ML21125A488
Text
UFSAR Revision 30.0 Revision: 19.1 Change
Description:
UCR-1719
Title:
Doppler Power Coefficient Used In Safety Analyses AMERICAN ELECTRIC POWER (where 100% power is 3588 MWt)
COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.0-1 Sheet 1 of 1 UNIT 2
n RCCA POSITION (FRACTION OF NOMINAL)
UFSAR Revision 30.0
UFSAR Revision 30.0 s 0.3 N
3 0.2 f
2 0.1 RCCAPOSITION (FRACTION VS. NOMINAL) 1 Figure 14.1.0-3 NORMALIZEDRCCAREACTIVITY WORTHVS. RCCA POSITION UNIT 2 July, 1993
UFSAR Revision 30.0 1
0.9 0.8 0.7 0.8 0.1 0.4 3N 0.3 0.2 0.1 0
0 1 2 3 TIME AFTER RCCA DROPBEGINS (SECONDS)
Figure 14.1.0-4 NORMALIZEDRCCA REACTIVITY WORTHVS. TIME AFTER RCCADROPBEGINS I
UNIT 2 July, 1993
UFSAR Revision 30.0 2400 PSIA
\ \ \ \
\ \
\ \ \
\ \ \ \
\ \ \
\ \ \ \
\ \ \ \ \
\ \ 8 \
- \ \
45 STEAMGENERATOR
\_ \.
'J \
\
\
\
\
SAFETY VALVES OPEN 40 S60 565 570 S7S 580 58s 5% 595 699 695 610 615 626 62S
OTAT Protect ion Lines Core Thermal Safety Limits Figure 14.1.0-s Overtemperature and Overpower AT Protection Core Conditions
- Transition Cycles
- Nominal Vessel Average Temperature = 576'F
- Nominal Pressurizer Pressure - 2250 psia UNIT 2 July, 1993 I
UFSAR Revision 30.0 I\?\\
65
\\ \\
\ \\
/\\ \\
\\ \\
\\ \
PaA \
\
\
1
\
I/\,LA
\ \
\ \
\ \
\ \
\ \ \
2250 SAFETYVALVESOPEN \ PSIA
\
8
'5 589 SOS 690 695 619 615 629 625 654
OTAT Protection Lines Core Thermal Safety Limits Figure 14.1.0-6 Overtemperature and Overpower AT Protection Core Condi'tions:
- Full VANTAGE5 Core
- Nominal Vessel Average Temperature = 581.3.F
- Nominal Pressurizer Pressure - 2100 psia.
UNIT 2 July, 1993 I
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Revised Overtemperature and Overpower T Protection AMERICAN ELECTRIC POWER Core Conditions: -Full VANTAGE 5 Fuel COOK NUCLEAR PLANT -Nominal Vessel Average Temperature = 581.3°F NUCLEAR GENERATION GROUP -Nominal Pressurizer Pressure = 2100 psia BRIDGMAN, MICHIGAN (see section 14.1.0.6-1 for discussion)
UFSAR Figure: 14.1.0-6A Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 101 100 101 102 TIME AFTER SHUTDOWN(SECONDS) figure 14.1.0-7 1979 ANS Residual Decay Heat Used In Accident Analyses UNIT 2 July, 1993
UFSAR Revision 30.0 Revision: 18 Change
Description:
UCR-1611
Title:
Rod Withdrawal from Subcritical Nuclear Power and Heat Flux AMERICAN ELECTRIC POWER Versus Time COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.1-1 Sheet 1 of 1 Unit 2
UFSAR Revision 30.0 Revision: 18 Change
Description:
UCR-1611
Title:
Rod Withdrawal from Subcritical Fuel Average AMERICAN ELECTRIC POWER and Clad Temperatures Versus Time COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.1-2 Sheet 1 of 1 Unit 2
UFSAR Revision 30.0
- 0. i 0 2 4 .6 a 10 12 14 16 ;a 20 TIrnE ISECI Figure 14.1.26-l Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 80 PCM/Sec Insertion Rate, MaximumReactivity Feedback UNIT 2 July 1991
C Fi t3 PRESSURIZER WlER VOLIJHf IF 131 PRE SSlJR I Zf R PRf SSWf I IS I II I hl L l-u al 0 iii L u In 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 c-2 0 0 0 0 0 0 0 0 0 0 0 0 0 0
nl L
Q
-(CD ii P
ifl l-l
- c UFSAR Revision 30.0 fu L
ii Q) nJ 0
UFSAR Revision 30.0 600 560 0 2 4 b 8 10 12 :4 lb :3 20 4.
3.5 3.
2.S 2.
1.* , I I.5 0 2 4 b. a 10 12 14 16 18 20 TIN ISECI figure 14.1.28-3 Rod Withdrawal at Power Core Average Temperature and ONBR Versus Time for Full Power, 80 PCM/SecInsertion Rate, Maximum Reactivity Feedback UNIT 2 July 1991
UFSAR Revision 30.0 1
0 2s so. 7S 100 12s IS0 17s 200 225 250 275 300 325 350 375 400 TIflE 1 SEC 1 figure 14.1.26-4 Rod Withdrawal at Power Nuclear Power Versus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UiJIT 2 July 1991
UFSAR Revision 30.0 1800. J /
- 0. so. 100. lS0. 200. 250. 300. 350. 400.
2000.
1800. l
- 600.
1400.
1200.
1000.
800. C
- 0. so. 100. 150. LOO. tso. 300. 350. 400.
TIM cSEc)
Figure 14.1.28-5 Rod Withdrawal at Power Pressurizer Pressure and Water Volume Versus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2 July 1991
UFSAR Revision 30.0 660 640 600 --
0 2s so 75 100 125 IS0 17s 200 225 2;O 27s 300 325 350 375 400 4.
3.5 3.
2.s J
2.
I.5 1.
0 2s so 75 100 12s 150 175 200 22S 250 27s 300 325 350 37s 400 rIna (SEC)
Figure 14.1.28-6 Rod Withdrawal at Power Core Average Temperature and ONBRVersus Time for Full Power, 4 PCM/Sec Insertion Rate, Maximum Reactivity Feedback UNIT 2 July 1991
UFSAR Revision 30.0 m-- -- -.-- -- )--..-.- - .-e-e- -
r-I
/ CQ 1L dcl 4-
- ca -
-.- oc -
-- - I\.- ----a
--- --+q+y.-- ---
- ---.-e--w---- GiI r
tL. a.. --. -- \\
1 : - f T \
. r.-. r ;
. - --__. .-..--?-. - (v
_. _ -I ;j.. \ :
e-. -
- .. ..: i ._- - ; L;, f : , ! CD.
. .- ; 1,;m . tb -:.a _ .- _ - !
5 I . _. .- [
.-- - m-e -. .. -_--_ -. ---
I -A
.: . ; --. . :.- ._ ;~ . . .
! i . i f --- -MB- _ *e--B 6 I,..m.:~~ I
. . .-.. -- L____. -_. _
-- .- , -. - - . ;:1*.:1.- !. .!
it.:..: - ,
-- - :-/-.: -.. _.. -. .._
a
. L I
I i
-. -_ m--w a-CI 0 m aD m (v
T66~ Am 2 LINn
. . W b io b c h, i
1:::: / ..f ; I..: ;
-.m m
.---_--me m
. I L
m-- WV -- --
UFSAR Revision 30.0
.-- --.- - - I - e---e - -'; w- z - _-__ --
, rn xCI
.- .- -.m-. - - -- __-.---a - -. = ; i\ .- -
i
, s:: -1
-- m-e-. _ ____ *_.-- -- F;s 2, y-m- -
---sag-
_ _ -j p ; .-..;. . \\A -/-
m 0
v
-..m..-.
__ .-.. I -**- --. --
-.-v-e --, .* - _ _---A ,-- ..-*
-- _- .m-L.- :--:-___ __ _.- --- . .
~-
-- - - _a - ._ -__ - .- -.
UFSAR Revision 30.0
- - - - I _ - - - -
.-- 7 ---. _ _
--.--- ------we_. .
_._- .-- a--*.- - - --.. - - ---.
-. .-.-.. a m-- % i .+-- -.--..-a: A - _ . _ ._ _ __ __
ao zz 2 i
-- - X ..- --- --_--- - - - --.
33 Y
x !
1 -.
-- -.-- f \ --
\ II \.
_ _- - I \
\ ,
L
.- .: .: 1 f :
\ \
-. .--. \ --. --- a- --------. -
\
-- ---- .a--._-_--_--_
e---p-
-- .- )--; -/---.. ..- ^ ---_ -
- . L
- -. :.. :.I : i.-
-_ . ---_ 1 ----- - --.-
L - =- I*- :
b t:z.: :
/ --
. .-M--w.
I.. . --. -. . I
- i - - --- ---
I UNIT 2 July 1991
UFSAR Revision 30.0 1.2000 L i
8 g ~80000 l i
i 70000 70000 9.
t 60000 +
60000 t Figure 14.1.3-1 Dropped RCCA(s)
Nuclear Power and Core Heat Flux Versus Time for a Typical Response in Automatic,Control UNIT 2 July 1991
UFSAR Revision 30.0
+
ii 550.0 l 9 t
Y 9
530.0 l w I
Y s
l 510.0 l . .
L .
- 1900.0 --
s .
i 1800.0 l .
1700.0 -9 ..
4 c Q 8 4 8 r! ?
0 d si s, e g ie s nnt csatt Figure 14.1.3-2 Dropped RCCA(s)
Average Coolant Temperature and Pressurizer Pressure Versus Time for a Typical Response in Automatic Control I
UNIT 2 July 1991
UFSAR Revision 30.0 0 1 L 3 4 6 6 7 a 9 10 TIflE [SEC 1 figure 14.1.6-l Complete Loss of Flow Core Flow Coastdown Versus Time UNIT 2 July 1991
UFSAR Revision 30.0
.8
.b
.4
.2 0.
0 1 2 3 4 5 b 7 8 9 10 2640.
2500.
2400.
2300.
2200.
2100.
2000.
1900.
1800.
- 0. 1. 2. 8. 4. 6. b. 7. 8. 9. 10.
TlnL (SEC1 Figure 14.1.6-2 Complete Loss of Flow Nuclear Power and Pressurizer'Pressure Versus Time UNIT 2 July 1991
HOT CHANNELttEAT FLUX (FRAC OF NOMINAL) AVERAGECHANNELttEAT FLUX (FRAC OF NOMINAI.)
b- L 0 . . L . 0 . . . . .
. $ l ; OD . z b . kJ A
- Q . Iu .
UFSAR Revision 30.0
UFSAR Revision 30.0 2.0 2.6.
1.8 1.6 1.4 0 1 2 3 4 5 6 7 8 9 10 TIME (SEC) figure 14.1.6-4 Complete Loss of Flow DNER Versus Time UNIT 2 July 199i
UFSAR Revision 30.0 A.4 1.2 1.
.e
.6
.4
.2 0.
0 1 2 3 4 6 6 7 8 9 10 1.4 1.2 1.
.8
.6
-4
.2 0.
0 1 2 8 4 s 6 7 0 9 10 TIllE (SEC) figure 14.1.6-5 Partial Loss of Flow l/4 Faulted Loop and Core Flows Versus Time UNIT 2 July 1991
UFSAR Revision 30.0 3
P
- 0. -
0 1 f 3 4 5 4 1 8 9 1
10 2bOO. -
2500.
2400.
2300.
2200.
2100. L 2000. .
1900. ..
1.00. a
- 0. r 1. g. 3. 4. 5. 6. 7. a. 9. 10.
TIM fSCCl Figure 14.1.6-6 Partial Loss of Flow l/4 Nuclear Power and Pressurizer Pressure Versus Time UNIT 2 July 1991
UFSAR Revision 30.0 1.4 1.2 I.
l 8
- b l 4
.2 0.
1.4 I.2 1.
.I
.b l 4
.2
- 8. c Figure 14.1.6-7 Partial Loss of Flow I/4 Average Channel and Hot Channel Heat Flux Versus Time UNIT 2 July 1991
UFSAR Revision 30.0 5.0 4.5 4.0 3.5 a
s a
3.0 2.5 2.0 1.5 \
0 I 2 3 b 5 5 7 8 9 10 TIME (SEC)
Figure 14.1.6-8 Partial Loss of Flow l/4 DNBR Versus Time UHIT 2 July 1991
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Total Core Flow and Faulted Loop Flow vs. Time For AMERICAN ELECTRIC POWER The Locked Rotor Event COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.6-9 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Nuclear Power and RCS Pressure vs. Time For The AMERICAN ELECTRIC POWER Locked Rotor Event COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.6-10 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0
. . G -
- . ~-----y
\,
I
.3 - ..
5.
Figure 14.1.6-11 l/4 Locked Rotor Average Channel and Hot Channel Heat Flux Versus Time UNIT 2 Julv 1991
UFSAR Revision 30.0 ii?O. T /
I ,.f
- tsi. 7 j
- 300. -.ii i
SOO.
TIME (SEC)
Figure 14.1.6-12 l/4 Locked Rotor Clad Inner Temperature Versus Time rJNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Minimum Reactivity Feedback With Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-1 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Minimum Reactivity COOK NUCLEAR PLANT Feedback With Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-2 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Core Average and Loop 1 Temperatures vs. Time For AMERICAN ELECTRIC POWER Loss of Load, Minimum Reactivity Feedback With COOK NUCLEAR PLANT Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-3 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Maximum Reactivity Feedback With Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-4 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Maximum Reactivity COOK NUCLEAR PLANT Feedback With Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-5 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Core Average and Loop 1 Temperatures vs. Time For AMERICAN ELECTRIC POWER Loss of Load, Maximum Reactivity Feedback With COOK NUCLEAR PLANT Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-6 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Minimum Reactivity Feedback Without Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-7 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Minimum Reactivity COOK NUCLEAR PLANT Feedback Without Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-8 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Core Average and Loop 1 Temperatures vs. Time For AMERICAN ELECTRIC POWER Loss of Load, Minimum Reactivity Feedback Without COOK NUCLEAR PLANT Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-9 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Nuclear Power and DNBR vs. Time For Loss of Load, AMERICAN ELECTRIC POWER Maximum Reactivity Feedback Without Pressurizer COOK NUCLEAR PLANT Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-10 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Pressurizer Pressure and Pressurizer Water Volume AMERICAN ELECTRIC POWER vs. Time For Loss of Load, Maximum Reactivity COOK NUCLEAR PLANT Feedback Without Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-11 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 Revision: 18.1 Change
Description:
UCR-1630
Title:
Core Average and Loop 1 Temperature vs. Time For AMERICAN ELECTRIC POWER Loss of Load, Maximum Reactivity Feedback Without COOK NUCLEAR PLANT Pressurizer Spray and PORVs NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.8-12 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 I
- ' i I
.6 i
.A :
I
.2 j I
a.
.6 Figure 14.1.9-1 Loss of Normal Feedwater Nuclear Power and Core Heat Flux Versus Time UNIT 2 July, 1992
UFSAR Revision 30.0 Revision: 20.2 Change
Description:
UCR-1815
Title:
Loss of Normal Feedwater Loop Temperature AMERICAN ELECTRIC POWER Versus Time COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.9-2 Sheet 1 of 1 UNIT 2
tQ .
w cbl cd w w 4
x l-l-W h, W fu UFSAR Revision 30.0 rl l-l ii w CM w w w L &
UFSAR Revision 30.0 20 40 60 80 100 120 140 160 180 i TIME (SEC) 540-p 520-u
=o 4 20 40 60 80 100 120 140 160 180 :
TIME (SEC)
DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)
NUCLEAR POWER TFMNSIENT Kc CORE AVERAGE TEMPERATURE vs. TLME FOR THE SINOLE LOOP FEEDWATER MALFUNCIION WlTH AUTOMATIC ROD CONTROL AT FULL POWER Figure 14.l.lOB-1 L
UNIT 2 July, 1993
UFSAR Revision 30.0 2700.
z;; 2600.
n
- 2500.
2 g 2400. t z
n 2300.
I2 z 2200.
iz I z 2100.'
E I -
2000.
1900.
I 1800.1 0. 20. 40. 60. 80. 100. 120. 140. 160. 180. 21 TIME (SEC) 5.
4.5 4.
3.5 fs B 3.
2.5 , a-2.
1.5
- 1. c 0 zo 40 60 80 100 120 140 180 160 i TIME (SEC)
DONALDC.COOK NUCLEARPLANT UNIT 2(FULL vs CORE)
PRESSURIZER PRESSURE k DNBR 8. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WlTH AUTOMATIC ROD CONTROL AT FULL POWER Figure 14.1. IOB-2 UNIT 2 July, 1993
UFSAR Revision 30.0 680 680 G:
, 040 3 620 a 000 h
e 520 t 500 0 20 40 60 80 100 120 140 160 160 2 TIME (SEC)
DONALD C. COOK NUCLEAR PLANT UNIT 2(FULL v5 CORE)
NUCLEAR POWER ?RANSIENT & CORE AVERAGE TEMPERATURE va. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WITH MANUAL ROD CONTROL AT FULL POWER Figure 14.l.lOB-3 UNIT 2 July, 1993
UFSAR Revision 30.0 2
- 2600.
h t 2500.-
2400. --
2300.'.
2200. *'
21oo.q 2000.-
lQOO.*-
1800. l
- 0. 20. 40. 60. 80. 100. 120. 140. 160. 180. 2 TIYE (SEC) 5.
1.4 0 20 40 60 80 100 120 140 180 180 2 TIME (SW DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)
PRESSURIZER PRESSURE & DNBR VI. TIME FOR THE SINGLE LOOP FEEDWATER MALFUNCTION WITH MANUAL ROD CONTROL AT FULL WWER Figure 14.l.lOB-4 UNIT 2 July, 1993
UFSAR Revision 30.0 1.4 1.2 1.
.a
.6
.4
.t 0.
0 20 40 60 80 100 120 140 160 700 660 660 640 620 600 580 560 540 520 500 u 60 10 100 120 140 160 110 200 TIRE (SEC)
DONALD C. COOK NUCLEAR PLANT UN-IT ~(FULL vs CORE)
NUCLEAR POWER TRANSIENT & CORE AVERAGE TEMPERATURE VI. TIME FOR THE MULTI-LOOP FEEDWATEX MALFUNCTION WITH AUTOMATIC ROD CONTROL AT FULL POWER
, Figure 14.1.10B-5 July, 1993 UNIT 2
UFSAR Revision 30.0 2700.
2600.
2500.
2400.
2300.
2200.
2100.
2000.
1900.
1100, 1700.
- 20. 40. 60. 10. 100. 120. 140. 160. 110. 200.
TIWE (SEC) 5.
4.5 4.
3.5 2.5 0 20 40 60 10 100 120 140 160 110 200 TIM (SEC)
DONALDC.COOK NUCLEARPLANT UNIT~~ULLVXORE)
PRESSURIZER PRESSURE & DNBR VL. TIME FOR THE MULTI-LOOP FEEDWATER MALFUNCI-ION W-ITH AUTOMATIC ROD CONTROL AT FULL FOWER Figure 14.l.lOB-6 July, 1993 UNIT 2
UFSAR Revision 30.0
.b
.c
.2 0.
0 20 40 60 10 100 120 140 160 TIHE :'SEC) 700 610 660 640 620 600 510 560 540 520 500 -- -
0 LO 40 60 10 100 120 110 160 110 200 TIHE (SEC)
DONALD C. COOK NUCLEAR PLANT UNIT ~(FULLVSCORE)
NUCLEARPOWERTRANSIENT&CORE AVERAGETEh4PERATUREv~.TIMEFOR THEMULTI-LOOPFEEDWATER MALFUNCTIONWITHMANUALROD CONTROLATFULLPOWER Figure 14.1. IOB-7 UNIT 2 July, 1993
1 UFSAR Revision 30.0 2700.
2600.
zsoo.
2400.
2300.
2200.
2100.
2000.
1900.
1100.
1700.
- 0. 20. 40. 60. 80. 100. 120. 140. 160. 1ao. 200.
TIRE (SEC) 5.
4.5 4.
3.5 0 20 40 60 10 100 120 140 160 110 200 TIRE (SEC)
DONALD C. COOK NUCLEAR PLANT UNIT SKULL vs CORE)
PRESSURIZER PRESSURE & DNBR vs. TIME FOR THE MULTI-LOOP FEEDWATER MALFUNCI7ON WTH MANUAL ROD CONTROL AT FULL POWER Figure 14.1. IOB-8 UNIT 2 July, 1993
UFSAR Revision 30.0 0 20 40 bO 80 100 120 140 1 CO 180 200 226 240 2bO 280 300 azso. .
i 2000. +
A-6 I
17fO.
1500. I 12SO
- 1000. !
750. .
500. *-
aso. *-
t
- 0. !
- 0. 40. 80. 120. 1 co. LOO. 240. 280.
TlnE (SEC1 Figure 14.1.118-l Excessive Load Increase Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback w ith Manua 1 Rod Control UNIT 2 July 1991
UFSAR Revision 30.0 so0 0 20 40 co a0 100 :20 I40 I bO 180. 200 220 240 zb0 290 300 3.2 .
- 3. a.
s.;
- i i 0
- 2.b i
2.4 5
0 2.2 0
u
- 2.
3 ud 1.8 0
l.b 1.4 .
1.2 I
- 1. C 0 20 40 co 80 100 120 .I40 I co 180 200 220 240 Lb0 280 300 rlnc I SEC 1 Figure 14.1.118-2 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Minimum Reactivity Feedback with Manual Rod Control UNIT 2 July 1991
UFSAR Revision 30.0 I. 4 F
r
- .. - -t J.
0 20 40 bo 80 100 120 I40 I CO 180 200 220 240 2bO 2ao 300 tsoo.
- czso. *-
I 3000.
1750.
1 1500. --
LZSO. ..
1000. .-
7s 0 . . *-
SOO. *-
214-a *-
- 0. J 4
- 0. 40. 80. 120. 1 b0. 200. 240. 280.
TIRE (SEC1 Figure 14.1.118-3 Excessive Load Increase Nuclear Power and Pressurizer Versus Time for Maximum Reactivity feedback with Manual Control UNIT 2 July 1991
UFSAR Revision 30.0 0 20 40 LO 80 100 120 140 lb0 I80 200 220 240 260 280 300
- 1. J 0 20 40 LO 80 100 120 140 lb. 18@ 200 220 240 2bO 280 300 ttnc ISlCl Figure 14.1.118-4 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Maximum Reactivity Feedback with Manual Control I
UNIT 2 July 1991
UFSAR Revision 30.0 2000. +
IfSO. .-
LSOO. --
1250. .-
1000. .-
tso. ..
500. .-
tso. *-
- 0. I
- 0. 40. 80. 120. 1bO. 200. 240. 280.
trn2 I stc I Figure 14.1.11B-5 Excessive Load Increase Nuclear Power and Pressurizer Pressure Versus Time for Minimum Reactivity Feedback with Automatic Rod Control UNIT 2 July 1991
UFSAR Revision 30.0 se0 LfO IL0 550 s40 530 520 510 500 0 20 40 co 80 100 f20 140 lb0 180 200 22c 240 260 280 300 2.L 2.4 2.2 2.
1.8
- 1. L 1.4 1.2 1.
0 20 48 co 80 100 120 148 lb0 18k 108 221 24I 2bO 2so 30) rlnc I see I 14.1.118-6 Excessive Load Increase Core Average Temperature and DNBR Versus Time for Minimum Reactivity Feedback with Automatic Rod Control I
UNIT 2 July 1991
UFSAR Revision 30.0
.b
.4
. 2 a.
0 20 40 b0 80 100 I20 I40 lb0 180 200 22'J 240 260 280 300
!OOO*
17SO.
1500.
izso.
1000.
7so.
soo.
aso.
0.
- 0. 40. 00. 120. 1 b0. 200. 240. 2IO.
TIRC I SEC I Figure 14.1.116-7 Excessive Load Increase Nuclear Power and Pressurizer Pressure Versus Time for Maximum Reactivity Feedback with Automatic Rod Control UNIT 2 July 1991
UFSAR Revision 30.0 sea c 570 .
SbO *-
550 --
s40 .-
s30 .
520
- 510 *-
SO0 i 0 20 40 LO 80 100 I20 140 I60 180 200 220 240 are 280 300 3.2 y
- 3. *-
3.3 i i 2.b .'
2.4 --
0 20 40 b0 a0 IO0 .t@ 140 160 1.0 200 220 240 2bO 200 300 tint 1 stc I Figure 14.1.118-8 Excessive Load Increase Core Average Temperature and ONBR Versus Time for Maximum Reactivity feedback with Automatic Rod Control UNIT 2 July 1991
UFSAR Revision 30.0 Revision: 20.2 Change
Description:
UCR-1815
Title:
Loss of Offsite Power to the Station Auxiliaries AMERICAN ELECTRIC POWER Nuclear Power and Core Flow Versus Time COOK NUCLEAR PLANT NUCLEAR GENERATION GROUP BRIDGMAN, MICHIGAN UFSAR Figure: 14.1.12-1 Sheet 1 of 1 UNIT 2
UFSAR Revision 30.0 rzo. ;
@DO.:I I THOT Figure 14.1.12-2 Loss of Offsite Power to the Station Auxiliaries Loop Temperature and Pressurizer Water Volume Versus Time July, 1992 UNIT 2