ML20101B581
| ML20101B581 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 05/29/1992 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20101B574 | List: |
| References | |
| NUDOCS 9206040202 | |
| Download: ML20101B581 (1) | |
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which automatically initiates appropriate action to prevent exceed.g established J
limits.
Safety is not compromised, however, by continuing operation w.'k certain instrumentation channels out of service since provisions were made for this in j
the plant design.
This specification outlines limiting conditions for opert. tion I
necessary to preserve the effectiveness of the Reactor Control and Protection System when any one or more of the chhnnels is out of service.
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Almost all reactor protection channels are supplien with cufficient redundancy to l
provide the capability for channel calibration and '.est at power.
Exceptions are j
backup channels such as reactor coolant pump breakers.
The removal of one trip channel on process control equipment is accomplished by placing that channel i
bistable in a tripped mode; e.g., a two-out-of-three circuit becomes a one-out-f of-two circuit. Tiie source and intermediate range nuclear instrumentation system channels are not intentionally placed in a tripped mode sluce these are one-out-of-two trips, therefore the trips are bypassed during testing. Test 4eg-of4he l
RIS power range channel requires bypan hg-the-Deepped-Rod protectica from MIb for the ch uncl being tested.
However, the P,cd Pc;itien-Gystem-still prov4es the dropped rod preteetient Testing does not trip the system unless a trip condition exists in a concurrent channel.
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The operability of the accident monitoring instrumertation ensures that j
sufficient information is available in selected plant parameters to monitor and i
assess these variables during and following an accident. The PORY block valves i
have local, external indication of whether the block valve is open or shut.
If necessary, this local indication can be visually verified during a containment
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entry inspection to verify the block valve is shut.
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The subcooling displays are comprised of two separate channels which reccive temperature and pressure information directly from installed instrumentation.
These channels display the temperature differential between the sensed conditions 9206040202 920529 15.3.5-5 May 18, 1992 PDR ADOCK 05000266 P
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