ML20207N557

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Proposed Tech Spec Changes,Clarifying Reactor Coolant Flow Logic Testing
ML20207N557
Person / Time
Site: Point Beach  
Issue date: 01/06/1987
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20207N515 List:
References
NUDOCS 8701140287
Download: ML20207N557 (1)


Text

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TABLE 15.4.1-l'(1 of 4)

.e i

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS'AND TEST OF INSTRUMENT CHANNELS No.

Channel Description Check Calibrate Test Remarks 1.

Nuclear Power Range S(1)**

D(1)**

B/W(2)**

(1) Heat Balance-M*(3)**(4) Q*(3)**(4)

(2) Signal to AT; bistable action (permissive, rod stops, trips)

(3) Upper and lower chambers for axial.

off-set (4) Compare incore to excore axial flux difference.

Recalibrate if_the absolute difference is greater than or equal to 3 percent.

2.

Nuclear Intermediate Range S(1)**

N.A.

P(2)

(1) Once/ shift when in service (2) Log level;. bistable action (permissive, rod stop, trips)-

3.

Nuclear Source Range S(1)

N.A.

P(2)

(1) Once/ shift when in service (2) Bistable action (alarm, trips) l 4.

Reactor Coolant Temperature S

R B/W(1)**

(1) Overtemperature -AT (2).

(2) Overpower - AT 5.

Reactor Coolant Flow S**

R M**

Logic channel' testing for reactor trip on loss of reactor coolant flow in both loops shall be tested each refueling interval.

l 6.

Pressurizer Water Level

'S**

R M**

j 7.

Pressurizer Pressure S**

R M**

8.

4 KV Voltage N.A.

R M**

Reactor protection circuits only l

1 l

9.

Analog Rod Position S(1)**

R M**

(1) With step counters l

By means of the moveable incore detector system.

l Not required during periods of refueling shutdown, but must be performed prior to starting up if l

it has not been performed during the previous' surveillance period.

Tests of permissive and low power trip bistable setpoints which cannot be done during power operations shall be conducted l

prior to startup if not done in the previous two weeks.

l 8701140287 870106 PDR ADOCK 05000266 P.

PDR

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