River Bend Station, Unit 1, Revision 25 to the Updated ...100 80 20 scram worth at 100% = -$37.05 0...

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 A T

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


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 ~~-


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


REVISION 17

LOSS OF FEEDWATER HEATER, I MANUAL FLOW CONTROL

RIVER BEND STATION I UPDATED SAFETY ANALYSIS REPORT


REVISION 17

RIVER BEND STATIONUPDATED SAFETY ANALYSIS REPORT

FEEDWATER CONTROLLER FAILURE

FIGURE 15.1-3

TIME (SECONDS) TIME (SECONDS)

TIME (SECONDS)TIME (SECONDS)R

EAC

TIVI

TYC

OM

PON

ENT(

S)

(PER

CEN

TO

FR

ATED

)

I NEU 1011 FlUX 2 AV( SUIIHtt H~~ ~ nux I VES ~~-paul a B~IPIII HOI uur no 2 SAF "um ~:

IM~f I ~~L lf ~AU ~i i! .....

~ 5

~(\ UJ 1-~ l tt. t

\\ IM.t

!....

( ~ 0 1-

~ z UJ u 0:: UJ ••.• e::

~ IM.t

\. ... rr r-..-. ••• '·' lt.t "·' . .. .... •• • •• .. "·· ....


I I.EY L II NCH -lll' rP·SitiiTI 2VU tl STUNlC \.1 ~m IIUCTIYIT

n~~ ~~~~.!'mfi ~~~ U.l IIUCTI TT , .... H~· • :tmm l.t

iii l; / i= z UJ z

'"~· 0

~ / ~ ...

0 t-Jj u

...___.___ >-1-

> ... i= ~ .... UJ FIGURE 15.2-1 0::

PRESSURE REGULATOR ·Itt. I ••• ... . .... ll.t - ·l.t ••• • •• "·· •••• .. .. DOWNSCALE FAILURE TIME (SECONDS) TIME (SECONDS)

Perce nt 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 . T I M E (SECI T I M E (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


REVISION 17

UPDAT ED SAFETY ANALYSIS REPORT


REVISION 17


LOAD REJECTIONWITH BYPASS FAILURE

FIGURE 15.2-3


TIME (SECONDS)TIME (SECONDS)R

EAC

TIVI

TYC

OM

PON

ENT(

S)

(PER

CEN

TO

FR

ATED

)

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 I S E C l

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 r lOII

I M ,IL_~~------~---------+-----------r----;

o I I w I f- "' :.r I ~ IM.t j <.Iii C LL 0 fz 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 ...... L_

•••

··-.~· .... . ..• • •• TIME (SECONDS)

1 •• ~\ I ' 't' lJlO' , •• C!)IIJI I l (fl i= z w z o I c 1 I I [l. •·•I lw I> 2 0 u >f-

> f= I I I I I 0 ·t.tl 1 JJ <( w 0:::

. .. , .. . . TIME (SECONDS)


FIGURE 15.2-5

TURBINE TRIP WITH BYPASS FAILURE


REVISION 17


FIGURE 15.2-6 THREE-SECOND CLOSURE OF ALL MAIN

STEAM ISOLATION VALVES WITH POSITION SWITCH SCRAM


REVISION 25

1 VESSEL PRES RISE (PSI) 2 RELIEF VALVE FLOW 3 BYPASS VALVE FLOW

I


REVISION 17

FIGURE 15.2-7

LOSS OF CONDENSER VACUUM AT 2 INCHES PER SECOND


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


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


REVISION 17


1040 PSIA, 549°F TO 100 PSI, 33OOF 100 PSI, 33OOF TO 14.7 PSI, 125OF1

NORMAL SHUTDOWN DEPRESSURIZE VESSEL TO (OFFSITE POWER) MAIN CONDENSER

I‘

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

-


William J Fountain

USAR Revision 8, August 1996

NOTES FOR FIGURE 15.2.12

ACTIVITY A

Initial pressure — 1072 psiaInitial temperature — 553 °F

For purposes of this analysis, the following worst-case conditions are assumedto 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 Inthe operator not being able to open one of the RHR shutdown cooling linesuction valves.

ACTIVITY B

Initial pressure — 1072 psiaInitial temperature — 553 °F

Operator Actions

During approximately the first 10 minutes, reactor decay heat is passed to thesuppression pool by the automatic operation of the SRVs. Reactor water level isreturned to normal by the automatic operation of HPCS and RCIC.

After approximately 10 minutes, it is assumed one RHR heat exchanger isplaced 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 thetransient, the operator initiates depressurization of the reactor vessel. Controlleddepressurization procedures consist of controlling vessel pressures and waterlevel by using selected SRVs, RCIC and HPCS systems.

When the reactor pressure approaches 100 psig, the operator prepares foroperation of the RHR system in the shutdown cooling mode. At this time (152min), the suppression pool temperature is 168°F.

ACTIVITY C1 (Division 1 fails, Division 2 available)

System pressure approximately 100 psigSystem 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 pumpedthrough the RHR heat exchanger (where a portion of the decay heatis removed) into the reactor vessel. The cooled suppression poolwater flows through the vessel (picking up a portion of the decayheat), out the ADS valves, and back to the suppression pool. Thisalternate cooling path is shown in Figure 15.2-15. Cold shutdown isachieved approximately 3 hours after the transient occurs.

(b) Utilizing RHR Loops B and C together, water is taken from thesuppression pool and pumped directly into the reactor vessel. Thewater passes through the vessel (picking up decay heat) and out theADS valves returning to the suppression pool as shown In Figure15.2-12. Suppression pool water is then cooled by the operation ofRHR Loop B in the cooling mode as shown in Figure 15.2-12. in thisalternate cooling path, RHR Loop C is used for injection and RHRLoop B for cooling. Cold shutdown is achieved approximately 11hours after the transient occurred.

ACTIVITY C2 (Division 2 fails, Division 1 available)

System pressure approximately 100 psigSystem temperature approximately 340 ºF

Operator Actions

Utilizing RHR Loop A, as Shown in Figure 15.2-16, instead of Loop B, analternate cooling path is established as in Activity C1 of item 2(a) above.


ACTIVITY C1 ALTERNATE SHUTDOWNCOOLING PATH UTILIZING

RHR LOOPS B AND C

FIGURE 15.2-12

REVISION 14 SEPTEMBER 2001



RPV PRESSURE RESPONSEFAILURE OF RHR SHUTDOWN COOLING

ACTIVITY C1(A)

FIGURE 15.2-13



RPV PRESSURE RESPONSEFAILURE OF RHR SHUTDOWN COOLING

ACTIVITY C1(B)

FIGURE 15.2-13a



TEMPERATURE RESPONSEFAILURE OF SHUTDOWN COOLING

ACTIVITY C1(A)

FIGURE 15.2-14



TEMPERATURE RESPONSEFAILURE 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


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


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


REVISION 17


I VESSEL PRES RISE (PSI) FLUX 2 RELIEF VALVE FLOW

125. 3 BYPASS VALVE FLOW

75.

25.

-25. CI . 10. 20. 311. '10.

T I M F [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 I S f C1

FIGURE 15.3-2

TRIP OF BOTH RECIRCULATION PUMPS


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


REVISION 17


Q

"' f-< <

"' ·~ 0

fZ "' u

"' i.t.l 0..

1 NE UTRON FLUX 2 AVE . S URFACE HEAT FLUX 3 COME INLET F LOW

aso.l i \ I I I 4 COME INLE T S UB

&00.

%0.

2 ..... ... •• T IME ( SEC )

LEVEL ( I NCH REF- SEP - SKIRT ) 2 3 4 uo

~ 2 ,....._

aao. f2

'/ ~ . I' L\ , L:.l ;_\ 2 2 2

4 \. :l ·~-- ' 4 .

:110.

o ..... Ui. a. •· T I ME ( S EC) -.:


= "' fZ ""' :z:

~ 0 u ,.. .... > 6 .., til

1

U5

75 ~ 2

~

1 VESSEL P RES RISE ( P S I)

% ) %)

\ 2 /::-

45 ~ I 4 5 45 ....... .

1/ ' 3 3 3 3

25

1 2 3 2 ? ' 2

....•.... ~ . -.15.0. 10. x . -- ... T I ME (S E C)

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 T OTAL R E ACT I V I TY

-·· ...2.0: 20.

TIME ( SEC )

FIGURE 15.3-4

FAST CLOSURE OF TWO MAIN RECIRCULATING VALVES


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


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 H E A T FLUX 3 CORE I N L E T F L O W 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 1 2 R E L I E F 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 R E A C T I V I T Y 3 SCRAM R E A C T I V I T Y 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


REVISION 17


1 ? VESSEL S T E A M F L O W 3 T U R B I N E S T E A M F L O W 4 F E E D W A T E R F L O W

L E V E L ( I N C H R E F 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 D I F F U S E D FLOV! 1 ( % , I

t

0 . 10. 20. 30. 4 0 . TIME (SECI

>-

> I-

I- - I . - - $

-2. I

FIGURE 15.4-2 _ _

FAST OPENING OF ONE MAIN RECIRCULATION LOOP VALVE

AT 30% PER SECOND


REVISION 17


150.

1 NEUTRON FLUX II~ ' I I jS ~:i.f~r:~tc~L~T Ft...ux

i 4 COflE INL&:f SUB

m t oo. lil ~

i $0.

•SEer'·

t LEVEl. INCH-REF-SEP-SKIRT 2 VESSEL STIOAMFLOW 2'50. ·::J .TtJRBINE STEAMFLOW 4 FEEDWATER FLOW

Perce nt rated p o wer 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

~ -E

i -1-~------~.-------+--------+--------;--------

15\:C) 8.

FIGURE 15.4-3

FAST OPENING OF BOTH MAIN RECIRCULATION LOOP VALVES

AT 13% PER SECOND


REVISION 17

1 NEUTRON F L U X 2 PEAK F U E L 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)


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 A V E VOID FRAC(%) 6 TURBINE STEAM FLOW (%)

L

4 u L l

3 3 3 12 - -_ 17 l?!

-25. - 1 1 1 1 l 1 1 1 * U

0 . 10. 20. 30. 40. TIME [SECl

River Bend Station, Unit 1, Revision 25 to the Updated ...100 80 20 scram worth at 100% = -$37.05 0...

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Transcript of River Bend Station, Unit 1, Revision 25 to the Updated ...100 80 20 scram worth at 100% = -$37.05 0...