ML20069J471

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Proposed Tech Specs Changing Axial Flux Difference Limits to Reflect Results of Cycle 8 Core Maneuvering Analysis
ML20069J471
Person / Time
Site: Wolf Creek Wolf Creek Nuclear Operating Corporation icon.png
Issue date: 06/07/1994
From:
WOLF CREEK NUCLEAR OPERATING CORP.
To:
Shared Package
ML20069J469 List:
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 TOTAL Z

ERROR

@@ y co FUNCTIONAL UNIT ALLOWANCE (TA)

_(S)

TRIP SETPOINT ALLOWABLE VALUE

1. Manual Reactor Tnp N.A.

N A.

N.A.

NA N A.

X4 e

2.. Power Range, Neutron Flux O$ z

a. High Setpoint 7.5 4.56 0

5109% of RTP*

$112.3% of RTP*

y 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

5. Intermediate Range, 17.0 8.41 0

525% of RTP*

535.3% of RTP*

a Neutron Flux 5

6

6. Source Range, Neutron Flux 17.0 10.01 0

510 cps 51.6 x 10 cps 5

g

7. Overtemperature AT 7.0 5.39 1.67 See Note 1 See Note 2 L

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

. - - ~. -

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 at RATED THERMAL POWER);

avg 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 (i) for qt ' 9b betwe

-232 % nd + 5%, fj(AI) = 0, where qt and qb are percent l

5 g

4 RATED THERMALM'ER in the top and bottcm halves of the core respectively, and qt + Absi 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

m.

.ve---

w

aae, s

s,.,

-n

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