ML20244A616

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Responds to NRC .Forwards Reanalysis of Effects of Major Loca.Requests Permission to Remove Present Administrative Limit of 2.31 & to Restore Existing Tech Spec Limit of 2.32
ML20244A616
Person / Time
Site: Beaver Valley
Issue date: 05/07/1979
From: Dunn C
DUQUESNE LIGHT CO.
To: Schwencer A
Office of Nuclear Reactor Regulation
References
TAC-7861, NUDOCS 7905110011
Download: ML20244A616 (86)


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Duquesne U@t m m._

435 Sixth Avenue it urgh, Pennsylvania 7

Director of Nuclear Reactor Regulation Unisted States Nuclear Regulatory Conmiission Attention:

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Schwencer, Chief Operating Reactors, Branch No. 1 Division of Operating Reactors Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 Appendix K LOCA Analysis Gentlemen:

Enclosed are three (3) signed originals and thirty-seven (37) copies of a reanalysis of the effects of major loss of coolant accident on Beaver Valley No. 1 Unit.

This reanalysis hac been performed in respcuse to your letter of September 13, 1978.

During this interim period, we have administratively limited the allowable value of F to 2.31.

The results of this reanalysis disclose that the peak clad temperature that will be achieved subsequent to the most limiting break, the size of which has not changed, is 2123.7 F.

Since this value is less than the 2200 F licit permitted by Appendix K to 10CFR50, we request that permission be granted to remove the present administrative limit of 2.31 and to restore the existing Technical Specification limit of 2.32.

Very truly yours, 4

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C.

N. Dunn Vice President, Operations 0

Enclosure 0

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A. Schwencer Appendix K LOCA Analysis May 7, 1979 (CORPORATE SEAL)

Attest:

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S'taan Secretary COMMONWEALTH OF PENUSYLVId!IA)

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COUNTI OF ALLEGHENY

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On this r9 ^-

day of

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1979, before me, EP!R'( G, STOECKER

, a Notary Public in and for said Common-I wealth and County, personally appeared C.

N.

Dunn, who being duly sworn, deposed, and said that (1) he is Vice President of Duqueune

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Light, (2) he is duly authorized to execute and file the foregoing d

Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.

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D HPdY C. STCECMEP,,htary Pu' cc Nuer:1, M:etheny Cce,ty, Pa.

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(412) 471-i300 435 Sixth Avenue Pittsburgh, Pennsylvania 15219.

May 7, 1979 Director of Nuclear Reactor Regulation l

Unisted States Nuclear Regulatory Commission l

Attention:

A. Schwencer, Chief Operating Reactors, Branch No. 1 Division of Operating Reactors Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334 J

Appendix K LOCA Analysis Gentlemen:

l Enclosed are three (3) signed originals and thirty-seven (37) copies of a reanalysis of the effects of major loss of coolant accident on Beaver Valley No. 1 Unit.

t 1

l This reanalysis has been performed in response to your letter of September 13, 1978.

During this interim period, we have administratively limited the allowable value of F to 2.31.

The results of this reanalysis disclose that the peak clad temperature that will be achieved subsequent to the most limiting break, the size of which has not changed, is 2123.7'F.

Since this value is less than the 2200*F limit permitted by Appendix K i

to 10CFR50, we request that permission be granted to remove the present administrative limit of 2.31 and to restore the existing Technical Specification limit of 2.32.

Very truly yours, f

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7 C. N. Dunn l

Vice President, Operations I

Enclosure l

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+A. Schwencer i

Appendix K LOCA Analysis May 7, 1979 (CORPORATE SEAL) i Attest:

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H.W. S'taas Secretary COMMONWEALTH OF PENNSYLVANIA)

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COUNTY OF ALLEGEENY

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M.6d

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day of h

1979, before On this ma,

HENRY G. STOECKER

, a Notary Public Tn and for said Common-waalth and County, personally appeared C. N. Dunn, who being duly cworn, deposed, and said that (1) he is Vice President of Duquesne Light, (2) he is duly authorized to execute and file the foregoing Submittal on behalf of said Company, and (3) the statements set forth in the Submittal are true and correct to the best of his knowledge, information and belief.

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HENRY G. ST0ECKER, NMary Public I

Pit:4turgh. Megheny Ccunty, Pa.

lay Commissicn Expires February 20,1982

LOCA REANALYSIS 2

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3 The Loss of Coolant Accident (LOCA) has been re-analyzed for Beaver Valley Unit 1.

l The following information amends the Safety Analysis Report section on Major Reactor Coolant System Pipe Ruptures.

The description of the various aspects of the LOCA analysis is aiven in WCAP-8339[2]

The individual computer codes which comprise the Westinghouse Emeraency Core Cooling System (ECCS) evaluation model are described in detail in separate reports b'0]along with code modifications specified in references 7,10, and 11.

The analysis presented here was performed with the February 1978 version of the evaluation model which in-cludes modifications delineated in references 12, 13, 14, and 15.

I Resul ts 1

The analysis of the loss of coolant accident is 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 2.

Since there is margin between the value of peak linear power density used in this analysis and the value of the peak linear power i

density expected during plant operation, the peak clad temperature calculated in this analysis is greater than the maximum clad temperature expected to exist.

Table 1 presents the occurrence time for various events throughout the accident transient.

Table 2 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 2 for the br9ak analyzed. The location is indicated in feet, which presents elevation above the bottom of the active fuel stack.

I j

Table 3 presents a summary of the various containment systems parameters and l

structural parameters which were used as input to the C0C0 computer code used in this analysis.

Tables 4 and 5 present reflood mass and energy releases to the containment, and I

the broken loop accumulator mass and energy release to the containment, respectively.

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l The results of several sensitivity studies are reported [8I.

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 principal parameters for the limiting break.

The following items are noted:

Figures 1 - 3:

Quality, mass velocity and clad heat transfer coefficient -

for the hotspot and burst locations.

Figures 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 the core inlet to the pressure just beyond the core outlet.

Figures 7 - 9:

Clad temperature, fluid temperature and core flow.

The clad and fluid temperatures are for the hot spot and burst locations.

Figures 10 - 11:

Downcomer and core water level during reflood, and flood-ing rate.

Figures 12 - 13:

Emergency core cooling system flowrates, for both accumulator and pumped safety injection.

Fi.gures 14 - 15:

Containment pressure and core power transients.

Figures 16 - 17:

Break energy release during blowdown and the contain-ment wall condensing heat transfer coefficient.

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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 EI) presented in 10CFR50.46 That is:

1.

The calculated' peak clad temperature does not exceed 2200 F based on a total core peaking factor of 2.32 2.

The amount of fuel element cladding that reacts chemically with water or steam does not exceed 1 percent of the total amount of Zircalloy in the reactor.

i l

3.

The clad temperature transient is terminated at a time when the core geometry is still amenable to cooling.

The cladding oxidation limits of 17% are not exceeded during or after quenching.

4.

The core temperature is reduced and decay heat is removed for an I

extended period of time, as required by the long-lived radioactivity remaining in the core.

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r References for Section 15.4.1 j

1.

" Acceptance Criteria for Emergency Core Cooling Systems for Light Water Cooled Nuclear Power Reactors",10CFR50.46 and Appendix K of 10CFR50.46.

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-8302 (Proprietary Version),

WCAP-8306 (flon-Proprietary Version), June 1974.

4.

Bordelon, F.M., et al., "LOCTA-IV Program:

Loss-of-Coolant Transient Analysis", WCAP-8301 (Proprietary Version), WCAP-8305 (Non-Proprietary Version), June 1974.

5.

Kelly, R.D., et al., " Calculational Model for Core Reflooding after a Loss-of-Coolant Accident (WREFLOOD Code)".

WCAP-8170 (Proprietary Version),

{

WCAP-8171 (Non-Proprietary Version), 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., "The Westinghouse ECCS Evaulation Model:

Supple-mentary Information", WCAP-8471 (Proprietary Version), WCAP-8472 (Non-Proprietary Version), January 1975.

8.

Salvatori, R., " Westinghouse ECCS - Plant Sensitivity Studies", WCAP-8340 (Proprietary Version), WCAP-8356 (Non-Proprietary Version), July 1974.

9.

Deleted 10.

Letter from C. Eicheldinger of Westinghouse Electric Corporation to D.B.

Vassalo of the Nuclear Regulatory Commission, letter number ftS-CE-924, J

January 23, 1976.

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Attached in Appendix A, are the results of a generic sensitivity study for a typical 3-loop plant with 17 x 17 fuel.

This sensitivity study was performed to demonstrate that the limiting break does not change due to a correction in the metal-water heat of reaction calculation which is included in the February 1978 version of the Westinghouse ECCS evaluation model.

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 I

Since this agrees with past sensitivity studies [ 8 ] only the limiting of 0.4.

break for Beaver Valley Unit 1 is printed here.

i I

l 11.

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, 1978.

]

12.

Eicheldinger, C., " Westinghouse ECCS Evaluation Model, February 1978 Version", WCAP-9220'(Proprietary Version), WCAP-9221 (Non-Proprietary Version), February,1978.

13.

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.

i

-14.

Letter from T.M. Anderson of Westinghouse Electric Corporation to Tedesco of the Nuclear Regulatory Commission, letter number NS-TMA-2014, December 11,1978.

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NET FREE VOLUME 1.89 x 10 ft l

INITIAL CONDITIONS Pressure 9.5 psia 0

Temperature 90 F RWST Temperature 40 F Outside Temperature 35 F i

SPRAY SYSTEM Number of Pumps Operating 2

Runout Flow Rate 2200 gpm/ pump Actuation Time 55 sec l

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TABLE 3 CONTAINMENT DATA (continued)

U STRUCTURAL HEAT SINKS Wall 2

Number Material Thickness (ft)

Surface Area (ft )

1 Concrete 0.5 6,972 2

Concrete 1.0 77,446 3

Concrete 1.5 36,848 4

Concrete 2.0 17,010 5

Concrete 3.0 8,632 6

Carbon Steel 0.03125 18,270 Coacrete 4.5 7

Carbon Steel 0.03125 32,445 Concrete 4.5 8

Carbon Steel 0.04167 26,250 Concrete 25 9

Concrete 2.0 13,125 Carbon Steel 0.03125 Concrete 10.0 10 Stainless Steel 0.06875 3,270 11 Carbon Steel 0.02202 10,750 12 Carbon Steel 0.06242 748 13 Carbon Steel 0.1932 2,132 14 Carbon Steel 0.1833 5,479 l

15 Carbon Steel 0.0893 3,770 1

16 Carbon Steel 0.1041 10,938 17 Carbon Steel 1.020 600 18 Carbon Steel 0.0119 118,091

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(1) All walls are painted with the exception of walls 9 and 10.

The thickness of paint is 5.0 mils for all painted walls with the exception of wall 11, which has a paint thickness of 3.75 mils.

TABLE 4 REFLOOD MASS Afl0 EllERGY RELEASE TO THE C0flTAIflMENT DECLG CD = 0.4 i

Time Mass Flow Rate Energy Flow Rate (sec.)

(ibm./sec.)

(BTU /sec.)

40.67 0.0 0.0 41.25 0.88 1134.93 46.79 36.88 47819.58 55.86 183.90 132247.29 69.76 271.95 150274.85 87.06 293.70 149966.30 106.56 302.21 145462.49 127.96 308.71 140313.27 175.76 320.34 129206.29 231.76 332.28 117166.12 299.66 344.82 105614.94 i

TABLE 5 BROKEN LOOP ACCUMULATOR MASS AtlD ENERGY RELEASE DECLG CD = 0.4 Time (sec.)

Mass Flow (ib./sec.)

Energy Flow (BTU /sec.)

0.0 6214.2 251251.6 1.0 3790.5 225992.3 2.0 3478.0 207361.9 3.0 3232.9-192745.6 l

4.0 3033.8 180879.5 5.0 2867.8 170978.2 6.0 2725.6 162504.8 7.0 2602.1 155139.3 8.0 2493.2 148645.7 9.0 2395.4 142815.7 10.0 2306.8 137536.4 11.0 2226.2 132731.1 12.0 2152.4 128331.7 13.0 2084.3 124267.4 14.0 2021.2 120508.3 15.0 1962.7 117021.3 16.0 1908.2 113769.6 17.0 1857.1 110721.7 18.0 1809.4 107878.2 19.0 1765.8 105281.5 20.0 1726.0 102908.0 21.0 1689.2 100715.9 22.0 1654.7 98659.0 23.0 1622.4 96731.9 l

24.0 1592.3 94936.5 25.0 1564.2 93257.8 26.0 1537.6 91677.2 27.0 1685.8 91573.3 29.15 0.0 0.0

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I APPEf1 DIX A Generic Sensitivity Study Results for a 3-Loop Plant with 17 x 17 Fuel

4 's TABLE 1 O Large Break Time Sequence of Events

  • CD = 0.8 CD = 0.6 Co = 0.4 DECLG DECLG DECLG (Sec)

(Sec) (Sec) O. O. O. START Reactor Trip Signal 0.483 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 C ~ .,,g e a / a e e e 4 W i: e j l

4 0 kna ) = t m 5 t r D 3 5 6 5 3 0 2 f r o C 9 t t / e f 7 7 7 0 0 6 1 W W w p i 2 3 M M k n G t u L e ( C e E 5 f t D n 5 0 6 c e 7 1 7 1 i A c 2 2 1 b I r u S e c P p f f 6 o o 0 0 3 0 0 % 0 0 2 2 0 6 0 0 1 = 1 1 6 5 9 5 3 8 0 D5 S C 0 7 4 7 0 G 6 T 2 ( 2 L U G S L E 1 C R E D D N n A o i T g U e P R N 2 I 3 E S 0 L I B S A Y 5 T L = 5 7 S. 0 7 3 7 RN D 7 A C 3 7 2 7 0 5 6 1 5 G K' g L A n C E i E R t D B ar ) E e 1 G p l ( R O e ) A v n L s e e o ( p L l i s m c t n n u g y c o o P n C a i ) i - i e t s t g n g ) R c d a n r o g F a n l i o e i u r e o u t t m t l ( ) e ) R c ) c a c u c P t t t e t l R a l e e e a e r s e a F o e j e r e W e e ( e C r V r n b u f / f t f e g u I u t ( d ( a e ( e w n r r s T - a a W m h o i e e s y r n l n / i n t P k w t e t r s e o C o d T o a o a r e o r p i i a i n e e P W P f t e m t l t l t t i r P a a t e a a a C s a o r r r S r e T c c c r c s C e a o o e m o o o e u o e r e t t f n a d L L L r B L i d o n a a o e r a o t e C i l l G a 3 m C d l f i s L u u r P t C u o m l R t n l m m e m l n e a k u u b a l u k i a a c t a c c m e e s a x t t u i o e c c u t u e e a o o Q L T P A A H S F R P M T H

TABLE 3 ACTIVE HEAT SINK bATA l FOR MINIMUM POST-LOCA CO:iTAit.;4ENT PRESSURE I Containment Spray System' Parameters A. Maximum spray system flow, total 6,000 gpm i B.- Fastest post LOCA initiatior. of spray system Assuming off-site power loss at start of LOCA 50 sec II Fan Coolers A. Maximum number of fan coolers operatinc 4 B. Fastest post LOCA initiation Assuming off-site power loss at start of LOCA 108. sec () 'C. Performance data U See Figure 6.2.1-40 for fan cooler atmosphere heat removal rate Fan c'oolers are cooled by the reactor plant component cooling water system. II Reactor Plant Component Cooling Water System 'A. Maximum number of CCW heat exchangers used 2 B. Maximum CCW heat Exchanger UA 8.00x106 Bhi/hr ft C. Maximum CCW flow per flow path 12,800 gpm D. Lowest normal service water temperature 50 F E. Maximum service water flow per CCW 16,000 gpm heat exchanger t e s

f.. ,4, * [','. '.* l,'., TABLE 3 - C0tlTIt!UED o L." PASSIVE HEAT SINK DATA FOR MINIMUM NdT-LOCA CONTAINMENT PRESSURE f: A. Heat' Sink Description Slab Slab Material Surface Number Description, Material Thickness (in) 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. Interna. . Concrete Concrete 12 160.000 4. S tr uctu r al Carbon 0.044 68,955 Concrete Steel 0.054 11,309 0.074 55,164 0.168 11,033 0.282 16,156 ~ 0.336 68,955 O.431 690 0 0.672 132,394 1.345 10,343 5. Containment 3". Conc r e t e 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 and Personnel Hatchs B. Ther'mophysical Properties Thermal Density Specific Heat Conductivity 3 lb/ft.' Btu /lb F . Btu /hr-ft F C Concrete 145 O.156 0.92 Carbo'n Steel 490 0.12 27.0 ) l j

TABLE 4 = 0.4 DECLG REFLOOD MASS / ENERGY RELEASES C D Time Mass Flow

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(sec) lb/sec Btu /cee 0 37.031 0 37.806 .000551 .60515 38.106 .53389 6.97779 x 102 41.738 34.19009 4.46906 x 104 50.734 207.14 1.35096 x 103 66.434 250.01 1.40361 r. 103 5 86.234 2'66.10 .1.38578 x 10 108.934 275.95 1.35234 x 103 5 i 1.30939 x 10 133.934 284.55 5 192.334 300.83 1.21454 x 10 268.234 322.01 1.11802 x 105 435.334 349.72 1.00680 x 103

  • A,ccumulator nitrogen was released between 48.0 and 68.0 seconds at a mass flow rate of 192.27 lbm/sec.

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TABLE 5 FM 4

-7 BROKEN LOOP ACCUMULATOR !! ASS AND ENERGY RELEASES TO Cot 1TAINMENT FOR LIMITING Ca.iE - DECLG (C D" 0*4)

I Time Mass-Fl'ow* Energy Flow i (sec) lb/sec Btu /sec l 0.0 4600.1 2.741637 x 105 2.0 3771.8 2.247966 x 10 5 4.0 3280.6 1.955220 x 10 5 6.0 2942.6 1.753775 x 103 8.0 2689.7 1.603067 x 10 5 10.0 2488.5 1.483139 x 105 13.0 2251.6 1.341939 x 10 5 l 16.0 2068.9 1.233066 x 103 20.0 1889.8 1.126317 x 10 5 24.0 1756.9 1.047135 x 10 5 24.829 1756.9 1.047135 x 10 5 C

  • Enthalpy of accumulator water is 59.60 BTU /LBM.

g 9 t e e s = e e 9 i 0 6 a 9 g C t b ---__~----_o..-________

11ilj' \\ s ~ .,i.- ~ ^ i, O 30 1 ~ s 2 ~ 2 0 ) 1 4 0 G = D s C ) G LCE D s._ 2 ) S y D t N i l o a u C Q. E 'o S i ( d / V iu \\ E o l M F I T s A 1 eru 2 g i F 5 2 6 o t s 5 7 w 2 ~ I -o i 0 5 0 5 0 s O 1 2 0 7 s. 2 1 0 0 0 l l 1 O _> h oxw { g d u_o > C g g 1l l ?t W

." % -' ' - - '~' ~ a--- ~ -~ ~*** * .a.s....-.-..--. ' ~. ~ ~. ~. ~ ~. = ,,,,_..., i....

  • 5 l

_, f, es .i y .1.4000 ~CD e 9.5 CECtG UPP( AME AD Af fM07 OVAtlff CT FLUID $Ut$1. 6.C0 ff t a Pf AE. s.0c rTles '1.2100 C r

  • t. cogs 1

1 2 y 0.n00 j l? t f s a / . g e.5000 jy 7 0 0.2100 8.t d* E*dd N O I 4 4 4 d d d ddd 4 a o**** TIMt (SEC) Q i l 1 t Fluid Quality DECLG (C = 0.6) D Figure 1 B f

~ s *.. e l P., i -.l g h4 l CO

  • 0.0 0(Ctt UP CoAun., rm0

..,r a s. t.A D,, A,t T N 0 7,, A.,...,......-..- lu f. n, 1st100 u_ j C5 e .r J ~-1.0000 '}, I e 'h p0.F500 ,/ \\,( ,,1 m r, 17, g / A }. =..sco. / 1 e, I, 1; e.4 1-h hhhhhct I I $ $ $$$<N k @ @ @ @828 4 ; d a g,. f g d y g'pg'd g g 8. g.g ypp] 4 ei ' 4 444446 4 4 T!dt t$tC) i g: i. 1 s -i Fluid Quality DECLG (C = 0.8) D Figure 1 C l l I 1 1 1 k l o

] I11!I i

1) 5 o

3 0 1 5 2 I 20 ) 1 4 0 = I D 5 C ( I G L C -,. ED 2 I ) A y S t D 2 c i N o ~ O e l C r e I 0 E u V l S g s 1 ( 1 i s F a E M M I I 5 T l '5 7 2 { 00 l 1 l '5 ] 2 5 6 ] 2 l l -n i 5 0 5 0 5 0 5 0 7 5 2 2 5 7 I 1 p GMjCAa GSW $I e ~ ~ [i I

.~ ' ~, 6 -- C _, ....__.,_.s u N N,N.. 100.00 / CD e 0.6 otCtG \\PPtte:!ADAfin0f .af MAS $ V(LOClly gyt$f. 6.00 fit 3 P(AEe 8.00 FTN O 75.tc0 'e*b } e $ 52.C93 i 25.0 3 / E-M \\ ~ 0.0 em r \\ ~' s ~ 4 b-

  • y m.M T

o ~ ' s0.000 C-csoo.co d n 4 4d4ddu 4 4

4. 4 d 4 M N

N I Ndd*M E ' E I E !!!h O. TIMt (SEC) l 1 I 4 i p l Mass Velocity DECLG (C = 0.6) l D Figure 2 B

s 's l s. I . L. j ) 1 ggglg$g*ci,,sOtttG ju'l,El,m,0 {yp,f ,,,, j,, y .t ,r =5 g is.co 3e wn.m S. l/ , / e= // o / u, w s 7 ./ y g e e.s <u \\} -100'.= I ~ .'em.= I 853 8 8 8 8*bwCCg 8 8 8 88888 8P93 [ 8,8,880d 8 *8 ep o o o o 8 gr ~

    • d g

i d, p d dd..w-p e ~ ~. t_.. w tsnt utes 9 Mass Velocity DECLG (C = 0.8) D Figure 2 C

m.,. 0 9 e e e 9 e a , es 4 \\ O e , s e W G A Q eo o B C $2.e ~ J O w Q W 5 o u ^ M o "a s q. g n v e3 e Ls.J s ("J .M 3 cn w O 3 I 9e r O R Y ~ h g 9 h l l 1 s ^ i i i l I i l I I Ii I I o n u O O O O C (do-8H7' 13/019) 1H310133303 83dSHYH1 1Y3H 4 L-_----

l

...;.;......-.....~....----,....----.~-~~---*-..~----u-I . 'i e ~,.,.. d 1 C. = - - :-:--- - =- --i, .q j l CDAo.8Cft'LC UPPERNI A0 At TMot ME AT f t Atl.C0tff!CIInf GUA51. 4.00 fit PtAE. 0.00 rTles %Q.G3 r 400.00 a 300.c0 % ta.co s' B e 5 hg'!ff M-b II i i r L

== 60.C.'0 i i D *A.000 ] g I $43.000 - j, i } 5 " ** l WK A_ +4 m h

f. N.DCC n

W u,e BY.. \\

  • LT i.

6.C.CJ I e 6 1.of.G0 uj 4.0000

s. coco l

i 2.0000 l. t a. l'W ^ l

  1. k k

g E B B B f!NE titCl Tl l, l Clad Heat Transfer Coefficient DECLG (C = 0.6) j D Figure 3 B

j r ? ~ s r e, j l' r O-a [ el co e 0.8 etcte uttravt Ao at fxof y (( ut At in Aus.cctrrtcttut tuali. 4.75 rit PC As. s.00 ritet g,co saa.co r +m.m a

0' i no.co

~ % ex.oo e h f. etp u .Ch $ 50.cM -l i i e es.cm 3^ gm.wo, y g a n.sw \\ ~ y t i !N ',/ s.co:o i s.wm

  • e.omo s

3,0000 2.0000 l1000o 8 8 8 8 8 E 'E I I E m r istc. / 1 Clad Heat Transfer coefficient DECLG (C = 0.8) D Figure 3 C tli __a

9 e ^;^r --- 3 d e e l OO O l g a gm.n N. O E O .O J O O ~ O uJ O g f -m 2 2: 3 W O Q 8 0 8 g s w w ay w .Z O. O$ ~ S 4 e O .O '\\ 4 e e m Q g 8 8 o O w a w a w N N (visa) 38nss38a C

e e f, ,4. .1 a8 O. i m I I 1 o y s d u O O 0 \\J - O Lu O b 7 o o u 2 $e o o W h o m .,o g w w O O. o / e i I i I I C O O o o o O o o o o u m o m o ~~ N N = (VISd)380SS38d C e e* t A

e D: f '.db??? j l j e W'* ) CM i O: i 9 { t i E i o d il C O I O .J W Q w ~ O e v 6 M w O T E 4 Z o c) o h O L A W 3 f/3 .o C w w O W 2 0"' _O 0 m W e C l O O O ( O \\ O o o o W Q W W N N (visa) sansssaa lC 4 e S e

t s 4 I 1 t 4 LO 1 ) i i 10.0 7.5 5.0 - -ous n 2.5 ~ m .J X O 0 oa u. x at W -2.5 m -5.0 -7.5 / l l -10.0 0 10 20 30 TlHE (SECONDS) C Figure 5 A Break F.sw Rate DECLG (CD=0.0

s - = 'A.-- i 1.00t *05 to e 0.6 OtCLC UPPtpWE AD AT IN07 St( AK ft0V T.we C %; s.mo l r.we .e e.s c.we 4 M e* y .f. M * ..we g a s-g e e a i n itur ucci Break Flow DECLG (C = 0.6) D figure 5 B 4 1


-- J' D

e .n e s. e 8 s e *. .- - ~.. y .a._ s / t / i.00C*05 to e 0.8 CECLC 'UPrtaxt40 At twof St( AE TLOV v.w+ 7 4. ene 9% enn

s.a+

b e.w* M 9 'Od = e.s i O we .s. m

  • l

.r. w e 4 1 I. - I. I.' I. .s e a e e g f!ME ISCC) Break Flow DECLG (C = 0.8) D Figure 5 C o n

6~......, m._ . _ _ _ _ _ _ ~ ~. ~; .eswe .i . O _ 4 s, l N.800 0.4 0(CLC C0st'Pa.0 top son. i 0% t s

i. n.coe

.~ t. %e e,e M 4 mv-s .esm 1 . O -som.

  • N.000 I

I I I ll d i i. i .i. nur istc .1 I l 1 Core Pressure Drop DECLG (C =00 D Figure 6 A i l 1 II p

r l-..--- ~ n s 4 70.000 ~~ 't o e 0.8 ottLG UPPI Aut AD Af TM0f t0at 98.0s09 10.000 E t E ts.000 R E so ( ~ ~ ~ 3s ~ .f5.000 s M.000

  • 10.000 E

E $e e e e flMt titCI Core Pressure Drop DECLG (C = 0.6) D Figure 6 B l 4 e D

= s i 1 a l 1 ] ......._.___.__i_._...__.__._...._,___, j -1 l { N.Ns s. 1 / ) i

70. M (D = 0.8 OfCLC UPP( ANI AD AT TH0T CORE PA.OROP g

I } w.= = r. C n.tco 9

t 8

^ 0.0 v- ~ } .n ow .w.coe .ro.000 / l E E d d i n

  • a s

TIMI istti Core Pressure Drop DECLG (C = 0.8) D Figure 6 C 1 l

'. e, s.

)

.. :.. : =. e + 0 + D f o m l l a o o =r o E l C 0 ) Ow O M e 2 o o n to E m es O h z m C T I, I o e n w L G 9 .m. 3 en x w E 2 w x 8 N f e b g e - 9 e f li j C O O O O 8 O O O O W C W e N CM = = Q (do) 00810H 38f11Y83dH3130VB3AV OY10 3 i 9 4 4 a l ___._--__m._m.____m._.

C. -~ ~ ~ .., ~.. a = " * " (( 1 1 o o D l l .m M a o o I = 0 1 9. i 0 J O uJ O \\ B g C E m 1 e G cc i' z N ,l n e a f4 L b ~ i g u. m e g g w a 2 o oo o N i o i o I i I l J e ~ g o o-o 8 g o o m w a a n (do)00810H3801Y83dH3130Y33AYC710 A

..m__ N.. f.. ~ e e d e 9 O t 4 6 8 8 G ( 9 e 8 m I o 7 l E j 8 s ~ W c) J N M L g h h i w N x w O, C = ~ %0 Cc --6 ~ O I I I I O O O O O 8 O O O O b N .=

ll( l [ 3 005 0 ) l 0 4 1 0 1 = D C ( G LC E D er 0 u 0 A l ta 3 r 8 e ) p 'S e m D r e N u T O g C 1 L' i d E F i S u 2 l ( F 6 5 E 7 M f I / T 0 0 l 2 L 0 ] 0 1 w i i.' 0 0 0 0 0 0 0 0 0 0 0 5 0 5 0 5 0 5 0 7 5 2 0 7 5 2 1 1 1 1 2 ~,:O 5 5 M o_ad ua O I l l l

b s a s .. J.. *. s 4 \\ w.

L._
  • ~~'~~~~L

~ 2 NO3.0 C0 = 0.C'OtCLC 'UPPth( AD af TM07 FLUlO TEMPER Atua[ BUR $T. G.00 rit i P(AK. t.sv viol C !?$2.0 C a y r500.0 s 1250.0 r g(l E t*40.0 - ?) i "g no.m 7 I {sw.= rw.m ^ ~ u / 8 8 8 8 8 0 4 E E E 6 TIMt ($(C) p Fluid Temperature DECLG (C = 0.6) D Figure 8 8 i i i l

l i - C =. 1 p 1 eam.e CD e 0.8 CICtt utPrant A0 Af TM0f nulo TIweta Atung suasf. s.75 nc : ttAa. s.co nio c m e.e i i 5

rsos.e 5250.0

-T 5 \\ \\ t = ion.e = e V. 1 / o y F50.00 I 1 . Moo 1 C 250.00 0.8 s s s 8 8 e i i R I R TIME t$t.Cl =1 i Fluid Temperature DECLG (C =0.8) D Figure 8 C l

i:. :- O 7000 5000 4 2500 S CORE TOP m %m 1 .J g 0 O cx:so a T CORE BOTT0H N -2500 -5000 I I -7dOO O 10 20 30 TlHE(SECONDS) 4 Figure 9 A Core Flow Top and Bottom DECLG (CD = 0.4)

D 0 e e g s o 1 ..,_....._,__.,__,___,,,__m_, s ~. %. N.' s /. j 7030.0 a } to a p.e pgCLC UPPf AN( A0 Af TWOf i g Mowa Aft coat gottom ta for. is) Soco.9 O C-Wd 11 y f500 0

i l

<e 3a a .Y. g- ^ ae p L .csec.0 4 5ccc,0 -1000.0 e f I. I. I. I e d E C 2 d TIMt ($tt) P e Core Flow DECLG (C = 0.6) D Figure 9 B O n j

4 'i* e

  • ?

s s o_ e,

0

.g '1 j -~ ~ - - _.. . _ _. _ ~ ~ - -,~.... ,Wi p. N /. .3 a e d \\ 7000.0

  • kB*0.4C(Ctc

'uP7( AW( A0 At TWOf l fl0VR Af( COAC 80ff 0M i) IOP e (et _ 5000.0 ..i eseo.s e E .F. 4 Q,,, _ -n V _ m +- .eseos /~ l ..soon.e .roco.e E I I I E s a c g g j e l ?!Mt (S(C) 1 Core Flow DECLG (C 0.8) = D Figure 9 C

  • I q

e ij\\il)l ,L I 00 5 e roC dn a re mo cn w 0 o l 0 D !t )4 0 = D C ( G L CED 0 l 0 t 3 A n e i ) 0 s S 1 n s D al r e N e O r Tv e C u dL E g o r S i o ( F e lf te a E RW o M h. I h M K T 0 i 02 0 I 0 1 0 0 5 0 5 0 5 0 5 0 0 7 5 2 0 7 5 2 1 1 1 1 2 pu_ " s *- " 5p5 i h l l 1 ll1lll

~ 0 0 1 4 0 1 0 3 ) S 6 N O C E S ( EM o I Z T 00 i 2 C Z 0 0 I 1 0 0 0, 5 0 5 0 5 0 5 0 7 5 2 0 7 5 2 1 1 1 1 2 pu. ica emOx G' A

8 8 e + 4 ,.3.. a ,..-e 'e e 6 o O* o m O i

  • =

1 O 3 O I C N I w 4J 4 E J 0 = uC 3o t O O m a COd s I i O O i 3 0 I O wO o e o ~ M C p O .I N a e o C i

2. a i

M E >T 1 o g . p'. o 5-ta 9 Q 3 0 w Ch og m E ~e - a n E O w Z o o N l O ed e . \\\\ o ~ 1 I I I i I i I o o. m. o. e. o. m. o. e. o N .o N m N o N m,- N Q (.u) mal um 4 0

  • 3

g [

c g.

00 5 9 y t i c o le V te ln I e r 0 o 0 C 11 ) 4 0 = D C ( GLCED 0 t 0 n 3 A , e i ) s S 1 n D 1 a N r O e T C r d E u o S g o ( i l F f e EM . R I T O 00 2 00 1 ~ 0 l 0 5 9 5 0 5 0 5 0 0 7 2 0 7 5 2 ( 0 0 0 1 I I 1 2 gv%x " mOa 8Su. O-w ~

4 s.T.m e e O O O.. m j c .c C z O ~ O ( =r c I h G c O O e M O 9 m V3 m - I O m 0 z Ic O e O L W D V) O 6 w +- W G z yc 8 N e O ~ O - --L. i i i I I I I C o m O m. O m o m o o. N. m. N. .O N m N e e o e O O O N (03S/NI)31V80001d O J e a

O 5 00 1 8 0 0 3 O 0 02 00 N 1 I y fh t ,.4 ,I } 0 0 5 0 5 0 5 0 5 0 0 7 5 2 0 7 5 2 0 0 0 2 1 I 1 l 7M~x-. W r E a 8a t. A O Ii lI 1 .(

- A a- \\ I .O 1 i ( 10000 8000 -oww %m .a. 6000 S u -o e L6000 a 58 u< o 2000 / I I O O 10 20 30 TlHE(SEC'ONDS) l 4 Figure 12 A -n Accumulator Flow (Blowdown). DECLG (CD =

~ L., l ~~ ' - ~ ~~'~~T.- -- 1 e a 'Cp e 0.8 otttG uff(RN( A0 Af fM07 J AttVH. (LOW c.

  • toco.0

= d n oe ~ g soco.o 4000.0 ~ o.... 09 I. I. I. I. g e c 2 c TIMt ($CCI p Accumulator Flow DECLG (C =0.6) D Figure 12 B

_--------_.T'~ l. a / ~. l, ',!. e i i e m G t 1.M * (0 s 0.0 0(Ctt 'UPPtautiO At tuot AttVM. (LOW ~~ ~ s enco.o at t ~ M.$ 4 N C#.. anos.e e.s I I. - 8 I. / I. .g g a c z c ?!Mt t$tC) Accumulator Flow DECLG (C = 0.8) D Figure 12 C 1 fl

p e 9 h 4 9 0 e S 4 e es

  • M e

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