ML19281A084
| ML19281A084 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 03/01/1979 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7903060159 | |
| Download: ML19281A084 (80) | |
Text
{{#Wiki_filter:A; earna Ftver Cercy COO NTn 1 Bin S"ce4 Pz.! Cr* ce bw 2641 8 rr nyum. Ao w a 3-231 te'epor e 200 323 B11 m F. L CLAYTON, JR se m a ne; ?.e : Mal)ama POWCT "r muH rrn v.+. toc cyrMn March 1, 1979 Docket No. 50-348 Dire tor of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Mr. A. Schwencer Gentlemen: JOSEPH M. FARLEY NUCLEAR PLANT-UNIT NO. 1 ECCS ANALYSIS In a letter dated April 27, 1978 the NRC issued an Order for Modi-fication of License amending the Farley Nuclear Plant-Unit No. 1 License No. NPF-2. This order required submittal of a revised analysis of ECCS cooling performance calculated in accordance with a revised Westinghouse evaluation model, corrected for the identified errors (associated with the zirconium-water reaction heat generation) and approved by the NRC. By letter to Westinghouse dated August 29, 19 78 (J . F. Stolz to T. M. Anderson), the NRC approved the February, 1973 version of the Westinghouse ECCS Evaluation Model (WCAP-9220) which included corrections to the identified errors. Accordingly, we have performed the required ECCS reanalysis utilizing the February, 1978 Westinghouse Evaluation Model. The results of this analysis are provided in the enclosure and confirm that the Farley Plant ECCS system performance meets the acceptance criteria of 10CFR50.46. Should you have any questions, please advise. Yours truly, O A 1 kd I F. L. Claytot, Jr. [L FLCJr/TNE:bhj Enclosure cc: Mr. R. A. Thomas Mr. G. F. Trowbridge ( 7003060 / 67 h
ENCLOSURE J. M. FARLEY NUCLEAR PLANT-UNIT NO.1 ECCS ANALYSIS I.
Introduction:
The analysis specified by 10CFR50.46(l) " Acceptance Criteria for Emergency Core Cooling Systems for Light Water Power Reactors" is presented below. The analytical techniques used are in compliance with Appendix K of 10CFR50, and are described in Section II. The results of the loss of coolant accident analysis are presented in Section III and show compliance with the acceptance criteria. The results for the small-break loss of coolant accident are presented in FSAR Section 15.3.1 and are in conformance with 10CFR50.46 and Appendix K of 10CFR50. II. Method of Thermal Analysis: The loss of coolant accident (LOCA) has been reanalyzed for the 0.4 DECLG break which is the limiting break for the Farley Plant. The results of this analysis are presented in Section III. The descrjption of the various aspects of the LOCA analysis is given in WCAP-8339(2). The individual computer codes which comprise the Westinghouse Emergency Core Cooling System (ECCS) evaluation model are described in detail in separate reports (3)-(6) along with code modifica-tions specified in references (7), (8), and (9). The analysis presented was performed with the February 1978 version of the evaluation model which includes modifications delineated in references (10), (11), (12), and (13). Also included is Appendix A which presents the results of a generic , sensitivity study for a typical three loop plant with 17 x 17 fuel. This sensitivity was performed to determine the limiting break size using the February 1978 version of the Westinghouse ECCS evaluation model which incorporates a correction to the clad metal-water heat of reaction calcula-tion. The results of this generic sensitivity study show that the limiting break for Westinghouse plants of this type is a double ended cold leg guillotine with a discharge coefficient of 0.4. Since the Joseph M. Farley Nuclear Plant was previously limited by the 0.4 DECLG break, and since the generic sensitivity has the 0.4.DECLG as the limiting break, only the 0.4 break is presented along with the results of the sensitivity study. III. Results of Thermal Analysis: The analysis of the loss of coolant accident was performed at 102 percent of the licensed core power rating. The peak linear power and total core power used in the analysis are given in Table 1. Since there is margin between the value of peak linear power density used in this analysis and the value of the peak linear power density expected during plant operation, the peak clad temperature calculated in this analysis is greater than the maximum clad temperature expected to exist.
Enclosure Page 2 Table 1 presents selected input values and results from the hot fuel rod thermal transient calculation. For these results, the hot spot is defined as the location of maximum peak clad temperatures. That location is specified in Table 1 for the break analyzed. The location is indicated in feet which presents elevation above the bottom of the active fuel stack. Table 2 presents the occurrence time for variance events throughout the accident transient. Table 3 presents a summary of the various containment systems parameters and structural parameters which were used as input to the COCO computer code (6) used in this analysis. Tables 4 and 5 present reflood mass e-d energy releases to the contain-ment, and the broken loop accumulator mass and energy release to the containment, respectively. The results of several sensitivity studies are reported ( ' . These results are for conditions which are not limiting in nature and hence are reported on a generic basis. Figures 1 through 17 present the transients for the principle parameters for the break sizes analyzed. The following itens are noted: Figures 1-3: Quality, mass velocity and clad heat transfer co-efficient for the hotspot and burst locations Fogures 4-6: Core pressure, break flow, and core pressure drop. The break flow is the sum of the flowrates from both ends of the guillotine break. The core pressure drop is taken as the pressure just before ti.e core inlet to the pressure just beyond the core c utlet Figures 7-9: Clad tenperature, fluid temperature and core flou. The clad and fluid teceperaturcs are for the hot spot and burst locations Figures 10, 11: Downcomer and core water level during reflood, and flooding rate Figures 12, 13: Emergency core cooling system flowrates, for both accumulator and pumped safety injection Figures 14, 15: Containment pressure and core power transients Figures 16, 17: Break energy release during blowdown and the con-tainment wall condensing heat transfer coefficient for the worst break
Enclosure Page 3 IV. Conclusions-Thermal Analysis: For breaks up to and including the double ended severance of a reactor coolant pipe, the Emergency Core Cooling System will meet the Acceptance Criteria as presented in 10CFR50.46. That is:
- 1. The calculated peak clad temperature does not exceed 22000F based on a total core peaking factor of 2.32.
- 2. T' e amount of fuel element cladding that reacts chamically with rater or steam does not exceed 1 percent of the total amount of Zircalloy in the reactor.
- 3. The clad temperature transient is terminated at a time when the core geometry is still amenable to cooling. The cladding oxida-tion limits of 17% are not exceeded during or after quenching.
- 4. The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived radioactivity remaining in the core.
V.
References:
- 1. " Acceptance Criteria for Emergency Core Cooling Systems for Light Water Cooled Nuclear Power Reactors" - 10CFR50.46 and Appendix K of 10CFR50. Federal Register, Volume 39, Number 3, January 4,1974.
- 2. Bordelon, F. M. , Massie, H. W. , and Zordan, T. A. , " Westinghouse ECCS Evaluation Model - Summary," WCAP-8339, July 1974.
- 3. Bordelon, F. M. , et. al ., " SATAN-VI Program: Comprehensive Space-Time Dependent Analysis of Loss-of-Coolant," WCAP-8306, June 1974.
- 4. Bordelon, F. M. , et. al . , "LOCTA-IV Program: Loss-of-Coolant Transient Analysis," WCAP-8305, June 1974.
- 5. Kelly, R. D. , et. al, " Calculational Model for Core Reflooding af ter a loss-of-Coolant Accident (WREFLOOD Code)," WCAP-8171, June 1974.
- 6. Bordelon, F. M. , and Murphy, E. T., " Containment Pressure Analysis Code (C0C0), "WCAP-8327 (Proprietary Version), WCAP-8326 (Non-Proprietary Version), June 1974.
- 7. Bordelon, F. M. , et. al . , "Westinghcuse 'ECCS Evaluation Model -
Supplementary Information," WCAP-8472 April 1975.
- 8. " Westinghouse ECCS Evaluation Model - October 1975 Version," WCAP-8623, Ncvember 1975 (Nonproprietary).
- 9. Letter from C. Eicheldinger of Westinghouse Electric Corporation to D. B. Vassallo of the Nuclear Regulatory Commission, letter number NS-CE-924 dated January 23, 1976.
Enclosure Page 4
- 10. Kelly, R. D., Thompson, C. M., et. al., " Westinghouse Emergency Core Cooling System Evaluation Model for Analyzing Large LOCA's During Operation With One Loop Out of Service for Plants Without Loop Isolation Valves," WCAP-9166, February, 1970.
- 11. Eicheldinger, C., " Westinghouse ECCS Evaluation ?lodel, February 1978 Version, "WCAP-9220-P-A (Proprietary Version), WCAP-9221-A (Non-Proprietary Version), February, 1979.
- 12. Letter from T. M. Anderson of Westinghouse Electric Corporation to John Stolz of the Nuclear Regulatory Commission, letter number NS-TMA-1981, November 1, 1978.
- 13. Letter from T. M. Anderson o Westinghouse Electric Corporation to Tedesco of the Nuclear Regu~ tory Commission, letter number NS-TMA-2014, December 11, 1 8.
- 14. Federal Register, "Supplemc t to the Status Report by the Director-ate of Licensing in the matter of Westinghouse Electric Corporation ECCS Evaluatian Model conformaace to 10CFR50.46 Appendix K",
November 1974.
TABLE 1 LARGE BREAK - ANALYSIS INPUT AND RESULTS Quantities in the calculations: Licensed core pov er rating 102% of 2652 MWt Total core peaking factor 2.32 Peak linear power 102% of '2.11 kw/f t Accumulator water volume 1025 cubic feet per tank Accumulator pressure 600 PSIA Steam Generator Tube Plugging Level 1.5 percent (uniform) Fuel Parameters Cycle 1, Regions-All Results: DECLG, CD = 0.4 Peak clad temperature (OF) 2158.4 Location (feet) 7.5 Maximum local clad / water reaction (%) '7.17 Location (feet) 7.5 Total core clad / water reaction (%) <0.3 Hot rod burst time (seconds) 28.6 Location (feet) 6.0
TABLE 2 LARGE BREAK - TIME SEQUENCE OF EVENTS CD = 0.4 Event: Occurrence Time (Seconds) Accident Initiation 0.0 Reactor Trip Signal 0.507 Safety Injection Signal 0.95 Start Accumulator Injection 16.8 End of ECC Bypass 26.75 End of Blowdown 29.91 Bottom of Core Recovery 39.57 Accumulators Empty 51.83 Start Pumped ECC Injection 25.95
TABLE 3 CONTAINMENT DATA 6 3 Net Free Volume 2.3 x 10 Ft Initial Conditions Pressure 14.7 PSIA Tempera ture 900F RWST Temperature 350F Service Temperature 350F Outside Temperature 400F Containment Spray c;s tem Parameters Number oi Pumps Operating 1 Maximum Spray System Flow 5550.0 GPM Fastest Post LOCA Initiation of Spray System Assuming Offsite Power loss at Start of LOCA 48.0 Sec. Fan Coolers Maximum Number of Fan Coolers Operating 4 Fastest Post LOCA Initiation Assuming Off-Site Power Loss at Start of LOCA 27.4 Sec.
TABLE 3 (Continued) C0C0 INPUT
SUMMARY
AREA THICKNESS WALL (FT2 ) COMPOSITION (FT) 1 75,000 Steel / Concrete 0.02083/3.75 2 4,700 Steel / Concrete 0.05/3.75 3 69,800 Concrete 0.75 4 77,000 Steel 0.0058 5 80,500 Steel 0.0113 6 47,600 Steel 0.03 7 23,600 Steel 0.0583 8 11,800 Steel 0.1917 9 13,27- Concrete 9.0 10 7,900 Steel / Concrete 0.0208/1.5 11 12,500 Steel 0.0087
TABLE 4 REFLOOD MASS AND ENERGY RELEASE TIME MASS RELEASE * (SEC) (LB/SEC) 39.574 0.0 0.0 40.624 0.8563 0.0562 40.924 0.8386 0.05434 41.024 0.8362 0.5537 46.024 3.67601 2.1378 55.024 277.9 149.549 68.981 322.88 241.854 86.181 335.53 312.108 105.481 342.58 402.685 126.581 348.31 548.857 173.991 358.26 1683.423 229.581 367.11 19573.896 295.681 375.69 20509.724 379.189 386.35 21538.623
- Nitrogen gas released at 103.474 lb/sec between 50.9 and 90.9 seconds.
TABLE 5 BROKEf1 ACCUMULATOR fMSS A11D ENERGY RELEASE TIME IMSS RELEASE EfiERGY RELEASE (SEC) (LB/SEC) (BTU /SEC) 26.897 1524.243 88406.072 26.908 1523.974 88390.474 26.958 1522.759 88320.012 27.15 1517.998 88043.884 27.35 1513.092 87759.361 27.551 1508.219 87476.710 27.751 1503.445 87199.791 27.951 1498.728 86926.237 28.15 1494.031 86653.824 28.341 1489.337 86381.568 28.550 1484.730 86114.346 28.750 1480.141 '85848.164 28.950 1475.596 85584.552 29.150 1471.069 85322.006
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APPENDIX A GENERIC PARAMETERS 3 LOOP PLANT 17 x 17 FUEL
TABLE A-1 LARGE BREAK TIME SEQUENCE OF EVENTS CD = 0.8 CD = 0.6 CD = 0.4 DECLG DECLG DECLG (SEC) (SEC) (SEC) START 0. O. O. Reactor Trip Signal 0.48's 0.487 0.497 S. I. Signal 0.77 0.87 1.07 Acc. Injection 10.5 12.1 15.5 End of Blowdown 22.54 24.159 28.63 Bottom of Core Recovery 31.589 33.256 37.031 Acc. Empty 39.914 41.559 45.634 Pump Injection 25.77 25.87 26.07 End of Bypass 19.32 21.028 24.696
TABLE A-2 LARGE BREAK - ANALYSIS INPUT AND RESULTS Quantities in the calculations; Licensed Core Power Rating 102% of 2775 Mwt Total Core Peaking Factor 2.10 Peak Linear Power 102% of 11.66 kw/f t Accumulator Water Volume 1000 cubic feet per tank Accumulator Pressure 600 PSIA - Number of Safety Injection Pumps Operating Steam Generator Tube Plugging Level 0 percent (uniform) Fuel Parameters - Cycle 1 Region 1 Resul ts: DECLG, CD = 0.8 DECLG, CD = 0.6 DECLG, CD = 0.4 Peak clad temperature ( F) 1877 2056 2193
, Location (feet) 7.5 7.5 7.5 Maximum local clad / water reaction (%) 2.7 4.8 7.6 Location (feet!) 7.5 7.5 7.5 Total core clad / water reaction (%) <0.3 <0.3 <0.3 Hot rod burst time (seconds) 55.0 26.8 30.0 Location (feet) 6.75 6.0 6.25
TABLE A-3 ACTIVE. HEAT SINK DATA FOR MINIMUM POST-LOCA CONTAINMENT PRESSURE I. Containment Spray System Parameters A. Maximum spray system flow, total 6,000 gpm B. Fastest post-LOCA initiation of spray system Assuming off-site power loss at start of LOCA 50 seconds II. Fan Coolers A. Maximum number of fan coolers operating 4 B. Fastest post-LOCA initiation Assuming off-site power loss at start of LOCA 108 seconds C. Performance data See Figure 18 for fan cooler atmosphere heat removal rate Fan coolers are cooled by the reactor plant component cooling water system. III. Reactor Plant Component Cooling Water System A. Maximum number of CCW heat exchangers used 2 B. Maximum CCW heat Exchanger UA 8.00 x 106 Btu /hr ft C. Maximum CCW flow per flow path 12,800 gpm D. Lowest normal service water temperature 500F E. Maximum service water flow per CCW heat exchanger 16,000 gpm
TABLE A-3 (Continued) PASSIVE HEAT SINK DATA FOR MINIMUM POST-LOCA CONTAINMENT PRESSURE A. Heat Sink
Description:
Slab Slab Material Surface Number Description Material Thickness (in.l Area, ft2 1 Containment Carbon Steel 0.25 26,550 Dome Concrete 51 2 Containment Carbon Steel 0.25 53,500 Shell Concrete 54 3 Internal Concrete 12 160,000 Concrete 4 Structural Carbon Steel 0.044 68,955 Concrete 0.054 11,309 0.04 55,164 0.168 11,033 0.282 16,156 0.336 68,955 0.431 690 0.672 132,394 1.345 10,343 5 Containment Concrete 12 6,100 Floor Carbon Steel 0.25 Concrete 264 Concrete 33.5 4,200 Carbon Steel 0.25 Concrete 264 6 Reactor Carbon Steel 0.25 1,840 Cavity Floor Concrete 12.0 Carbon Steel 0.25 Concrete 96 7 Equipment & Carbon Steel 2.0 650 Personnel Hatches B. Thermophysical Properties: Thermal Density Specific Heat Conductivity lb/ft3 Btu /lb F Btu /hr-ft F Concrete 145 0.156 0.92 Carbon Steel 490 0.12 27.0
TABLE A-4 CD= 0.4 DECLG REFLOOD MASS / ENERGY RELEASES TIME MASS FLOW
- ENERGY FLOW (SEC) LB/SEC BTU /SEC 37.031 0 .0 37.806 .000551 .60515 38.106 .53389 6.97779 x 10 2 4
41.738 34.19009 4.46906 x 10 50.734 207.14 1.35096 x 10 5 66.434 250.01 1.40361 x 10 5 86.234 266.10 1.38578 x 10 5 108.934 275.95 1.35234 x 10 5 5 133.934 284.55 1.30939 x 10 192.334 300.83 1.21454 x 10 5 268.234 322.01 1.11802 x 10 5 435.334 349.72 1.00680 x 10 5
- Accumulator nitrogen was released between 48.0 and 68.0 seconds at a mass flow rate of 192.27 lbm/sec.
TABLE A-5 BROKEN LOOP ACCUMULATOR MASS AND ENERGY RELEASES TO CONTAINMENT FOR LIMITING CASE - DECLG (CD = 0.4) TIME MASS FLOW
- ENERGY FLOW (SEC) LB/SEC BTU /SEC 5
0.0 4600.1 2.741637 x 10 5 2.0 3771.8 2.247966 x 10 4.0 3280.6 1.955220 x 10 5 6.0 5 2942.6 1.753775 x 10 8.0 5 2689.7 1.603067 x 10 10.0 2488.5 1.483139 x 10 5 13.0 5 2251.6 1.341939 x 10 16.0 5 2068.9 1.233066 x 10 20.0 5 1889.8 1.126317 x 10 24.0 5 1756.9 1.047135 x 10 24.829 1756.9 1.047135 x 10 5
*Enthalpy of accumulator water is 59.60 BTU /LBM.
0
- e l.40 1.25 -
m 1.00 - E . V , M -
.! 0.75 --- .
5 7 5' .
. g. '
g 0.50 - 3 so' 6.25' 0.25 - o i I I l illi i i i l illi l l l l llll ; ; j ;;;;; 10~I 2 100 I 5 2 5 10 '2 5 102 2 5 10 3 TlHE(SECONDS) -
- FIGURE lA Fluid Quality - DECLG (C = 0.4)
D . O g O
.1.NE10
, CD e 8.5 C tts WPPtanta0 Af fp0T . ,
CUALiff Cf FLc!D tutsf. s.40 rit i Pf AE. s.cs rites - i.r =
. c- . .
=
. =
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= .
=
- 3l
= A
- ..se:. j/
7 e.no
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a a a g rangs a a smags-
. .- e e e e e eses.: .: a a : ass =d E I !f R E!!@
!!Mt 45tts .
FIGURE 18. . Fluid Quality - DECLG (C = 0.6) D l l T e l r
" a. . 1.MKn
~ ~ ~ ~ ~
CD e 8.0 DICLC 8'P6 8. t As af feiO? tUAttif Cr ftul0 Sun 57. 5.75 rit 3 P[At. 8.te es*** 1.2300
)
n"
& ^
- .same '
3 l i e * ** . s U'.) u / e
/
/
= s.soco 7
s.rsoo
. p . ., ,r, ,
s.s Ig [g Eg$g $$$b3
~
5 5 5 $ EE.$.k- ( g g ggg.: 4 .: s ,c a - 2 2 .RS--- - - - - - rint istti 4 FIGURE 1C , ~ Fluid Quality - DECLG (C D
= 0.8) i e
l
. 6 e
4 l . i 9 e e
100 75 -
. 7.5' .
50 _ G u ft 25 - . s.2s'
~
S
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, _im 10-I 2 5 100- 2 5 10 1 -
2 5 102 2 5 , 10 3 TlHE(SECONDS) FIGURE 2A Mass Velocity - DECLG (C D
= 0.4) 'l I:
. k
~ -- - -
800.01 ** CD e e.s etCLG \PPran[ A0 AT Tuof .
/ Sutif. 6.30 FTL 8 Ptas. s.co FTses NASS vtLOClif , i i l l 1 o l g, .O M .C:0 Y l E
2 53.tm .
=f -
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. g, tan, t
- :0.00
- h g g; d d J d dds.* 4 4 4, 4 J4M E R I R 322 k k k .~.-
. TIMI (5tti .,
, FIGURE 2B .- -
Mass Velocity - DECLG (C = 0.6)
, D .
t
===
p I . l . t
L Mut.te
.. , m CD e 0. *-
WPP ocir,8 Citts . . .f.t u. f.A.D a,fn,f a ,i ,r... ,.,8 n,.,. _. .. ,
=
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=
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, 1 I
FIGURE 2C - i Mass Velocity - DECLG (CD = 0.8) e e 5 O e . c..* f
. 8 e e e
I
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g
0
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)
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=
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.,, (
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)
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~~ ** -
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*$300.co
'6 24.00
( 2 5lb' r 1 w,H
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* $ 43 G0 g N-_ ,
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' 8.0c00 1.W . _ _ _ _ _ _ _ _ . _ _ , _ _ _ , , ,_ _,
I k k #k k e O p . B- B E B flut titCI
. FIsVRE 3B Clad Heat Transfer Coefficient - DECLG (C D = 0.6)
.- CD e 0.8 ttCLC UPPitstAD At fra; ,
E 3.00 N( Af it Aa1.CO[ff!Cl[uf SW411. 6.7% TIL D P(AL. s.C3 FTiet 1 y eco.co en mm ' E m.= a
= . .
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= l. '
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.* as. coo 1 E "
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3.8000 2.0000 . .
- .erairt.
g,geco
- 8 s s s f
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flMt titCl FIGURE 3C i Clad Heat Transfer Coefficient - DECLG (CD = 0.8) I I
g 4 *
- O
=
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^
- c M < a O
- e W Ltj Q t.LJ Q O E
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==
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, . s (visa)sanssava .
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5 2
~
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)
8 0
=
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. C
(
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( G I e F r E u H s l s T e 0 r 1 P
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.m o
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=
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5 0 5 0 5
- 2 2 1 1 7 D wcsmwg oi
- 0
10.0 7.5 - 5.0 - u w n 2.5 - m o 0 N '. J l ts. . I w ,
<< l
. W -2.5 -
b 5.0 -
-7.5 -
-10.0 -
0 10 20 30 , Tike (SECONDS) FIGURE 5A Break Flow Rate - DECLG (Cg = 0.4) e m,-
L84MP5
. CD e ..E DICLC WPP!8st AD At 1807 .
Bat AE ftov T.We O . E 1. DIX *0e 2.MO
=.
U e 4.M*
. *4.CEO
- 7. M @ * ..
-t
.g,ge *
*retitt s -
g n a n s N . N TIME titti . FIGURE 5B ' Break Flow Rate - DECLG (C D = 0.6) 4 4 e
- c. .
- 9 e
- *
- e,. ,
,, ew - w %e
N~ .
/
t
/ .
i.dre
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~ _
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-s. a + ,
-r. w +
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l E e I a f. 2
- '. I.
c fint istt FIGURE SC Break Flov! Rate - DECLG (CD = 0.8) f l I O I ee-o em..
"" * ***e eee ee ..
4 N~ . M.Coe 0.4 5(CLC . CDe[ Ps.084P
- so.sas . .
3 i -
.- n. ace 0.8 g
, w -
-n.sco
.se.coe
.ir.,,,
a I I. E f. g
.. d 2 d : i n ur urci
. . FIGURE 6A -
, Core Pressure Drop - DECLG (CD = 0.4) e
t 70.a30 ,
- 8 WPF(ast&D A1 Test (88[ t pro
- 50. 2 . . - .
= ,
C. rs. coo C =
.e . -
0.0 ' ~ y '
. l
-f5.CCO
. s M.Cal) enttrie
-re.eco g,
l e E e k
=
k e. k c n ar istti . FIGURE 6B Core Pressure Drop - DECLG (C = 0.6) D
. g I
e * .
. m , .
N.
/ . . . . . . . . .
r . t l' . . . . _ _ . . . . . . . e N.000 Cp a 8.8 CICLC DPP!BatA0 af 1m0T o
- g C0ag ra.pspr r _
E m N 21.500 *
- m.
- es w
3, k i
.es. coa
)l
~
.sa.aco .
eterrte
-ra.0w
~
j E 6 E d I i I i
?!st altts FIGURE 6C Core Pressure Drop - DECLG (C = 0.8) i D
- l. -
I- . 6 c. b i
. . 8 e .
CLA0AVERAGETEMPERATURE}iOTR00(OF)
. - - M N .
d O Ut O
- O O O O O o o o o l
t I . I . . 4 SEE. g "t3
- CD w .
O *
- g Of a Q.
H M t
,B a 8 -
CD = 1 % . 09 m m r+ w . C O ^ . M C tse .m . . G. M m M. v.e . m n vi e N o J C > .= g rT1 O M F . O C4
^ o ~
g C . . . II O M v + 8 Q V * . O Q
CLA0AVERAGETEMPERATUREHOTROD(OF)
" ~ N N B @ O un O
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M N
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I- . . (D CW . X (") a e O. -
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~=
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p O o m
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ll C
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- e~ a u.
p LL2.
+3 to I 5.
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. N .
U
=
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' O.
- C
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.I I I I O O 8
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.:P m
e.
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m e a c <mw v c o o a w a
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mn. m s. k w u. = J s 4,o W s. G) o a.
. - o .
N y . r
/ -
5
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i __
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. o o o o o o o o o o m o m o m o W 8
g 3_ .m .n . - o s .
= " .
(do) 3HMYH3dH3101fn3 . , . e
- N
e Foto.S CD e e.g'egggg grrgent AB af fnOf .. FLUID ftMPleAtunt aussi. 5.00 ris a PIAE. s.sv eitos - c sm.0 O *
= rso.e .
o j
~
sno.o
\_ ;
r 1 E
~
em.e -1 e [ . N , 5
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m .co . soa.co . '! N ; ma . -- , s.s =>"en
/
- 8 8 -
8
. I. , a.
4 2 - . B $ g trat istes i _ P
, 3 FIGURE 8B l
Fluid Temperature - DECLG (C = 0.6) D ,
- i i
I 4 ? I 8 4 I g .
- g
4908.8 CD e 8.8 t! ctg WPPite[as at test But1T. 5.75 fit a PC AE. 8.C0 rises FtVID TIMPts&futt C 1738.8
- r
.a
** Dee.e 1F50.8
= -
t g seco.s l
\t_
-\L a
E 750.00 , -
. \
W# h.
^^^
g*A,ge -
'e rei r*,
gj ,
~
k k k *
.k 8 0 E E E ! i TINC (St,CI
~
. . FIGURE 8C- .
/
Fluid Temperature - DECLS (C = 0.8) D
. i l
t, '
. - :: l i
7000 1 5000 _ 2500* S CORE TOP l 5
.a 1
. ~ . .
a . . y , CORE BOTTOM . N
-2500 -
i
. i
-5000 -
i
- i i
-7000 ' ' '
0 10 20 30 TlHE(' SECONDS) Figure 9A Core Flow - Top and Bottom - DECLG (CD = 0.4) I i l 8 I i
~. .
/ . .
o i FocJ.0 , , l CD e e. watts strtomfA0 Af fue? .
.I t fl0wsAft Coat 30ffen' s: for . to !.
I t i secs.s 1 5 t, 3 n
, rus.o ,
G , 1 . ' ,
^ ^
e.s _ m p - ~
=n00.0
. i
-sece.o t
~
> sin,n
.,00 i
I i I i 4 c R z I f
. fint attes , l I
FIGURE 9B - Core Flow - DECLG (C D = 0.6) l t a g . l l 6 I. g..
-. - ~ . - . . .
N. N. -
/. -
s
/ .
t . 7tlCO.9 s . to = 0.8 Cttts tertautap at Tuoi 2-fievaart Coat scTTon as f or. . to t 5000.9 0
- g. '
e . y tun.e n a c' -
.:. g
** y _ p ~
-esos.e r~
. 6e
.,,aa,, ,,,e,,,
2 l 4 I 4 I d I i I d Tint istti FIGURE 9C ! Core Flow - DECLG (C D - 0.8) e t ri t
.=
- w
. I 20.0 17.5 -
.E .
15.0 - A."
, p I2.5 -
a - w g 10.0 - a g 7.5 - gc. , 5.0 -- 2.5 - 0 0 100 200 300 110 0 500 TIME (SECONDS)
. FIGURE 10A Reflood Transient - DECLG (CD= 0.4) Downcomer and Core Water Levels ,
e
' ~ ~ ~ - - - , . _ , ,
20.0 . 17.5 . -., z, 15.0 - g- 12.5 __ ci [G 10.0 - a g 7.5 - Z
- C d 5.0 -
2.5 _.- i o I I I
~
0 100 200 300 400 500 TIME (SECON63) FIGURE 10B Reflood Transient - DECLG (CD= 0.6) Downcomer and Core Water Levels ,.
. a g
. : - n t
20.0 17.5 - . i i l 15.0 - o 12.5 - e 7u. , s W 10.0 - w - ' oc w . g 7.5 - x , l,7 - I 5.0 - c . 2.5 -
.0 I l 0 . 100 -
200 - 300 1100 500
, TlHE(SECONDS)
FIGURE 10C . Reflood Transient - DECLG (CD= 0.8) Downcomer and Core Water Levels
e ,t e
.- .0 .
b O g O
. e .
2.00 e 1.75 - - 0 i.50 - 4 . _ s= w u 1.25 - - C 5 w I.00 - . '
=C * . tu ,
8 0.75 - S m 0.50 - 0.25 - 0 I 1 I i - 0 100 - 200 , 300 1100 500 TlHE(SECONDS) FIGURE 11A Reflood Transient - DECLG D(C = 0.4) Core Inlet Velocity I
~.-_,
= *
- ee
*s
. o o
sn
. o O
. t y
. 4
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m
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.
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m O
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. g "w d.
O & !! g W LLJ Q M CX U w D v C3 W w e
*Z L w
- U
. W. LAJ o O
- O g M
4 e
~ C O
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. C
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F-
. . . .zy o
O O O CC
. - o 5 -
W ... - .- . . . . . , o 8 Ln o an o m o an o an. N. N k.m O. N. sn. . N - - = O o o (03S/1)3.LYH00073 -
- e
2.00 l 75 - l.50 - 3 . . g u -
. M l.25
~ .
5 s i.00 -
.= .
g i . v i,, . 3 0.75 m 0.50' - 0.25 , I l 1 - 1 I 9 O 100 200 300 110 0 , 500
, TlHE(SECONDS) ,
FIGURE llc Reflood Transient - DECLG D(C = 0.8) Core Inlet Velocity' ., ,
. ..)-
- 10000 8000 -
E w
. =
d 6000 - x o J . . o w w .
- 4000 -
~ .
8 u
, 2000 -
e n
'l J l 0 10 20 30
. TlHE(SECONDS)
FIGURE 12A Accumulator Flow (Blewdown) - DECLG (C D = 0.4) 3 f 8 1 e
' - * * ' a-so.., , _ ,_
1.8EIa04 Cp = 0.s OttLC SPF[8m( AS Af IM0f
- ACCUM. FLO W c.
y m.o e . g sac.s .
=
=
m .o , r:xm.o M. [ a E e I g I-a c rixt iste
. FIGURE 12B - -
Accumulator Flow - DECLG (CD = 0.6)
,aw g, ,
. I i
I
?
e .-- I 1 4 9 ~ .. . . .
. . 6 1.m c
. CD e 0.0 Ottts 'g*Ptemt D af fm0!
- ACCUN. FLOW
{- exo.e e . m i
~
= s:co.e O N
- r sooo.e enco.e e., , ,,o n 3
[ s I-i I d I i f i
. TIMI titCl .
FIGURE 12C . Accumulator Flow - DECLG (C D
- 0.8) l i .
I 1 I e
- a. ..
D
8 E 6. - . . m 8" 3 w
. l
- m I
x 'l -
) ~
e . I
= .
l
@ l ,
m i . a2
. l .
o l : I ' I I I I i l i
. 0 ,
.. 0 40 80 120 160 200 I 240 280 TlHE (SECONDS)
FIGURE 13A
. Pumpe.d ECCS Flow during Reflood - DECLG (C = 0.4) .
D ..w, . . . . .- ~ .-
O
. r o f 2
- O
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~
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O 5 10 15 20 25 TlHE (SECONDS) . FIGURE 15C Core Power Transient - DECLG (C D = 0.8)
e
. 4
. 1 I
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3.00 i [ CW m .h - 3~ 1.00 - CO w
~
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. W g . .
w -l.00 -
~
w - auf W . CC
-3.00 -
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~
i TlHE.(SEC0HDS) FIGURE 16 Bre&k Energy Released +0 Containment - DECLG (C = 0.4) "}' D. e
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