ML20095E073
| ML20095E073 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 04/16/1992 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20095E069 | List: |
| References | |
| NUDOCS 9204270279 | |
| Download: ML20095E073 (8) | |
Text
___ _ _ _ - _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _. _ _ _ _ _ _ - _ _ _ _ _.
s TABLE 15.4.JEII(l?3TT5J
~
! ! (! Of i}
HINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TEST OF INSTRUMENT CHANNELS No.
Channel _ Description Chect Calibrate Tee Remarks l.
Nuclear Power Range S(l)**
D(1)**
1; i
(1) Heat Balance M(6 M*(3)**(4) Q*(3)**(4)
(2) Signal to AT; (bistable action perni :ive, rod : tops, trips)
(3) Upper and lower chambe:'s for axial off-set (4) Compare incore to excore axial flux difference. Reca11brate if the absolute difference is greater than or equal to 3 percent.
2.
Nuclear Intermediate Range S(l)**
N.A.
P(2)
(1) Once/ shift when in service (2) Log level; (bistable action permissive, rod stop, trips) 3.
Nuclear Source Range S(l)
N.A.
P(2)
(1) Once/ shift whcn in service (2) Bistable action (alarm, trips) 4.
Reactor Coolant Temperature S
t Q{lJ*?
(1} Overtemperature -&T M(4t**
(2)
(2) Overpower - AT 5.
Reactor Coolart Flow S**
R Q43 M"(1)
(1) " 610; :nd ringle leep less of-flew
- 0gic testing.
R(2)
-(P Logic ch:n7:1 testing for 7t h trip en 10:0 cf :: cter ecelant flew in both loop: shall be per-forscd each refueling interval.
6.
Pressurizer Water level S**
R Q33 gti 7.
Pressurizer Pressure S**
R Q**
HAA 8.
4 KV Voltage N.A.
R M**
Reactor protection circuits only Unit I - Amendment No. 121 9204270279 920416 May 18, 1989 Unit 2 - Amendment No. 124 PDR ADDCK 0500 6
8.
4 KV Voltage N.A.
R M**
Reacter protection circuits only 9 7_As.iT6EIR5 DIP 6sifi3nW-mas's iT
.N~a'T3(1)g**W*N,f., _E"Z?FMNiWNET~$f)1,)eulth7sEE:cTKiriEFs kin TW su m%., u,, esuu m-mosm wea y mu.s.~m..;u..gg o.u n..c. w., _= ;n.. =_.,:
,, m. s,,
g, By means of the moveable incore detector system.
O Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been m
performed during the previous surveillance period.
Tests of the permic ive end low power trip bistable setpoint which cannot be done during power operations shall be conducted ~phior to startup if not done in the previous twc weck: 'sidiilTaii[{Qnjt'sfv]l.
Unit 1 - Amendment No. 121 May 18, 1989 Unit 2 - Amendment No. 124
.y TABLE 15.4.1-1 (2 of 5)
Channel No. Description
' Check Calibrate Test Ramarks 10.' Rod Position Bank Counters S(l)**
N.A.
N.A.
(1) With analog rod position
'll. Steam Generator Level
.5**
R QD}H M(4-)**
(1) Sclud:: test Of Igic fer
- tcr trip = 1= 1= 1 ::1
=d :ete itic ::t=ti= legie fer :=itier/ feed::ter p q 4
- 12. Steam Generator low Tevif S**
R-
%~
l C61ncMdst~w1SJ3 team FloQ^ '
Feed Flow Mid d di:
~
M**
f
- 13. Charging Flow N.A.
R N.A.
- 14. Residual Heat Removal Pump Flow N.A.
R N.A.
- 15. Boric Acid Tank Level D
R N.A.
- 16. Refueling Water Storage Tank Level N.A.
R N.A.
t
- 17. Volume Control Tank Level N.A.
N.S.
-i r
- 18. Re":ctor Containment Pressure S
R Q
(1) Isolation valve signal t
- 19. Radiation Monitoring System 0
R M
(1) Radioactive Effluent Monitoring
{
Instrumentation Surveillance
.1 Requirements 4re specified in 15.7.4.
- 20. Boric Acid Control N.A.
R N.A.
- 21. Containmant Water Level M
R N.A.
- 22. Turbine Overspeed Trip
- h.A.
R M(1)**
(1) Block trip t
- 23. Accuwiator Level and Pressure S
R N.A.
[
~
- Overspeed Trip Mechanism, and Independent Turbina Speed Detection and Valve Trip System
- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during the previous surveillance period.
Unit 1 - Amendment No. 116 February 8, *989 Unit 2 - Amendment No. 119
_~;
TABLE'15.4.1-1 (3 of 5)
No. Channel Description Check Calibration Test Remarks
- 24. Containment Pressure 7,
R QM Narrow range containment pressure S
R M**
(-3.0, +3 psig excluded)
- 25. Steam Canerator Pressure S***
R QM iteam Generator Pressure S* **
R M**
M-Terbke First St;ge Pressure S**
R M**
- 26. Emergency Plan Rtdiation Survey Q
R
-Q Instruments-
- 27. Enviror: mental Monitors M
N.A.
N.A.
28 Overpressure Mitigating S
R
- 29. PORY Position Indicator S
R R
- 30. PORY Block Valve Position Q
R N.A.
4 Indicator
- 31. Safety Valve Position M
R N.A.
Indicator
- 32. POR\\
arability H.A.
R Q
Perf6rnance of a channel functional test but excluding valve operation R
H
- 33. Subcooling Margin Monitor M
R N.A.
- 34. Undervoltage on 4 KV Bus N.A.
R M**
For Auxiliary Feedwater Pump Initiation
- 35. Auxiliary Feed *ater Flow Rate Sc6 R
N.A.
Flow Rate indication will be checked Remarks at each unit startup and shutdown
- 36. Degraded 4.16 KV Voltage S
R M**
e
- 37. a.
Loss of Voltage (4.16 KV)
S' R
M**
b.
Loss of Voltage (480 V) 5 R
tt * *
- 38. 4160 V Frequency N.A.
R N.A.
s
\\
April 14* 1988 Unit 1 - Amendment No. 113 Unit 2 - Amendment No. 116 t
TABLE.15.4.1-1 (Page 4 of 5)
!!o. Channel Description Check Calibrate Test Remarks
- 39. Containment High Range Radiation S**
R H**
Calibration to be verification of response to a source.
- 40. Coutainment Hydrogen Monitor D
R/Q N.A.
Gas Calibration - Q, Electronic Calibration - R Sample gas for calibration at 2% and 6% hydroger..
- 41. Reactor Yessel Fluid Level System M
R N.A.
- 42. In-Core Thermocouple M
R N.A.
Calibration to be verification of response to a source.
- Not required during periods of refueling shutdown, but must be performed prior to starting up if it has not been performed during tca previous surveillance period.
- During cold or refueling shutdown, a check of one pressure channel per steam generator is required when the steam generator could be pressurized.
- When used for the overpressare mitigating system Oach PORY shall be dcmonstrated operable by:
1 a.
Performance of a channel functional test on the PORY actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the PORY is required operable and at least once per M -
thereafter when the PORY is required operible.
b.
Testing valve operation in accordance with the inservice test requirements of the ASME Boller and Pressure Vessel Code,Section XI.
I Unit 1 - Amendment No. 113 April 14, ;988 Unit 2 - Amendment No. 116
a TABLE 15.4.1-1 (Page 5 of 5)
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.S - Each Shift M - Monthly D - Dail;
'P - Prior to each startup if not done previous week.
W - Weekly R - Ecch Refueling intereal (But not to exceed 18 months).
B/W - Biweekly.
N.A. - Not applicable..
Q - Quarterly Not requir2d during periods of refueling shutdown, but must be performed prior to starting up if it has not been.
performed during the previous. :.urveillance interval.
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