ML17075A337
| ML17075A337 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 03/20/2017 |
| From: | AmerenUE |
| To: | Klos L Office of Nuclear Reactor Regulation |
| Klos L | |
| References | |
| Download: ML17075A337 (384) | |
Text
HOLD UP IN _.,
CONTAINMENT A LOCA, FHA IN CONTAINMENT (NO,.
AND CAE HOLDUP)
STEAM VENT &
SAFETY VALVES OR RADWASTE BUILDING
.r ATMOSPHERE D r CONTROL ROOM SGTR, MSLB, WGDTR AND E (NO HOLD UP) CAE A'
FUEL BUILDING (NO HOLDUP)
B c .
FILTERS FHA IN FUEL BUILDING REV. OL-9 5/97 CALLAWAY PLANT FIGURE 15 A -1 RELEASE PATHWAYS
Allowable In leakage Values 3000 ~--------------------------------------------------------------~
2500
.§
-; 2000 C'l ctl
~
ctl
~
1500 "C Unacceptable
- I Ill
~ 1000 0
(.) Acceptable 500 0 5 10 15 20 25 30 Control Room lnleakage (cfm)
REV. 16 9/06 CALLAWAY PLANT FIGURE 15A-2 ALLOWABLE INLEAKAGE VALUES
\
\
\
70 \
\
\
\
OP.:iT
\
Setpolnt LL..
I 60
~
<I) 0 \
Full Power \
1-- \
Operating Point I for High Tavg
\
0 \
-+-' \
\
<I) 50 \ '\
a \
\
\
\
' \
40
\
\
\
30~~~~~~=c~~~~~~=c~~~~~~~
570 580 590 600 610 620 630 Tavg (Deg-F)
CALLAWAY PLANT FIGURE 15.0-1 lllUSTRA TIOt~ OF OVERPOWER Atm OVERTEMPERA TURE PROTECTIOt~
Rev. 17 11/13
0 IOTE I - *uPPER CURVE* LEiST IE61TIVE DOPPLER OMLY POWER DEFECT:: -o.7ao/o-0P(O TO 100~ P'OWER)
-2 IOTE 2 - *lOWER CURVE" MOST IEBATIV£ DOPPLER OILY POWER DEFECT :: -1
- 8%~ P ( 0 TO I 0~ POWER)
-4 ac
~..,_ -6 as ~ (EOL)
~
le ac -10
~
~ -12
-1~
Q a
-16
-18
..20 0 20 110 &0 100 PERCEKT POWER REV. OL-7 5/94 CALLAWAY PLANT Figure 15.0-2 Doppler Po"W"er Coefficient Used in Accident Analysis
1.2 1.1
~ 1.0
- z::
Cl)
~ 0.9
~
~ 0.. 0.8
- ~
~ ~ 0.7
&1.1
~~
~ ~ 0.6
~:
- 0'0.5
~~
~ ~ 0.~
&1.1 u
~ 0.3 1-CI) eo.2 0.1 0
0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 .1.0 1.1 1.2 1.3 1.~ 1.5 1.6 IIORMlll ZED DROP TItE (TitE AFTER DROP IE61.S/DROP TltE TO TOP OF DlSitPOT}
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 16.,0.3 RCCA POSITION VERSUS TIME TO DASHPOT
,...... 1.0
~ 0.9 t=
u
~ o.s
~
~
j: 0.7
~
~ 0.6
(.)
~ 0.5 Cll:
Q
~
~ 0.~
0 z
0.3 0.2 0.1 0
0 0.2 o.~ o.s o.s 1.0 ltOD POSITION ( FUCTI Cit INSERTED}
REV. OL-7 5/94 CALLAWAY PLANT FIGURE 15.o.4 NORMALIZED ROO WORTH VERSUS PERCENT INSERTED
1.0
- 0.6 i
- 5 Cll:
~
Q 0.~
~
j a:
0.2 0
0 0.1 0.2 0.3 0.~ 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 1.~
IIORMALIZED ROD DROP TUE TUE AFTER DROP lEG IMS TUE TO TOP OF DASHPOT Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.0-6 NORMALIZED RCCA BANK REACTIVITY WORTH VERSUS NORMALIZED DROP TIME
CALLAWAY - SP Figure 15.0-6 Deleted REV. OL-~15 5/06
ABBREVIATIONS USED:
AFWS - AUXILIARY FEEDWATER SYSTEM ECCS - EMERGENCY CORE COOLING SYSTEM CVCS - CHEMICAL AND VOLUME CONTROL HL - HOT LEG SYSTEM CL - COLD LEG ESFAS - ENGINEERED SAFETY FEATURES CCWS - COMPONENT COOLING WATER ACTUATION SYSTEM SYSTEM ."
FW - FEEDWAfER RCS - REACTOR COOLANT SYSTEM RTS - REACTOR TRIP SYSTEM SWS -SERVICE WATER SYSTEM SIS - SAFETY INJECTION SYSTEM HPI - HIGH PRESSURE INJECTIO~
Sl - SAFETY INJECTION LPI - LOW PRESSURE INJECTION RT - REACTOR TRIP Cl - CONTAINMENT ISOLATION CS - CONTAINMENT SPRAY SG - STEAM GENERATOR NOTES:
I. FOR "TRIP INITIATION AND SAFETY SYSTEM ACTUATION, MULTIPLE SIGNALS ARE SHOWN BUT ONLY A SINGLE SIGNAL IS REQUIRED. THE OTHER SIGNALS ARE BACKUPS.
- 2. NO TIMING SEQUENCE IS IMPLIED BY POSITION OF VARIOUS BRANCHES.
REFER TO EVENT TIMING SEQUENCES PRESENTED IN TABULAR FORM IN PERTINEHl ACCIDENT ANALYSIS SECTION OF CHAPTER 15.0 OF THE FSAR.
3
- WHEN OVERTEMPERATURE AND OVERPOWER ARE USED IT REFERS TO OT-DELTA T AND OP-DELTA T.
DIAGRAM SYMBOLS:
( ) - EVENT TITLE 0 -BRANCH POINT FOR DIFFERENT PLANT CONDITIONS I..____. . . .!- SAFETY SYSTEM
- > - SAFETY
< 11\ ACTION
-SYSTEM REQUIRED TO MEET SINGLE-FAILURE CRITERIA
\ J lp\- -MANUAL ACTION REQUIRED DURING SYSTEM OPERATION
\ )
- CALLAWAY PLANT FIGURE 15.0-7 ABBREVIATIONS AND SYMBOLS USED IN SEQUENCE DIAGRAMS Rev. OL-4 6/90
~~~.11~-1 HIGH NEUTRON FLUX 1/2 ( EXCESSIVE HEAT REMOVAL DUE TO FEEOWATER SYSTEM MALFUNCTIONS SOUI!CE RANGE' HIGH NEUTRON FLUX 1/2 INTERMEDIATE RANGE HIGH NEUTRON FLUX 2/14 POWER< PIO POWER > PIO HIGH NEUTRON FLUX 2/14 POWER RANGE POWER RANGE OVERPOWER AT 2/14 OVERPOWER AT 2/14 y RTS RTS 1- OVERTEMPERAl\JRE AT 2/14 LOW-LOW SG LEVEL 2/4 t' ' , ' INANYLOOP IS F' II
\
IS F,I REACTOR REACTOR TRIP TRIP BREAKERS '
BREAKERS
~' I \
~s IS F,I
... , I ' ,
CONTROL RODS CONTROL RODS GRAVITY GRAVITY INSERTION INSERTION PASSiVE PASSIVE CONTROL ROO CONTROL ROD REACTiVITY REACTIVITY
'FOR POWER < P6 CONTROL CONTROL CALLAWAY PLANT FIGURE 15.0-8 EXCESSIVE HEAT REMOVAL DUE TO FEEDWATER SYSTEMS MALFUNCTION REVOL-8 11/95
lt+,ll'+-2 EXCESSIVE LOAD INCREASE
-FULL POWER OVERPOWER t.T 2/'+
OVERTEMPERATURE t.T 2/'+
HIGH NEUTRON FLUX 2/'+
POWER RANGE y RTS PRESSURIZER SAFETY SG SAFETY VALVES VALVES Is I
FI I
PASS 1VE PASSIVE REACTOR TRIP BREAKERS SAFETY VALVES SAFETY VALVES OPEN TO RELIEVE OPEN TO RELIEVE
, ... RCS PRESSURE SECONDARY SYSTEM PRESSURE I
\
s F' I CONTROL RODS GRAVITY INSERTION NOTES: I. THIS DIAGRAM APPLIES TO BOTH MANUAL PASSIVE AND AUTOMATIC CONTROL MODES.
- 2. FOR THIS TRANSIENT. REACTOR PROTECTION SYSTEM FUNCTIONS ARE ASSUMED TO BE OPERATIVE. BUT A RT IS NOT EXPECTED.
CONTROL ROD REACTIVITY 3. NO SAFETY VAI..VE SET PRESSURES CONTROL ARE APPROACHED IN THE SECTION 15.1.3 ANALYSIS.
CALLAWAY PLANT FIGURE 15.0*9 EXCESSIVE LOAD INCREASE REVOL-8 11195
DEPRI'SSUIIIZUICM Of MAIN SlUM SYSitH NIGH Rt'UTRIM !lUX 21*
POO{R RANG£ OY£RPOW£R .6-T 21*
I Sl SIGNAl lOW PRES SUR IZ(R z/q I
~ ns HIGN-2 CONIAIMIOI 2/3 Sl SIGNAL LOW PRESSURIZER PRESSURE l__..~
PRESSURE PRESSURE 2/4 , HIGH-I COHIAINMEHT 2/3
- s .
r'l PRESSURE rl [SFAS I lOW STW4 liM[ 2/3 ESfl!
I HI-HI SG LEVEL 2(q I
£SFAS I
PRESSURE IN ANY SG OT.6.T 2/4 lOW STEAM liME 2/3
' ,. HIGH II£Gll!YE SlUM 2/3 , ,-
- s r'1 PRESSURE Rll[ IN OM[ lOOP IS r'l I
- 1
' s _,
'~
( < Pll) \
TR" ' ' '
BRUKERS HAMUAL 1/2
,. I SIS I SltlH liNE MAIN I S f'
\
I IS r
- -,' ISOIJIION VALVES ""
ISOlA !ION 1
COHIROl RODS GRAVtTY INJECTION Or
)
INSERT ION ClOSE FAST BORATED WATER CLOSE Mil IN I'll PASSIVE TO PR{Y{Ml ACIING STElH ISOlUION VAlV£S REI'UIIN TO liNE ISOIJIION CRITICAliTY' VALVES CONTROl ROO RtlCIIYI TY Sl SIGNAl rl [SFAS I
CONTROL
'OPERATOR I{RHINATES SAFETY INJ{CTION 2/q
- r:.
lOW-LOW SG LEVEL '
HOW TO liMIT RCS PRESSURE AND IN OHE SG
', s PRESSURIZER lEVEL. SEE SECTION 7.~
FOR IMOICl!ORS IMO RECORDERS IYIIIJBl£ NIMUll 1/2 TO l1IE OPERA TOR fOllOWING IH[ [Y[HI.
LOW-lOW SG LEVEl 1/q I lfWS I
- , s- F:
IN 2/~ SG (l'UIIIINE DRIVEN PUMPS) ,
cm
"'0 0 -
- tl l> OEUV£R AUllliARV (I)~
m
, r I'll TO CONTROL CORE
-tc -c G)
HEAT R(MOYAL
- tl
....U1m b
....0 I
I (A)
1~, II~-~
LOSS OF EXTERNAL ELECTRICAL LOAD
_i==FULL POWER HIGH PRESSURIZER PRESSURE 2/t+
rl RTS OVERTEMPERATURE ~T 2/t+
HIGH PRESSURIZER 2/3 PRESSURIZER SG WATER LEVEL SAFETY SAFETY REACTOR WW-WW SO LEVEL 2/4 TRIP VALVES VALVES INONESG BREAKERS PASS l.VE PASSIVE I \
Is F I CONTROL RODS SAFETY VALVES SAFETY VALVES GRAVITY OPEN TO RELIEVE OPEN TO RELIEVE INSERTION RCS PRESSURE SECONDARY SYSTEM PASSIVE PRESSURE CONTROL ROO REACTIVITY CONTROL LOW-LOW SG LEVEL 2N ESFAS IN ONE SG MANUAL 1/2
's F,'
\
I AFWS
- S F\
'FOR CASE WHERE TURBINE TRIP OCCURS, ... ,
A REACTOR TRIP SIGNAL ON TURBINE TRIP "'
!S ANTICIPATED {FOR POWER > P9)
DELl VER TURBINE TRIP SIGNAL DUE TO: AUXILIARY FW TO 2/3 LOW TRIP FLUID PRESSURE CONTROL CORE
~~~ TURBINE STOP VALVE CLOSURE HEAT REMOVAL CALLAWAY PLANT FIGURE 15.0*11 LOSS OF EXTERNAL LOAD REVOL-8 11195
LOSS OF OFFSITE POWER TO STATION AUXILIARIES LOW-LOW SG LEVEL 2/11 '-----~=====:::::.-FULl POWER IN AHY LOOP ANTIGIPATEO RT ON PRESSURIZER SG TURBINE TRIP SAFETY SAFETY LOW-lOW SG LEVEL 2/1.1 LOW REACTOR COOLANT VALVES VALVES IN ONE SG 2/3
~ S F~ :~ F' '
FLOW IN ONE LOOP ... ,
I lOSS OF OFFS ITE POWER ' '
REACTOR MANUAL 1/2 AFWS TRIP BREAKERS L()I-LOW SG LEVEL 2/1.1 IN 2/11 SG (TURBINE DRIVEN PUMPS)
I "' ' \
1S F I CONTROL RODS GRAVITY INSERTION 1 DEll VER AUXILIARY FW TO CONTROL CORE r- HEAT REMOVAL 0
~
)>0 e-n 0 xo
)>
r
!:-n
)>(I)
- o:::j G')
c ~
n;m ::D ~
(1)"'0 m )>
0
~
-a c.n -<
m b "'0
- 0 *
-a r
-f N
)>
0 (I) z
-f -t
)>
-f 0
z
lOSS OF NORMAL FEEDWATER FULL POWER OVERTENI'ERATURE AT PRESSURIZER SG LOW-LOW SG LEVEL 2/q SAfETY SAFETY VALVES VALVES IN ONE SG, lOW-lOW SG LEVEL 2N LOSS Of OFFS I TE POWER IN ANY LOOP MANUAL 1/2 REACTOR TRIP BREAkERS
- LOW-LOW SG LEVEL 2/~
SAfETY VALVES OPEN TO RE L1 EVE IN 2/q SG (TURBINE ORIVEII PUMPS)
RCS PRESSURE IS f~
\ '
CONTROL ROOS GRAY I TY DEL I YER INSERTION AUXILIARY FW TO CONTROL CORE HEAT REMOVAl r-0
~ 0 0 )>
r-z
~
0 C5
- D c 3: ::D m )>
)>
r- U1 -<
m m ....b* "0 0
- e w
~
2
~
m
-f
- g; ::D
+=
\0<::
V'l 0 +=
I
~ m I
00
MAJOR RUPTURE OF A MAIN FEEOWATER ll HE HIGH PRESSURIZER 2/q FUll POWER 51 SIGNAL PRESSURE I
f-1 RTS I OVERTEMPERATURE dT 2/q (s
lOW STEAM ll HE PRESSURE IN ONE lOOP 2/3 I lOW-lOW SG lEVEL IN ANY SG 2/q lOW-LOW SG LEVEL IN ANY SG 2/q
. F'
~
I HIGH-I CONTAINMENT PRESSURE 2/3
[SFAS J I £SFAS l LOW-LOW SG LEVEL 2/q IN 2/q SG (TURBINE DRIVEN PlJ4PS 51 SIGNAL REACTOR MANUAL 1/2 TRIP , ' ,
- ~
HIGH PRESSURIZER LEVEL 2/3 BREAKERS
{s F'I I S
LOSS OF OFFS I TE POWER
's -',
I F' PRESSURIZER SAFETY I SIS I I AFWS l VALVES CONTROL R(lOS PASS IV£ GRAVITY INSERTION I'
Is Fl ' ,'s ;~
PASSIVE I '~ /
\ . ,
OPERATOR TURNS OFF HIGH HEAD SAFETY INJECTION PUMPS INJECT BORATED DEll VER SUBSEQUENT TO RECOVERY OF UVE SAFETY VAL YES WATER INTO RCS AUXILIARY CONTROL ROO IN THE INTACT 1SGs REACTIVITY OPEN TO TO PREVENT FW TO RELIEVE RETURN CONTROL CORE SH SECTION 7. S FOR INOICAT ORS CONTROL RCS PRESSURE TO POWER HEAT REI<<lVAL AND RECORDERS AVAILABLE TO THE OPERATOR FOLLOWING THE EVENT 3:
~ (')
c..
0 l>
"TT:JJ r
~::0 "TT cc C) c
~
- lE~
~-i ::0 ~
-ic m
.... -<l>
m:O
- om r-0 U1 0
I
~
-"TT z~ .1:1>
m 3: z
- -1
)>
z
\0
~ ~
VI < ~
~
~
I
-.J 00
LOSS Of FORCED REACTOR COOLANT flOW POWER > P7 TOTAL LOSS SINGLE REACTOR COOLANT PUMP LOCKED ROTOR.
SHAFT BREAK (fUll POWER)
UMDERVOL TAGE LOW RCS FLOW 2/3 2/3 IN ONE LOOP UNDERFREQUEMCY
~ s f ,~ I
\ S f I
IN ONE LODP 1
I S f I
' ,' i PRESSURIZER SAFETY VALVES I
f
, s f ', I i '
I IS
,I \ , I S f 1 CONTROL RODS CONTROL RODS CONTROL ROOS GRAVITY GRAVITY GRAVITY INSERTION INSERTION INSERT IOM CONTROL ROD REACTIVITY CONTROl
+=
I 00
UNCONTROLLED ROO CLUSTER CONTROL )
( ASSEMBLY BANK WI THORAWAL
.-~___./
HIGH NEUTRON FLUX 1/2 SOURCE, RANGE SUBCR I TICAL AT PCTWER HIGH NEUTRON FLUX 1/2 INTERMEDIATE RANGE HIGH NEUTROH FLUX (LCTW) 2/q POW£R RANGE HIGH NEUTRON FLUX (HIGH) 2/q PMR RANGE PRESSURIZER SG 1 f- RTS SAFETY SAfETY RTS HIGH NEUTRON FLUX RATE 2* q VAL YES VALVES POWER RANGE PASSIVE PASSIVE REACTOR I HIGH NEUTRON flUX {HIGH) 2/q POW£R RANGE REACTOR SAFETY VAL YES TR!P TRIP SAFETY VALVES OVERTEMPERATURE ~T 2/q OPEN TO RELIEVE BREAKERS OPEN TO RELIEVE _t BREAKERS RCS PRESSURE SECONDARY SYSTEM PRESSURE c OVERPOW£R ~T 2/q , -,
z IS f I 0
)>0 HIGH PRESSURIZER 2/q
~~
CONTROL RODS CONTROL RODS GRAY I TY PRESSURE GRAVITY m:O INSERTION INSERTION 3:0 0 HIGH PRESSURIZER 2/3 OJI
-<m
., ~
r-PASSIVE WATER LEVEL PASSIVE tuo
)>:::0 G) c ~
zO :a m ~
_, ....U10 -<~
Ac CONTROL ROD
- e:n CONTROL ROO REACTIVITY REACT! VITY CONTROL CONTROL
-tC J:(l) ....
~
c-t en
- om
)>:a 2
- EO -4
)>0
,z
~~ -t
~< :a 0 0 1:""4 r- of=
I a U>
00
1~, II ~-1 0 DROPPED ROD CLUSTER CONTROL ASSEMBLY' OVERTEMPERATURE AT 2/'4 RTS I \
I s FI DROPPED ROD CLUSTER CONTROL
\
... , I ASSEMBLY" REACTOR TRIP BREAKERS ROD CONTROL SYSTEM AND/OR REACTIVITY FEEDBACK , ... ,
ESTABLISH NEW REACTOR 1 S F\
CONDITIONS \ I CONTROL RODS OPERATOR USES MANUAL GRAVITY IHSERTI ON ROD CONTROL TO RETRIEVE RCCA(s)
PASSIVE CONTROL ROD REACTIVITY CONTROL
- TRIP SEQUENCE MAY OCCUR IF ROD WORTH IS LOW AND AUTOMATIC ROD WITHDRAWAL IS RAPID.
TRIP IS NOT MODELED IN THE SAFETY ANALYSIS.
CALLAWAY PLANT FIGURE 15.0*17 DROPPED ROD CLUSTER CONTROL ASSEMBLY REV. OL-5 6/91
I~ ,II ~-II SiNGLE ROD CLUSTER CONTROL ASSEMBLY WITHDRAWAL AT FULL POWER OVERTEMPERATURE AT 2/ij RTS
/
'\ S F I I REACTOR TRIP BREAKERS 1
/ ...'
S FI
\ ...... /
CONTROL RODS GRAVITY INSERTION PASSIVE CONTROL ROD REACTIVITY CONTROL CALLAWAY PLANT FIGURE 15.0-18 SINGLE ROD CLUSTER CONTROL ASSEMBLY WITHDRAWAL AT FULL POWER REVOL-8 11195
I ~.11~-12 STARTUP OF AN INACTIVE REACTOR COOLANT LOOP MAXIMUM PERMISSIBLE POWER FOR OPERATION WITH ONE LOOP OUT OF SERVICE HIGH NEUTRON FLUX (HIGH) 2/~
RTS POWER RAHGE WITII LOW FLOW ABOVEP-8
/ .... ,
I S F1
\ I REACTOR TRIP BREAKERS
\I S F' l
' ... "' I CONTROL ROOS GRAVITY INSERTION PASSIVE CONTROL ROO REACTIVITY CONTROL CALLAWAY PLANT FIGURE 15.0-19 STARTUP OF AN INACTIVE REACTOR COOLANT LOOP REVOL-8 11/95
SUBCRITICAL MANUAL CONTROL ROD INSERTION*
LIMIT ALARMS AUDIBLE COUNT RATE eves ROD POSITION eves ROD INSERTION STEP COUNTER ** LIMIT ALARMS
- PRESSURIZER FROM BF, DETECTOR eves SAFETY 5G SAFETY VALVES ROD POSITION VALVES STEP COUNTER **
RTALARM (NOTE A)
POWER RANGE eves OVERTEMPERATURE L1T 2/4 AUDIBLE COUNT RATE , ',
IS F1 FROM BF, DETECTOR OVER POWER L1T 214 HIGH NEUTRON FLUX HIGH PRESSURIZER 2/4 NOTE:
SOURCE RANGE FLUX MULTIPLICATION PRESSURE - NOT A SAFETY SYSTEM.
BDMS AUTO SUCTION HIGH PRESSURIZER 2/3 CLOSE MAKEUP WATER CONTROL VALVES.
SWAPOVER (NOTE A)
WATER LEVEL ,* '(
NOTE A CLOSE CHARGING LINECONTROL VALVES FROM VCT.
IS F 1
,_ , TERMINATECHARGING PUMP FLOW.
BORATE IF NECESSARY CONTROL RODS GRAVITY INSERTION REV. OL-15 5/06 CALLAWAY PLANT FIGURE 15.0-20 BORON DILUTION
RUPfURE Of A CONTROL ROO DRIVE MECHANISM HOUSING HIGN NEUTRON fLUX (HIGH) f();ER RANGE 2/~
ZERO PuW£R )_ fUll f();ER
'V' HIGH NEUTRON POWER RANGE flUX 1 lOW} 2/q I I HIGH NEUTRON FLUX :HIGH)
POWER RANGE 2/q HIGH NEUTRON flUX RATE 2/~ -l RTS PRESSURIZER SAfETY PRESSURIZER SAFETY RTS 1- HIGH NEUTRON flUX : l();) 2/~
POWER RANGE VALVES VALVES POWER RANGE
/
HIGH NEUTR~ flUX 1/2 I S f 'I PASSIVE PASSIVE IS f \I HIGH NEUTRON FlUX RATE 2/q IHTUMEOIATE RANGE
' ' POWER RANGE I < I
~-
HIGH NEUTRON flUX 1/2 SOURCE RANGE REACTOR REACTOR TRIP TRIP BIIEAKERS SAfETY VALVES ) SAFETY VAL YES BREAI(fRS OPEN TO REll EVE OPEN TO REliEVE RCS PRESSURE RCS PRESSURE
',I ,
(~ f IS r'*I I
MOTE I: SEqi.IE HCE fOllOWING ESFAS ACTUATI~ IS SIMI LA R TO THAT FOR A SMAll lOSS Of COIHROL ROOS CONTROL ROOS coouHT [VENT :LOCA) SEE FIGURE 15 *<I-tS GRAVITY GRAY I TY INSERTION INSERltON PASSIVE PASSIVE COIHROl ROO CONTROL ROO REACII VI TY RUCTIVI TY COIHROl CONTROl
- lJ
.,c:-i lOW PRESSURIZE~
PRESSURE HIGH-I CONTAINMENT 2/~.
2/3 HIGH-3 CONTAINMENT 2/~
lOW PRESSURIZER PRESSURE HIGH-I CONTAINMENT 2/Q 2/J I
c: 0 PRESSURE PRESSURE PRESSURE HIGH-3 COHIAIHMtHI 2/q 3::D ,...l> MANUAl 1/21 1
MANUAL 1/2 ~ ! PRESSURE mm no
- c.,
)>0 C5 ~
I ESFAS
- s1 SIGNAl)
I I ESfAS (C!)SIGHAl)
I ctJFAS
( SIGNAL) l
~0 c:
- lJ
~ ,
cnz '
~
' ~
m l> ~s f, 'I ', s r,~ :s f ,'I : s f,'
I 3:-i '
- c::D MOTE I NOTE I oo c:*
C/):l]
b.
U1 N
-o
~0 0
.... :lJ
\0 ~ <
- v. < m 0 +=
t""4 I I 00 +=
I ij, II ij-15
!"ADVERTENT ECCS OPERATION AT POWER LOW PRESSURIZER 2/~
PRESSURE RTS MANUAL 1/2 I S FI
\ I REACTOR TRIP BREAKERS 1
\
S F\I
' ... j. ..
CONTROL RODS GRAVITY INSERTION PASSIVE CONTROL ROD REACTIVITY CONTROL CALLAWAY PLANT FIGURE 15.0-22 INADVERTENT ECCS OPERATION AT POWER Rev. OL-0 6/86
ACCIDENTAL DEPRESSURIZATION OF REACTOR COOLANT SYSTEM 1 - - - - FULL POWER OVERT£MPERATURE AT 2N LOW PRESSURIZER 1-4-----i PRESSURE MANUAL 1/2
[S f I
' ~
REACTOR SIS TRIP BREAKERS I
, . \
\S f I INJECT BORATED WATER
~
0 CONTROL RODS INTO RCS TO PREVENT RETURN TO POWER AND
- u- GRAVITY MAINTAIN CORE COOLING me INSERTION
)>m 0 nz
.... ~ ., ,...)>
o,..
- DC Om Gl c ~
0"'0 o::n
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r-m ....
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Zc
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- 0
~g; z
~< .,0 0 +=
r 00 I
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lOot PltsSUIIl£1 ,,, lOot PRtSSUlll£1 PUSS OR£ OrttAIOR (SI}
rt(SSUR(
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AM OPEAATOII II!CUI.ATION" or CI ON PRESSURU£11 LEVEL, RCS PJt£SSUft£,
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CVCS LETDOWN LINE RUPTURE REACTOR COOLANT ACTIVITY RELEASE TO AUXILIARY BLDG ATMOSPHERE UNFILTERED RELEASE TO ATMOSPHERE AUXILIARY BLDG DUCT RADIATION MONITOR OPERATOR CLOSES LETDOWN ISOLATION VALVE AFTER RECEIPT OF THE ALARM WITHIN 30 MINUTES CALLAWAY PLANT FIGURE 15.0*26 eves LETDOWN LINE RUPTURE Rev.OL-0 6/86
GWPS GAS DECAY TANK RUPTURE RELEASE TO BUILDING ATMOSPHERE UNFILTERED RELEASE TO ATMOSPHERE VENTILATION VENT RADIATION MONITOR fr:\ OPERATOR
~ TERMINATES PROCESS GAS INFLUENT ISOLATION TIME 2 HRS CALLAWAY PLANT FIGURE 15.0-27 GWPS GAS DECAY TANK RUPTURE Rev. OL-0 6/86
RECYCLE HOLDUP TANK FAILURE (56,000 GAL)
LIQUID GASES RELEASE TO RELEASE TO GROUND BUILDING ATMOSPHERE UNFILTERED RELEASE ENTERS TO GROUNDWATER ATMOSPHERE
- See Section 2.4.13 of the Site Addendum CALLAWAY PLANT FIGURE 15.0-28 FLOOR DRAIN TANK FAILURE Rev. OL-0 6/86
FUEL HANDLING ACCIDENT IN FUEL BUILDING GASES RELEASED FROM FUEL POOL WATER
/ '
I SF \
' /
FILTERED BY ESF EMERGENCY VENTILATION SYSTEM IODINE ADSORBER TO ATMOSPHERE RADIOLOGICAL CONTROL CALLAWAY PLANT FIGURE 15.0-29 FUEL HANDLING ACCIDENT IN FUEL BUILDING Rev. OL-0 6/86
FUEL HANDLING ACCIDENT INSIDE CONTAINMENT ACTIVITY RELEASED FROM REFUELING POOL (0-2HRS)
CONTAINMENT RADIATION MONITORS DETECT HIGH ACTIVITY AND ISOLATE CONTAINMENT RADIOACTIVITY CONTAINED Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 15.0-30 FUEL HANDLING ACCIDENT INSIDE CONTAINMENT
CALLAWAY - SP Figure 15.0-31 has been deleted.
Rev. 1 05/15
- - - Si le- p Ca tAu -loop o~ e
- - - <:j le-Loop Ca**
I~ U -l ,, <l e X
225 3
- - - Si le-l<lap Co.. e l~ u '-lo p Cq
/I
~'---::----~
- ..... __ / - --
225 0 5 TIM ~ fsec)
CALLAWAY PLANT FIGURE 15.1-1 NUCLEAR POWER, CORE HEAT FLUX AND PRESSURIZER PRESSURE TRANSIENTS FOR HFP FEEDWATER MALFUNCTION FLOW INCREASE CASE Rev. 17 11/13
1.4 11 a:
~
~,.. Oll
~g 0$
- > 1M z
~2 0
0 60 100 1.4 1.2 X
~
~~
- 5~
oa ..
l:!
~ 0~
8 c.** .
01 0
0 20 10 60 100 2400 w
a:
- > 2200
!(!
a:~ 2000 eJu;Q.
fi- 1&.0 Ia 1600 Q.
1100 0 20 40 60 60 100 nME (sec)
Ffhc: analysis that produced the above f..gures conservatively bounds the actual plant configuration. This analysis uses different setpOint coefficients in the OPL\T reactor trip setpoint from what is cullentty configured. The effect orthe differences between the a"aJysis inputs and the plant configuration 1s that the analysis input$ result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-1A IIUCLEAR POWER, CORE HEAT FLUX AIID PRESSURIZER PRESSURE TRAIISIEIITS FOR HFP FEEDWATER TEMPERATURf RfDUCTIOIIIIICIDEIIT 11!11. fl fill
a::
w
~
0 z 0. E-01 0::
L5.!::.
_J
(.)
z E+ on ~----------------------------------------------~
X
_J LL...
t:(z 0.6£-01 wo
- x:::t.....
LLJ a:::
0 CALLAWAY PLANT FIGURE 15.1-18 NUCLEAR POWER, CORE HEAT FLUX AND CORE REACTIVITY TRANSIENTS FOR HZP FEEDWATER MALFUNCTION
- FLOW INCREASE, MULTI-LOOP CASE Rev. 0 11/13
Aft d U!o Singl -loop Ca.,
- - - - noft c eel U;; p. Si le-Loop Co'"e
'j --- ----* All Loop:;. M I i-Loop Ca..
!:i w
---,\
I I
I I
(.)
~
0
- - - <: j le-l p Ca..
tAU -l ,, C1 *e
\ ,. .....
- - - Si le-L op Co .. e tAu '-loop q *e 6 ~--------------------------------------------------~
5 z
J 2
--~~----(._ - - - - - J j
CALLAWAY PLANT FIGURE 15.1-2 REACTOR COOLANT LOOP DB..TA-T, VESSB.
AVERAGE TEMP AND DNBR TRANSIENTS FOR HFP FEEDWATER MALFUNCTION -
FLOW INCREASE CASE Rev. 17 11/13
I
~ 8G
...l!l 60
§1::'
~~ 40 8~ 20
~
0:
0 0 20 40
.~ 60 80 100 0: 6()(1
.......~ 580
"' I
!!It:'
560 ge W(,)
~
cl
"'"'~
~
520 0 20 40 60 8G
1110
~
5
~
- l:\
- z
(
c J
2 1
0 20 ~0 TIME (:~<<)
60 ao 1110 The analysis that produced the abo..*e figures con$ervatively bounds the actual plant configuration. This analysis uses different setpoinl coefficients in the 0P6T reaaor trip setpoint from what i.s cumntly configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-2A REACTOR COOLAIIT LOOP DELTA-T VESSEL AVERAGE TEMP AIID DIIBR TRAIISIEIITS FOR HFP FEEDWATER TEMPERATURf RfDUCTIOIIIIICIDEIIT RB/,11 1110
20
(/)
(/)
w 0:::
20 w
(/)
(/)
w 0:::
20 CALLAWAY PLANT FIGURE 15.1-28 VESSB. AVERAGE TEMP, PRESSURIZER PRESSURE AND WATER VOLUME TRANSIENTS FOR HZP FEEDWATER MALFUNCTION
- FLOW INCREASE, MULTI-LOOP CASE Rev. 0 11/13
I .20 I I I I I 0:::.--.. I. 15 t--
w*
3:2:
oO I. 10 1---
o__Z o:::LL I .05 f--
<(0 Wu I .00
_j<(
Uo:::
- JLL Z....__. .95 f--
.90 2400 2300 -
0:::
Ww No:::.-..
1-!::J<(
2200 ~
o:::(.f)t-1 2100 f--
- J(.f)(.f)
U1wo__
U1o:::....__. 2000 -
Wo__
0:::
ll.
1900 f--
1800 1400 1300 o:::W w:L 1200 N::J.-..
1-!_jl- 1100 o:::OLL
- J> 1000 U1o:::::J U1wu 900 WI-....__.
0:::<( 800 o__3:
700 600 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-3 NUCLEAR POWER, PRESSURIZER PRES-SURE AND WATER VOLUME TRANSIENTS FOR TEN PERSCENT STEP LOAD INCREASE, MINIMUM REACTIVITY FEEDBACK, MANUAL REACTOR CONTROL 014-A-20766-7
3.00 I I I I I 2.75 r--
2.50 r--
2.25 -
0:::
co z 2.00 -
0 I. 75 r--
I .50 r--
I .25 r--
I .00 620.
lL I 610. r--
wu
(_l)w
<{0 600. r--
0:::.....__....
Ww
>o:::
<{:.:J 590. ~
wf-0:::<{ 580. -
oO:::
uW o_
2:
w 570. -
f-560. -
550. I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-4 DNBR AND VESSEL AVERAGE TEMPERATURE TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MINIMUM REACTIVITY FEEDBACK, MANUAL REACTOR CONTROL 014-A-20766-8
I. 20 I I I I I 0::..-.. I. 15 1--
w*
3:L oO I. 10 1--
rr_Z o::LL I .05
<(0 wu
__j<( I .00 [1 Uo::
- JLL Z.._, .95 1--
.90 2400 2300 1--
0:: ..._
Ww No::.--
1-i:J<(
2200 -
0::(])1-i 2100 .....__
- J(j)(j)
(J)WQ_
(])0::.._,
Wrr_ 2000 -
0::
Q_
1900 -
1800 1400 1300 -
o::W -
w:L 1200 N:J...........,
1-i__jf- I 100 -
o::OLL
- >> 1000 -
(j)o:::J (J)wU 900 f--
WI-.._,
0::<( 800 1--
(L3 700 -
600 I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-5 NUCLEAR POWER, PRESSURIZER PRES-SURE AND WATER VOLUME TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MAXIMUM REACTIVITY FEEDBACK, MANUAL REACTOR CONTROL 0 14-A-20766-9
3.00 I l l l I 2.75 r--
2.50 r--
2.25 r--
0::
z 2.00 ~
(()
0 I. 75 r--
I .50 r--
I .25 r--
I .00 620.
LL I 610. r--
wU C9w o::'-' 600.
<{0 Ww
>o:: 590.
<{::)
wl-o::<t: 580. -
oO::
uW [L L:: 570. -
w 1-560. -
550. I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-6 DNBR AND VESSEL AVERAGE TEMPERATURE TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MAXIMUM REACTIVITY FEEDBACK, MANUAL REACTOR CONTROL 014-A-20766-10
I .20 0::..----.. I. 15 w*
32:
oo I. I 0 o....Z o::LL I .05
<(0 Wu I .00
_j<(
Uo::
- JLL .95 z'-'
.90 2400 2300 0::
Ww No::...---.. 2200 1---t:::J<(
O::cn~---~
- Jt.nt.n 2100 Lnwo....
(f)O::'-' 2000 Wo....
0::
0....
1900 1800 1400 1300 -
o::W -
1200 w:L N:::J.....--..
1---t_j~ 1100 -
o::OLL
- J> 1000 I--
(f)o:::::J t.nwu 900 r-W~'-'
0::<( 800 r-0....3 700 f--
600 I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. Ol-1 6/87 CALLAWAY PLANT FIGURE 15.1-7 NUCLEAR POWER, PRESSURIZER PRES-SURE AND WATER VOLUME TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MINIMUM REACTIVITY FEEDBACK, AUTOMATIC REACTOR CONTROL 014-A-20766-11
3.00 2.75 2.50 2.25 rr OJ z 2.00 0
I. 75 I .50 I. 25 I .00 620.
LL I 610. 1--
wu C.9w
<t:o cr...___.. 600.
1--
Ww
>rr 590.
<t::::J
~-
f.- - --
wl--
rr<t: 580. -
orr uW ()_
- L 570. 1--
w I-560. f--
550. I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-8 DNBR AND VESSEL AVERAGE TEMPERA-TURE TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MINIMUM REACTIVITY FEEDBACK, AUTOMATIC REACTOR CONTROL 0 14-A-20766-12
I .20 0::..----. I. 15 w*
32:
oo I. 10 o_Z o::LL I .05
<to Wu I .00
_j<t:
Uo::
- JLL .95 Z...__._
.90 2400 2300 -
0:: ~
Ww No::..----. 2200 -
1--l:::J<t:
0::(111--l 2100 -
- JU1U1 U1wo...
U1o::...__._ 2000 -
Wo_
0::
D...
1900 -
1800 1400 1300 r--
o::W w2: 1200 f--
N:::J..----.
1--l_jf- 1100 -
r--
o::OLL
- J> 1000 r--
U1o:::::J U1wu 900 r--
WI-...__._
o::<t: BOO r--
0...3 700 r--
600 I I I I I 0 50 I 00 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-9 NUCLEAR POWER, PRESSURIZER PRESSURE AND WATER VOLUME TRAN-
~ENTSFORTENPERCENTSTEPLOAD INCREASE, MAXIMUM REACTIVITY FEED-BACK, AUTOMATIC REACTOR CONTROL 014-A-20766-13
3.00 I l I l l 2.75 1--
2.50 1--
2.25 1--
cr:
co ~
z 2.00 0
- l. 75 1--
l .50 1--
I .25 ~
I .00 620.
lL I 610. -
wU C9w cr:-........- 600. -
<(0 Ww ..........
>cr:
<(::::::)
590. -
wl-cr:<t:: 580. -
ocr:
uW D..
2: 570. 1--
w 1-560. 1--
550. I I I I I 0 50 100 150 200 250 300 TIME (SEC)
Rev. OL-1 6/87 CALLAWAY PLANT FIGURE 15.1-10 DNSR AND VESSEL AVERAGE TEMPERATURE TRANSIENTS FOR TEN PERCENT STEP LOAD INCREASE, MAXIMUM REACTIVITY FEEDBACK, AUTOMATIC REACTOR CONTROL 014-A-20766-14
1.07,-- -- - - - - - -- - - -- - ----,
1.06 0.99 0.98 -....--~---.--~-~-~--~---l 200 250 300 350 400 450 500 550 600 Core CoolanJ Average Terrperature (Oeg. F)
CAJ..LAWAY PLANT I'IQQE16.1-11 K,. ~U&Ia1BIPBM111E
CALLAWAY - SP Figure 15.1-12 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.1-13 Deleted REV. OL-~15 5/06
- 1800 E
~"
1600 1400
~
B 1200 .
...*~ 1000 800
~
a.
a.
0 600 c
'0
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0 5 10 15 20 25 30 40 Cor* Pow<lr (por<:tnl)
CAJ..LAWAY PLANT Dill PLIRPGIIIBlH I IB&CK
CALLAWAY - SP Figure 15.1-15 Deleted REV. OL-~15 5/06
~
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- ... .. ... ~ ~
Z' *"
,g 3
CAJ..LAWAY PLANT MICLEiMPCWIERANJ CORE taT R.lll TRAllllmii'ORA IIIMIII LII!DB\
CIR'IITEPCM!RAVAIL.AII.E
Iu
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c-CAJ..LAWAY PLANT PN IWttftPN IUEAII)FN *
- M Wo\TI!RYCt..I!T!Wai!INT'&I'ORAtnall UEIIR,CW&IEPCMRAVM ** F
CALLAWAY - SP Figure 15.1-16 Deleted REV. OL-~15 5/06
- f~LitOI)
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~c
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--- loo~l...,IIJ
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... ~-----------------------------,
CAJ..LAWAY PLANT FIOIIE11.1-11A YBIIB. IlLEr AMI LOOP AVBWIE
,_JIBM'I'Ia!'I'MIIIImii'IRA 81111111 UEIIR, OfRIIEPCfMRAVM ** E
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~-
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CAJ..LAWAY PLANT RGIIE1&1-118 II'Eo\C1MIY AliDCCIEIIIJCIIDI
'T'RANIIII!!NI'8 I'ORA SI'IINI LIM!II!R, GFSIEPOMRAVM ** F
CALLAWAY - SP Figure 15.1-17 Deleted REV. OL-~15 5/06
- - I#W(.,.
- - - r.,.;,,d lcoop tiW nO"'
l~ 2. } QI'Oj 4 11'11 1'\:7.
>Me---------------------------------,
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~---- -
lWIOCu;c:)
CAJ..LAWAY PLANT I'IOUE11L1-17A A I 1Mf\1ERA.CW AIDII1EIIII
"-MTMNIIII!!IImS I'ORA lm!IUI LIM!II!R, WIEPCWIRAVM ** F
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8 llM~(&ee*
CAJ..LAWAY PLANT 81'ENI FABIII'IIIEANJ COIIER.CM TMNIIII!!NI'& !'ORA STIINI LIM!II!R, GFSIEPOMRAVM ** F
CALLAWAY - SP Figure 15.1-18 Deleted REV. OL-~15 5/06
.~.------------------------------------,
X 5~
l 0
- rJ TI- ($.CC)
RfV. OL*15 5!06 CALLAWAY PLANT IIICUiMIQWRAII)CCH:IaT R.Ut TMIIBCI'II'DRimNI I..N!IIB\
tDOfRIIEPCfMRAVM ** F
- >c
..Ill -....
h I* 1000 \.._
500
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CALLAWAY PLANT PN!II'*7 FRPIBit..IEANl PBIIM'fRWATBl VCLUII!TIW 1ft-~~ II'IINII.NIBt, II)G+&IEPCila:AVM ** F
CALLAWAY - SP Figure 15.1-19 Deleted REV. OL-~15 5/06
ft~olle6 loop
- - - l oCi's 2 or-d J
- -- loc>> of D~----------------------------------------~
... _1:,,,__ - -
$DO - - --:.::::--... =--== . . _ __ _
- ~_...:::
-- - - - ~ --- - -----=:::::-=-.-_ ;:.
- 1$0
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- - - l OOI!S 2 Oncl 3
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~~----------------------------------------~
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~
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CALLAWAY - SP Figure 15.1-20 Deleted REV. OL-~15 5/06
- uf* nw
- - - f(ltlut t.o¢t II* , ..,_.
1.~1'$ 2. 3 WM14 JIW fllN
'M~-----------------------------------,
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- f**lp,l l_~
lw:. ;t, J m*'
-*~-----------------------------------------,
CAJ..LAWAY PLANT FIGIIE11.1-2M HI LW'\TERR.OWAII)In9ll R.OW TIWaEMSI'IlRASI'I!NI LIM!II!R, IDCWSIEPOMRAVM ** F
- - loJlt.,$ l0:9
-- - \~ ~ On4J
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vr--------
. --------=:------ --
---:::-..::..-..=
- .. 000 0
~~
0 u
A l'IMC t KCI CAJ..LAWAY PLANT 4n'EMI PI&I'IEAMJCOAER.CM TIWIIIIMSI'IIRASI'IMII LIM!Ili!R, IDCWSIEIGMRAVM ** F
1.4 1.2
~
a.z-0 0.8
~g 0.6 0
=>
z 0.4 0.2 0
0 10 20 30 40 TIME (SEC) 1.2 X 1
~
....,.- 0.8
- c
- Z wp
- J:e, LU 0.6 8
0.2 0~~~-~~~~~-~~~_.~--._~-r~--~~~-i 0 10 20 40 TIME (SEC)
The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1*21 STEAMLINE RUPTURE FULL POWER CORE RESPONSE REV.12 1/10
2000 4-~_.~--~~~_.~~~~~_.~--~~~_.~--~
0 10 20 30 40 TIME (SEC) 900
~ 4-~_.~~~~~~~~~~~~~~~~~~~~~
0 10 20 30 TIME (SEC)
The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1*22 STEAMUNE RUPTURE FULL POWER CORE RESPONSE REV.12 1/10
INTACT LOOPS
- - - - FAULTED LOOP
~ ,---------------------------------------------------~
530 520+-__.__.----l'--.l-..-t-.......---1.-lo..._.......-+-~---"-"--...l.--+-___,j,--'---'--....:....--l 0 10 20 30 T1t.tE (SEC)
~ ~----------------------------------~
sro ~__.__. __ ~._-+-_.__, __.__..._-+-_.----l__ .l-..~~~--~ ...........:....~
0 10 20 30 40 TIME (SEC)
The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-23 STEAMUNE RUPTURE FULL POWER CORE RESPONSE REV. 0 1/10
Intact Loop
--- - Faulted Loop 2500
~ 2000
~0 ,, .... - - ....
0::~ 1500 .......
~'
~! 1000
~ 500 0
0 10 2500 2000 31C-
~~ 1500 I
~
~! 1000 500 0
0 10 2 30 40 TIME fsEC) 1200 1100
~
(/)'i'
~ (/) 1000 O::Q.
a.- '
()
U) 900 .._ ___ _....
800 TIME~SEC) 0 10 30 40 The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-24 STEAMUNE RUPTURE FULL POWER CORE RESPONSE REV. 0 1/10
2000 500 o +-~_.~--~+-~_.~--~+-~_.~--~+-~_.~--~
0 10 20 30 TIME (SEC)
The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-25 STEAMUNE RUPTURE FULL POWER CORE RESPONSE REV. 0 1/10
4 2
1 ~~~--~~~~--~~~~--~~~~~~._~~~~
0 10 20 30 40 TIME (SEC)
The analysis that produced the above figures conservatively bounds the actual plant configuration. This analysis uses different setpoint coefficients in the 0Pl1T reactor trip setpoint from what is currently configured. The effect of the differences between the analysis inputs and the plant configuration is that the analysis inputs result in delayed protection and more limiting results.
CALLAWAY PLANT FIGURE 15.1-26 STEAMUNE RUPTURE FULL POWER CORE RESPONSE REV. 0 1/10
'.2- . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
TIME SEC)
CALLAWAY PLANT FIGURE 15.2-1 TURBit~E TRIP EVEtH WITH PRESSURIZER SPRA V Atm POWER OPERA TED RELIEF VALVES Rev. 17 11/13
w 2600 ll
=>
(/)
(/)
w ll Q_~
2400
<(
ll -
w lfl 1"-1 ~
ll
=> 2200
(/)
(/)
w ll Q_
2000 1800 -f-.....1....---1..----1-+-_.__.....1....---1..---f-..___.__.....~....-+----'-..___.__-+----1..----1-.l.........l 0 20 40 60 80 100 TI ME (S EC) 1800 1700 w
2
=> 1600
_j 0
> 1500 ll w
- -n 14oo
- S: c-LL t5 "-..-/ 1300 1"-1 ll
=>
(/)
1200
(/)
w ll Q_
1100 1000 900 0 20 40 60 80 100 TI ME (S EC)
CALLAWAY PLANT FIGURE 15.2-2 TURBINE TRIP EVENT WITH PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 17 11/13
....J w
~
w llME (SEC)
....J w
(/)
(/)
w llME (SEC)
CALLAWAY PLANT FIGURE 15.2-3 TURBINE TRIP EVENT WITH PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 17 11/13
TIME {S EC) 5 ~------------------------------------------------~
~
- 0 z
0 TIME SEC)
CALLAWAY PLANT FIGURE 15.2-4 TURBINE TRIP EVENT WITH PRESSURIZER SPRAY AND POWER OPERATED RB.IEFVALVES Rev. 17 11/13
' .2. . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ,
o ~~~-~~~-~~~~-~~-+~~~~~-~~~~
0 TIME SEC)
CALLAWAY PLANT FIGURE 15.2-5 TURBINE TRIP EVENT WITHOUT PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 16 11/13
2 0 ~-----------------------------------------------,
2
(/)-
(/) ~
~ (/) 2 TIME 0 ~-----------------------------------------------,
0 no +-~_.~~+-~~~--~~~_.~--~~~~--~~-~-~
0 /0 40 TIME SEC)
CALLAWAY PLANT FIGURE 15.2-6 TURBINE TRIP EVENT WITHOUT PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 16 11/13
....J w
(/)
~
TIME (SEC 0
TIME ( EC CALLAWAY PLANT FIGURE 15.2*7 TURBINE TRIP EVENT WITHOUT PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 16 11/13
4 0 ~--------------------------------------------~
w .......,
- z w
10 CALLAWAY PLANT FIGURE 15.2-8 TURBINE TRIP EVENT WITHOUT PRESSURIZER SPRAY AND POWER OPERATED RB.IS: VALVES Rev. 16 11/13
.2
_J -
4:. -
o::Z W:z -
~ a
.s---
oz -
o.. u.... -
0::: .s--
~z -
_. 0 --
I- ,4--
z~ -
c::: -
u....
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- I I I I I I Ill I I I I I I Ill II I II 0
0 I 2 3 I 10 I 10 w
~
(/)
~
~
CL 0~ -
~~
w......
z w
(.!)
- 2
<(
w tli
- o TIME (SEC)
CALLAWAY PLANT FIGURE 15.2-9 NUCLEAR POWER AND STEAM GENERATOR PRESSURE TRANSIENTS FOR LOSS OF AC POWER Rev. 17 11/13
- - - HOT LEG COLD LEG
, ---- --- ------- - - ~.
I I
',2- r - - - - - - - - - - - - - - - - - - - - - - - - - . .
10 TIME (SEC)
- All loop**
CALLAWAY PLANT FIGURE 15.2-10 REACTOR COOLANT TEMPERATURE AND MASS FLOW RATE TRANSIENTS FOR LOSS OF AC POWER Rev. 17 11/13
0 TI ME (SEC)
CALLAWAY PLANT FIGURE 15.2-11 PRESSURIZER PRESSURE AND WATER VOLUME TRANSIENTS FOR LOSS OF ACPOWER Rev. 17 11/13
.2 1-1-
1-
_..... *-r-
_J 1-
..:( 1-
~ z 1-w~ .s -o 1-Oz 1-o... l.J.... 1-
~ .6 -I-1-
l3z
.....J Q 1-1-
1- ,4 z~ 1-e::
l.J....
1-
......... 1-
.2 1-1-
1-I I I I I I Ill I I I I I I Ill I I II 0 I I I 0 1 2 3 I 10 I 10 w
~
(/)
r:l
~
a...
0~ -
~~
w .....,
z w
(.!)
2
~
Vi
- o TIME (SEC)
CALLAWAY PLANT FIGURE 15.2-12 NUCLEAR POWER AND STEAM GENERATOR PRESSURE TRANSIENTS FOR LOSS OF NORMAL FEEDWATER TO ALL STEAM GENERATORS Rev. 17 11/13
- - - HOT LEG COLD LEG 0 2 0
3 1*
' . 2 ~-------------------------.,
TIME (SEC)
- All loop**
CALLAWAY PLANT FIGURE 15.2-13 REACTOR COOLANT TEMPERATURE AND MASS FLOW RATE TRANSIENTS FOR LOSS OF NORMAL FEEDWATER TO ALL STEAM GENERATORS Rev. 17 11/13
(/)
(/)
w
~
a..
0 TIME (SEC)
CALLAWAY PLANT FIGURE 15.2-14 PRESSURIZER PRESSURE AND WATER VOLUME TRANSIENTS FOR LOSS OF NORMAL FEEDWATER TO ALL STEAM GENERATORS Rev. 17 11/13
I 2 10 1
- .o ~------------------~
~== -
~~ - .o*
~7 -.o2 W <t g§ ~ - .03 ow
_J - -.04
~
r-CALLAWAY PLANT FIGURE 15.2-15 NUCLEAR POWER, CORE HEAT FLUX AND TOTAL CORE REACTIVITY TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
w
- .:2
(/)
(/)
w a_
TI ME (SE )
CALLAWAY PLANT FIGURE 15.2-16 PRESSURIZER PRESSURE AND WATER VOLUME TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
s ~------------------------------------------------~
TIME ( EC)
CALLAWAY PLANT FIGURE 15.2-17 REACTOR COLLANT MASS FLOW FATE AND REEDWATER LINE BREAK TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
7 0----------------------------------------------------.
SA RAll HOT l£
- I ~/
/ .-
/
_, /
I I
I I r '
,' ., \ \
OLD LEG , .,' \
, I 2
1 TIME (S EC CALLAWAY PLANT FIGURE 15.2-18 TEMPERATURE TRANSIENT IN FAULTED LOOP FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
H if LEG
\
\ I
./ \ I COLD LEG
~~ \ I
-- ' \
/
I
~,
\ I 7 o ~--------------------------------------------------~
COLD LEG 2
1 TIME ( EC CALLAWAY PLANT FIGURE 15.2-19 TEMPERATURE TRANSIENT IN INTACT LOOPS FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
w
~
- J
(/)
(/)
I UJ
~
a_
_J
_J w
I ,-..
~/
(/) ~
~(/)
a a..
t-: -
w
- z:
UJ 0
UJ
~
L OP -F LTE LOO
- o 0 TIME SEC)
CALLAWAY PLANT FIGURE 15.2-20 STEAM GENERATOR SHELL PRESSURE TRANSIENT FOR MAIN FEEDLINE RUPTURE WITH OFFSITE POWER AVAILABLE Rev. 17 11/13
0 1
10 CALLAWAY PLANT FIGURE 15.2-21 NUCLEAR POWER CORE HEAT FLUX AND TOTAL CORE REACTIVITY TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
(/)
(/)
w a..
TIME ( EC)
CALLAWAY PLANT FIGURE 15.2-22 PRESSURIZER PRESSURE AND WATER VOLUME TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
0_J 5
I.J....
o a:::
_J~
u....
~
L5 w a:: W w u...
wl-
...,.. z
- i :5 0..
~~
f:2 Wu...
li TIME { EC)
CALLAWAY PLANT FIGURE 15.2-23 REACTOR COOLANT MASS FLOW RATE AND FEEDWATER LINE BREAK TRANSIENTS FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
7 o ~--------------------------------------------------~
SA RAll HOT L£ __.., - - ,.
I I
/
,,/
I ~
I ,'
OLD LEG ,,'
I 2 ..
10 1 10 0 TIME (SEC CALLAWAY PLANT FIGURE 15.2-24 TEMPERATURE TRANSIENT IN FAULTED LOOP FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
o ~--------------------------------------------------~
H T LEG I
I - , -" --- " ..
,, /
__, ; '\ , I '~ _
COLO LE
\
\ ,' "
\ I
\ I
\I 7 o ~--------------------------------------------------~
I
./
I , /
COLO LE __ _ - - --- ,,
, , /
,I 2
1 nt~E ( EC CALLAWAY PLANT FIGURE 15.2-25 TEMPERATURE TRANSIENT IN INTACT LOOPS FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
w 0::: LOO
(/)
(/)
UJ 0:::
a_
_J
_J w
I -
(/) <(
~(/)
o a..
t-: -
w
- z:
UJ 0
- s UJ l/)
L p -F LTE LOO
- o TIME SEC)
CALLAWAY PLANT FIGURE 15.2-26 STEAM GENERATOR SHELL PRESSURE TRANSIENT FOR MAIN FEEDLINE RUPTURE WITHOUT OFFSITE POWER Rev. 17 11/13
CALLAWAY - SP Figure 15.2-27 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-28 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-29 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-30 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-31 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-32 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-33 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-34 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-35 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-36 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-37 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15,2-38 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-39 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-40 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-41 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-42 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-43 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-44 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-45 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.2-46 Deleted REV. OL-~15 5/06
u
~
lfg ..
r* A 2
- 0 TTM£ (SEC)
CALLAWAY PLANT R._,.,._,
R.CMTMMIENT8 FORRIIR LGCIN IN CIPI!Rf.o'T'ICIN, TWO
....,. caunm DOICIIII
1A u
~ I "0
.. -z ..
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- 4-~--~~-+--~~~~.~~~~~t- . ~~--~~~--~~~
- 4 * * "
~
w
~
~~ ,,
~
=>
OICO w
0:
1900 ~
- 2
- TlMIS (SeC)
- I 10 CAJ..LAWAY PLANT MICLEiMPCMIIIBlAm PABIJ'*ZFRPREIII'IIIIE TMNIIII!!NI'& I'ORI'OIRLGClNINGPI!MTIGN,
'I'M)FUIN~DD'JlN
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0 2
0
- 2 * '
- 10 1.4 1.2 X
~
i 1-
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z-A 0
1-0
- 0 2 * *
- 10 TIME (SEC)
CAJ..LAWAY PLANT CCIEAVBMGEAIDHMCIWIE IBT IUIICTMNIIIIM'SI'aRI'OIRLODPISIN CFIM...._ 'IWDFUIPI CDI>nwll IIOMII
7 5
a:
~ 4 0
3 2
1 0 2 e 10 T IME (SEC)
CAJ..LAWAY PLANT AIUE1u-4 INIRT.W.ENr RIRRIIR LOCIP81NCIPI!!MTICIN,
'I'M)FUIPll CQIIIIK! Dali'M
CALLAWAY - SP Figure 15.3-4A Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.3-4B Deleted Rev. OL-15 5/06
- ~---------------------------- .
I
- 0
..J ~
II.()
a:-
0 .6
()
2-CALLAWAY PLANT caER..CIW 1JIIAt Wll' RR l'alR LCIIIN IN QFI!!RATICIN, Fllllt I'UIN CQU1W:lllOIMIJ
lA u
II J
2i ..
~~ **
z 0
- ' *
- I 10 w
Lr
-.... * *
- 10 0
' TIME (SEC)
CALLAWAY PLANT HOU!LtUo41 IIUCU:.MPOrBIMDFN IW MFN IUL TRAI?Ftre Jlllti'IIUILCXIFIIIa ....~
..... _ . . count~!~ Dm1lt
1.4 X
3
~
1-X wZ'
- oo
<~
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w a:
0 0 2 * *
- 10 1.4 1.1 X
- J
~
1-
"'x-
..,o z~
z-ij 1-0 X
0 0
'
- TIM E (SEC)
- 10 CAJ..LAWAY PLANT RIIIRi:,U.T COREAVBWIEAM:I HIJ1" CIWIB. taT R.IIX TMNIIIIM8 I'DIU'DIRLODPS INCIPI!!MTION, RIIR,_P8 CGUI'INCIIIICrMI
It ID z
0 0
- B 10 T IME(SEC)
CAJ..LAWAY PLANT IIIRTIWIBIJ Fat I'IIIILOJlFIIICI'IIIII'<~
RIIR.,_P8 CGUI'INCII DaM!
CALLAWAY - SP Figure 15.3-BA Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.3-88 Deleted REV. OL-~15 5/06
WitH Of~ tt POWCR
--- v.vn10u1 orrsnr POI'I(R 1.4 1.2
~
0
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"-o
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- - - WITHOt.n orrsn£ POVIffl
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~0
.,0~ **
1- .2
~
- > 0
- .2
~-- -- --- -- ---- - -- ---- -
- .6 0 2
- nME(SEC)
- *' 10 CAJ..LAWAY PLANT ROIIE1u-t R.CM~ENT&FCIR l'llllt LOCII'SINCIPI!Ro\TION, CIEI..OCM!IRmCR
WITH OfTSfl£ POWER WITHOVl Off SrTE POWER
~~ ------------------~---------------------------,
2700 1-2100 2500 2400
/. /-------
2300 2200 2100 TI M E (SEC)
Nlrl'mi:
- Per NIAL.ol4,a45P81 penalt;y 11M liMn added to tM akulatltd peak AC8 p,...,.,.
~IIIIWI"' a laolc<HI rator III!OianL '"Tu'-11.14.
CAJ..LAWAY PLANT RGIIE1...,0 PQKiaC'IllllCOCII.ANT PI&IIIRE ll'lllll'llllll.Ollfl .. CI'~~
CIII!LOCICB) Rai'Gil IE!f.1e 11te
WBH OHSilE POWER
--- WO~OUl OFFSIT( PI)';[R
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1.2 ..
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0 z-X liX
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0 0 2
- T1ME (SEC)
- 10 CAJ..LAWAY PLANT MICLEWlPCIIIIIBI, COREAYE!WieAN:I 1m CIMII". IBT lUI( TIWIIIII'II'IDR Rlllli.OCPI .. IRM...,.._ CIEUX:I'P'II'IImllt
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CN..LAWAY PLANT R-..E,u-12 IE't. C&A*
MAXIM~ CLADTBIP!Wo'T\R:
AT 11M ..ol' -l'lllR LOCI Ill til-~ tiiELootiDRmtllt
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
CALLAWAY - SP Figures 15.3-13 thru 15.3-24 have been deleted.
Rev. OL-4 6/90
102 i-
- !I§ H~l 100
~i 1(3- l l0-2L---------~--------------~--------
- 0. 5. 10. 1s. 20. 25 . 30.
TIME I SEC J REV. OL-5 6/91 CALLAWAY PLANT FIQU"E 11A-1 CO"E AVE"AGE HUCLEA.Jil.-ow£"
TRANSIENT FO" UNCONT"OLLEO "00 WITHO"AWAL F"OM A IUte"ITICA.L CONDITION
1*
~
a
. '1
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.::~
.7
.6 c.>
.5 0::
- 4
/\
.3
.2
\~
0.
- 0. s. 1121. IS. 20. 25. 312l.
T 111£ tS£CJ REV. OL-5 6/91 CALLAWAY PLANT FIGURE t5.C*2 THERMAL FLUX TRANSIENT FOR UNCONTROLLED ROD WITHDRAWAL FROM A IUBCRJTICAL CONDITION
~ 1800.
1600.
1400.
I 1200.
1000.
~ 800.
~ 600.
~ 400.
- 0. 5. 10. 15. 20. 25. 30.
U-800.
~ 750.
I 700.
650.
~ 600.
~ 550.
~
500.
- 0. 5. 10. 15. 20. 25. 30.
TlME ISECl REV. OL-5 6/91 CALLAWAY PLANT FIGURE 15.,*3 FUEL AND CLAD TEMPERATURE TRANSIENTS fOR UNCONTROLLED ROD WITHDRAWAL FROM A SUB*
CRITICAL CONDITION
1.4 1.2 1*
cr w
a.z-0 0.8
~g
~
o.s-z o.*
0.2 0
0 2.5 5 7.5 10 TIME {SEC) 1.4 1.2 -
X
~
0.8
!<<Z' wo
- 1:~
0.6
~
8 0.4 0.2 0
0 2.5 5 7.5 10 TIME (SEC)
CAJ..LAWAY PLANT RIIIIE,u-t IN:GNI'ADI.LED IICCA BU<<WITIIlMWAL RDII RLL FOWS\wmt IIIINIII&-.
IBCIMIYI R'\CIC (ttl PCIIIEC '111111lMWAL MTE) 11:11. te ttte
!:! 2300
~
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1300 1200" ffi
~~ 1100t___________________________________
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~ goo-g:
800 2.5 5 7.5 10 TIME (SEC)
CAJ..LAWAY PLANT HOIIIRtL+41 IJClNIRl'!l I mRCCA IWI(
~WIILI'IQI RU.PCVJER'MIH IIIINIII. . !aCTIVITY I' '""M:K (ttiPCIIII&~YMLMTEt RBf.1e 1110
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CAJ..LAWAY PLANT I'IGIIE1L+t IINCCINI'ID.LED IICCA au<<
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CAJ..LAWAY PLANT IJibliiiRl'll mRCCA IWI(
WITICRAWAL FftCIM RLL PCMIR WITH MINMW. !aCTIVITY l""'"*l:K (t PCIIIIEC WIIHIMWAL MTEt REI/, tl 11t0
2400,----------------------------------------------,
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TIME (SEC) 160Q'T'""-----------------------------------------------,
30 60 90 120 TIME ( SEC)
CAJ..LAWAY PLANT RGIIE1U4 IINCGNI'IIDI.LED RCCA IIUK WITIIIRo\WAL I'RICIIII RLL I"'WBl MIHM. .._IIEio\ClMIY ftii"MQC 11 PCMIIB: WITitR\WAL MT~
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2*6 1.8r--------._j 30 60 90 120 TIME (SEC)
CAJ..LAWAY PLANT IID'llftRL'III mRCCA UM(
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CAJ..LAWAY PLANT RtiiiE1...._,0 MIMM&-.INIRYERII.REi!UmVITY INIII!ImON MTI!; RDD'WIT1IlM*I.
. . . . . . . FllltSa' I'CNR 1&. ,, 1110
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CAJ..LAWAY PLANT RGIIE1M-'11 MINM. DNilYERII.IBC'TlVITY INIII!!ImON MTI!; RDDWinllAo\WAI.
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-I 0 1 l l 10 10 10 10 10 R£ACTMIY ADDfllON RATE (PCt.t/SEC)
CAJ..LAWAY PLANT RGIIE1...._,Z M1NML-. DNilYERII.IaC'TlVITY 1NIII!!ImCIN MTI!; RDDWIT1IlMWAI.
FRillliOF&aNI' I'GMR RE¥.18 ,,,
- l. I
__J
<( 1.0 z
0:::1-1
~5 oz 0.9 0...
I.J...
0:::0
<(
wz
__JQ 0.8 U~-t
- >I-ZU
<(
0:::
I.J... 0.7 0.6 0.5~--------------------------------~
I . 2 ,..--------------------------...,
I. I
__J
<(
xz
__J~ 1.0 I.J...Q z
1-I.J...
<Co w 0.9 Iz wo 0:::1-1 ol-uu <(
0.8 0:::
I.J...
0.7 0.6 ~------~------~-------~------~
0 50 100 150 200 TIME (SEC)
REV. 16 10/06 CALLAWAY PLANT FIGURE 15.4*12a NUCLEAR POWER TRANSIENT AND CORE HEAT FLUX TRANSIENT FOR DROPPED ROD CLUSTER CONTROL ASSEMBLY
600 I I I WLL
(!)o 580 "--
~
<( .........
0:::
ww
>0:::
<(::J 560 1--
I-
_j<(
wo:::
(J)W (J)(L WL:
>W I-540 I--
520~--------------------------------~
2400 ~----------------------------------~
2300 w
0:::
- J
{f) w . . . . . 2200
{f) 0:::<(
(Lt-t
{f)
>-CL
~ ........ 2100 L:
1-1 0:::
(L 2000 1900 ~------_.--------~------~~------~
0 50 100 150 200 TIME (SEC)
REV. 16 10/06 CALLAWAY PLANT FIGURE 15.4-12b PRESSURIZER PRESSURE TRANSIENT AND CORE AVERAGE TEMPERATURE TRANSIENT FOR DROPPED ROD CLUSTER CONTROL ASSEMBLY
-. ..1 c
-Iz 0
z 0
u c
~.....
TIME (SEC)
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.(-13 NUCLEAR POWER TRANSIENT FOR STARTUP OF AN INACTIVE REACTOR COOLANT LOOP
1.4
~ 1.2
~
z
~
0 z I.
~
0 z
0
~
u
~
.9 ff *'
.4
~ HOT
.2 AVERAGE \ CHANNEL CHANNEL '-... .....
a.L-~~~~==============
- o. s. I D. ~
I
- 2a
- 2'5
- 30
- ss.
TIME (SEC)
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.4*14 HEAT FLUX TRANSIENT FOR STARTUP OF AN INACTIVE REACTOR COOLANT LOOP
2.2 2.
~
c: I *9 z
~
0 1 .6 1.~
z 0
u c:
- 1. 2 I.
e:
.9 0 .6 rt a: -~
0 u .2 3.
- c. s. I D. 15. ~J. 2'5. ~- ss. ~0. 45. sa.
TIME (SEC)
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.4*15 CORE FLOW TRANSIENT FOR STARTUP OF AN INACTIVE REACTOR COOLANT LOOP
2~:3.2.
~-
~-
c f;
2~.
I.,. 22'00 *
--f
....w
~ 21ro.
21~.
f .?~.
~-
- c. s. . ~
~~- :5. n. .?S
- 5.:). S'S. -'Z. 45. sa.
7U:.
&9-J.
~
a &62.
~ 6.&2.
~
c t 6.2~ *
..., 6CJ
- u c
c S963 *
~-
~
u 5-'C.
sn.
S~l.
- c. s. ....
- ~ : s. n. 2'5. sz. ~- "~- -'S. ...
c._...
TIME CSEC)
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.4*16 CORE AVERAGE TEMPERATURE AND PRESSURIZER PRESSURE TRANSIENTS FOR START UP OF AN INACTIVE REACTORCOOLANTL~
u Ll
... J
- LJ
- l
" 1.1 1.1 L1 l.t l.l l u
- ' I I lC
~ {!It)
.. u ** u ..
CAJ..LAWAY PLANT RIME1M-'IT IIIRTIWIBJrRIR ln'AIIIU' fill AlllaC'IM!
I&CI'CRCOCI 'Jlr LOlli'
CALLAWAY - SP Figure 15.4-17A Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.4-178 Deleted REV. OL-~15 5/06
40 26-385 R P H M L K J H G F E . D C B A
-8.9 7.1!
5.6 -9. I -8.5 2
-8.2 -6.8 -11. I 0.2 3
-7.9 8.2 -7.7
-8.1! -6.0 -3.8 -1.8 5
-8.5 8.1! -7.1! -5.5 0.3 6
-7.7 5.0 -I. 2 1.0 7 1-7.7 -7.3 -5.9 f- 3. 2 I. 5 3.2 3.4 3.6 8 1-6.9 2.7 5.9 6.0 9
-3.4 0.7 10.6 10 1-5.3 -1.8 5.9 17. I II. 4 II 1.3 I 2. 3 24.6 12
- 0. I 0.7 7.7
~ 23.6 13
- 2. 5 1!.7 II. tBx( 17.6 I~
2.1 6.5 IS CASE A Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 15.4-18 REPRESENTATIVE PERCENT CHANGE IN LOCAL ASSEMBLY AVERAGE POWER FOR AN INTERCHANGE BETWEEN A REGION 1 AND A REGION 3 ASSEMBLY
18094-1 R P N M L t< J H G F E D C B A
-4.8 -4.5 1
-0.4 -4.8 -4.8 2
-4.8 -4.4 -2.6 1.4 3
-2.8 -3.1 -4.5 4
-3.9 -4.3 -4.6 -1.5 5
-3.8 -3.8 -3.6 -2.9 0.5 6
-3.6 -2.0 -2.3(
~\ 2.2 7
~ 11.3
\ J
-3.5 -3.4 -2.6 -0.7 11.4 5.8 4.4 8
-3.2 5.2 16.7 5.4 9
-1.7 0.5 8.8 10
-2.2 -1.0 2.2 6.9 6.6 - -11 0.0 2.9 6.5 12 1.2 0.0 1.6 10.3 13 3.2 0.8 3.2 6.0 14 0.3 1.5 15 CASE B-1 Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 15.4-19 REPRESENTATIVE PERCENT CHANGE IN LOCAL ASSBL Y. AVG. POWER FOR AN INTERCHANGE BETWEEN A REGION 1 AND A REGION 2 ASSBL Y. WITH THE BURN. POISON RODS BEING RETAINED BY THE REGION 2 ASSEMBLY
4026-387 R P N M L K J H G F E 0 C B A 1.0 1.1
- 5. I 1.0 1.0 2 1.1 I. I 1.9 4.9 3 1.7 I. 7 1.4 ij I. I 1.8 1.1 0.7 5 0.0 0.2 1.8 3.9 4.0 6 0.0 5.2 2.2 -0.3 7 0.7 -O.E 0.3 5. 11 ~~ I. 5 -0.3 -0.6 -0.7 8
~ 1.1
\ Ll
-1.0 1-0.8 -0.9 9
-1.4 -3. I -1.3 10
-0.9 -I. 7 1.7 -0.9 II
- f. 2. 5 -2.9 -1.1 12 0.7 -1.9 -2.9 2.5 13 2.3 -2.8 -2.4 -0.8 lij
-2. I -2.8 15 CASE B-2 Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 15.4-20 REPRESENTATIVE PERCENT CHANGE IN LOCAL ASSBL Y. AVG. POWER FOR AN INTERCHANGE BETWEEN A REGION 1 AND A REGION 2 ASSBL Y. WITH THE BURN. POISON RODS BEING TRANSFERRED TO THE REGION 1 ASSEMBLY.
4026-388 R p N M L K J H G F E 0 C B A
-2.2 -2.1 2.0 -2.0 -2. I 2
-1.5 -1.6 -1.0 2.0 3
-0.9 -1.0 -0.4 Lt
-0.4 1.2 -o. 5 -1.4 5
-2.1 -1.6 2.3 5.7 -2.0 6
-3.2 9.7 Lt.4 -1.7 7
-2.3 -1.6 1.8 13.6 X 5.6 -O.Lt -1.6 -2. I 8
-2.2 9.7 I. I -2.2 9 0.3 Lt.5 -0.9 10
-1.9 -0.4 1.8 -0.5 -1.9 II
-0.9 -0.6 -1.1 12 0.4 -1.4 -I. 5 2.0 13 2.0 -2.1 -2.0 -o.9 Itt
-1.9 -2.2 15 CASE C Rev. OL-0 6/86 CALLAWAY PLANT FIGURE 15.4-21 REPRESENTATIVE PERCENT CHANGE IN LOCAL ASSEMBLY AVERAGE POWER FOR AN ENRICHMENT ERROR (A REGION 2 ASSEMBLY LOADED INTO THE CORE CENTRAL POSITION)
4026-389 R P N M L K J H G F E D C B A
-II -14 0.4 -9.2 -12 2
-12 -14 -15 -13 3 3.2 I. 2 -II If
-I. 5 -12 -15 -16 5 9.8 7. I -L6 -8.0 -16 6 9.2 -2.3 -12 -14 7 20.0 17.8 10.8 0.8 -10 15 -16 8 27.2 -5.5 -II -15 9 20.7 5.8 -12 10 42.0 [>( 23.6 1.9 -8.6 - 13 II 14.0 -1.7 8.9 12 38.6 20.4 2.8 -7.0 13 35.9 7.0 -3.3 -6.3 I If 15.3 2.9 15 CASE D Rev. Ol-0 6/86 CALLAWAY PLANT FIGURE 15.4-22 REPRESENTATIVE PERCENT CHANGE IN LOCAL ASSEMBLY AVERAGE POWER FOR LOADING A REGION 2 ASSEMBLY INTO A REGION 1 POSITION NEAR THE CORE PERIPHERY
z<
2
- E 0
z I..J._ 1-5 0
z 0
~
~
-u_
~
1
~
a... 0.5
~
c:...>
z=> 0 0 2 4 6 8 0 2 IME (SECO S)
CALLAWAY PLANT FIGURE 15.4-23 NUCLEAR POWER TRANSIENT, BOL, HFP, ROD EJECTION ACCIDENT Rev. 12 11/13
FUEL CE ER TE~ ERA - URE FUEL AVE AG E TE MPER TU E C LA 0 l.l I 1:. R I 1:. tA P l R I E.
~[ L I G 4900 Oeg r c 6000 w
e sooo ~--------~----~-------------------*--
w 0::
=>
< 4000 ffi a..
3000 0
- 5 2000 , ;',
_,----------... '~- ~- ---
-- -~. --... ____
(..)
c (
~ 000 ' '
_J w
- =;:)
0 0 2
- 6 TIME (SECO DS)
CALLAWAY PLANT FIGURE 15.4-24 HOT SPOT FUEL AND CLAD TEMPERATURES VERSUS TIME, BOL, HFP, ROD EJECTION ACCIDENT Rev. 12 11/13
' J 25
~
~
0
- z 2o--
LL..
0 z
0 ts--
t-
~
-e: to--
Ck:
w
~
a...
s-
~
__J u
~
o ~==~~--~*
i ~*--~
- 4*--*~~ * ~*--~! **~*~~
- 4*--~* ~
~ ~~~
0 2 4 6 8 TIME (SECO DS)
CALLAWAY PLANT FIGURE 15.4-25 NUCLEAR POWER TRANSIENT, EOL, HZP, ROD EJECTION ACCIDENT Rev. 12 11/13
F E RA - URE F F R TURF AT R F
C'6(XX)
<.!)
L.a..J e scro w
~ 4000 a:::
w a..
w F-300) 0
- 5 2(XX)
~~- - -- - - ---~ .......... _, ___ _
~ ~ - - - ....
(..)
0
~ l (XX) d::::::>
u..
0 0 2 4 6 8 10 n E (SECO DS)
CALLAWAY PLANT FIGURE 15.4-26 HOT SPOT FUEL AND CLAD TEMPERATURES VERSUS TIME, EOL, HZP, ROD EJECTION ACCIDENT Rev. 12 11/13
10.0 t.O I
0 9.0 8.0
)(
= 7.0
--l
] 1:
0 6.0
...J 1.1..
liiC 5.0 I.I.J Clc: ij,Q
=
0 I.I.J 1-3.0 cr a:
c,:)
uJ 2.0 1-z 1.0 0
0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 ij,O TIME (SECONDS x lo-3)
Rev. OL-2 6/88 CALLAWAY PLANT FIGURE 15.4*27 REACTOR COOLANT SYSTEM INTEGRATED BREAK FLOW ROO. EJECTION ACCIDENT
r surizcr Filii g s tl R Cas w
a..z-0 0
Lf.LL..
_J
(.)
- z:
200 0 0 60 TIME (SEC)
CALLAWAY PLANT FIGURE 15.5-1 INADVERTENT OPERATION OF ECCS DURING POWER OPERATION Rev. 16 11/13
Pr urizc:r Filii '9 C DNBR Coso
--- ---- * 'I Se7point kls~.tn ed 2
1.\.J a::
(/)
~
0::.
a..~
es ~ 2~
N .....,..
I a:: I
\
I V) \
I
~
a:: I Q..
I
- - - Pr urizvr Filii 9 C v NBR 6
CALLAWAY PLANT FIGURE 15.5-2 INADVERTENT OPERATION OF ECCS DURING POWER OPERATION Rev. 16 11/13
PT uriz r Fillinq C
- - - - ONBR <Ale
',2- r - - - - - - - - - - - - - - - - - - - - - - - - - ,
a::
- z 0
400 5 CALLAWAY PLANT FIGURE 15.5-3 INADVERTENT OPERATION OF EGGS DURING POWER OPERATION Rev 16 11/13
2,000 w
~
- J
-l 0 1,800 a: I='
Ww 1-w 1,600
~u_
a:o wCJ N::J 1,400 a:- o
- J U)
U) w 1,200 a:
a..
1,000 0 300 600 900 1,200 1,500 TIME (Sec.)
2,600 w
a:
- J U)
U) 2,400 -
w a:
a.._ /
a:<C WUJ NO..
2,200 -
a:-
- J U)
U) w 2,000 f-a:
a..
I I 1,800 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.)
5/94 CAu.AWAY PLANT FIGURE 15.5-4 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MINIMUM REACTIVITY FEEDBACK, WITHOUT PRESSURIZER SPRAY
1.2
<{
1.0 1-a:
w -
z
$; ~ 0.8 1-0 0z CL a: u... 0.6
<{ 0 1-w
.....! z 0 0
~ f- 0.4 1-z 0
<{
a:
u... 0.2 -
I I I I 0
0 300 600 900 1,200 1,500 TIME (Sec.)
700 w u...
C)
<{
-OJ 650 1-a: CD w 0
<{ w a: a: ~
w f- 600 1-f- <{
<{
$; a: w w CL a: ~ 550 0 w 1-0 f-I I 500 0 300 600 900 1,200 1,500 TIME (Sec.) REV. OL-7 5/94 CALLAWAY PLANT FIGURE 15.5-5 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MINIMUM REACTIVITY FEEDBACK, WITHOUT PRESSURIZER SPRAY
2,000 w
~
_I 1,800 0
w w 1- w 0: 1 -
1,600
<( LL..
~ ()
0: m w ::> 1,400 N
0:
(f)
()
(f) 1,200 w
0:
a..
1,000 0 300 600 900 1,200. 1,500 TIME (Sec.)
2,600 w
0:
- > 2,400 1-(f)
(f) w 0:
a.. -
<(
0: (f) 2,200 w a.. 1-N 0:
(f)
(f) w 2,000 1-0:
a..
I I I I 1,800 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.) 5/94 CALLAWAY PLANT FIGURE 15.5-6 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MINIMUM REACTIVITY FEEDBACK, WITH PRESSURIZER SPRAY
1.2
_J
<(
1.0 1-a:z w-
~~ 0.8 1-oO a_Z a: 0LJ_ 0.6 r-
<(
w
_J z
() 0
- > I- 0.4 r-()
z <(
a:
LJ_
0.2 ~
I I I I 0
0 300 600 900 1,200 1,500 TIME (Sec.)
700 w
~
<(
LJ_
0> 650 -
a: CD w 0
<( w a: a:
w ::> 600 r-I- I-
<(
<(
~ w a:
w a_
a: ~
0 w 550 1-() I-I I 500 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.) 5/94 CALLAWAY PLANT FIGURE 15.5-7 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MINIMUM REACTIVITY FEEDBACK, WITH PRESSURIZER SPRAY
2,000 w
~
=>
0 1,800 a::
wl- -
1- w 1,600
<(w
$~
a::-
w en 1,400 N[S a:: -
- J g:s 1,200 w
a::
a..
1,000 0 300 600 900 1,200 1,500 TIME (Sec.)
2,600 w
a::
=>
U) 2,400 ~
v U) w a::
a..
a::
w U)
<(
2,200 ~
N a..
a::
=>
U)
U) w 2,000 -
a::
a..
I I I I 1,800 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.)
5/94 CALLAWAY PLANT FIGURE 15.5-8 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MAXIMUM REACTIVITY FEEDBACK, WITHOUT PRESSURIZER SPRAY
1.2
.....J 1.0 1-a:z w-
~~ 0.8 1-oO a..Z a:LL 0.6 1-c:t:O wz
.....Jo 0- 0.4 1-
- >I-zO a:
I..L 0.2 t-I I I I 0
0 300 600 900 1,200' 1,500 TIME (Sec.)
700 w
<.9
-I..L 650
<!: 0) i-a: (l) w 0
<!: w a: a:
w ::> 600 ,....
I- I-a:
~ w w a..
a: ~ 550 t-0 w
(_) I-I I I 500 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.) 5/94 CALLAWAY PLANT FIGURE 15.5-9 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MAXIMUM REACTIVITY FEEDBACK, WITHOUT PRESSURIZER SPRAY
2,000 w
~
- J
_J 1,800 0
a:-
wl-1-w 1,600
<(w
~IJ..
a:()
wc:o 1,400 N:J
-(.)
a:-
- J
(/)
(/) 1,200 w
a:
CL 1,000 0 300 600 900 1,200 1,500 TIME (Sec.)
2,600 w
a:
- J
(/) 2,400 ,. .
(/)
w a:
CL a:
w
<(
(/) 2,200 r-N a:
- J CL
(/)
(/)
w 2,000 -
a:
CL I I I I 1,800 0 300 600 900 1,200 1,500 REV. OL-7 TIME (Sec.)
5/94 CALLAWAY PLANT FIGURE 15.5-10 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MAXIMUM REACTIVITY FEEDBACK, WITH PRESSURIZER SPRAY
1.2
....I
<{
1.0 ~
a:Z UJ~ 0.8 ~
~0 Oz O..LL a:o 0.6 -
L5z
.....10 o-
- lt- 0.4 '-
z~
a:
lL 0.2 -
0 0 300 600 900 1,200. 1,500 TIME (Sec.)
700 w
CJ
<{
lL OJ 650 -
a: Q)
UJ 0
<{ w a:
a: :::l UJ 600 -
t- t- <{
<{
~ w a:
UJ 0..
a: ~ 550 r 0 UJ 0 t-I I I I 500 0 300 600 900 1,200 1,500 TIME (Sec.) REV. OL-7 5/94 CALLAWAY PLANT FIGURE15.5-11 CHEMICAL AND VOLUME CONTROL SYSTEM MALFUNCTION MAXIMUM REACTIVITY FEEDBACK, WITH PRESSURIZER SPRAY
1-2,..------- - - - -- - - - -- ---.
5~--------------------------------~
4
~J Q
zr---~
25 50 100 llME (Me)
CAJ..LAWAY PLANT IIIIICUiMPO'tBAII)DMit
'IIWIIIII'fl Rltl&l'laiMI&II' Cl a*a t#AWF M*PMUFEI'YVALVE Rl'f. t1 tltO
2400 2200
~
...~
2000 e5te
!::!~
1800 ii: 1800
~
Q.
1400 1200 0 2S 50 75 100 600
... \
...~
580 Q.
k
~~ 560 540
~
25 50 75 100 TIM£ [a)
CAJ..LAWAY PLANT P&SJ!H ERPN IIIEAII)n.IB.AVBWE
,_I'BMnR!TRIIIIBII'II'IIIN\DIMIIWI' CIPBINBCIFA I'IBOIIFRIAmYVALVE 1&'.11 11te
P1CS$1..' i ZC I
- - - - R u p t u r ed S1e arr Cene r olor
- -* l n to c l S:eom Generotor ( oop 2)
~0 ~--------------------------------------~
-:;;;: 2000 l/)
a..
\
o ~~--~~------U4--------~~~--4-~L----Y 0 1000 2000 3000 <<JOO 5000 Time (s)
Nolo:
,_.._~_m ___ .,ll*f. . . lo IIIMM Dnii'IIIWt*llhll IDfldl& II .,._AIO&IDI"'.,_
- - ... - .. bo ..- .. "'-'tho RC8
"""' ....- . l * ................ ...,.. .. lho
-~- . . .lllo<llhoiiGIRIIIIIho ........
llffllda d u. **...w.t .........
_,.,_..._...,o_porlonudlhol
..,.....,..,. -lhoiU!Ibor<l ..-ASOa
.. -ror~~~o.-. -.r.... -10~wo.
11* . . . . ih. b.-r ..... E**M*16nlbl tf.w ~ CAJ..LAWAY PLANT
. -... l!*tflp& ,.....,. . lhol .... a.-
AIIO .,. ' '4i;i - porlomod 10 .,.....~ lllllologlool
-<llh fh4w o p o b* * *- . . - *
- _.......,wwaUJ.Id~U.ad.,. ~ PN II" MAIDIIIBIII GBBIATCR(NP1111D AIDINrACT tai!I'~TGIIS) F'fBIIA!TIWIIII!NI'8 RIRtnalll CI&.EMTCRTIIENPI'IIEEIIENI' II&', 11 fll1
Ru p t u r e d L oo p Hot L eq
- - - - R tJp t ured Lo o p Co I d Le g MO ~-----------------------------------------.
<..:> 500 w ........ -- .....
Q w
--"".... ~
\
\
0::: 4()0 I
- > I 0:::
1 111 w Jl l , --- - -~ -
~ 300 If 1/ J"" ~
w ' t I I I- T *I 200 IOO ~~-L~-+-----L~4-~-----4--~--L-4,----~-LY 0 1000 2000 lOOO 4000 5000 Time (s)
Hal&
llwthoml~-madol..-. adlniHII~II
~ ~
- -_ ..........- . . . . . 1110 RC8 liPid e~a-.n lNIIIIIIIilllniNIVIIW* lfllb _ , _
.. ~-~--. . ., ~8GIII.IIId~
....itllllflecta- thl*tiCWid~
~r+._..Mw
- -for~
.. 11\11111 oo -
I n ollqorll\lllll
- ._...,-.:wm_.ua
- I-..,
'""" 1*
c Ill II-
., ,,,., __llll'm_tta..,., .......,..
..,.,.,~ llw~- .... -~-
~-----~~~~~ laCTORCOCILAHT &'/'lrTEM TEM~TIIE IIIPI'IIIm L~ TIWiiii!NI' I'DRSI'I!!NI c "'lATClRn&!lll'niEBIIM'
ln t o ct Loop - ot L eq { ooo 2)
- - - - ln toct Loop Cold Leg (loop 2) 700 .------------------------------------------.
6001-- - ~
'C'
<..!)
w 500 -- ----,
r---- -- --
0 /
~
w -,
5 400 ~-
~
0::
- t'
- 300 w
1-200 100 -
0 1000 2000 3000
- 4000 5000 Time (s)
Note:
The thennal-hydraulic model presented in this figure is based on an analysis that credits all three ASOs on the intact steam genel'3tors to be available to support the RCS rapid cooldown. This is conservative with respect to the thennal-hydraulic analysis of the SGTR and the potential effects of the associated transient .
.Additional calculations have been perfonned that conservatively reduce the number of credited ASOs available for the rapid cooldown from three to two. This results in a longer rapid cooldown dur.Jtion than is shown on this figure. The analyses that use the reduced ASO CAJ..LAWAY PLANT availability were perfonned to quantify radiological RGIIIE11.HC consequences ofthe prolonged cooldown. Conservative flowl'3tes and dumions were used in the radiological consequence analyses.
laCTORCGCILAHI' 8'fln'EII TEIIPBIATIIE (INTACT LCICI~ lRo\NijiM RIIUITENI
-1111\TClRnB!IIPnR!II!VIIII'
- ... e/lt
lnloc l Slaom Ge n ero l o r s (tol a l}
~00 .--------------------------------------------.
l.U
':;;;: 2000 0::
1000 0 ,_.__,
0
~ *---"---;c-----------~-L 1000 2000
~*--L-r----
~ ~~- ~+-
3000
' ~' - '
L ------ct~'
~00
- L
' ~'---------i 5000 Time (s)
Note:
The thennal-hydraulic model presented in this figure is based on an analysis that credits all three ASOs on the intact steam genemors to be available to support the RCS rapid cooldown. This is conservative with respect to the thennal*hydraulic analysis of the SGTR and the potential effects of the associated transient .
.Additional calculations have been perfonned that conservatively reduce the number of credited ASOs available for the rapid cooldown from three to two. This results in a longer rapid cooldown dur.Jtion than is shown CAJ..LAWAY PLANT on this figure. The analyses that use the reduced ASO availability were perfonned to quantify radiological ROUE1U.
consequences ofthe prolonged cooldown. Conservative flowmes and dur.Jtions were used in the radiological I1BIII R.CIWM1E(IITACT GBBIA'IICIIII) consequence analyses. TIWIIIIM I'ORSI'MII GII!!N!W.TCIR TIIEIIPniEEIIIM llllf.11 fl'11
Run l ure d SLe orn Gene ra tor 1200 . - - - - - - - - - - - - - - - - - - - - - ----,
1000
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0 1000 2000 3000 4000 5000 Time (s)
Note:
The thennal-hydraulic model presented in this figure is based on an analysis that credits all three ASOs on the intact steam gener.Jtors to be available to suppon the RCS rapid cooldown. This is conservative with respect to the thennal*hydraulic analysis of the SGTR and the potential effects of the associated transient.
Additional calculations have been perfonned that conservatively reduce the number of credited ASOs available for the rapid cooldown from three to two. This resuhs in a longer rapid cooldown dur.Jtion than is shown CAJ..LAWAY PLANT on this figure. The analyses that use the reduced ASO availability were perfonned to quantify radiological consequences of the prolonged cooldown. Conservative flowr.Jtes and dur.Jtions were used in the radiological 1119111 R.CWM1E(111'1111DGBIM'RII) consequence analyses. TIWIIIIM I'Oiltn'MII GII!!N!W.TCIR TIIEIIPniEEIIIM llllf. 11 fl'lt
l{uo tu r e d St e cw Ge ne r o lor
- - - - l nto ct St e oll' Generat o r ( oop 2) 700 ~---------------------------------------,
_ooo
<-=>
w 1--- -'J"( - - - - - -
0 500 400 +
0 1000 2000 3()00 4000 5000 Time (s)
Note:
The thennal-hydraulic model presented in this figure is based on an analysis that credits all three ASOs on the intact steam genemors to be available to support the RCS rapid cooldown. This is conservative with respect to the thennal*hydraulic analysis of the SGTR and the potential effects of the associated transient .
.Additional calculations have been perfonned that conservatively reduce the number of credited ASOs available for the rapid cooldown from three to two. This results in a longer rapid cooldown dur.Jtion than is shown CAJ..LAWAY PLANT on this figure. The analyses that use the reduced ASO availability were perfonned to quantify radiological consequences ofthe prolonged cooldown. Conservative flowmes and dumions were used in the radiological II1EIIIII GBBUITCRTEIIPIRII111E(III"'UUD consequence analyses. AIDINI'ACT CBIIIATall) 'IIWIBG'IINR Sl'llUI CIIHN.'TORTIIEIIPI'IIEE!IIENI' IEif.11 fll1
Ru :>tured Ste c w G~ r1~rolo r 500 , --------------------------------------------,
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(/)
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< 100 2000 .3()00 4000 5000 Time (s)
Note:
The thennal-hydraulic model presented in this figure is based on an analysis that credits all three ASOs on the intact steam genemors to be available to support the RCS rapid cooldown. This is conservative with respect to the thennal-hydraulic analysis of the SGTR and the potential effects of the associated transient .
.Additional calculations have been perfonned that conservatively reduce the number of credited ASOs available for the rapid cooldown from three to two. This results in a longer rapid cooldown duration than is shown on this figure. The analyses that use the reduced ASO availability were perfonned to quantify radiological consequences ofthe prolonged cooldown. Conservative flowrates and durations were used in the radiological $lUll .. -TCRATMCtFI!EIIC m consequence analyses. YALYER.CIW MTE(IIPTIIU) E.W.TOft TIW81M RJIUII'INI CiiNRo\TGR TIIEIIIPTlNI!IIIM
lnt c c l S t e om Ct!ne1otors ( l ot c l) 1200~---------------------------------------------,
600 400 200 0 1000 2000 3000 4000 5000 Time (s)
Nota:
11-. -~- madii.,...Ziilal 11IHI fi!Jn lo
....,.-~~.t_
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CALLAWAY - SP Figure 15.6-48 Deleted REV. OL-~15 5/06
CALLAWAY - SP Figure 15.6-5 Deleted REV. OL-~15 5/06
PCT E_EVAT ON
- 7 . 0 rl
BURST ELE VAT I DN - 1. 2 ,; FT 1600 1400 r ~.... , k'c' ',.
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CAJ..LAWAY PLANT FIGIIEtu*
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CALLAWAY - SP Figure 15.6-7 Deleted REV. OL-~15 5/06
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CALLAWAY - SP Figure 15.6-1 0 Deleted REV. OL-~15 5/06
PCT ELEV AT ON - 7 .0 FT
- - - - BURST ElEVAT I ON = ].25FT 10 I
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r" .. _ ... - - - ......- - - - - - - --
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B.EYATICI.
11fT"' PC1' N111111111$i' Mila
PCT E l EV ~T ON ~ 7 . 25 FT
--- - BURST H£'/AT I ON = fi. .2 S FT 10 ~--------------------------------------------,
r - - - - , - - - - - - - - - - -- -
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B.EYATICI.
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PCT E ~ Ev AT ON ~ 6.25 FT
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RG&IE1t..,OD CI..ADDINaiiiiFttEIElT TIIANIRR COB'f!C:IENI' AT PC:T AMJ IIRSr
PCT E ~EV AT ON ~ 7-25 FT
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PCT E_EV AT ON ~ 9.0 rT
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CI...IDDINB IIIFJtCEIElT TRANIIFER COB'FICIENr AT PC:T A1G EIR5r
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CALLAWAY - SP Figure 15.6-11 Deleted REV. OL-~15 5/06
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- 7.0 FT
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0000 ~--------------------------------------,
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CAJ..LAWAY PLANT FIOUE1u-te Z INCH CCI DLBJ &lUX IIICI Fill ILL VI. Till!
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CAJ..LAWAY PLANT FIGUE1LH' Z liCit CCI Dl.m &UX CGRI!MIXTIII!LI!III!L V& TIM!
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CAJ..LAWAY PLANT FIGUE16.M2 31NCH COLD LEIIIIIIRBU(
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CAJ..LAWAY PLANT FIGUE16..._
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CAJ..LAWAY PLANT FIGUE16..._
41NCH COLD LEIIIIIIRBU(
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CAJ..LAWAY PLANT FIGUE16.MI 41NCH COLD LEIIIIIIRBU(
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liNCH COLD LEIIIIIIRBU(
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CAJ..LAWAY PLANT FIGUE16.-
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CALLAWAY - SP Figure 15.6-34 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-35 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-36 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-37 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-38 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-39 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-40 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-41 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-42 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-43 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-44 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-45 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-46 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-47 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-48 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-49 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-50 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-51 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-52 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-53 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-54 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-55 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-56 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-57 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-58 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-59 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-60 Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61a Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61b Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61c Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61d Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61e Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61f Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61g Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61h Deletedl Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61i Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61j Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61k Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61l Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61m Deleted Rev. OL-15 5/06
CALLAWAY - SP Figure 15.6-61n Deleted Rev. OL-15 5/06