ML18088A927
| ML18088A927 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  (DPR-067) |
| Issue date: | 01/12/1976 |
| From: | Florida Power & Light Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18088A927 (189) | |
Text
egg/g(p DockGt Lt8 St. Lucie Unit 1
ECCS Performance Results and Isolated Safety Injection Tank Study g-q~@~.yy~!~'~
I.
Introduction and Summar On January 4, 1974, the Atomic Energy Commission issued Hew Acceptance Criteria for Emergency Core Cooling Systems for Light-Mater-Cooled Reactors~ ).
The analysis presented herein demonstrates that the St. Lucie Unit 1
ECCS design satisfies these new criteria.
The analysis has been performed using the Combustion Engineering (C-E) large break evaluation model~ '.
The large break evaluation model results are presented in Secti.on II and cover primary system ruptures larger than 0.5 ft~.
As demonstrated in CEHPD-137~ ), breaks smaller than 0.5 fthm-are not limiting.
Therefore, a small break spectrum analysis is not presented..
C-E has recognized the similarities which exist for the NSSS of the 2560 ANt
'eactor Plants (Calvert Cliffs 1, Millstone Point 2, St. Lucie 1, and Calvert Cliffs II) and has performed a generic blowdown calculation.to be used for a11
f
of these ECCS performance evaluation analyses.
The features of each of these
. reactors have been compared and the appropriate parameters for the calculation were selected on the basis of conservatism (e.g.,stored energy in the fuel has been maximized).
- However, due to the sensitivity of the thermal behavior of the hottest rod to the unique features of the fuel, containment building, and safeguard
- systems, explici,t refill reflood, and hot rod thermal transient calculations have been performed for St. Lucie l.
Hot rod temperature calculations were performed for the entire spectrum of break sizes at a peak linear heat generation rate (PLHGR) of 15.8 kw/ft.
The worst break (that which limits the PLHGR) was identified as.the 0.8 DEG/PD*.
The results of this study supersede those reported in Reference 5 and show that the plant meets the NRC Acceptance Criteria published in the Federal Register on January 4, 1974.
Conformance is summarized as follows:
Criterion (1)
Peak Clad Tem erature.
"The calculated maximum fuel element cladding temperature shall not exceed 2200 F."
The spectrum analysis yielded a peak clad temperature of 2192 F for the 0.8 DEG/PD break.
Criterion (2}
Maximum Claddin Oxidation.
"The calculated total oxidation of the cladding shall nowhere exceed 175 of the total cladding thickness before oxidation."
The spectrum analysis yielded a local'eak clad oxidation
- 0.8 DEG/PD
= 0.8 Double-Ended Guillotine rupture of the Pump Discharge leg.
percentage of 10.42Ã for the 0.8 DEG/PD break.
Criterion (3)
Maximum H dro en Generation.
"The calculated total amount of hydrogen generated from the chemical reaction of the cladding with water or steam shall not exceed 15 of the hypothetical amount that would.be generated if all of the metal in the clad-ding cylinders surrounding the fuel, excluding the cladding surrounding the plenum volume, were to react."
The 0.8 OEG/PO break produced the highest core-wide oxidation which was
< 7875.
Criterion (4}
Copiable Geometr "Calculated changes in core geometry shall be such that the core remains amenable to cooling."
The clad swelling and rupture model which is part of the C-E Evaluation Model accounts for the effects of changes in core geometry if such changes are predicted to occur.
With these core geometry
- changes, core cooling was enough to lower temper-atures.
Ho further rupture can occur since the calculations were carried to the point at which the temperatures were de-creasing.
- Thus, a eoolable geometry has been maintained.
0 Criterion (5)
Long Term Coolin "After any calculated successful initial operation of the ECCS, the calculated core temperature shall be maintained at an acceptably low value and decay heat shall be removed for the extended period of time required by the long-lived radioactivity remaining in the core."
The spectrum analysis presented in this report shows that the rapid insertion of borated water from the ECCS will suitably limit the peak clad temperature and cool the core within a short period of time.
Subsequently, the safety injection pumps would supply cooling water from the refueling water tank to remove decay heat resulting from the long-lived radio-activity remaining in the core.
When the refueling water tank is nearly empty, the safety injection pumps would then be lined up to recirculate water from the containment sump.
In this manner, the core would be cooled for an indefinite period of time.
In addition to the spectrum analysis sumnarized above and discussed in Section II, a reanalysis was performed in which one Safety Injection Tank was isolated from the primary system.
The method of analysis and the results are presented in Section III.
Worst break results, for the cases with and without an isolated SIT,
, are compared below at a PLHGR of 15.8 kw/ft:
0.8 DEG/PO Results Peak Clad Temperature
( F)
Local Clad Oxidation (~)
Core-Wide Clad Oxidation
(~~)
One SIT Isolated 2T<R
- 10. 97
<.880 No SIT Isolated 2T99
- 10. 42
<.787
It is conc1uded'that the LOCA criteria are met for the case in which one SIT is isolated.
Since all calculations assumed full power operation, there is no need to reduce power when one SIT is isolated.
The PLHGR limit for both types of operation
{SIT isolated and not isolated) is 15.8 kw/ft.
II.
La e Break Anal sis A.
Method of Calculation The calculations reported in this section were performed using Combustion -Engineering's large break evaluation model which is des-cribed in Reference Z.
In addition, the following modifications to the model, as documented in Reference 3, have been included in these calculations:
1.
The containment wall noding technique has been revised in order to provide a converged wall temperature solution.
2.
Based on a recent review of steam-water mixing data, the resis-tance across the ECCS injection section during the period after the safety injection tanks have emptied has been revised.
In the C-E model, the CEFLASH-4A computer program is used to determine (6) the primary system flow parameters during the blowdown phase, and the COMPERC-II computer program is used to describe the system behavior (7) during the refill and reflood phases.
The core flow and thermodynamic parameters from these two codes are used as input to the STRIKIN-II~ )
program which is used to calculate the hot rod. clad temperature transient.
The peak clad temperature and peak local clad oxidation percentage are
t 4
therefore obtained from the STRIKIN-II calculation.
The core-wide clad oxidation percentage is obtained from the results of both STRIKIN-II and the COMZIRC'
'omputer programs.
P;Su 1.
1)
B.
Emer enc Core Coolin S stem Assum tions The Emergency Core Cooling System consists of two high pressure pumps,,
two low pressure pumps and four safety injection tanks.
Automatic op-eration of the pumps is actuated by a low-low pressurizer pressure signal or a high containment pressure signal.
Flow is initiated from the safety injection tanks when the cold leg pressure drops below 215 psia plus the elevation head.
Parameters pertinent to the calculation of the LOCA are presented in Table II-1.
In performing the LOCA calculations, conservative assumptions are made concerning the availability of safety injection flow. It is assumed that off-site power is lost and all safety injection pumps must await diesel startup before they can begin to deliver flow. (It is assumed, however, that off-site power is available for the containment spray pumps).
Also, it is assumed that all safety injection flow delivered to the broken cold leg is lost.
An analysis of the possible single failures that can occur within the ECCS has shown that the worst single failure for large breaks is the failure of one of the low pressure pumps to start
~.
Thus, only one low pressure pump is used in the current LOCA anaIysis for St. Lucie Unit l.
The above assumptions lead to the conclusion that the following safety
injection flows are available:
75% of the flow from two high pressure pumps 75% of the flow from one low pressure pummp Flow from three safety injection tanks In the analysis reported in this section, no credit is taken for pump flow until the tanks are empty.
C.
- Core, S stem and Containment Parameters The ssgnificant core and system parameters us d 'h 1
e sn e
arge break cal-culations are presented in Table II-1 Th k
e pea linear heat rate was assumed to occur in the top of the core, the conservative location as identified in Section IV.A.4 of Reference 2.
A conser t' erva ive eginning-of-life moderator temperature coefficient ( +0 2 10 x
ap/ F'as used for all cases.
Hot fuel rod conditions, as'etermined by the FATES(
~ computer
- program, were evaluated at a rod-average burnup of 3389 HTD/HTU; a parameter study was performed which indicated that clad temperature and oxidation were maximized at this exposure.
Containment parameters as presented bl II-2 Con in a
e are chosen to minimize containment pressure such that a conservative determination of core re-flood rate is made..
is made..
Pressure suppression equipment startup times are selected at their minimum values corresponding to off-site power being avail able.
In general, all possible break locations are considered in a LOCA analysis.
- However, as demonstrated in other Appendix K LOCA calcu-lations (References 2 and 1O, for. example}, hot leg ruptures and cold leg ruptures.
on the suction side of the pump yield clad temperatures substantially lower than those observed for cold leg ruptures on the discharge side of the pump.
Pump discharge leg ruptures are limiting due to the minimization of blowdown core flow and reflood rate for this break location.
Thus, only these breaks need to be considered in order to identify that rupture which results in the highest clad temperature or largest amount of clad oxidation.
Since core flow is a function of the break size, calculations have been'performed for both guillotine and slot breaks over a range of break sizes from 0.5 ft2 to twice the flow area of the cold leg.
E.
Results Table II-3 presents a listing of the large break sizes analyzed in this study along with the figure numbers presenting the pertinent transient data for each break.
As noted in Table II-3, the results for each of the breaks analyzed are displayed graphically in Figures II.1 through II.7.
For each break, the nine variables listed in Table II-4 are plotted as a function of time.
For the break having the highest clad temperature and clad oxidation (0.8 DEG/PD), the, additional quantities listed in Table II-5 are also presented.
The water level in the downcomer (Figure II.5-M) is presented t
\\
only for one break because all breaks have the same transient behavior.
Times of interest for the various breaks are shown in Table II-6, while Table II-7 summarizes peak clad temperatures and clad oxida-tion percentages.
As described in Reference 2, the method used to calculate core-wide clad oxidation is conveniently simple, but is very conservative.
The following major conservatisms can be enumerated:
(1)
During blowdown, all rods experience the same amount of oxidation as the hot rod.
(2)
During the entire transient, all rods experience the same rupture region oxidation as the hot rod.
(3)
In initializing the multi-region COMZIRC calculation, the CEFLASH-At~It tl tddf lt 1
t df 11 d
having above average power.
(4')
During refill/reflood, the flattest ossible power distribution is used, even though inconsistent with the PLHGR.
In addition to the above four conservative features of the method, there is also a major conservatism in the particular manner in which the core-wide oxidation percentages were determined for St. Lucie Unit l.
The hot assembly region power in CEFLASH-4A was based on a peak LHGR of 17.0 kw/ft, thus allowing flexibilityduring the determination of the allowable peak LHGR based on the STRIKIN-II prediction of the hot rod thermal behavior.
However, since the STRIKIN-II calculations yielded an allowable PLHGR:.of only 15.8 kw/ft, this procedure leads to a very conservative core-wide clad oxidation calculation since the CEFLASH-4A hot assembly fuel and clad temperatures are used to initialize COMZIRC at the beginning of refilllreflood.
An eval-uation of this conservatism for another plant showed that the core-wide clad oxidation was reduced from 0.9335 to 0.776~~ when the CEFLASH-4A hot assembly reference PLHGR was reduced from 17.0 to 15,2 kw/ft.
Thus, the actual values for core-wide clad oxidation would be appre-ciably less than those reported in Table II-7.
Figure 1I-8 shows peak clad temperature plotted versus break size and type, showing the worst break to be the 0.8 DES/PD rupture.
Mass and energy release to the containment during blowdown is presented in Table II-8.
Also shown in this table is the steam, expulsion data during reflood.
The ECC water spillage and containment spray flow rates are presented graphically in Figure II.9.
\\
III.
Isolated Safet In'ection Tank Anal sis The calculations reported in this section were performed using the CE evaluation model as described in Section II-A. Additionally, a por tion of the study required a modification to the noding scheme employed in the CEFLASH-4A blowdown model.
The change was necessary in order to explicitly model a safety injection tank in each of the intact cold legs, thus allowing for the study of possible asymmetric effects.
Figure IV.A.l-l of Reference 2
shows the CEFLASH-4A nodal map used for the evaluation model.
In this model, the intact loop cold legs are lumped together; in the new model these cold legs have been separated and modeled individually.
In order to determine if asymmetric effects exist, the standard and modified CEFLASH-4A nodal models were used to analyze the 1.0 DEG/PD break.
Cases were run in which a Safety Injection Tank was successively isolated from each intact cold leg until all three SIT locations had been examined.
In all cases, the SIT attached to the broken cold leg is assumed to spill directly to the containment.
Results indicated there were no asymnetric effects during blowdown due to isolating the various safety injection tanks.
Based on the above findings, the standard CEFLASH-4A nodal model was used to analyze the worst break (0.8 DEG/PD as defined in Section II).
Refill/reflood calcualtions were performed using the COMPERC-II computer code.
COMPERC-II cannot model safety injection asymmetry, but can treat such asymmetry conservatively; i.e., the totaI SIT flow rate entering the vessel was reduced by one third, but the injection section pressure. drop in the cold leg having the isolated SIT was maintained at 0.4 psi, the value used when SIT flow is
~
~
present.
A more detailed calculation in which the asymmetry was modeled would show a larger steam flow rate through the cold leg having the isolated SIT;
the higher steam flow rate would lead to higher reflood rates and lower clad temperatures.
As done in the spectrum analysis, core flow and thermodynamic parameters from the CEFLASH-4A and COMPERC-II analyses were used as input to the STRIKIN-II code for the determination of the hot rod clad temperature transient as well as the peak local clad oxidation percentage.
The core-wide clad oxidation percentage was obtained from the results. of both STRIKIN-II and the COMZIRC computer programs.
Table III-1 presents a list of variables plotted as a function of time for the isolated Safety Injection Tank study.
Table III-2 compares parameters of interest for the worst break (0.8 OEG/PD) analyzed with and without an isolated SIT at a PLHGR of 15.8 kw/ft.
The results of this study indicate that the LOCA criteria are not exceeded at a
PLHGR of 15.8 kw/ft when one SIT is isolated.
The study also shows that, although the temperatures and oxidation percentages increased somewhat during reflood due to the longer refill period, the limiting clad temperature occurs during blowdown, as it did for the reference case described in Section II.
Therefore, since the peak clad temperature is limiting and occurs during blowdown, and since blowdown asymmetry effects are insignificant, the worst break will be the same for the isolated SIT configuration as it was for the reference configuration in which all tanks were operative.
IV.
Com uter Code Version Identification The following versioris of the Combustion Engineering ECCS Evaluation Model computer codes were used for this'nalysis:
CEFLASH-4A:
Version No. 74329 STRIKIN-II: Version No. 75105*
COMPERC-II:
Version No. 75097 COMZIRC Version No. 75055
" The STRIKIN-II Version 75066 has been modified to prevent occurrence of a negative square root (due to computer round-off error) when in nucleate boiling.
Versions 75066 and 75105 predict the same results upon successful computation.
V.. Refer ences 1.
Acceptance Criteria for Emergency Core Cooling Systems for Light-
~
~
Mater-Cooled Nuclear Power Reactors, Federal
- Register, Vol. 39, No.
3 - Friday, January 4, 1974.
2.
CENP0-132, "Calculative Methods for the C-E Large Break LOCA Evaluation Model," August, 1974 (Proprietary}.
CENP0-132, Supplement 1, "Updated Calculative Methods for the C-E Large Break LOCA Evaluation Model," December 1974 (Proprietary}.
3.
CENP0-132, Supplement
- 2. "Calculational Methods for the C-E Large Break LOCA Evaluation Model," July 1975.
4.
CENP0-137, "Calculation Methods for the C-E Small Break LOCA Evyluation Model," Combustion Engineering Proprietary Report, August, 1974 (Proprietary).
5.
6.
8.
St. Lucie Unit 1
FSAR, Large Break Analysis, Section 6.3.3.6.1 as amended by Revision 845, May 27, 1975.
CENP0-133, "CEFLASH-4A, A FORTRAN IV Digital Computer Program for Reactor Blowdown Analysis," April 1974 (Proprietary).
CENP0-133, Supplement 2,
"CEFLASH-4A, A FORTRAN IV Digital Computer Program for Reactor Blowdown Analysis (Modification}," December, 1974 (Proprietary).
CENP0-134, "COMPERC-EI, A Program for Emergency Refill-Reflood of the Core," April 1974 (Proprietary}.
CENPD-134, Supplement 1, "COMPERC-II, A Program for Emergency Refill-Reflood of the Core (Modification)," December 1974 (Proprietary}.
CENP0-135, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program," April 1974 (Proprietary).
CENP0-135, Supplement 2, "STRIKIN-II, A Cylindrical Geometry Fuel Rod Heat Transfer Program (Modification)," December 1974 (Proprietary}.
9.
CENP0-139, "C-E Fuel Evaluation Model," July 1974 (Proprietary}.
10.
Letter 0.
C. Switzer (NNECO) to O.
D. Parr (NRC) re: Millstone Nuclear Power Station, Unit 2 ECCS Re-evaluation, July 10, 1975, Docket No. 50-336.
Table II-1 General System Parameters uantit Reactor Power Level (102K of Nominal)
Average Linear Heat Rate (102% of Nominal)
Peak Linear Heat Rate Gap Conductance at Peak Linear Heat Rate*
Fuel Centerline Temperature at Peak Linear Heat Rate*
Fuel Average Temperature at Peak Linear Heat Rate Hot Rod Gas Pressure*
Moderator Temperature Coefficient at Initial Density System Flow Rate (Total)
Core Flow Rate Initial System Pressure Core Inlet Temperature e Outlet Temperature tive Core Height Fuel Rod OD Number of Cold 'Legs Number of Hot Legs Cold Leg Diameter Hot Leg Diameter Safety Injection Tank Pressure Safety Injection Tank Gas/Water Volume Va1ue 2611 6.2126 15.8 820.2 4055.1 2656.5 1147.6
+0.2 x 10 139.44 x 10 134.6 x 10 2250
'48 598 11.39
.44 2
30 42 215 930/1090 kw/ft kw/ft BTU/hr-ft - F OF oF psia hp/
F lbs/hr 1 bs/hr psia F
0F ft in.
ln in ~
psia "These quantities correspond to the burnup (3389 MWD/MTU, hot rod average) yielding the highest peak clad temperature.
Table II-2 Containment Physical Parameters Net Free Volume Containment Initial Condi tions:
Humidity Containment Temperature Enclosure Building Temperature Initial Pressure Initial Time for:
Spray Flow Fans (4)
Containment Spray Mater:
Temperature Flow Rate (Total, both pumps) an Cooling Capacity (per fan) 2.5111 x 10 Ft 100%
60 F
38 F
14.6 psia 25 seconds 0.0 seconds 55 F
3375 gpm Va or Tem erature F
60 120 180 220 264 Ca acit BTU/Sec 0.0 3472.0 7388.8 11611.1 20833.3 Heat Transfer Coefficient a.
Containment structure t'o enclosure building atmosphere heat transfer coefficient - 13.0 BTU/hr-ft - F.
b.
Sump to base slab - 10 BTU/hr-ft - F.
c.
Containment atmosphere to sump - 500 BTU/hr-ft - F.
I ~
e
Table II-2 Continued St. Lucie 1 Revised Passive Heat Sink Information llal 1 1.
Containment Shell 2.
Floor Slab 3.
Misc. Concrete 4.
Galvanized Steel 5.
Carbon Steel
-6.
Stainless Steel 7.
Misc. Steel 8.
Misc. Steel 9.
Misc. Steel 10.
Imbedded Steel Material Steel Concrete Concrete Zinc Steel Steel Steel Steel Steel Steel Steel Concrete Thickness Ft
.1171 20.0 1.5 0.0005833 0.01417 0.03125 0.0375 0.0625 0.02083 0.17708 0.0708 7.00 Area Ft2 86700 12682 87751 130000 25000 22300 40000 41700 7000 18000 k
BTU Hr-ft-F 25.9 1.0 1.0
- 64. 0 25.9 30.0 9.8
- 25. 9 25.9 25.9 25.9 1.0 pc Ft -oF 53.57 34.2 34.2
- 40. 6
- 53. 57 53.8 54.0 53.57 53.57 53.57 53.57 34.2 Exposure Side 1
Cont.
Vapor Cont.
Vapor Cont.
Vapor Cont.
Vapor Cont.
Vapor Cont.
Vapor Cont.
Vapor Cont. Vapor Cont. Vapor Cont. Vapor Exposure Side 2
Annulus Insulated Insulated Insulated Insulated Insulated Insulated Insulated Insulated Insulated
I
~
Table II-3 Large Break Spectrum Break Size, T
e and Location 1.0 x Double-Ended Slot Break in Pump Discharge Leg 0.8 x Double-Ended Slot Break in Pump Discharge Leg 0.6 x Double-Ended Slot Break in Pump Discharge Leg 0.5 Ft Slot Break in Pump Discharge Leg 1.0 x Double-Ended Guillotine Break in Pump Discharge Leg 0.8 x Double-Ended Guillotine Break in Pump Discharge Leg
~
~
.6 x Double-Ended Guillotine reak in Pump Discharge Leg Abbreviation
- 1. 0 x DES/PD 0.8 x OES/PD 0.6 x DES/PD 0.5 A S/PD 1.0 x OEG/PD 0.8 x DEG/PD 0.6 x DEG/PD
I I
0
Table II-4 Variables Plotted as a Function of Time for Each Large Break in the Spectrum Variable Fi gure Oesi nation Core Power Pressure in Center Hot Assembly Node Leak Flow Hot Assembly Flow (below hot spot)
Hot Assembly Flow (above hot spot)
Hot Assembly guality Containment Pressure 0.1 0.2 Mass Added to Core Ouring Reflood H
Peak Clad Temperature
Table II-5 Additional Variables Plotted as a Function of Time for the Worst Large Break Variables Figure Desi nation Mid Annulus Flow gualities Above and Below the Core Core Pressure Drop Safety Injection Flow into Intact Discharge Legs Water Level in Downcomer During Reflood Gap Conductance Local Clad Oxidation Clad Temperature, Centerline Fuel Temperature, Average Fuel Temperature and Coolant Temperature for Hottest Node ot Spot Heat Transfer Coefficient Hot Spot Heat Transfer Coefficient During Reflood Containment Temperature Sump Temperature Hot Pin Pressure Core Bulk Channel Flow Rate U
l a
~
~
Table II-6 Times of Interest for Each Large Break (PLHGR = 15.8 kw/ft)
(Seconds)
Break 1.0 x DES/PD 0.8 x DES/PD 0.6 x OES/PO 0.5 ft S/PO 1.0 x DEG/PD 0.8 x OEG/PD 0.6 x OEG/PD Hot Rod
~Ru ture 10.0 9.9 10.4 288. 9 10.8 29.3 SI Tanks on 17.3 17.6 19.3 173.0
- 17. 4 17.9 20.1 Start of Reflood 37.6 38.0 39.6 193.2
- 37. 7 38.3 40.6 SI Tanks
~Em t 70.4 70.8 72.6 225.4 70.5 71.1 73.4
Table II-7 Peak Clad Temperatures and Oxidation Percentages for the Break Spectrum at a
PLHGR of 15.8 kw/ft Break Peak Clad Tem erature oF Clad Oxidation 4
Local Core-Mide 1.0 DES/PD 0.8 DES/PD
- 0. 6 DES/PD 0.5 Ft S/PD 1.0 DEG/PD 0.8 DEG/PD 0.6 DEG/PD 2137 2149 2099 1777 2150 2192 2056 10.07 9.98 9.18 2.85
- 10. 29
- 10. 42
- 7. 71
<. 735
<.726
<.659
<.141
<.762
<.787
<.524
e
~
s
Table II.8 St. Lucie Unit I Blowdown Mass and Energy Release Data 0.8 x DEG//PD DITE OF OF TIME MASS FLON LBM SEC BTU SEC bfASS FLOW ENERGY RELEASE o.O
.o5
.(p
.l5
. Zo
.Z.5
.35
.4o
.So l.o l.S ZZ 24 5.0 5.2.
4.o 7.4 9L lO.O
$.0 7.'9 Ghv5s 7.
tp&27
(..8849 L.F89 t'..M7 g.~o
(..5559
(.A.ue l..oi47 5'.Wzl 478%
4iG3
'J 79(5 33374 3.oi4z 2.
Z.M5 255 2.184 (
/.9793 x tO
~ so<
a,o W.x795 Q;7lc9 5.79 5 LLQ 5.7695 5.4H7 3.%7 9.%k8 0944 3M]
53837 3.275l 2.842,3 z.l.l4 2.5{88 2.%5 2.? lip z.iiz4 f.9c50
!.@85 l.9iZ
(.485 I.I929 x lO
) IP" O.O 5.08ce 4.7872.
l.ozark l 3737
(.7i18 2 39K
~
5.37Z3 I'..%55 9.29l1 l l192.
l;Qo l.4a't4 I 7919 l 9709 2 l3'33 Z.ST75 2.~$
2.9(57 3.(4e 9.3993 9.55il.
3.736 3.9ceL x lo~
~ le~
.lO+
x la~
xylo~
x /O~
xi'
/0~
x/0 x/O~
O. Q f {o5&2.
3455 9.~24 7 6'942 9.2.'f88
(.Z9o 7 l.%co Z.i5{.~
z.s988
.w9o S.OZ2Z 4.%2Z 7.~g l9.7&
9.7239 l.oVW
/4628
(.~o,
/i@
( 7%Z 18/Ib.
/97 g.o870 2.~870
Table II.8 Cont'd GRAL OF OF SEC I(.o
)Z.o
- 13. 0
)4o
)5.o tt.a t T.o
)P.o
)3.o Zo 0 Zl 0 Z)7 l.883 I 3fcl l S.z'3N 4.u7
$.9%)
~MS Z.b(o>
Z.+94
~+g 9.8388 SEC
.. IO~
. (o~
10>
x lO~
x IG x (0~
/SEC.
~(0 x (0
<< /0
)r 10 x (0<
B l.aha 9.o 12779 Q.Ebon 5Zo5o 9 4ztJ3 2.4o>>
- 1. 8(4 i.2%8 5 4219 5.7lt,?.
f.o8%
%~M
/+99 4M4
+5z)o 45785 4.59
+4~
4>97 Z.z'.386 z.a%8 2.ef z.eH6 2 boZ2.
2.4A66 Z.&f40 z.at%
z.7570 2.'7%3 2.7hZ2
- 2. IG&o XIO8 Time o8 Start o
lus D
Reflood Qlalues b low are or ste only) 4E.~<
C8.51 78.5) 88.5)
)O8.31 l1g.&(
tz8.6]
O.O O.O 00 00
(.S.a) 1 99'.9%9
( 9tvZ l '31ZS
)9&
x JP G.o G.o
~ Io' IO~
zaire.
zest 2.5%4 zVsd.
z.4~~1 4.).)eg 4).)3~
44,)91 4A )91 4t 337 4Hz,i 449) 3 41)og Wvz97 2.7Q,o Z.'764+
l.V~4 z.ve/z Z.So8~
z.MS z.859>
z.as'.'Page to8
~
i
~
Table II. 8 Cont'd INTEG OP SEC.
)58.sl f58.3i i'd&.+t l1$.5l
!88.3t ig&.s~
gQ5.5'I 2@Hi 2433l 288~i 348.81 5ZS'5l 3489l
+~9l Var,a~
~.31 1 84x9 l 6648 i eeh i ss59 I 89zz t.5984 t.Goals t.9~
l.elt7 i.%5Z I
'SR'.94ig (887 l.917'.ea9i Z.ai@,
g.ol9 l 2~]o5 SEC g lo x IP zAzn zAs%
z.4a7 zAszs ZA4o7 z.4.eo z.+BZ z.47 z.+39c 2.5lQ.
z.~
263Z9 2.55lO 2.577o z.ss4 2,6 fl9 2.(,i95 2-4257 z.(.As SEC x (0
'57Mb 4vs~
4~
@&zan AAz 4Lu
'ksstz
@st 4es7e fe~s 5.o15>
- 5. i~47 s.~s@
5.i9%
s.zan 5'Z750 5 5%7 ]@5 z.'9357 Z.'9%5 2.98zg V.e v4 5.0~
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Table III-1 Variables Plotted as a Function of Time for Isolated Safety Injection Tank Analysis Variable Figure Desi nation Core Power Pressure in Center Hot Assembly Node Leak Flow Hot Assembly Flow (below hot spot)
Hot Assembly Flow (above hot spot)
Hot Assembly guality Containment Pressure Mass Added to Core During Reflood Peak Clad Temperature Mid Annulus Flow gualities Above and Below the Core Core Pressure Drop afety Injection Flow into Intact Discharge Legs ater Level in Downcomer During Reflood Gap Conductance Local Clad Oxidation Clad Temperature, Centerline Fuel Temperature, Average Fuel Temperature and Coolant Temperature for Hottest Node Hot Spot Heat Transfer Coefficient Hot Spot Heat Transfer Coefficient During Reflood Containment Temperature Sump Temperature Hot Pin Pressure Core Bulk Channel Flow Rate A.
B C
0.1 0.2 E
F G
H*
I J
K L
M N
0 p
R S
T U
V
- For the worst case, the temperature of the rupture node is also shown.
Table III-2 A Comparison of -Times, Temperatures, and Oxidation Percentages for the Worst Break (0.8 DEG/PD) with and without an Isolated SIT PLMGR = 15.8 kw/ft Break Mot Rod
~Ru ture SI Tanks on Start of SI Tanks Refloud
~Em t Peak Clad Tem erature F
Clad Oxidation 5 Local Core-Hide ne SIT Isolated 10.0 17.9 46.5
- 71. 3 2191 10.97
<.880 o SIT Isolated 10.0 17.9
- 38. 3 71.1 2192 10.42
<.787
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FIGURE II.6-F ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILIOTINE BREAK IN PUMP DISCHARGE LEG CONTAINMENT PRESSURE 60.000 50 000 40 F000 KC 30.000 2.0.000 10.000 Ga000 CD k
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2.2.0 0 rib ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK. IN PUMP DISCHARGE LEG PEAK CLAD TEMPERATURE 2,0 1800 3.800 j 400
+ 1000 800 600 00 0
100 2.00 300 TlHE>
SECONDS.
400 500 600 70
FI GURE II.6'-I ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG
..,MID-ANNULUSFLONI l.5000.
10000 5000's C)~ -5000.
-10000 s
-15000.
CD CD CD LA CD CD CD CD W
CD nJ CD CD C
iA oJ
FIGURE II.6-J ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG
.. QUALITIES ABOVE AND BELOW THE CORE ABOVE THE CORE BELOMf THE CORE 1.0,000 r8000 l
1 I I
)l
.8000 I i J
/I 0.0000 CD CD CD r
iTNE: TN SEC CD CD CDr oJ CD CD r
lA oJ
~
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k
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FI GURE II.6-K ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE PRESSURE DROP 30.000 2.0.000
~0.000 Lal 0.000 LxJ 0
I
-3.0.000
~-P.0.000
-30 ~000.
CD CD CD
~
CD R
lA CD' CD CD N
CD CD CD TTHE IN SEC
u.t uRE II.6-L ST. LUCIE UNITI 0.8 X. DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG SAFETY INJECTION FLOVl INTO INTACTDISCHARGE LEGS 8000 7000 6000 4
Soao C) 4000 C)
~
3000 2000 0
0 20 40 60 TIME AFTER RUPTURE, SEC.
80 500
FIGURE II.6-M ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG WATER LEVEL IN DOWNCOMER DURING REFLOOD 1,8 <<000 15 <<000 1P <<000
~1 9<<000 S <<000 3 <<000 0 ~ 000 CD CD CD CD CD CD CD CD CD CD CD nJ CD CD CD CD (Y)
CD CD CD CD CD CD CD CD LD TTHE AFTER CONTACTs SEC
, F800 I L JL ~
ST. LUCIE UNITI 0.8 x DOUBLE.ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT SPOT GAP CONDUCTANCE.
00 1400 1000
~00 800 o
400 2.0 0 100 2.00 300 TZHEa SECONDS 400 500 600
U 6 LI.6-ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG PEAK LOCAL CLAD OXIDATION 100 200 300 TZMEs SE'CONDS 400 500 600
,.450u 00 ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CLAD TEMPERATURE CENTERLINE FUEL TEMPERATURE AVERAGE FUEL TEMPERATURE AIUD COOLANT TEMPERATURE FOR HOTTEST NODE 3500 3000 2.50 0 FUEL CENTERLINE
~00
~.1.500 CLAD AVERAGE FUEL 1000 COOLANT 100 2.00 300 40,0.
500 TZMEa SECONDS 600
180 J
ST. LUCIE UNIT I 0.3 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT SPOT HEAT TRANSFER COEFFICIENT o
140 3.0 0 l
0 C)
CD 80 40 2.0 100 200 300 TZME>
SECONOS 400 500
I
~
g
, ~
FIGURE II.6-R ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT SPOT HEAT TRANSFER COEFFICIENT DURING REFLOOD 30>>000 P5.000 CD I
I 20
~ 000 1.5>>000 CD C) 10 000 CL 5.000 0.000 LCD CD g
CD CD CD CD CD CD CU CD CD CD CD CD CD CD CD CD CD CD TAHE I:IFTEP.
CQNTACT
( SEC
)
~
~
0 0
FI GVRE II.6-S 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG ST. LUCIE UNIT I CONTAINMENT TEMPERATVRE 280 240 200 160 120 80 40 100 200 300 TIME, SECONDS 400 500
~
~
FI GURE II.6-T ST. LUCIE UNIT I 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG SUMP TEMPERATURE 280 240 200 160 120 80 40 0
0 100 200 300 TIME, SECONDS 400 500
~
I 0
FI GURE II.6-U ST. LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG
" -"HOT ROD INTERNAL GAS PRESSURE 1200 INIT AL
= 1147.6 PSIA 1000 800 RUPTURE (10.0 sec)
A 600 CL 400 200 0
20 40 60 TIME, SECONDS 80 100
l
FIGURE II.6-V ST. LUCIE UNIT I 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE BULK CHANNEL FLOIC RATE 30000m CORE INLET CORE EXIT 20000>
10000.
CD C) "-10000.
~-2.0000.
BULK CHANNEL REPRESENTS 98%
OF TOTAL CORE FLONI AREA
-30000 s CD CD LA CD CD CD CD CD LO CD CD oJ CD CD R
LA'J TIME TN SEC
Figure II.7-A 2560lNiR PLANTS 0.6 x DOUBLE ENDED GU'LLGTINE BREAK IN PUlViP OISCl<ARGE LEG CORE POiA'ER 3.RP001 i.R0000 a6000 R4000 R2.000 OR0000 CD
.CD CD R
CD CD CD CD R
tD CD CD CD Cd CD CD CD CD CD CD CD CD R
CD CD CD CD TTME XN SEC
Figu re II.7-8 2560 MWt PLANTS.
0.6 x DOUBLE ENDED GUILLOT.'.NE BREAK IN PUMP DISCHARGE L'G P RES SUP E IN CENTER HOT AS S EMBLY NODE 2.400 <<0
, j,
~ $r
~
2000 <<0 lS00 <<G 0
~1
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12.00 <<0
.Lsd Q
~
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800<<0 400 <<0 0<<0 CD CD CD\\
CD CD CD CD LA CD CD CD CD CD CD lA CD CD CD CD cd CD CD, CD L
cd TAHE TN SEC
Figu re II.7-C 2560 MWt PLANTS 0..6 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG LEAK FLOW PUMP SIDE
REACTOR VESSEL SIDE i20000a l00000m 80000~
CD uz 60000 a
C) 40000 r
'20000m Oa
,CD CD CD R
CD CD C) lA CD CD CD CD CD CD CD CD CD CD t
k LA nJ CD CD CD R
LA TIME 1N SEC
I I
Figure II.7-D.I 2560 M>A't PLANTS 0.6x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG
. FLOMl IN HOT ASSEMBLY - PATH 16,. BELO'A'OT SP(JT 301000 P.O F000 10 F000 C3 Os000
'.-~0a000
-2.0 F000
.-30 I000 CD CD CD CD CD CD CD tA
~
CD CD CD CD.
CD CD CD tA CD CD CD CD aJ CD
~
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cf
Figure ',I.7-D. 2 2560 M'Plt PLANTS 0.6 x DOUBLE ENDED GUILLOTINE BREAK IN -PUM, DISCHARGE LEG FLOMl IN HOT ASSEMBLY - PATH 17,.ABOVE HOT SPOT 30>>000 20<<000
~ ~
~i Cll ca
~0>>000 0>>000 C)
-3.0>>000
-2.0>>000
-30>>000 CD.
CD h
CD CD CD CD lA CD CD CD CD CD CD CD LA CD CD CD CD oJ CD CD tA nl
~
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Figure II.7-E 2560 Milt PLANTS
~ 0. 6 x DOUBLE ENDED GUILLOTINE BREAK,IN PUMP DISCHARGE LEG HOT ASSEMBLY QUALiTY
NODE 13, 8ELOVJ HOTTEST REGiON
. NODE 14, AT HOTTEST P.EGIGN NODE 15, ABOVE HOTTEST REGION
~
- ~
. 3.F0000
~8000 a8000 r4000 I
/1 l)
.l l
lljl Il
.ll
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V
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/
aP000 0 I0000 CD.
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~
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FI GURE II.7-F ST. LUCIE UNITI 0.6 x DOUSLE ENDED GUILLOTINE SREAK IN PUMP DISCHARGE LEG CONTAINMENT P RES SURE 80>>000 50>>000 40>>000 Q
30>>000 Ck CL 2.0.000 10.000 0>>000 CD CD CD CD CD CD CD CD CD CD CD CD CD CD CD
~
CD CD CD CD CD CD CD tA TIME AFTER RUPTURE, SEC
I
'I 0
0
I I ~
FIGURE II.7-G ST. LUCIE UNITI 0.6 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG MASS ADDED TO CORE DURING REFLOOD i20000r 100000
'0000>
~1 CL COV O
80000 i Ch N
40000
'0000m Oi CD CD CD
, CD CD CD CD C)
CD CD oJ CD CD CD CD CD
~
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CD CD CD CD C)
CD tA TAHE AFTER
. CONTACT>
SEC
2.2.0 0 FIGURE II.7-H ST. LUCIE UNITI 0.6 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG PEAK CLAD TEMPERATURE 2.000 J.800 3400
~~ J.2.00
~~J.000 800 800 400 J.O 0 2.00 300 TTlvl~P P,Q<Pj~f
~00 o00
2200 2000 Figure II.8
-ST. LUCIE UNITI PEAK CLAD tEMPERATURE vs BREAK AREA (PEAK LHGR =15.8 KII/FT).
o~g 8gP 1800 1600 C3 I
9 DISCHARGE LEG SLOTS 8
DISCHARGE LEG GUILLOTINES DISCHARGE LEG BREAKS 1400 0.6 DE 0.8 DE 1.0 DE 1200 0
6 8
BREAK AREA, FT 10
12000
. 11000 10000 9000 8000 7000 6000 5000 4000 3000 2000 1000 Figure II.9 ST. LUCIE I COMBINED S PILLAGE AND SPRAY INTO CONTAINMENT 1 TANK SPILLING DIRECTLY INTO CONTAINMENT
~ EFFECTIVE ANNULUS SPILLAGE EFFECTIVE PUMP S PILLAGE S PRAY FLOW 0
40 80 120 160 200 240 280 320 360 400 TIME FROM BREAK, SEC
FIGURE III.A ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE POWER 1>>2001 1%0000
%8000
%6000
%4000 2.000 0%0000 CD CD CD CD.
CD CD CD k
CD CD CD CD k
cU CD CD CD CD k
Ch CD CD CD CD k
CD CD k
LA TINE TN SEC
FIGURE III.B ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG PRESSURE IN CENTER HOT ASSEMBLY NODE 2400.0 2.000 <<0 1600 <<0 12.0 0'<<0 800<<0 4on<<o 0<<0
~ tD LA C)
C)
TjNE TN SEC I
k nJ
I
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I FI GU RE III.C ST. LUCIE UNIT I ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG LEAK FLOW PUMP SIDE REACTOR VESSEL SIDE 12.0000>>
100000>>'0000>>
60000>>
~i 40000>>
'2.0000>>
0 ~
CD C7 CD CD CD C)
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~
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I 0
FIGURE III.D.l ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUhAP DISCHARGE LEG FLOW IN HOTASSEMBLY - PATH 16, BELOW HOT SPOT 30 000 20 F000 10 s000 CD 0 >000
-10 F000 C)
-20 s000
-30 F000 CD CD CD CD CD CD lA CD CD CD CD CD CD lA CD CD CD CD cV CD CD CD rJ TlME TN SEC
~
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1
FIGURE:III. D. 2 ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG FLOW IN HOT ASSEMBLY - PATH 17, ABOVE HOT SPOT 30 000 2.0 <<000 10 <<000 CD 0 <<000
-10 <<000
-2.0 <<000
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CD lA oJ T1ME ZN SEC
i
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4 1.0000 I
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l
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tl t
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FIGURE III.E ST LUCIE UNITI ISOLATED SAFETY INJE CTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT ASSEMBLY QUALITY NODE 13, BELOW HOTTEST REGION NODE 14, AT HOTTEST REGION NODE 15, ABOVE HOTTEST. REGION
<<S000 f
CZ C3
<<4000 I
I
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l
<<2.000 0<<0000 CD CD CD CD LA
'D CD C)
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LA CD C)
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cd Tj:ME TN SEC
FIGURE III.F ST. l.UGIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CONTAINMENTP RESS VRE 60kooo 50>>000 40 aooo 30kooo UJ zo.ooo 10 %000 Okooo CD k
CD CD k
CD CD CD k
CD CDnl CD k
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~
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FIGURE III.G ST. LUCIE UNITI ISOLATED SAFETY INJECTlON TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG MASS ADDED TO CORE DURING REFLOOD l2.0000 k 100000 k
80000k 60000k CD C) 40000>>
Time sec 0;0-15.0 15.0-77.2 77.2-400.0 Reflood Rate 1.86 in/sec 1.16 in/sec 0.72 in/sec P.0000 r Ok CD CD k
CD k
CD CD CD k
CD CD nJ CD CD k
CDCD'D CD k
CD CD CD CD CD CD EO TlME AFTER CONTACTs SEC
h
I I
2.2.0 0 FIGURE III.H ST. LUCIE UNIT I ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG PEAK CLAD TEMPERATURE 2.000 3.800 1600 J.400
~ i.2.00
~ 1000
.800 800 100 2.00 300 T'1HE>
SECONDS 400 500 600
FIGURE III.I ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG MID-ANNULUSFLOII 15ooo.
10000 s
5000m CD LrJ Os CQ
-5000 C)
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CD CD CD CD CD CD CD CD CD CD LA CD CD CD oJ CD CD CD lA oJ TAHE 1N SEC
FIGURE III.J ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE EG QUALITIES ABOVE AND BELOW THE CORE ABOUE THE CORE
-- BELOW THE CORE
- j. <<000
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FIGURE III.K ST. LUCIE UNITI
-ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE PRESSURE DROP 30>>000 2.0.000 10>>000
~1 0>>000
-10.000
-20 000
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e e
FIGURE III.L ST. LVCIE UNITI
.. ISOt.'ATED. SAFETY IN JECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG SAFETY INJECTION FLOV/ INTO INTACT DISCHARGE LEGS 6XO CD 4000 3000 2000 1000 20 40 60 80 TIME AFTER RUPTURE, SEC 500
FI GURE III.M ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK.
0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG WATER LEVELIN DOWNCOMER DURING REFLOOD 18 8000 158000 12.8000 S
000 O
68000 38000 08000 CD CD CD CD 8
CD CD CD CD 8
CD CD Cd CD k
CD CD CD CD k
CD CD CD CD k
CD CD LA TTME AFTER CONTACTS SE'C
gl w
f 2800 FIGURE III.N ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT SPOT GAP CONDUCTANCE J.600 l,400 l2.0 0 l.000 800
+I 800 C3 Q
400
. 2.00 o
0 100 200 300
,Tj:HF>
SECONDS 400.....500 600 70
FIGURE III.O ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED. GUILLOTINE BREAK IN PUMP DISCHARGE LEG PEAK LOCAL CLAD OXIDATION j.00 2.00 300 Tj:ME>
SECONDS 400 500 600 70
4500 Kh Ill.
ISOLATED SAFETY INJECTION TANK ST LUCIE UNITI 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN P UMP DISCHARGE LEG CLAD TEMPERATURE, CENTERLINE FUEL TEMPERATURE AVERAGE FUEL TEMPERATURE AND COOLANT TEMPERATURE FOR HOTIEST NODE, 4000 3500 3000 2.500 FUEL CENTER INE 2.000 a
1,500 CLAD AVERAGE FUEL 3 000 500 COOLANT o
3.00 200 300 TTMEr SECQNI3S 500 600 70
j.8 0 ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT SPOT HEAT TRANSFER COEFFICIENT j.e 0 lpp C)
CD 60 gp 2,0 o
100 200 300 T1ME>
SECONDS 500 500 600 70(
I e
FIGURE III.R ST. LUCIE UNIT I
- 0. 8 x DOU SLE EQIPRLI0%7l HlNBRNQlÃDISCHA RGE LEG HOT SPOT HEAT TRANSFER COEFFICIENT DURING REFLOOD 30.000 2.5.000 CD I
RO>>000 I
I 15>>000 CO CD 10>>000 5
000 0>>000 CD CD CD CD CD CD nJ CD CD CD CD CD CD CD CD CD CD T1HE AFTER CONTACT
( SEC
)
FIGURE III.S ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CONTAINMENTTEMPERATURE 240 200 160 120 40 0
0 100 200 300 TIME, SECONDS 400 500
1 I
FIGURE III;T ST. LUCIE UNITI j:SQLATED SAFETY INJECTION TANK 0.8 x'DOUBLE ENDED GUILLOTINE BREAK IN-PUMP DISCHARGE LEG SUMP TEMPERATURE 240 200 E60
~i 120 80 40 100 200 300 TIME, SECONDS 400 500
FI GURE III.U ST. LUCIE UNITI ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG HOT ROD INTERNAL GAS PRESSURE 1200 PILI IA~
1147.
PSIA 1000 C/l Q
800 RUPTURE 10.0 sec)
A UJ N
600 400 200 20 60 40 TIME, SECONOS 80 100
~
~
FI GVRE III.V ST. LUCIE UNITI
. ISOLATED SAFETY INJECTION TANK 0.8 x DOUBLE ENDED GUILLOTINE BREAK IN PUMP DISCHARGE LEG CORE BULK CHANNEL FLOW RATE CORE INLET CORE EXIT 30000%
2.0000 10000 i CD LU CA
, 0 ~
o
-10000
-2.00001 BULK CHANNEL REPRESENTS 98%%u OF TOTAL CORE FLOW AREA
-30000 I CD CD CDI CD CD CD CD R
LA CD CD CD CD CD CD LA CD CD CD CD oJ CD CD LA nJ TlME 1N SEC
N e
I