ML20248C665

Proposed Tech Specs Providing Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses

ML20248C665
Person / Time
Site:	Point Beach
Issue date:	05/28/1998
From:	WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20248C660	List: L-98-431, Application for Amends to Licenses DPR-24 & DPR-27,modifying TS to Provide Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses.Rev 1 to Calculation 9334281-01 Re RCP Internal Voltage Decay,Encl ML20248C665 ML20248C684 NPL-98-0431, Application for Amends to Licenses DPR-24 & DPR-27,modifying TS to Provide Specific Numerical Setting for Rt,Rcp Trip & AFW Initiation on Loss of Power to 4 Kv Buses.Rev 1 to Calculation 9334281-01 Re RCP Internal Voltage Decay,Encl
References
NUDOCS 9806020219
Download: ML20248C665 (4)

Text

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4 NPL 98-0431 Edited Technical Specification Pages l

l 9996020219 990528

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l PM ADOCK 05000266

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(c) for each percent that the magnitude of q,- q3 exceeds -17 percent, the AT trip setpoint h

shall be automatically reduced by an equivalent of 2.0 percent of rated power.

1 (5)

Overpower

, AT (1 + 13S)

I s aT [K4 - K5( 'S 'l)(l ~ T S)T-K.[T(l' T 8)- T'))

t s 4

4 where (values are applicable tb operation at both 2000 psia and 2250 psia) indicated AT at rated power, F AT,

=

average temperature, *F T

=

T s

572.9'F*

K, s

1.09 of rated power

• 0.0262 for increasing T K

=

5 0.0 for decreasing T

=

0.00123 for T 2 T l

K

=

6 0.0 for T < T

=

10 see

=

5 2 sec for Rosemont or equivalent RTD

=

T3 0 see for Sostman or equivalent RTD 2 see for Rosemont or equivalent RTD ta

=

0 see for Sostman or equivalent RTD 3120V.

(6)

Undervoltage - 275 r.

.a m, uviu m.

, vumr (7)

Indicated reactor coolant flow per loop -

290 percent of normal indicated loop flow (8)

Reactor coolant pump motor breaker open (a)

Low frequency set point 255.0 HZ (b)

Low voltage set point 275 percent of nc mal voltagc. 312DV.

These values apply to Unit 2 following U2R22 and to Unit i following UlR24. Prior to l

UlR24, the values for Unit 1 are: T s 573.9'F and K, s 1.089 of rated power.

+

Unit 1 - Amendment No.173 15.2.3-3 NRC Correction letter issued Unit 2 - Amendment No.177 July 31,1997

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as actuated by either high current, low supply voltage or low electrical fre-quency, or by a manual control switch. The significant feature of the breaker h

~

trip is the frequency setpoint, 55.0 }iZ, which assures a trip signal before the pump inertia is reduced to an unacceptable value. The high pressurizer water level reactor trip protects the pressurizer safety valves against water relief.

The specified setpoint allows adequate operating instrument error") and transient overshoot in-level before the reactor trips.

The low-low steam generator water level reactor trip protects against loss of feedwater flow accidents. The specified setpoint assures that there will be sufficient water inventory in the steam generators at the time of trip to allow for starting delays for the auxiliary feedwater system.")

Numerous reactor trips are blocked at low power where they are not required for protection 'and would otherwise interfere with normal plant operations. The prescribed setpoint above which these t' rips are unblocked assures their availability in the power range where needed. Specifications 15.2.3.2. A(1) and 15.2.3.2.C have 1% tolerance to allow for a 2% deadband of the P10 C) bistable which is used to set the limit of both items. The difference between the nominal and maximum allowed value (or minimum allowed value) is to account for "as measured" rack drift effects.

W is whodg on readw ccd"^r p=P Sustained 4 operation with erly one prp ""' not.ha permitted b:ve 5 percer.t bet If a pump is lost while operating b&ee"oy 5 percent :nd 50 percent w.

power, an orderly and

$$tYr:ductier " power hvel t; behw 3.5 pecent is allowed.

The power-to-flow ratio will be maintained equal to or less than unity, which ensures that the minimum DNB ratio increases at lower flow because the maximum enthalpy rise does not increase above the maximum enthalpy rise which occurs during full power and full flow operation.

References

")

FSAR 14.1.1

")

FSAR 14.3.1 FSAR 3.2.1

")

")

")

FSAR, Page 14-5

").

FSAR 14.1.2 FSAR 14.1.9

")

FSAR 14.2.6

")

")

FSAR 7.2, 7.3 FSAR 14.1.11 Unit 1 - Amendment No. 142 15.'2.3-7 October 27, 1993 Unit 2 - Amendment No. 146

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