Text

Proposed Tech Spec Re ESFAS Instrumentation Trip Setpoints
	ML20135F160
Person / Time
Site:	Catawba
Issue date:	09/10/1985
From:	; DUKE POWER CO.
To:	;
Shared Package
ML20135F155	List: ML20135F151; ML20135F160;
References
	NUDOCS 8509170175
	Download: ML20135F160 (19)
	v • d • e

._ _ _ _ _ _ _ _ _ _ _ . .- ._ .- - . . . _ _ _ _ . _ - _ _ _ . _. ____ _ . . _

TABLE 3.3-4 (Continued) i S ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS

, E c= -

a SENSOR TOTAL ERROR FUNCTIONAL UNIT ALLOWANCE (TA) (S) TRIP SETPOINT ALLOWABLE VALUE

[

z Z_

]

8. Auxiliary Feedwater (Continued)

c. Steam Generator Water 17 14.2 1.5 1 17% of span 1 15.3% of

Level - Low-Low from 0% to span from 0% to 30% RTP 30% RTP increasing increasing linearly to -

linearly to > 334% of span 3 i

.O T 54-9% of from 30% to 100%

span from 30% RTP

to 100% RTP

] w d. Safety Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

D

e. Loss-of-Offsite Power N.A. N.A. N.A. 1 3500 V > 3200 V

Trip of All Main Feedwater

f.

j Pumps N.A. N.A. N.A. N.A. N.A.

j g. Auxiliary Feedwater Suction i Pressure-Low -

4

! 1) 1 CAPS 5220, 5221, 5222 N.A. N.A. N.A. > 10.5 psig 1 9.5 psig

2) 1 CAPS 5230, 5231, 5232 N.A. N.A. N.A. > 6.2 psig > 5.2 psig l

j 9. Containment Sump Recirculation I a. Automatic Actuation Logic N.A. N.A. h.A. N.A. N.A.

and Actuation Relays

b. Refueling Water Storage . N.A. N.A. N.A. > 177.15 in hes > 162.4 inches Tank Level-Low i Coincident With Safety

) Injection See Item 1. above for all Safety Injection Setpoints and Allowable Values.

j 8509170175 850910 fDR ADOCK 05000413 PDR , - _ .. -. - _

i i

I g TABLE 2.2-1 (Continued)

! $ REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS 5

l

( TOTAL ALLOWANCE SENSOR ERROR I E FUNCTIONAL UNIT (TA) Z_ (S) TRIP SETPOINT ALLOWABLE VALUE

" 13. Steam Generator Water 17 14.2 1.5 >17% of span -

>15.3% of span from Level Low-Low irom 0%'to 30% 0% to 30% RTP*

RTP* increasing increasing linearly 4o,o A nearly to to 139-4% of span 2 54r9% of span from 3 00% RTP*

r 30% to 100% yg,3

14. Undervoltage - Reactor 8.57 0 1. 0 277% of bus 276% (5016 volts)

Coolant Pumps voltage (5082 volts) with a 0.7s response time

15. Underfrequency - Reactor 4,0 0 1.0 >56.4 Hz with a ->55.9 Hz

[ Coolant Pumps .

6.2s response time

16. Turbine Trip

a. Low Control Valve EH N.A. N.A. N.A. 1550 psig 1500 psig Pressure

b. Turbine Stop Valve N.A. N.A. N.A. 11% open 11% open Closure '

i 17. Safety Injection Input N.A. N.A. N.A. N.A. N.A.

from ESF

RTP = RATED THERMAL POWER

~

D t TABLE 3.3-2 (Continued)

U g REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES 5

e FUNCTIONAL UNIT RESPONSE TIME C

h 12. Low Reactor Coolant Flow

a. Single Loop (Above P-8) i I second

b. Two Loops (Above P-7 and below P-8) i I second

13. Steam Generator Water Level-tow-Low i M seconds 3. f

14. Undervoltage-Reactor Coolant Pumps i 1.5 seconds

15. Underfrequency-Reactor Coolant Pumps _< 0.6 second

16. Turbine Trip

'[

a. Low Control Valve EH Pressure N.A.

y b. Turbine Stop Valve Closure N.A.

co

17. Safety Injection Input from ESF N.A.

18. Reactor Trip System Interlocks N.A.

19. Reactor Trip Breakers N.A.

20. Automatic Trip and Interlock Logic N.A.

i 4

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o 7

g 500 -

z.

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0 e

m g 1 i ii11ll l l llllll l lllllll l lllllll I 5 10 5 10 2 5 10 3 5 10 4

TIME (SEC)

Nuclear Power and Steam Generator Pressure Transients for Loss of Of fsite Power CATAWBA NUCLEAR STATION Figure 15.2.6-1 9

a 14429 2

_ i lIllill i i l ilill i 1 lllill 1 l iilill 3

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~

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800 -

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TIME (SEC)

Pressurizer Pressure and Water Volume Transients for Loss of Offsite Power CATAWBA NUCLEAR STATION Figure 15.2.6-2

t. .

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TIME (SEC)

Reactor Coolant Temperature i Transient for Loss of Of fsite Power CATAWBA NUCLEAR STATION Figure 15 2.6 3 1

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TIME (SEC)

Nuclear Power and Steam Generator Pressure Transients for Loss of

~

Normal Feedwatu CATAWBA NUCLEAR STATION Figure 15.2.71

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TIME (SEC)

Pressurizer Pressure and Water Volume Transients for Loss of Normal Feedwater CATAWBA NUCLEAR STATION Figure 15.2.7 2 L

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EE h~ 650 -

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gg 600 -

s N 575 - COLD -

cc -

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.-~ .

575 coto f w E n. 550 -

o mo .

8' 525 -

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5 10 4

TIME (SEC)

Reactor Coolant Temperature Transient for Loss of Normal Feedwater CATAWBA NUCLEAR STATION Figure 15.2.7 3 l

l

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Nuclear Power Transient, Total Core Reactivity Transient, and Feedline Breakflow Transient for Main Feedline Rupture with Offsite Power Ava:lable CATAWBA NUCLEAR STATION Figure 15.2.81 f

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c

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r-200 6 - 2.50 ;

O I i

de

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1 5 10 5 10 2 5 103 5 104 TIME (SEC)

Pressurizer Pressure, Water Volume, and Relief Transients for Main Feedline j Rupture with Offsite Power Available CATAWBA NUCLEAR STATION Figure 15.2.8 2 s

,- - , - - - -- n --- -

~

k. 14429 9 700 i i i uuij a i iiniij i e 6 eivil i i e oiii -

H$

z >g 675 -

~

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HOT LEG

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n 650 -

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0 0 y y ,600 -

\

575 - COLD LEG h.

550 ' '"I "'"I "'"I "'"

l 5 10 5 102 5 103 5 10 4 TIME (SEC)

Reactor Coolant Temperature Transients for the Faulted and the intact Loops for Main Feedline Rupture with Of(site Power Available CATAWBA NUCLEAR STATION Figure 15.2.8 3

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m S 1250 -

W INTACT STEAM-GENERATOR h

m 1000 RECEIVING -

AUXILIARY m FEED'*ATER E

' 750 -

g INTACT STEAu GENERATORS NOT O RECEIVING H AUXILIARY

< FEEDWATER E 500 -

E E

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rAlf TED STEAM

, y [ GENERATOR H

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Steam Generator Pressure and Core Heat Flux Transients for Main Feedline Rupture with Offsite Power Available CATAWB A NUCLEAR STATION Figure 15.2.8 4

l

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Nuclear Power Transie'nt, Total Core Reactivty Transient, and Feedline Breakflow Transient for Main Feedline Rupture without Offsite Power Available CATAWBA NUCLEAR STATION Figure 15.2.8 5

- e- ,- m --m p ~ y w y - w- e w ------

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Pressurizer Pressure, Water Volume, and Relief Rate for Main Feedline Rupture without Offsite Power Available CATAWBA NUCLEAR STATION Figure 15.2.8 6

.. . . ~ , .

. B.*

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Hk 525
$ $Q] -
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<L-gg3575 g
s= e -
COLD LEG O O
. y w y 550 - ;
1 esd ay g 525 -
500 ' ""I "I ""'I "'"
l 5 10 5 102 5 103 5 10 4 TIME (SEC)
Reactor Coolant Temperature Transients for the Faulted
' and intact Loops for Main Feedline Rupture without Offsite Power Available
. CATAWBA NUCLEAR STATION Figure 15.2.8 7
. i*
}
)
su n .s<
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INTACT STEAM RECE V
@ ' o*
ME!WEX :
750 -
INTACT STEAM ogngnarons nor h
p RECEIVING
< AUXILIARY FEEONATER 500 -
W 2 250 -
y FAtJLTED STEAM GENERATOR
$ 0 l.2
~
I.0 -
N 8
Q O.B -
_E g 0.6 -
. d g 0.4 -
W '
O.2 -
U O I I I IIIII I I IIllI! I"i ' ' ' '
M i 5 10 5 10 2 5 103 5 104 TIME (SEC)
Steam Generator Pressure and Core Heat Flux Transients
' for Main Feedline Rupture without Offsite Power Available CATAWBA NUCLEAR STATION Figure 15.2.8 8
.

ML20135F160

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