ML20246P259
| ML20246P259 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/17/1989 |
| From: | WISCONSIN ELECTRIC POWER CO. |
| To: | |
| Shared Package | |
| ML20246P252 | List: |
| References | |
| NUDOCS 8903280169 | |
| Download: ML20246P259 (3) | |
Text
-
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(c) for each percent that ti..
magnitude of qt ~9b exceeds -17 percent, the'AT trip setpoint shall be automatically reduced by an equivalent of 2.0 percent of rated power.
(5) OverpowerAT(1f6}
3 5
1 1+ 45)T-K6[T(1f3)-M 1aTg [K4 -K(
15 4
.l l
where indicated AT at rated power, F
]
ATo
=
T average temperature, F
=
T' 574.2 F
=
K 5
'1.089 of rated power 4
0.0262 for increasing T K
=
5 l
0.0 for decreasing T
-)
=
d 0.00123 for T 1 T' K
=
6 0.0 for T < T'
=
C
=
10 sec l
5 l
3 2 sec for Rosemont or equivalent RTD T
=
0 sec for Sostman or equivalent RTD 4
2 sec for Rosemont or equivalent RTD 1
=
0 sec for Sostman or equivalent RTD i
(6) Undervoltage 275 percent of normal voltage (7) Indicated reactor coolant flow per loop -
190 percent of normal indicated loop flow l
(8) Reactor coolant pump motor breaker open (a) Low frequency set point 155.0 HZ (b) Low voltage set point 175 percent of normal voltage.
i Unit 1 Amendment 15.2.3-3 Unit 2 Amendment 6903280169 690317 t'
PDR ADOCK 05000266 P
l PDC
[
x s
i Basis The source range.high flux. reactor trip prevents a startup accident from sub-critical conditions from proceeding into the power range.
Any setpoint within its range would prevent an excursion from proceeding to the point at which-significant thermal power is generated.(1)
The high flux low power reactor trip provides redundant protection in the power range for a power excursion beginning from low power.
This trip insures that a more restrictive trip point is used for this case than for an excursion beginning from near full power.(1)
The overpower nuclear flux reactor trip protects the reactor core against
~i reactivity excursions which are too rapid to be protected by temperature and pressure circuitry.
The prescribed setpoint, with' allowance for errors, is consistent'with the trip point assumed in the accident analysis.(3).
The overpower AT reactor trip prevents power density anywhere in the core from exceeding 108% of design power density, and includes corrections for change in l~
density and heat capacity of water with temperature, and dynamic compensation for piping delays from the core to the loop temperature detectors.
The specified setpoints meet this requirement and include allowance for instrument errors.(2)'
The overtemperature AT reactor trip provides core protection against DNB for all combina"; ions of pressure, power, coolant temperature, and axial power distribu-tion, provided only that (1) the transient is slow with respect to piping transit' delays from the core to the temperature detectors'(about 4 seconds)(5), and (2) pressure is within the range between the high and low pressure reactor trips.
Unit 1 Amendment 15.2.3-5 Unit 2 Amendment
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