ML17226A116
| ML17226A116 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 07/28/2017 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards |
| Shared Package | |
| ML17226A087 | List:
|
| References | |
| RBG-47776, RBF1-17-0089 | |
| Download: ML17226A116 (35) | |
Text
16(
140 1m 1w 8C 60 40 D
P U
w a 8
0 Lu c
4 U
/
0 G
NATURAL PUMP CtRCULATlON 20 40 60 80 100 0
CORE FLOW (Y RATED)
FIGURE 15.0.1 im GENERIC POWER/FLOW MAP RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
100 80 20 SCRAM WORTH AT 100% = -$37.05 0
0.5 1.o 1.5 2.0 2.5 3.O 3.5 TIME AFTER SENSED PLANT VARIABLE EXCEEDS SCRAM SETPOINT (sec)
FIGURE 15.0-2 SCRAM REACTIVITY CHARACTERISTICS
120 100 n
0 00 6
8 E c
-~
SCRAM TECHNICAL SPECIFICATION ROD POSITION TIME
% INSERTION SECONDS 0
1 10 40 75 0.060 4 0.100 - 0.1w 0.060 + 0.138 - 0.188 0.060 + 0.317 - 0.307 0.060 + 0.874 - 0.924 0.050 + 1.020 - 1.07 0.5 1.o 1.5 2.0 2.5 3.O I
3.5 4.0 FIGURE 15.0-3 SCRAM TIME CHARACTERISTICS RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
40 30 I-2 20 w a 10 RIVER B CORE EOC1 RIVER BEND EOEC 0
I 1
0.02 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 FRACTIONAL 1 NSERTION FIGURE 15.0-4 CONTROL CELL CORE SCRAM R EACTlVlTY COMPARISON
~~-
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
150.
(1 LOO, w
+
B ux 1
- 10.
- 20.
- 0. 0.
TINE ISEC) 2 5
~
- 20.
UO.
- 0.
- 10.
-25.
TIME [SECI
.II FEEOURTEA FLOW 150.
t 4
- 20.
- 30.
110.
- 0. - 1 1 I ' '
4
- 10.
TIME (SECl
- 0.
- 1.
z -1.
I
-2, FIGURE 15.1-1 Percent rated power referenced to 2894 MWt LOSS OF FEEDWATER HEATER, REVISION 17 AUTO FLOW CONTROL RIVER BEND STATION UPIWT"' SAFETY ANALYSIS REPORT
LL 0
c I NEUTRON FLUX 2 AVE SURFACE HEAT 3 CORE INLET FLOW CORE INLET SUB
- 0.
- 25.
- 65.
I VESSEL PRES RISE ( P 2RELlEF VALVE FLOW FLUX 3 BYPASS VALVE FLOW 125.
- 75.
- 25.
I \\
I
.I C.
2c.
- 43.
EL.
- 80.
TlME (SEC)
TlME (SEC)
I LEVEL(INCH-REF-SEP-SKIRT 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 150.
4 FEEDWATER FLOW 1 FIGURE 15.1-2 Percent rated power referenced to 2894 MWt REVISION 17 LOSS OF FEEDWATER HEATE I
MANUAL FLOW CONTROL RIVER BEND STATION I UPDATED SAFETY ANALYSIS REPORT
Percent rated power referenced to 3039 MWt REVISION 17 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT FEEDWATER CONTROLLER FAILURE FIGURE 15.1-3 TIME (SECONDS)
TIME (SECONDS)
TIME (SECONDS)
TIME (SECONDS)
REACTIVITY COMPONENT(S)
(PERCENT OF RATED)
I NEU 1011 FlUX 2 AV( SUIIHtt H~~ ~ nux I VES ~~-paul a B~IPIII HOI uur no 2 SAF "um ~:
I M~ f I ~~L lf ~AU ~i i!
~
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( ~
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z UJ u
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IM.t
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rr r-..-.
lt.t TIME (SECONDS)
TIME (SECONDS)
I I.EY L II NCH -lll' rP*SitiiTI 2VU tl STUNlC
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UJ FIGURE 15.2-1 0::
PRESSURE REGULATOR
- Itt. I ***
ll.t -
- l.t ***
DOWNSCALE FAILURE TIME (SECONDS)
TIME (SECONDS)
Percent rated power referenced to 3039 MWt RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVI SION 17
150.
0 100.
E a
!+
U I-z 8 50.
a W
- 0.
FLUX 300.
200.
I NEUTRON FLUX 2 AVE SURFACE HEAT 3 CORE INLET FLOW I VESSEL PRES RISE (PSI) 2 SAFETY VALVE FLOW
- 3RELlEF VALVE FLOW 4 BYPASS VALVE FLOW
- 2.
- u.
- 6.
8.
TIME (SECI TIME (SECI I LEVEL(INCH-REF-SEP-SKIRT 12 VESSEL STEAMFLOW I
I I
3 TURBINE STEAMFLOW r,
4 FEEDWATER FLOW I
TIME (SEC)
M
- n z
W 7
D CL x er, CI
+
- 0.
k-
-1.
I k-u W
a a
-2.
I VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY
- 2.
- 4.
- 6.
- 8.
TIME [SEC)
FIGURE 15.2-2 GENERATOR LOAD REJECTION, TRIP SCRAM, BYPASS-ON RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDAT ED SAFETY ANALYSIS REPORT
Percent rated power referenced to 3039 MWt REVISION 17 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT LOAD REJECTION WITH BYPASS FAILURE FIGURE 15.2-3 TIME (SECONDS)
TIME (SECONDS)
TIME (SECONDS)
TIME (SECONDS)
REACTIVITY COMPONENT(S)
(PERCENT OF RATED)
I 0
W c
U U
L L 0
I-z W u w
a I NEUTRON FLUX 2 AVE SURFACE HEAT 3 CORE INLET FLOW 150.
100.
- 50.
- 0. 0.
- 2.
- 4.
- 6.
- 8.
TIME ISECI FLUX I
I
-loo.o. F...,....I
- 2.
- 11.
I TIME (SECI I LEVEL (INCH-REF-SEP-SKIRT 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW
- 1.
5 1
I I
4
- 8.
I VESSEL PRES RISE (PSI) 2 SAFETY VALVE FLOW 3 RELIEF VALVE FLOW 4 BYPASS VALVE FLOW I
~
- 0.
I VOID REACTIVITY 2 DOPPLER REACTIVITY 3 SCRAM REACTIVITY
- 2.
- u.
- 6.
- 8.
TIME ISECl Percent rated power referenced to REVISION 17 2894 MWt IIGURE 1 5.2-4 TURBINE TRIP, TRIP SCRAM, BYPASS AND RPT - ON RIVER BEND STATION r
UPDATED SAFETY ANALYSIS REPORT
1 H£UTIOtFlUI 2 AV( SU fACt ~EAT FL
! COlt I E.l rlOII I M,IL_~~------~---------+-----------r----;
o I
I w
I f-
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~ IM.tj <.Iii C LL 0
f-z w
~
w....
e::
- t.
TIME (SECONDS) l lE. Yf.LI IICH**lF *S£1'* ITJ 2 VtsSEL lftAIIILON 3 TUIIIII Sf£AULOII t.... '
.. I
- I*.*.*
TIME (SECONDS) l VESSEL PIUI RIUII'S I 2 UfUY 'UU£ rLOII
'lli.m ~!Hf n&!
~
I I
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TIME (SECONDS) 1 ** ~\\ I
't' lJlO', ** C!)IIJI I
l (fl i=
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JJ
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TIME (SECONDS)
Percent rated power referenced to 3039 MWt FIGURE 15.2-5 TURBINE TRIP WITH BYPASS FAILURE RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17
Percent rated power referenced to 3091 MWt FIGURE 15.2-6 THREE-SECOND CLOSURE OF ALL MAIN STEAM ISOLATION VALVES WITH POSITION SWITCH SCRAM RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 25
1 VESSEL PRES RISE (PSI) 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW I
Percent rated power referenced to 2894 MWt REVISION 17 FIGURE 15.2-7 LOSS OF CONDENSER VACUUM AT 2 INCHES PER SECOND RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
i-
.ux I
- 1. VESSEL PRES RISE f PSI) 2.RELIEF VALVE FLOW 3.BYPASS VALVE FLOW 300.
I. LEVEL (INCH-REF-SEP-SKIRT) 2.VESSEL STEAMFLOW 3.TURBINE STEAMFLOW
- 4. FEEDWATER FLOW
- 1.
I
-2.
- 40.
I FIGURE 15.2-8
- 1. VOID REACTIVITY
- 2. DOPPLER REACTIVITY
- 3. SCRAM REACTIVITY
- 4. TOTAL REACTIVITY LOSS OF NORMAL AND PREFERRED STATION SERVICE TRANSFORMERS RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
150.
G loo.
tr_
h 6 50.
J:
n:
+-
< J C:
- 0.
- 0.
- 2.
- u.
- 6.
TIM ISECI 200.
100.
- 0.
-1 00. 0.
- 2.
1 LEVEL (INCH-REF-SEP-SKIRT) 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW
- i I
4
- 6.
- 8.
TIM ISECl 300. -
1 VESSEL PRES RISE (PSI) 2 RELIEF VALVE FLOW 3 SAFETY VALVE FLOW ( )
4 RELIEF VALVE FLOW ( )
5 BYPASS VALVE FLOW ( )
l-M
- 0.
- 0.
- 1.
r
- 0.
B ::
z W
=,
-1.
w c
3 8
-2.
-P 4
1 VOID REACTIVITY 2 DOPVEACTIVITUC
.J3-SCRAM REACTIVITY -
4 TOTAL REACTIVITY 1
- 4.
- 6.
T I E ISECI I FIGURE 15.2-9 LOSS OF ALL GRID CONNECTIONS I I RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
LL Q
SI) 125.
7s.
- 25.
4
- 0.
- 10.
- 20.
- 30.
- 40.
TIME (SECI
- 75.
-2s.
-1 25. 0.
- 10.
20
- 30.
UO.
iIHE ISCCI
~-
FIGURE 15.2-10 LOSS OF ALL FEEDWATER FLOW RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
1040 PSIA, 549°F TO 100 PSI, 33OOF 100 PSI, 33OOF TO 14.7 PSI, 125OF1 NORMAL SHUTDOWN DEPRESSURIZE VESSEL TO (OFFSITE POWER)
I I
ADS/ RELIEF VALVE ALTERNATE PATH NORMAL SHUTDOWN (ONSITE POWER)
DEPRESSURIZE VESSEL VIA MANUAL REUEF VALVE ACTUATION + RHR SUPPRESSION POOL COOLING NORMAL SHUTDOWN INITIATED P = 1040 PSIA T = 549OF I
I I
ADSfREUEF VALVE ALTERNATE PATH AUTOMATIC RELIEF VALVE ACTUATION DEPRESSURIZE VESSEL VIA MANUAL REUEF VALVE ACTUATION + RHR SUPPRESSION POOL COOLtNG SHUTDOWN ACHIEVED VESSEL HEAD r REMOVED
~~
FIGURE 15.2-1 1
SUMMARY
OF PATHS AVAILABLE TO ACHIEVE COLD SHUTDOWN RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
NOTES FOR FIGURE 15.2.12 ACTIVITY A Initial pressure 1072 psia Initial temperature 553 °F For purposes of this analysis, the following worst-case conditions are assumed to exist:
(1) The reactor is operating at 102% nuclear boiler rated thermal power; (2) A loss of power transient occurs (see Section 15.2.6); and (3) A simultaneous loss of onsite power (Division 1), which eventually results In the operator not being able to open one of the RHR shutdown cooling line suction valves.
ACTIVITY B Initial pressure 1072 psia Initial temperature 553 °F Operator Actions During approximately the first 10 minutes, reactor decay heat is passed to the suppression pool by the automatic operation of the SRVs. Reactor water level is returned to normal by the automatic operation of HPCS and RCIC.
After approximately 10 minutes, it is assumed one RHR heat exchanger is placed in the suppression pool cooling mode to remove decay heat. At this time, the suppression pool will be 113° F. At approximately 24 minutes into the transient, the operator initiates depressurization of the reactor vessel. Controlled depressurization procedures consist of controlling vessel pressures and water level by using selected SRVs, RCIC and HPCS systems.
When the reactor pressure approaches 100 psig, the operator prepares for operation of the RHR system in the shutdown cooling mode. At this time (152 min), the suppression pool temperature is 168°F.
ACTIVITY C1 (Division 1 fails, Division 2 available)
System pressure approximately 100 psig System temperature approximately 340 °F Operator Actions The operator establishes either one of two closed cooling paths as follows:
(a)
Utilizing RHR Loop B, water from the suppression pool is pumped through the RHR heat exchanger (where a portion of the decay heat is removed) into the reactor vessel. The cooled suppression pool water flows through the vessel (picking up a portion of the decay heat), out the ADS valves, and back to the suppression pool. This alternate cooling path is shown in Figure 15.2-15. Cold shutdown is achieved approximately 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> after the transient occurs.
(b)
Utilizing RHR Loops B and C together, water is taken from the suppression pool and pumped directly into the reactor vessel. The water passes through the vessel (picking up decay heat) and out the ADS valves returning to the suppression pool as shown In Figure 15.2-12. Suppression pool water is then cooled by the operation of RHR Loop B in the cooling mode as shown in Figure 15.2-12. in this alternate cooling path, RHR Loop C is used for injection and RHR Loop B for cooling. Cold shutdown is achieved approximately 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> after the transient occurred.
ACTIVITY C2 (Division 2 fails, Division 1 available)
System pressure approximately 100 psig System temperature approximately 340 ºF Operator Actions Utilizing RHR Loop A, as Shown in Figure 15.2-16, instead of Loop B, an alternate cooling path is established as in Activity C1 of item 2(a) above.
RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT ACTIVITY C1 ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOPS B AND C FIGURE 15.2-12 REVISION 14 SEPTEMBER 2001
REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RPV PRESSURE RESPONSE FAILURE OF RHR SHUTDOWN COOLING ACTIVITY C1(A)
FIGURE 15.2-13
REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT RPV PRESSURE RESPONSE FAILURE OF RHR SHUTDOWN COOLING ACTIVITY C1(B)
FIGURE 15.2-13a
REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT TEMPERATURE RESPONSE FAILURE OF SHUTDOWN COOLING ACTIVITY C1(A)
FIGURE 15.2-14
REVISION 14 SEPTEMBER 2001 RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT TEMPERATURE RESPONSE FAILURE OF SHUTDOWN COOLING ACTIVITY C1(B)
FIGURE 15.2-14a
S/R VALVE VESSEL (I 11 SUPPRESSION I S ERVl CE WATER DISCHARGE 5 E RVI C E WATER SYSTEM FIGURE 15.2-1 5 ACTIVITY C1 -ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOP B RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
T L
S/R VALVE SUPPRESSION AREA I
EXCHANGER I
-1 I
SERVICE
+WATER DISCHARGE I
RHR SERVICE WATER SYSTEM I HEAT I
FIGURE 15.2-1 6 ACTIVITY C2-ALTERNATE SHUTDOWN COOLING PATH UTILIZING RHR LOOP A RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT
e
- 0.
- 0.
- 10.
- 20.
- 30.
UO.
TIME (SECI 11 FtEDWRTEP FLM 5
150.
1 4
- 0.
- 10.
- 20.
- 30.
UO.
TIME ISECl
.u x 125.
- 75.
- 25.
-25. 0.
- 10.
- 20.
TINE tSECi I.
UO.
U TOTRL F i E q C T I V I T Y I
- 10.
TIME
- 20. ISECI 30.
UO.
FIGURE 15.3-1 TRIP OF ONE RECIRCULATION PUMP RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
I VESSEL PRES RISE (PSI)
FLUX 2 RELIEF VALVE FLOW 125.
3 BYPASS VALVE FLOW
- 75.
- 25.
-25.
CI.
- 10.
- 20.
311.
'10.
TIMF [SECI I LEVEL (INCH-REF-SEP-SKIRT I VOID REACTIVITY 2 VESSEL STEAMFLOW 3 TURBINE STEAMFLOW 4 FEEDWATER FLOW
- 1.
I 2 OOPPLER REACTIVITY 3 SCRAM REACTIVITY 4 TOTAL REACTIVITY 3
-0 111.
211.
311.
- 40.
T I M t ISf C1 FIGURE 15.3-2 TRIP OF BOTH RECIRCULATION PUMPS RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
150.
II CORE INLET SUB
- loo.
Y IE L L Q
I-z u
w w
- 50.
a P-c I
I I
I
- 0.
- 10.
- 20.
- 30.
- 40.
- 0.
TIME (SECJ I
150.
100.
- 50.
- 0. 0.
- 10.
- 20.
- 30.
110.
TIME lSECl I )
TIME (SEC) 4 TOTFIL R t L C n V I T Y 2
7 2
3 1
3 1
3 u
1 1
~
- 10.
TIME
- 20. (SECI 30.
110.
I FIGURE 15.3-3 FAST CLOSURE OF ONE MAIN RECIRCULATION VALVE I RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
Q f-<
- ~
0 fZ u
i.t.l 0..
1 NE UTRON FLUX 2
AVE. S URFACE HEAT FLUX 3
COME INLET FLOW aso.l i
\\ I I
I 4 COME INLE T SUB
&00.
%0.
2 T IME
( SEC )
LEVEL ( I NCH REF-SEP - SKIRT )
2 3
4 uo
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2,....._
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T I ME
( S EC)
Percent rated power referenced to 2894 MWt
=
fZ
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~
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.... > 6 til 1
U5 75 ~
2
~
1 VESSEL P RES RISE ( P S I)
% )
%)
\\
2 /::-
45 ~
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3 3
3 3
25 1 2 3 2
?
2
~.
-.15.0.
- 10.
x.
T I ME (SEC)
- 1.
VOl 0 H.E A CTIVI"I'Y 2
DOPPLER HE ACT I V I TY 3
SCRAM REAe'£l.V l T Y I
¥
,/
I I 4 TOTAL RE ACT I V I TY
...2.0:
- 20.
TIME
( SEC )
FIGURE 15.3-4 FAST CLOSURE OF TWO MAIN RECIRCULATING VALVES RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17
150.
3 1
3
- 0.
- 10.
- 20.
- 30.
YO.
4 3
TIME ISECl 3
7 4
>r I-w - -
I-u
&l U
a FIGURE 15.3-5 SEIZURE OF ONE RECIRCULATION PUMP RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATE D SAFETY ANALYSIS REPORT
1 N E U T R O N F L U X I
1 I
I 2 AVE SURFACE HEAT FLUX 3 CORE I N L E T FLOW 4 CORE I N L E T SUB
- 50.
.oo.
- 50.
- 0. 0.
- 10.
- a.
- 30.
UO.
TIP!
ISECI 1 L E V E L (1NCH.REF.SEP-SKlRTl I
I I 2 F C V 1 POSITION (",>I 3 PUMP SPEFD 1 I"*,)
4 FEEOWATER FLOW
- 0.
- 10.
- 20.
- 30.
'10.
TIME (SECI 1 VESSEL PRES RISE (PSI)
I I
I 12 RELIEF V A L V E FLOW 4 DIFFUSER FLOW 1 ("->I 100.
- 50.
- 0.
-50. 0.
- 10.
- 20.
- 30.
- 40.
TIME [SECI 1 V O I D R E A C T I V I T Y I
I I
12 DOPPLER REACTIVITY 3 SCRAM REACTIVITY
- 1.
Y, c
- 0.
m L
W L
S 0
U B
B--
-1.
w -
i$ -2.
- 0. uii
- 2.
- 4.
6.
- 8.
TIRE (SECI FIGURE 15.4-1 ABNORMAL STARTUP OF IDLE RECIRCULATION PUMP RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
1
? VESSEL STEAMFLOW 3 T U R B I N E STEAMFLOW 4 FEEDWATER F L O W L E V E L ( I N C H REF SEP S K I R T )
250.
J
. II x 1 VESSEL PRES RISE (PSI) 1 2 R E L I E F V A L V E F L O W 3 BYPASS V A L V E FLOW 4 DIFFUSED FLOV! 1 (%,I t
- 0.
- 10.
- 20.
- 30.
- 40.
TIME (SECI I-I-
- I.
-2.
I FIGURE 15.4-2 FAST OPENING OF ONE MAIN RECIRCULATION LOOP VALVE AT 30% PER SECOND RIVER BEND STATION Percent rated power referenced to 2894 MWt REVISION 17 UPDATED SAFETY ANALYSIS REPORT
150.
1 NEUTRON FLUX II~ '
I I
jS ~:i.f~r:~tc~L~T Ft...ux i
4 COflE INL&:f SUB m too.
lil
~
i
$0.
- SEer'*
t LEVEl. INCH-REF-SEP-SKIRT 2 VESSEL STIOAMFLOW 2'50.
- J.TtJRBINE STEAMFLOW 4 FEEDWATER FLOW Percent rated power referenced to 2894 MWt
- I 200
_y;
"/
100 2!lt
\\...
0
-100.0.
- 10.
I.IS 1 VliSSEl.. PRES f'\\ISE (
2 RELIEF VP. LVI: f' 1.0 3 BYPASS VALVE FLO 4 DIFFUSER FLOW I I
$ Olf'FVSE:ft FLOW:! (
IS_
SH w
- W *
)
~
.l.
20.-
-30.
110.
TIME SECI
'VOID REACTIVITY 2 DOPi'LER R£ACTIV tTY I
F I
1 ll ~g~:t" ::::gn~::g o.1.va W<ct \\I
- J- ----===:
I I
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15\\:C)
- 8.
FIGURE 15.4-3 FAST OPENING OF BOTH MAIN RECIRCULATION LOOP VALVES AT 13% PER SECOND RIVER BEND STATION UPDATED SAFETY ANALYSIS REPORT REVISION 17
1 NEUTRON FLUX 2 PEAK FUEL CENTER TEMP 3 AVE SURFACE HEAT FLUX I 4 FEEDWATER FLOW 150.
I I
I 5 VESSEL STEAM FLOW L
1 LEVEL (INCH-REF-SEP-SKIRT)
Percent rated power referenced to 2894 MWt FIGURE 15.5-1 OF HPCS REVISION 17 2 W R SENSED LEVEL (INCHES) 3 N R SENSED LEVEL (INCHES) 5 DRIVE FLOW 1 (%)
125..
4 CORE INLET FLOW (%)
u5 Y 5 4 5; 45
- 75.
3
.3,-----J-INADVERTENT STARTUP 3
4
?
I
?
3
?
I I
I 1 VESSEL PRES RISE (PSI) 2 STM LINE PRES RISE (PSI) 3 TURBINE PRES RISE (PSI) 4 HPCS FLOW (% OF FW) 5 CORE AVE VOID FRAC(%)
6 TURBINE STEAM FLOW (%)
L 4
u Ll 3
3 3
12 17 l?!
-25.
1 1
1 1
l 1
1 1
U 0.
- 10.
- 20.
- 30.
- 40.
TIME [SECl