ML20069J471

Proposed Tech Specs Changing Axial Flux Difference Limits to Reflect Results of Cycle 8 Core Maneuvering Analysis

ML20069J471
Person / Time
Site:	Wolf Creek
Issue date:	06/07/1994
From:	WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20069J469	List: ML20069J466 ML20069J471
References
NUDOCS 9406150009
Download: ML20069J471 (2)

Text

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Attachment IV to VT 94-0006 Page 2 of 3 .

TABLE 2 2-1 T 04 @ REACTOR TRIP SYSTEM INSTRUMENTAT!ON TRIP SETPOINTS c4 m o SENSOR fE co FUNCTIONAL UNIT TOTAL ALLOWANCE (TA)

Z ERROR

_(S) TRIP SETPOINT ALLOWABLE VALUE

@@ y ,.

1. Manual Reactor Tnp N.A. N A. N.A. NA N A.

X4 e 2.. Power Range, Neutron Flux O$ zy a. High Setpoint 7.5 4.56 0 5109% of RTP* $112.3% of RTP*

00

38$ b. Low Setpoint 8.3 4.56 0 $25% of RTP* 528.3% of RTP*

.Obs

",3 3. Power Range, Neutron Flux, 2.4 0.5 0 54% of RTP* with 6.3% of RTP* with High Positive Rate a time constant a time constant 22 seconds 22 seconds

4. Power Range, Neutron Flux, 2.4 0.5 0 54% of RTP* with 56.3% of RTP* with High Negative Rate a time constant a time constant 22 seconds 22 seconds Y

a 5. Intermediate Range, 17.0 8.41 0 525% of RTP* 535.3% of RTP*

Neutron Flux

$ 6. Source Range, Neutron Flux 17.0 10.01 0 5105 cps 51.6 x 106 cps 5 <

g 7. Overtemperature AT 7.0 5.39 1.67 See Note 1 See Note 2 rt 4.86 Z

? 8. Overpower AT 4.6 2.02 0.14 See Note 3 See Note 4 p 9. Pressurizer Pressure-Low 3.7 0.71 2.49 21915 psig 21906 psig

,I 10. Pressurizer Pressure-High 7.5 0.71 -,

52385 psig 52400 psig

,b 11. Pressurizer Water Level-High 8.0 2.18 'J 592% of instrument 593.9% of instrument g span span e

• RTP = RATED THERMAL POWER

• • Loop design flow - 93,600 gpm

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Attachment IV to VT 94-0006 .

Page 3 of 3 , ,

TABLE 2.2-1 (Continued)

@ TABLE NOTATIONS (Continued) m Q_ NOTE 1: (Continued) m

$ T' < 586.5'F (Nom:nal T avg at RATED THERMAL POWER);

K3 = 0.000671; e

H P = Pressurizer pressure, psig; w

P' = 2235 psig (Nominal RCS operating pressure);

S = t.aplace transform operator, s-1; and fj(Al)is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that g (i) for qt ' 9b betwe -2325% nd + 5%, fj(AI) = 0, where qt and qb are percent l 4 RATED THERMALM'ER in the top and bottcm halves of the core respectively, and qt + Abs i total THERMAL POWER in percent of RATED THERMAL POWER; (ii) for each percent that the magnitud - qb excee -2325%, he AT Trip Setpoint shall be automatically reduced .274-8% of its valu ED THERMAL POWER; and (iii) for each percent that the magnitude of exceeds +5%, the AT Trip Setpoint shall be automatically reduced b of its value at RATED THERMAL POWER. l

z:

? NOTE 2: nners maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more than d' 1.34-8 of AT span. l M

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