
NUDOCS 9810060188
Download: ML20154C194 (3)

Text

.

TABLE 15.4.1-1 (continued)

PLANT CONDITIONS M

CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REOUIRED i

- 20.

Auxiliary Feedwater Fkmrate (13)

R ALL

-r i

[

21.

Boric Acid Control System R

ALL 22.

Boric AcidTankIxvel D-R ALL i

23.

Charging Flow R

ALL 24.

Condensate Storage Tank Imtl S(l)

R ALL i

~

25.

Containment High Range Radiation M(1)

R(14)

ALL i

26.

Containment Hydrogen Monitor D

ALL r

-Gas Cahkation Q(15)

ALL

-Electrome Calibration R

ALL l

27.

Containment Pressure S

R

' Q(1,3,9)

ALL

- t 28.

Containment Water Level M

R ALL 29.

Emergency Plan Radiation l

Survey Instruments Q

A Q

- ALL 4

30.

Environmental Monitors M

ALL 31.

In-Core TMnWes M

R(14)

ALL 32.

1.mv Temperature Overpressure Protectum System S(12)

R (10)

ALL i

i 33.

PORV Block Vahe Position Indicator Q

R ALL 34.

PORV Operability R

Q(11) -

ALL l

35.

i'ORV Position Indicator S(21)

R R

ALL L

l Unit 1 - Amendment No.

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TABLE 15.4.1-1 (continued)

PLANT CONDITIONS-

_N_O CHANNEL DESCRIPTION CHECK-CALIBRATE TEST WHEN REOUIRED m

36.

Radiation Monitoring System

- RE-218 WDS Liquid Monitor (7)

R(14)

Q ALL

- RE-223 Waste Distillate Overboard Monitor (7)

R(14)

Q ALL

- RE-231 A Steam Line Release Monitor M(1)

R(14)

ALL

- RE-232 B Steam Line Release Monitor -

M(1)

R(14)

ALL

- RE-101 Control Room Monitor S

R(14)

Q ALL

- RE-235 Control Room Noble Gas Monitor S

R(14)

Q ALL

-RE-215 AirEjectorMonitor D(1)

R(14)

ALL 37.

Reactor Vessel Fluid Level System M

R ALL-38.

Refueling Water Storage Tank Level R

-ALL 39.

Residual Heat Removal Pump Flow R

ALL 40.

Safety Valve Position Indicator M

R ALL 41.

Subcooling Margin Monitor M

R ALL 42.

Deleted l43.

Volume Control Tank Level A

ALL 44.

Reactor Protection System and M(1,23)

ALL Emergency Safety Feature Actuation System Logic 45.

Reactor Trip System Interlocks

-intermediate Range Neutron Flux, P-6 R(24)

R ALL

-Power Range Neutron Flux, P-8 R(24)

R ALL

-Power Range Neutron Flux, P-9 R(24)

R ALL

-Power Range Neutron Flux, P-10 R(24)

R ALL

-1st Stage Turbine Impulse Pressure R(24)

R ALL l

Unit 1 - Amendment No.

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NOTATION USED IN TABLE 15.4.1-1 l A-Annually (12 months)

S-Each shiA D-Daily W-Weekly Q-Quarterly M-Monthly P-Prior to reactor criticality if not performed during the previous week.

l R-Each refueling intenal(18 months)

- PWR-Power and Low Power Operation, as defined in Specifications 15.1.h. and 15.1.ra.

HOT S/D-Hot Shutdown, as defined in Specincation 15.1.g.l.

COLD S/D-Cold Shutdown, as defined in Specification 15.1.g.2.

REF S/D-Refueling Shutdown, as defined in Specification 15.1.g.3.

i I

ALL-All conditions of operation, as defined in Specifications 15.1.g, h, and m.

NOTES USED IN TABLE 15.4.1-1 (1)

Not required during periods of refueling shutdown, but must be performed prior to reactor criticality ifit has not been performed during the presious surveillance Period.

(2)

Tests of the low power trip bistable setpoints which cannot be done during power operations shall be conducted prior to reactor criticality if not done in the previous surveillance inten21.

(3)

Perform test of the isolation valve signal.

(4)

Perform by means of the moveable incore detector system.

(5)

Recalibrate if the absolute difference is 23 percent.

j (6)

Verification of proper breaker alignment and that the 120 Vac instrument buses are energized.

(7)

Source check is required prior to initiation of a release. Source check is an assessment of channel response by exposing the detector to a source ofincreased radiation.

i Channel check is required shiRly during a release. If monitor or isolation function is discowred inoperable, discontinue release immediately.

(8)

Verify that the associated rod insertion limit is not being violated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> whenever the rod insertion limit alarm for a control bank is inoperable.

(9)

Test of Narrow Range Pressure,3.0 psig, -3.0 psig excluded.

l l

Unit 1 - Amendment No.

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