EXPERIMENT DATA REPORT FOR LOFT NONNUCLEAR ...

TREE-N U REG-1 065 for U.S. Nuclear Regulatory Commission

EXPERIMENT DATA REPORT FOR LOFT NONNUCLEAR TEST L 1-3

GARY M. MILLAR

April 1977

n ~~ EGB.G Idaho, Inc.

IDAHO NATIONAL ENGINEERING LABORATORY

. .

ENERGY RESEARCH AND DEVEL<>PMENT ADMINISTRATION . ' ' . ._.

IDAHO OPERATIONS OFFICE UNDER CONTRACT EY-76-C-07-1570

QISTR~BUTIOI'I 0 U"E.NT IS UNLIMITE~~

f- THIS DOC WI

DISCLAIMER

This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency Thereof, nor any of their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness, or usefulness of any information, apparatus, product, or process disclosed, or represents that its use would not infringe privately owned rights. Reference herein to any specific commercial product, process, or service by trade name, trademark, manufacturer, or otherwise does not necessarily constitute or imply its endorsement, recommendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.

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Portions of this document may be illegible in electronic image products. Images are produced from the best available original document.

Pri nted in the United States of Ameri ca Avai lable from

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5285 Port Roya l Road Springfield, Virginia 22161

Price: Pr inted Copy $9.75; Microfi che $3.00

"The NRC will make available data tapes and operational computer codes on research programs dealing with postulated loss-of-coolant accidents in light water reactors. Persons requesting this information must reimburse the NRC contractors for their expenses in preparing copies of the data tapes and the operational computer codes. Requests should be submitted to the Research Applications Branch, Office of Nuclear Regulatory Research , Nuclear Regulatory Commission, Washington, D.C. 20555."

.-------------- NOTICE

This report was prepared as an account of work sponsored by the United States Government. Neither the United States nor the Energy Research and Development Administration , nor the Nuclear Regulatory Commission, nor any of their employees, nor any of their contractors, subcontractors , or their employees, makes any warranty, express or implied, or assumes any legal liability or responsibility for the accuracy, completeness or usefulness of any information, apparatus , product or process disclosed , or represents that its use would not infringe privately owned rights.

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EXPERIMENT DATA REPORT FOR LOFT

NONNUCLEAR TEST Ll-3

Approved:

~ I .. ..

L;· P. Leach, Acting Manager LOFT Experimental Program Division

,-.-----NOTICE-----~ This report was prepared as an account of wort 'POnsorr:ct by the United States Government. Neithet the Umted States nor the United States Energy ~arch and Development AdnUnistralion, nor any of theu emplovces, nor any of their oontructou subcontractors, or their employees, mates anY ~~nty, express or implied, or assumes any legal liability or responsib~ty for the accuracy, completeness or useful~ess of any mformation, apparatus, product or ~ro~ d~losed, or represents that its use would not mfnnge pnvately owned rights.

~·

-·DOCUMENT IS UNLIMITEQ OISTRIBUTION OF THIS .

4 -

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TREE-NUREG-1065 Distr1buted Under Category: NRC-2

Water Reactor Safety Research Systems Engineering

EXPERIMENT DATA REPORT FOR LOFT

NONNUCLEAR TEST L1-3

by

Gary M. Mi 11 ar

EG&G Idaho, Inc.

Apri 1 1977

PREPARED FOR THE U.S. NUCLEAR REGULATORY rQMMTSSTON AND

ENERGY RESEARCH AND DEVELOPMENT ADMINISTRATION IDAHO OPERATIONS OFFICE

UNDER CONTRACT NO. EY-76-C-07-1570

-ACKNOWLEDGMENTS

Appreciation is expressed to J. R. Chappell, L. D. Goodrich, G. Hammer, H. C. Robinson, T. K. Samuels, and the personnel of the LOF.T Data Systems Branch for their special help in prepari.ng this document.

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ABSTRACT

Test Ll-3 was the third in a series of five nonnuclear isothermal

blowdown tests conducted by the Loss of Fluid Test (LOFT) Program. For this test the LOFT Facility was configured to simulate a los·s-of-coolant

accident in a large pressurized water reactor resulting from a

200% double-ended shear break in a cold leg of the primary coolant system. A hydraulic core simulator assembly was installed in place of

the nuclear core. The initial conditions in the primary cool~nt system

intact loop were: temperature at 540°F, pressure at 2256 psig, and loop flow at 2.34 x 106 lbm/hr. During system depressurization, emergency core cooling water was specified to be injected into the lower plenum of

the reactor vessel using an accumulator, a low-pressure injection system pump, and a high-pressure injection system pump to provide data on· the

effects of emergency core cooling on the system thermal-hydraulic response. Injection into the lower plenum was initiated from the high

and low-pressure injection systems. Injection from the accumulator, however, was not initiated because a valve was inadvertently left

closed. The experimertt, therefore, was not completely successful in that one of 'the objectives outlined in the experiment operating

specification for this test was not accomplished. Test Ll-3 was repeated as Test Ll-3A to meet the experimental requirements. Despite these difficulties, .Test Ll-3 did provide very valuable data to verify

~xperiment repeatability .

i i i

SUMMARY

The intent of this report is to present selected data from LOFT Test Ll-3, which was performed as a part of the Ll (nonnuclear) series of LOFT Program tests. The ·data are presented in the form of graphs in engineering units for easy interpretation. In conjunction with the data obtained from direct measurement, chosen computed parameters are included to facilitate in the analysis of the system thermal-hydraulic behavior. Plots of representative instrument types and ranges and their associated error bands are also presented.

The Ll test series consists of five nonnuclear blowdown experiments which are initiated with isothermal conditions established in the reactor coolant loop. Test Ll-3, the third test in the Ll series, was conducted on June 28, 1976.

The LOFT Integral Test Facility is a highly instrumented, 'pressurized water reactor test system designed to be represent~tive of large pressurized water reactors (LPWR)·fo~ the simulation of loss-of~

coolant accidents (LUCA). lhe test assembly consists of:

(1) A reactor vessel with a hydraulic core simulator installed- 'in place of a nuclear core.

(2) An intact loop with active steam ·generator, pressuriz~r, and two primary coolant pumps connected in parallel.

(3) A broken loop with a simulated pump, a simulated steam generator, and two quick-opening blowdown valve assemblies.

(4) A blowdown suppression system consisting of a blowdown header, blowdown suppression tank, and a blowdown suppression tank spray system.

iv

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(5) An-emergency core coolant (ECC) injection system consisting of a low-pressure injection system (LPIS) pump, a high-pressure injection system (HPIS) pump, and an accumulator.

For the performance of the Ll-3 loss-of-coolant experiment (LOCE), the test assembly was configured to represent a 200% double-ended offset shear in a cold leg of a LPWR.

The areas of interest specific to Test Ll-3 were to evaluate (a) the effect of intact loop resistance on system thermal-hydraulic response by comparison with corresponding results from Test Ll-2 and (b) the effect on system thermal-hydraulic response by injection of ECC directly into the lower plenum of the reactor vessel~ To establish the imporfance of intact loop resistance, this test was conducted with . low resistance orifice plates insta1led in the steam generator which were based on core flow area scaling .. To specified to be directed to the accumulator ACC-A, HPIS pump A,

determine system response, ECC w~s lower plenum injection line using

and LPIS pump A. The accumulator injection failed to initiate; HPIS flow and LPIS flow were initiated at 32.6 and 37.5 seconds after rupture, respectively. This failure o~

accumulator injettion is not important to -future LOFT nuclear operat1on since the plant protection system (PPS) would have initiated all modes of ECC. The PPS was intentionally deactivated for the performance of this experiment.

Test Ll-3 was initiated from primary coolant system initial conditions of 2256 psig and 540°F with an_ intact loop flow rate of 2.34 X 106 1 bm/hr. The complete set of initial test conditions is specified in Reference 1 and is summarized in Table III of this report. Measured experiment conditions for Test Ll-3 were within their specified tolerance bands except that the intact loop flow rate was 2.34 x 106 lbm/hr instead of the 2.15 x 106 lbm/hr as specified. This

discrepancy did not adversely affect the experiment.

Data were successfully collected and processed from 512 of the 549

data channels utilized during Test Ll-3. Instrument malfunctions

v

pertinent to a particular data channel are specified in Table VI. Of the instruments which produced no useful data, none impacted the success of the experiment.

Test Ll-3 was not completely successful in aGcomplishing objectives as presented in Reference 1 and summarized in Section I

this report since. accumulator injection did . not initiate. experiment, however, did provide extremely valuable information verify. data repeatability for the same experiment conducted essentially the same initial conditions.

vi

the of

This to

from

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CONTENTS

ACKNOWLEDGMENTS i i

ABSTRACT.

SUMMARY .

I.

II.

I I I.

IV.

v.

VI.

VI I.

VIII.

IX.

1.

2.

3.

4.

. . .

INTRODUCTION.

SYSTEM. CONFIGURAfiON ..

MEASUREMENTS AND INSTRUMENTATION

TEST PROCEDURES . .

INITIAL CONDITIONS.

DATA CONSISTENCY CHECKS

· DATA PRESENTATION . . .

1. TEST Ll-3 MEASURED PARAMETERS SHORT-TERM PLOTS

iii

iv

1

. 6

12

30

35

41

51

(1 Second Or Less) ..... ; .. ~ . . . . . 101

2. TEST Ll-3 MEASURED PARAMETERS MEDIUM-TERM PLOTS (-10 to 70 Seconds). . . . . . . . . . . . . . 117

3. TEST Ll-3 MEASURED PARAMETERS LONG-TERM PLOTS ( 175- and 500-Second Plots). . 187

4. TEST Ll-3 COMPUTED PARAMETERS. 209

5. TEST Ll-3 ERROR.BAND PLOTS 241

REFERENCES ..•........

LIST OF ABBREVIATIONS AND ACRONYMS.

FIGURES

LOFT major components ..

LOFT piping schematic (with instrumentation)

Gamma densitometer beam configuration.

Gamma densitometer flow regime logic •

vii

264

267

10

11

14

15

5.

6.

7.

8.

9.

10.

11.

12.

13.

LOFT' thermo-fluids measurements instrumentation.

LOFT reactor vessel instrumentation.

LOFT pressurizer instrumentation ..

LOFT steam generator instrumentation

LOFT intact loop pump instrumentation.

LOFT accumulator instrumentation ...

LOFT ECC system instrumentation (left sid~).

LOFT suppression tank instrumentation ...

Determinat~ori O! time of rupture (T0) and vulve opemng t1mc I ~.I •••••••

TEST Ll-3 MEASURED PARAMETERS SHORT-TERM PLOTS (i SECOND OR LESS)

14. Valve opening (%) for broken loop QOBV, cold leg valve (CV-Pl38-l), and hot leg valve

19

20

21

22

23.

24

25

26

(CV-Pl38-15) . . . . . . . . . . . . . . . 102

15. Valve opening (%) for broken loop cold leg QOB~ (CV-Pl38-l) and cold QOBV inlet pressure (PT-Pl38-lll). . . . . . . . . . . . . . . 102

16. Valve opening (%) for broken loop hot leg QOBV lCV-P138-Ib) and hot leg QOBV 1nlet pressure (PT-Pl38-112). . . . . . . . . . . . . 103

17. Pressure in broken loop cold leg (PE-BL-1, -4, and -8) (filtered to 250Hz) . . . . . . . 103

18. Pressure in broken loop hot leg (PE-BL-2, -3, and -6) (filtered to 250Hz) . . . . . . 104

19. Pressure in intact loop cold leg, hot leg, steam generator outlet, and pressurizer (PE-PC-1 ~ -2, -3A, and -4) (filtered to 250 Hz) .. 104

20. Pressure in reactor vessel core simulator instrument stalk and downcomer instrument stalk 1 (PE-CS-lFF and -2FF and PE-1ST-3FF) (filtered to 250 Hz) .......... .

21. Pressure in blowdown suppression tank bottom, 180° from top vertical reference (PE-SV-1, -22,

. 105

-24, and -44). . . . . . . . ......... 105

viii

22. Pressure in blowdown suppression. tank bottom, 180° from top vertical reference (PE-SV-3, -26, -27, and -43). . . . . . . . . . . . .....

23. Pressure in blowdown suppression tank submerged, 112.5° from top vertical reference (PE-SV-2, -23,

106

and -25) · ..................... 106

24. Pressure in blowdown suppression tank submerged, 112.5° from top vertical reference (PE-SV-4, -28, and -29) . . . . . . . . . . . . . . . . . . 107

25. Pressure in blowdown suppression tank vapor space, 67.5° from top vertical reference {PE-SV-58 and -61) . . . . . . . . . . . . 107

26. Pressure in blowdown suppression tank vapor space, 45° from top vertical reference (PE-SV-57 and -59) . . . . . . . . . . . . . . . . ... 108

27. Pressure in blowdown suppression tank top, 0° from top vertical reference (PE-SV-17, -55, and -60) . . . . . . . . . . . . . . . . . . . . . . 1 08

28. Pressure in blowdown suppression tank submerged, 230° from top vertical reference (PE-SV-15 and -16) . . . . . . . . . . . . . . . . . 109-

29. Pressure in blowdown suppression tank header (PE-SV-14 and -18) . . . . . . . . . . . . 109

30. Pressure in blowdown suppression tank B-end submerged along vertical centerline (PE-SV-11, -13, and -27). . . . . . . . . . . . . . . 110

31. Pressure in blowdown suppression tank A-end submerged along vertical centerline (PE-SV-10, -12, and -24). . . . . . . . . . . . ; . . . . . 110

32. Pressure in blowdown suppression tank in a transverse plane, 316.5 in. from B-end reference (PE-SV-1, -2, and -58) . . . . . . . . . . . . . 111

33. Pressure in blowdown suppression tank in a tr·ar1sv~r·s~ pla.ne, 316.5 in. fron1 B-end r-efet'ence (PE-SV-15, -55, and· -57) ....... ~ . . . . 111

34. Pressure in blowdown suppression tank in a transverse plane, 263 in. from B-end reference (PE-SV-22 and -23) ............. ~ .. 112

35. Pressure in b1owdown suppression tank in a transverse plane, 263 in. from B-end reference (PE-SV-17 and -59) ..•....•...... 112

ix

36.

37.

38.

39.

40.

41.

42.

Pressure in blowdown suppression tank in a transverse plane, 28.5 in. from B-end reference (PE-SV-3, -4, -16,-60, and -61). . . ...

Pressure in blowdown suppression tank header snubber (end) (PE-SV-30) ......... .

Pressure in blowdown suppres~ion tank header snubber (end)' (PE-SV-31) ......... .

Pressure in blowdown suppression tank header snubber (bend) (PE-SV-45) ......... .

Pressure in blowdown suppression tank he~der snubbe1· (bend) (PE-SV~4G). . . .

Pressure in blowdown vacuum relief system rupture disc standpipe (PE-SV-54) .....

Pressure in bellows between broken loop and blowdown suppression tank header (PE-SV-70).

TEST Ll-3 MEASURED PARAMETERS MEDIUM-TERM PLOTS (-10 TO 70 SECONDS)

43. Density in broken loop cold leg, chordal density (DE-BL-lA, -lB, and -lC) (filtered

113

113.

114

114

115

115

il6

to 4Hz) . . . . . . . . . . . . 118

44. Density in broken loop hot leg, chordal rlPnc:;it.y (nF-Rl.-?A, -2R, and. ,2C) (filtered to 4 Hz) . . . . . . . . . . . . . . . . 1 18

45. Density in broken loop, average fluid densities. (DE-BL-1 and -2) (filtered to 4Hz). . . . . 119

46. Density in intact loop cold leg, chordal density (DE-PC-TB and -lC) (fi·ltered to 4Hz}. . . 119

4 7. Density in intact 1 oop hot 'I eg, chorda 1 density (DE-PC-2A, -2B, and -2C) (filtered to 4 Hz). . . 120

48. Density in intact loop at steam generator outlet, chordal density (DE-PC-3A, -3B, and -3C) (filtered to 4 Hz) . . . . . . . . ~ . . . . 120

49. Density in intact loop, avera~e fluid densities (DE-PC-2 and -3) (filtered to 4Hz). . . . . . . 121

50. Average fluid velocity in broken loop cold leg at OTT flange (FE-BL-1) (filtered to 4Hz) 121

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51.

52.

53.

Average fluid velocity in broken loop hot leg ~t OTT flange (FE-BL-2) (filtered to 4 Hz) ..

Average fluid velocity in broken loop cold and hot legs at OTT flanges (FE-BL-1 and -2) (fil-tered to 4 Hz) . . . . . . . . . . . . .

-Average fluid velocity in reactor vessel core simulator instrument stalk (FE-CS-1) (filtered to 4 Hz) . . . . . . . . . . . . . . . . .

54. Average fluid velocity in intact loop cold leg

122

122

123

at OTT flange (FE-PC-1) (filtered to 4Hz) . . 123

55. Average fluid velocity in intact loop hot leg at OTT flange (FE-PC-2) (filtered to 4 Hz) 124

56. Average fluid velocity in intact loop steam generator outlet at OTT flange (FE-PC-3) (filtered to 4Hz) . . . . . . . . . . . .... 124

57. Average fluid velocity ·in intact loop cold leg, hot leg, and steam generator outlet at OTT flanges (FE-PC-1, -2, and -3) (filtered to 4Hz). . . . . . . . . . . . . . . . . . . .. 125

58. Average fluid velocity in reactor vessel downcomer stalk 1, 47.1 in. above reactor vessel bottom (FE~lST-1) (filtered to 4Hz) ....... 125

59. Average fluid velocity in reactor vessel downcomer stalk 2, 47.1 in. above reactor vessel bottom (FE-2ST-l) (filtered to 4Hz) .... 126

60. Average fluid velocity in reactor vessel downcomer stalks 1 and 2, 47.1 in. above rear.tor vessel bottom (FE-lST-1 and FE-2ST-l) (filtered to 4 Hz) . . . . . . . . . . . . . . . . . 126

. 61.

62.

63.

64.

I

Flow rate in ECCS LPIS pump A discharge (FT-Pl20-85) . . . . . . . . . ...

Flow rat~ in ECCS HPTS pump A discharge (FT-Pl28-104). . . . . . ..

Flow rate in intact loop hot leg venturi ·(FT-Pl39-27-l and -27-3) ....... .

Liquid level in reactor vessel downcomer instrument stalk 1, bubble plot (LE-lST-1 and -2). . . . . . . . . . . . . .

xi

127

127

. . . 128

129

65.J Liquid level in reactor vessel downcomer instrument stalk 2, bubble plot (LE-2ST-l

·and -2). . . . . . . . . . . . . . .

66. Liquid level in blowdown suppression tank (LT-Pl38-33 and -58) . . . ...

67. Liquid level in pressurizer, southeast side (LT-Pl39-6). . . . . . . . . . .

68. Liquid level in pressurizer, southwest side (LT-Pl39-7). . . . . . . . . . .

69. Liquid level ih pressurizer, north side (LT-Pl39-8) ........ ~ ..... .

70. Liquid level in steam generator secondary coolant system {LT-P4-8B) ..... · .. : ..

. . .

. .

71. Average momentum flux in broken loop cold leg at

. 130

131

131

132

. 132

133

OTT flange (ME-BL-1) (filtered to 4Hz). . . 133

72. Average momentum flux in broken loop hot leg at OTT flange (ME-PC-2) (filtered to 4Hz). . . 134

73. Average momentum flux in broken loop cold and hot legs at OTT flanges (ME-BL-1 and -2) (fil-tered to 4 Hz) . . . . . . . . . . . . . . . 134

74. Average momentum flux in reactor vessel core simulator stalk (ME-·CS··-1) (filtered to 4Hz). 135

75. Average momentum flux in intact loop cold leg at OTT flange (ME-PC-1) (filtered to 4Hz) 135

76. Average momentum flux in intact loop steam generator outlet at OTT flange (ME-PC-3) (filtered to 4 Hz) . . . . . . . . . . . . . . 136

77. Average momentum flux in intact loop cold leg and steam generator outlet at OTT flanges

78.

(ME-PC-1 and -3) (filtered to 4Hz). . . . . . 136

Average momentum flux in reactor vessel downcomer stalk 1, 44.5 in. above reactor vessel bottom (ME-lST-1) (filtered to 4Hz) . . . . . 137

79. Momentum flux in reactor vessel downcomer stalk 2, 44.5 in. above reactor vessel bottom (ME-2ST-l) (filtered to 4Hz) ....... 137

80. Differential pressure in broken loop hot leg across 14-to-5-in. contraction (PdS-BL-1) (filtered to 4Hz) ............. '· 138

xii

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81. Differential pre~sure in broken loop cold leg across 14-to-5-in. contraction (PdE-BL-2) (fil-tered to 4 Hz) ... , . . . . . . . . . . . . 138

82. Differential pressure in broken loop across break planes (PdE-BL-3 and -4) . .. . . 139

83. Differential pressure in broken loop hot leg across pump simulator (PdE-BL-5) . 139

84. Differential pressure in broken loop hot leg across steam generator simulator outlet flange (PdE-BL-6) ................ · ..

85. Differential pressure in broken loop hot leg

140

across the steam generator simulator (PdE-BL-7) .. 140

86. Differential pressure in broken loop hot leg across steam generator simulator inlet flange (PdE-BL-8) (filtered to 4 Hz) ...... ·. . . . 141

87.

88.

89.

90.

Differential pressure in reactor vessel core simulator to downcomer instrument stalk 2, 24.'5 in. from reactor vessel bottom (PdE-CS-1) (filtered to 4 Hz) .............. .

Differential pressure in intact loop cold leg across primary coolant pumps 1 and 2 (PdE-PC-1).

Differential pressure in intact loop across the·steam generator (Pd~-PC-2) ...

Differential pressure in intact loop hot leg piping from reactor vessel outlet to the flow venturi (PdE-PC-3) (filtered to 4 Hz) .....

91. Differential pressure· in intact loop hot leg piping from flow venturi to steam generator

141

142

142

143

inlet (PdE-PC-4) (filtered to 4Hz). . . . . . . 143

92. Differential pressure in intact loop cold leg pri rna ry coo 1 ant pump discharge to reactor vessel inlet nozzle (PdE-PC-5) (filtered to 4 Hz) . . . . . . . . . . . . . . . . . . . . . . .. 144

93. Differential pressure in intact loop cold leg reactor vessel inlet to broken loop cold leg reactor vessel inlet (P~E-PC-7) (filtered to 4 Hz) . . . . · . . . . . . . . . . . . . . . . 144

94. Differential pressure in reactor vessel duwncomer stalk 1 to thi blowdown suppression tank (PdE-RV-1) . . . . . . . . . ........ 145

xiii

95. Differential pressure in reactor vessel intact loop cold-leg inlet to downcomer stalk 2 (PdE-RV-3) (filtered to 4Hz) ....... 145

96.

97.

Differential pressure in reactor vessel· upper plenum to the intact loop hot leg reactor vessel outlet nozzle (PdE-RV-4).

, Differential pressure in blowdown suppression tank across vacuum breaker line (PdE-SV-9) ..

98. Differential pressure in reactor vessel downcomer stalk 2, between 209.4 and 24.5 in. above reactor vessel bottom (PdE-2ST-2) (filtered to

146

146

4Hz) ....................... 147

99.

100.

101.

102.

103.

Differential pressure in intact loop across reactor vessel inlet and outlet nozzles (PdT-Pl39-30). . . Pressure in broken loop cold and hot legs (PE-8L-l and -2) . . . . . . . . . . .

Pressure in broken loop cold leg (PE-8L-l, -4, and -8). . . . •, . . . . . . . . . Pressure in broken loop hot leg (PE-8L-2, -3, and "-6). . . . . . . . . . . . . . . Pressure in reactor vessel core simulator instrument stalk, wide range (PE-CS-lA~ ..

104. Pressure in reactor vessel core simulator

the

. . . . 147

. . . . 148

. . . . 148

' ' ' 149

149

instrument stalk, narrow range (PE-CS-18). 150

105. Pressure in intact loop cold leg, hot leg, and steam generator outlet (PE-PC-1, -2, and -3A). 150

106. Pn::!::.::.ur·t! i11 iiiLdt.:L luu~ ~Ledlll yem:!r·ator outlet,. narrow range (PE-PC-38). . . . . . . . . . 151

107. Pressure in intact loop cold leg, hot leg, and pressurizer (PE-PC-1, -2, and -4). . . . . . . 151

108. Pressure in reactor vessel downcomer instrument stalk 1 and core simulator (PE-CS-lA and PE-lST -lA and -3A) ................ 152

109. Pressure in reactor vessel downcomer instrument stalk 1, 24.5 in. above reactor vessel bottom, narrow range (PE-lST-18) ............. 152

xiv

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110. Pressure in reactor vessel downcomer instrument stalk 1, 209.4 in. above reactor vessel bottom,

111.

112.

113.

114.

115.

116.

117 ..

118.

119.

120.

. 121.

122.

123.

124.

-125 ..

narrow range (PE-lST-38) . . . . . . . . . . 153

Pressure in reactor vessel core simulator and downcomer instrument stalk 1 (PE-CS-lFF and PE-lST-lFF and -3FF) . . . ...... .

Pressure in reactor vessel core simulator and downcomer instrument stalk 2 (PE-CS-lA and PE-2ST -lA) . . . . . . . . . . . . . . . .

Pressure in reactor vessel downcomer instrument

153

154

stalks 1 and 2 (PE-1ST-3FF and PE-2ST-3FF) . 154

Pre~sure in reactor vessel ctire simulator and downcomer instrument stalk 2 (PE~CS-2FF and PE~2ST-3FF). . . . . . . . . . . . . . . . . . 155

Pressure in blowdown suppression· tank bottom under downcomer 4, 180° (PE-SV-1) (filtered to 60 Hz) • .• • • • . • • • . • • . . • . . 155

Pressure in blowdown suppression tank across from downcomer 1, 157.5° (PE-SV-3) . . . . . 156

Pressure in .blowdown suppression tank header above downcomer 4, 321° (PE-SV-14) . . . . . 156

Pressure in·blowdown suppression tank 54.5 in. north of downcomer 2, 32]0 (PE-SV-17). . . . 157

Pressure in blowdown suppression tank header above downcomer 1 (PE-SV-18) . . . . . . . . 157

Pressui"e in bluwtluwn suppress1on ·tank bottom 54.5 in. north of downcomer 3, 180° (PE-SV-22) 158

Pressure in blowdown suppression tank bottom 54.3 in. north of downcomer 2, 180° (PE-SV-26) 158

Pressure in blowdown suppression tank bottom under downcomer 2, 180° (PE-SV-43) . . . 159

Pressure in bluwdown suppress1on tank top 6 in. north of downcomer 4, 0° (PE-SV-55).

Pressure in blowdown suppression tank top above downcomer 1, 0° (PE-SV-60) . . .

Pressure in blowdown suppression tank bottom (PE-SV-1, -22, -26, and -43) ........ .

XV

159

160

160

126.

127.

128.

129.

130.

131.

132.

133.

134.

135.

136.

137.

13.8.

139.

140 ..

141.

142.

Pressure in blowdown suppression tank top (PE-SV-17, -55, and -60) ....... .

Pressure in blowd.own suppression tank' header above downcomers 4 and 1 (PE-SV-14 and -18).

Pressure in ECCS lower plenum injection line (PT-Pl20-64) ............ . -.

Pressure in ECCS lower plenum injection line and

161

161

162

lower plenum (PT-Pl20-64 and PE-lST-lA). 162

Pressure in ECCS LPIS pump A di.scharge (PT-Pl20-83) . . . . . . . . . . .

Pressure in blowdown suppression tank .header 35 in. south of downcomer 1 (PT-Pl38-23) .

Pressure in blowdown suppression tank top (PT-Pl38-55 and -56) . . . . . . . .

Pressure in intact loop hot leg venturi (PT-Pl39-2 and -3) ....

Pump speed for intact loop pumps and 2 (RPE-PC-1 and -2). . . .

Temperature in broken loop cold leg, hot leg, and reflood assist bypass system (TE-BL-1, -2, and -3). . . . . . . . . . . . . . . . . . . .

Temperature in broken loop cold leg and hot lrig warmup lines (TE-CL-1 and TE-HL-2) ...... .

Temperature in reactor vessel core simulator instrument stalk (TE-CS-1) ........ .

Temperature in intact loop cold leg, hot leg, and steam generator outlet (TE-PC-1, -2, and -3)

Temperature in blowdown suppression tank liquid ~t t~nk hottom (TE-Pl38-22) ..... .

Temperature in blowdown suppression tank vapor at tank top (TE-P138-34) .....

Temperature in broken loop cold leg QOBV inlet and isolation valve inlet (TE-Pl38-62 and -63) . . . . . . . . . . . . .....

Temperature in broken loop hot leg QOBV inlet and isolation valve inlet (TE-Pl38-66 and -65)

xvi

Hi3

163

164

164

165

165

166

166

167

167

. 168

168

169

143. Temperature in intact loop pressurizer vapor and liquid (TE-Pl39-19 and -20). . . . . . . 169

144. Temperature in intact loop cold leg upstream of DTT flange (TE-Pl39-29) . . . . . . . . 170 .

145. Temperature in intact loop hot leg in elbow near venturi (TE-Pl39-32 and -33). . . . 170

146. Temperature in steam generator intact loop cold leg, hot leg, and secondary side (TE-SG-1, -2, and -3). . . . . . . . . . 171

147. Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-1, -2, and -3) 171


149. Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-7, -8, and -9) . . 172

150. Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-10, -11, and -12). . 173

151. Temperature in blowdown suppression tank 107.2 in. from tank bottom (TE-SV-1 and -7). . . . 173

152. Temperature in blowdown suppression tank 93.0 in. from tank bottom (TE-SV-2 and -8) ......... 174

153. Temperature in blowdown suppression tank 74.7 in. from tank bottom (TE-SV-3 and -9). . . . . . .. 174

154. .Temperature in blowdown ·suppression tank 57.2 in. from tank bottom (TE-SV~4 and -10) . . . 175

155. Temperature in blowdown suppression tank 39.0 in. from tank bottom (TE-SV-5 and -11). 17.5

156. Temperature in blowdown suppression tank 14.7 in. from tank bottom (TE-SV-6 and -12). 176

157. Temperature in reactor vessel downcomer instrument stalk 1 (TE-lST-1, -2, -3, and -4). 176

158. Temperature in reactor vessel downcomer instrument stalk 1 (TE-lST-6, -8, -9, and -10) 177

159. Temperature in reactor vessel downcomer instru-.ment stalk 1 (TE-lST-11, -12, -13, and -14). . . 177

xvii

160.

1,61.

162.

Temperature in reactor vessel downcomer instru-ment stalk 2 (TE-2ST-2, -4, -7, and -9). . . .. · 178

Temperature in reactor vessel downcomer instru-ment stalk 2 (TE-2ST-10, -12, and -14). . .. 178

Temperature in reactor vessel downcomer instrument stalk 1, 189.3 in. from reactor vessel bottom (TE-lST-l). . . . . . .......... 179

163. Temperature in reactor vessel downcomer instrument stalks 1 and 2, 165.3 in. above reactor vessel bottom (TE-lST-2 and TE-2ST-2). . . . . 179

lb4. lemperature in reactor vessel downcomer instrument stalk 1, 141.3 in. above reactor vessel bottom (TE-lST-3) .................. 180

165. Temperature in reactor vessel downcomer instrument stalks 1 and 2, 117.3 in. above reactor vessel bottoni (TE-lST-4 and TE-2ST-4) .. ' . . .. 180

166. Temperature in reactor vessel downcomer instru- · ment stalk 1, 69.3 in. above reactor vessel bottom (TE-lST-6). . . . . . . . . . . ... 181

l67. Temperature in reactor vessel downcomer instrument stalk 2, 33.3 in. above reactor vessel bottom (TE-2ST-7). . . . . . ........... 181

lGO. T~mp~ratur~ in r~actor vessel do~ncomer instrument stalk 1, 29.3 in. above reactor vessel bott6m (TE-lST-8). . . . . . . . . . . . . . . . 182

169. Temperature in reactor vessel downcom~r instrument stalks 1 and 2, 25.3 in. above reactor v~~~el hnttnm (T~-l~T-9 anrl lE-2ST-9). . . 182

170. Temperature in reactor vessel downcomer instrument stalks 1 and 2, 21.3 in. above reactor vessel bottom (TE-lST-10 and TE-2ST-10). . . . . 183

171 Temperature in reactor vessel downcomer instrument s ta 1 k 1 , 17. 3 in above reactor ves·se 1 bottom (TE-lST-11) . . . . . . . . . . . . .. 183

172. Temperature in reactor vessel downcomer instrument stalks 1 and 2, 13.3 in. above reactor vessel bottom (TE-lST-12 and TE-2ST-12) ...... 184

173. Temperature i~ reactor vessel downcomer instrument stalk 1, 9.3 in. above reactor vessel bottom (TE-lST-13) . . . . . . . . . . . .... 184

xviii

174. Temperature in reactor vessel downcomer instrument stalks 1 and 2, 45.9 in. above reactor vessel bottom in DTTs (TE-lST-1~ and TE-2ST-14). 185

175. Temperature in ECCS lower plenum injection line (TT-P120-65) ................ : . 185

176.

177.

178.

179.

180.

181.

182.

183.

184.

185.

186.

TEST Ll-3 MEASURED PARAMETERS LONG-TERM PLOTS (175- AND 500-SECOND PLOTS)

Density in broken loop cold leg, chordal density (DE-BL-lA, -lB, and -lC) ....

Density in broken loop hot leg, chordal density (DE-BL-2A, -2B, and -2C) .

Fluid velocity in broken loop cold leg at OTT flanges (FE-BL-1) .... ~ ....... .

Fluid velocity in reactor vessel downcomer instrument stalk 2, 47.1 in. above reactor vessel bottom (FE-2ST-1) ...... .

Flow rate in blowdown suppression tank spray system 60-gpm header (FE-Pl38-138) ..

Flow rate in blowdown suppression tank spray system pump discharge (FE-P138-139) ..

Flow rate in blowdown suppression tank spray system 220-gpm header (FE-P138-140) ..

Flow rate in blowdown suppression tank spray system pump recirculation line (FE-P138-153)

Flow rate in ECCS LPTS pump A discharge (FT-Pl20-85) ........... .

Liquid level in blowdown suppression tank (LT-Pl38-33 and -58) .......... .

Momentum flux in the broken loop cold leg at nTT flange (ME-BL-1) ......•....

187. Momentum flux in reactor ~essel downcomer instrument s~alk 2, 44.5 in. above reactor

188

188

189

190

191

191

192

192

193

193

194

vessel bottom (ME-2ST-·l) ............. 194

188. Pressure in.reactor vessel core simulator instrument stalk, narrow range, and intact loop steam generator outlet (PE-CS-lB and PE-PC-3B). . . . . . . . . . . .• . . . . . ~ .

xix

195

189. Pressure in blowdown suppression tank across from downcomer 1, 157.5°, and bottom 54.5 in. north of downcomer 3, 180° (PE•SV-3 and -22) .. 195

190.

191.

192.

Pressure in blowdown suppression tank top north of downcomer 4 and above downcomer 1 (PE-SV-55 and -60) . . ....... .

Pressure in ECCS lower plenum injection line (PT-Pl20-64) .......... .

Pressure in ECCS LPIS pump A discharge (PT-Pl20-83) ............ .

193. Pressure in blowdown suppress1on tank top 48 in. north of downcomer 1 and 49 in. north

196

196

197

of downcomer 2 (PT-Pl38-55 and -66). . . . . 197

194. Pressure in'blowdown suppression tank spray system pump discharge and cooldown heat exchanger outlet (PT-Pl38-136 and -151). . . 198

195. Temperature in broken loop cold leg and hot leg (TE-BL-1 and -2) . . . . . . . . . . . . 198

196. Temperature in reactor vessel core simulator instrument sta 1k (TE-SC-1) . . . . 199

197. Temperature in intact loop cold leg, hot leg, and steam generator outlet (TE-PC-1, -2, and -3) 199

198. Temperature in blowdown suppression tank spray system pump discharge (TE-Pl38-142). . . . 200

199. Temperature in blowdown suppression tank spray system 60-gpm header and 220-gpm .spray header (TE-Pl38-141 and -143) . . . . . . . . . . . . 200

200.. Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-1, -2, and -3) 201


202. Temperatare in blowdown suppression tank A-end thermocouple stalk (TE-SV-7, -8, and -9) 202

203. Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-10, -11, and -12). . 202

204. Liquid level in blowdown suppression tank north end (LT-Pl38-33) ................. 203

XX

205. Liquid ~evel in blowdown suppression tank south end (LT-Pl38-58) . . . . . . . . . . . . . . . 203

206. Pressure in blowdown suppression tank across from downcomer 1, 157.5° (PE-SV-3) . . . . . . 204

207. Pressure in blowdown suppression tank bottom 54.5 in. north of downcomer 3, 180° (PE-SV-26) .- 204

208. Pressure in blowdown suppression tank bottom under downcomer 2 and under downcomer 3, 180° (PE-SV-43 and -44) . . . . . . . . . . . . . . . 205

209. Pressure in blowdown suppression tank top 48 in. north of downcomer 1 and 49 in. north of downcomer 2 (PT-Pl38-55 and -56) .. : 205


211. Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-4 and -6). . . 206

212. Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-10) ... ; . . . . . 207

213.

214.

215.

216.

217.

218.

219.

220.

TEST Ll-3 COMPUTED PARAMETERS

Flow regime and average density in broken loop cold leg .... · .......... .

Flow regime and average density in broken 1 oop hot_ 1 eg . . . . . . . . ._ . . . . . . . .

Flow regime and average density in intact loop hot 1 eg . . . . . . . . Enthalpy in broken loop cold leg

Enthalpy in broken loop hot leg.

Enthalpy in intact loop cold leg

Enthalpy in intact loop hot leg.

Enthalpy in intact loop at steam generator outlet . . . . . . . . . . . . . . . . .

221. Mass flow rate per system volume in broken loop cold leg calculated from FE-BL-1 and

210

211

212

213

213

214

214

. 215

ME-BL-1. . . . . . . . . , . . , . . . . . . . . . 215

xxi

222. Mass flow rate per system volume in broken loop cold leg calculated from DE-BL-1 and ME-BL-1 . 216

223. Mass flow rate per system volume in broken loop cold leg calculated from DE-BL-1 and FE-BL-1 .................... 216

224. Ma.ss flow rate per system volume in broken loop cold leg calculated from DE-BL-1 and PdE-BL-2 . . . . . ·· . . . . . . . . . . . . . . . 217

225. Mass flow rate per system volume in broken loop hot leg calculated from DE-BL-2 and· ME-.BL-2 ...................... 217

226. Mass flow rate per system volume in broken loop hot leg calculated from DE-BL-2 and FE-BL-2. . . . . . . . . . . . . . . . . .

227. Mass flow rate per system volume in broken loop

. 218

hot leg calculated from DE-BL-2 and PdE-BL-1 ... 218

228. Mas~ flow rate per system volume in intact loop cold leg calculated from FE-PC-1 and ME-PC-1 ... 219

229. Mass flow rate per system volume in intact loop cold leg calculated from FE-PC-1, PE-PC-1, and DE-PC-lB . . . . . . . . . . . . . . . . . . 219

230. Mass flow rate per system volume in intact luup cold leg Cdlculated from DE-PC-10 and ME-PC-1. . . . . . . . . . . . . . . . . . . . . . 220

231. Mass flow rate per system volume in intact loop cold leg calculated from DE-PC-lB and FE-PC- 1 .· . . . . . . . . . . . . . . . . . . . . . 220

232. Mass flow rate pe~ system volume in intact loop hot leg calculated from FE~PC-2 and PE-PC-2 ...................... 221

233. Mass flow rate per system volume in intact loop hot leg calculated from DE-PC-2 ~nd FE-PC-2. . . . . . . . . . . . . . . . . . . . . 221

234. Mass flow rate'per system volume in intact loop steam generator outlet calculated from FE-PC-3, PE-PC-3A, and DE-PC-3 .......... 222

235. Mass flow rate per system volume in intact loop steam generator outlet calculated from DE-PC-3 and ME-PC-3 ............ .

xxii

222

236. Mass flow rate per system volume in intact loop steam generator outlet calculated from DE-PC-3 and FE-PC-3. . . . . . . . . . . . . .. 223

237. Mass flow rate per system volume in intact loop pressurizer calculated from LT-Pl39-8 and PE-PC-4. . . . . . ~ . . . . 223

238. Pump speed, electrical, in intact loop primary coolant pumps 1 and 2. . . . . . . . . . . . . 224

239. Pump speed, electrical and mechanical, in intact loop primary coolant pump 1. . . . . • . . . . . 224

240. Pump speed, electrical and mechanical, in intact loop primary coolant pump 2. . . . . . . . . . 225

241. Pump motor slip in intact loop primary coolant pumps 1 and 2. . . . . . . . . . . . . . . . . 225

242. Pump motor individual electrical horsepower in intact .loop primary coolant pumps 1 and 2. 226.

243.

244.

245.

246.

247.

248.

249.

250.

251.

252.

253.

,254.

Pump motor total electrical horsepower in intact loop primary coolant pumps 1 and 2.

Pump total water horsepower in intact loop primary coolant pumps 1 and 2 ...

Pump combined efficiency in intact loop. primary coolant pumps. 1 and 2 ....... .

Pressure, closure, in intact loop (filtered to 4 Hz) . • • • • • • • • • • • • • •

Static quulity in broken loop cold leg

Static quality in brok~n loop hot leg.

Static quality in intact loop cold leg

Static quality in intact loop hot leg:

Static quality in intact loop at steam gene~utor outlet ....... .

Flow quality in broken loop cold leg

Flow quality in broken loop hot leg.

Flow quality in intact loop cold leg

xxiii

226

227

227

228

220

229

229

230

230

231

231

232

255.

256.

257.

258.

259.

260.

261.

262. "

263.

264.

265.

266.

267.

268.

269.

Flow quality in intact loop hot leg. . . . . . . . 232

Flow quality in intact loop at steam generator outlet . . . . . . . . . . 233

Saturation temperature in broken loop cold leg overlaid with TE-BL-1. . . . . . . . . . . . . 233

Saturation temperature in broken loop hot leg overlaid with TE-BL-2. . . . . . . . . . . 234

Saturation temperature in intact loop cold leg overlaid with TE-PC-1. . . . . . . . . . . 234

Saturation temperature in intact loop hot leg overlaid with TE-PC-2. . . . . . . . . . . . 235

Saturation temperature in intact loop steam generator outlet overlaid with T£-PC-3 . . . 235

Saturation temperature in reactor vessel core simulator instrument stalk overlaid with TE-CS-1 . 236

Saturation temperature tn reactor vessel downcomer instrument stalk 1 overlaid with TE-lST-9 ..................... 236

Saturation temperature in reactor vessel downcomer instrument stalk 2 overlaid with TE-2ST-9 .............. .

Void fraction in brokl:m loop cold lea.

Void fraction in broken loop hot leg .

Void fraction in intact loop cold 1 eg. ·

Void fraction in intact loop hot leg ..

Void fraction in intact loop at steam generator outlet . . . . .

TEST Ll-3 ERROR BAND PLOTS

237

?17

238

238

239

239

270. Valve opening (%) in broken loop hot leg QOBV with error bands (CV-Pl38-l5). . . . . . . . 242.

271. Chordal density in broken loop cold leg with error bands (DE-BL-lA) (filtered to 4Hz). . 242

272. Average velocity in broken loop cold leg at DTT flange with error bands (FE-BL-1) (filtered to 4 Hz) . . . . . . . . . . . . . . . . . . . . . . 243

xxiv

273. Average velocity in reactor vessel downcomer instrument stalk 1 with error bands (FE-lST-1) (filtere~ to 4 Hz) . . . . . . . . . . , . 243

274. Flow rate in blowdown suppression tank spray system pump discharge with error bands (FE-Pl38-139). . . . . . . . . . . . . . 244

.275. Flow rate in ECCS LPIS pump A discharge with error bands (FT-Pl20-85) .... ; ..... . ·. . •244

276.

277.

278.

279.

.280.

Flow rate in ECCS HPIS pump A discharge with error bands (FT-Pl28-104). . . ...

Flow rate in intact loop hot leg venturi with error bands (FT-Pl39-27-3) .

Liquid level in blowdown suppres?ion tank south end with error bands (LT-Pl38-58) ..... .

Liquid level .in pressurizer north side with error bands (LT-Pl39-8) .......... .

Momentum flux in broken loop cold leg at OTT flange with error bands (ME-BL-1) (filtered to 4 Hz). . . . . . . .. . . . . . . . . . · . . . .

281. Momentum flux in reactor vessel downcomer instrument stalk 1 with error bands (ME-lST-1) (filtered

245

245

246

247

to 4 Hz) ..................... 247

282. ·Differential pressure in broken loop hot leg at 14-to-5-in. reduction with error bands (PdE-BL-1) (filtered to 4 Hz) ................ 248

283. Differential pressure in broken loop cold leg at 14-to-5-in. reduction with error bands (PdE-BL-2) (filtered to 4Hz) . . . . . . . . . . . . . . 248

284. Differential pressure in broken loop cold leg across break plane with error bands (PdE-BL-3) .. 249

285. Differential pressure in broken loop hot leg across steam generator simulator outlet flange with error bands (PdE-BL-6) (filtered to 4 Hz) .. 249

286.

287.

Differential pressure in intact loop cold leg across primary coolant pumps 1 and 2 with error bands (PdE-PC-1) .............. .

D1fferent1al pressure 1n intact loop across steam generator ·with error bands (PdE-PC-2). ·.

XXV

250

250

288. Differential pressure in intact loop hot leg reactor vessel outlet to flow venturi with error bands (PdE-PC-3) .............. 251

289. Differential pressure from reactor vessel downcomer stalk 1 to blowdown suppression tank with error ban~s (PdE-RV-1) . . . . . . .. 251

290. Differential pressure in intact loop across the reactor vessel inlet and outlet nozzles with error bands (PdT-Pl39-30) . . . 252

291. Pressure in broken loop hot leg with error bands (PE-BL-2) ..... ~ . . . . . . . . . . 252

292. Pressure in reactor vessel core simulator instrument stalk, wide range, with error bands (PE-CS-lA) . . . . . . . . . . . . . . . . . . 253

293. Pressure in reactor vessel core simulator instrument stalk, narrow range, with error bands (PE-CS-lB) ...... · ........... 253

294. Pressure in reactor vessel core simulator instrument stalk, short-term plot, with error bands (PE-CS-2FF) .......... , . ~ .. 254

295. Pressure in reactor vessel core simulator instrument stalk, 70-second plot, wi~h error bands (PE-CS-2FF) ................. 254

296. Pressure in blowdown suppression tank header above downcomer 4, short-term plot, with error bands (PE-SV-14) .................. 255

297.

298.

299.

300.

Pressure in blowdown suppression tank header above downcomer 4, 70-second plot, with error bands (PE-SV-14) .............. .

Pressure in ECCS lower plenum injection point with error band::; (PT--Pl20-64) ....... .

Pressure in ECCS LPIS pump A discharge with error bands (PT-Pl20-83) ........ .

Pressure in blowdown suppression tank top with error bands (PT-Pl38-55) ...... .

255

256

256

257

301. Pressure in broken loop cold leg QOBV inlet, short-term plot, with error bands (PT~Pl38-lll) .. 257

302. Pressure in blowdown suppression tank spray system pump discharge with error bands (PT-Pl38-136). . ............. 258

xxvi

303.

304.

305.

306.

307.

308.

309.

310.

Pump speed in intact loop operating pump 2 with error bands (RPE-PC-2). · ..... .

Temperature in broken loop hot leg with error band~ (TE-BL-2) ......... .

Temperature in blowdown suppression tank liquid at tank bottom with error bands (TE-Pl38-22) ............. .

Temperature in blowdown suppression tank vapor at tank top with error bands (TE-Pl38-34) ...

Temperature in broken loop cold leg at QOBV inlet with error bands (TE-Pl38-62) .....

Temperature in broken loop cold leg isolation valve inlet with error bands (TE-Pl38-63). · ..

Temperature in blowdown suppression tank spray system 60-gpm header with error bands (TE-Pl38-141) ................ .

Temperature in intact loop pressurizer liquid with error bands (TE-Pl39-20) ........ .

258

. 259

259

260

260

261

261

262

311. Temperature in intact loop cold leg at steam generator inlet plenum with error bands (TE-SG-1). 262

312. Temperature in blowdown suppression tank B-end thermocou~le stalk with error bands (TE-SV-6) ... 263

I.

II.

I I I.

IV.

v.

VI.

VI I.

TABLES

Nomenclature for LOFT Instrumentation.

Chronology of Events for Test Ll-3 .

LOCE Ll-3 Initial Conditions ...

Primary Coolant Temperature Distribution at Rupture . , , . . , . . . • •

Water Chemistry Results for Test Ll-3.

Measured Parameters for LOFT Test Ll-3 .

Computed Parameters for.LOFT Test ll-3

xxvii

18

34

36

38·

40

54

85

/

EXPERIMENT DATA REPORT FOR LOFT NONNUCLEAR TEST Ll-3

I. INTRODUCTION

The intent of this report is to present the Ll-3 test data in an uninterpreted but readily usable form for use by the nuclear ·community in advance of detailed analysis and interpretation. The data, presented herein in the form of graphs in engineering units, have. been analyzed and qualified to the extent necessary to ensure that they are reasonable and consistent. Initial assessment of the data from this test and comparison with the experiment prediction[2] for Test Ll-3 were performed in the quick look report[ 3] for nonnuclear experiment Ll-3. Test Ll-3A has subsequentlY been performed as a repeat of Test Ll-3, since Test Ll-3 did not meet all of the test objectives and specifications presented in Reference 1.

The Loss of Fluid Test (LOFT) Program is part of the Water Reactor Safety Research Program sponsored by the Nuclear Regulatory Commission and is adminisiered by the Energy Research and Development Administration. .·The tests ar~ conducted at the Idaho National Engineering Laboratory (INEL), Test Area North (TAN). The objectives of the program are:

(1) To provide data required to evaluate the adequacy and improve the analytical methods currently used to predict the loss-ofcoolant accident (LOCA) response of large pressurized water reactors (LPWRs). The performance of engineet:'ed safety features (ESF) with particular emphasis on emergency core cooling system (ECCS) and the quantitative margins of s.afety inherent in the performance of ESF is of primary interest.

(2) To identify and investigate any unexpected-event(s) or threshold(s)· in the response of either the plant or the. ESF, and

·,

develop analytical techniques that adequately describe and account for such unexpected behavior.

In order to meet these objectives, the LOFT Integral Test Facility[a] has been designed to simulate the major components of a

LPWR, and several series of the experiments have been planned to produce data on the combined thermal, hydraulic, nuclear, and structural processes expected to occur during a LOCA.

The first LOFT test series (designated Ll) is the nonnuclear test series which consists ·of five isothermal blowdown tests .. This test series has been designed to make available large scale isothermal blowdown and reflood system data as a first phase of the LOFT Program. Varied parameters include break size, break location, break opening time, primary coolant system flow resistance, emergency core coolant (ECC) injection location, and primary coolant system pressure. Blowdown suppression tank performance, as influenced by initial tank level, water temperature, pressure, and spray system control, will be evaluated. Specifically, the purposes of this test series are:

(1) To determine that the equipment/systems function properly

(2) To demonstrate that the entire test facility can withstand the structural loads of blowdown

(3) To determine that the blowdown test procedures are adequate

[a] The term "integral" is used to describe an experjment combining the nuclear, thermal, hydraulic, and structural processes occuring during a LOCA and differentiates it from the separate effects, nonnuclear, small-scale, thermohydraulic experiments conducted for

loss-of-coolant analysis.

2

' '

(4) To provide experience to operators prior to nuclear tests

(5) To obtain . isothermal . loss-of-coolant experiment (LOCE) data for comparison with similar data from other experimental programs, and to experimentally verify thermal-hydraulic system behavior prior to nuclear blowdown.

A detailed description of the LOFT Facility and the Ll test series can be found in Reference 4.

of: Tests in the Ll test series conducted prior to Test Ll-3 consist

(1) Test Ll-1[5J, which was conducted from initial conditions of 540°F and 1322 psig and was a iOO% hot leg break simulation. ECC injection was directed to the cold leg.

(2) Test Ll-2(6], which was conducted from initial conditions of 540°F and 2255 psig and was a 200% cold leg break simulation· without ECC injection. cold leg 13.3 minutes wall delay,. experiment.

ECC was·injected into the intact loop after Test Ll-2 initiation for a 11 hot

Test Ll-3 was conducted from initial conditions of 540°F and 2256 psig and was a 200% cold leg break simulation. ECC injection was directed to the lower plenum of the r~actor vessel using low-pressure injection system (LPIS) pump A and high-pressure 1njection system (HPIS) pump A. The accumulators, however, failed to inject ECC into the lower plenum during this test. Test Ll-3, therefore was repeated as Test Ll-3A[?] to obtain accumulator ACC-A injection.

3

The specific purposes of Test Ll-3 were to:

(1) Compare break flow data with predictions

(2) Measure pump resistance and coastdown characteristics

(3) Determine system performance with ECC injection into the lower plenum

(4) Determine two-phase flow resistance . of various components

system

(5) Evaluate the scaling effects of the various primary system components

(6) Evaluate the effect of intact loop resistance on system thermal-hydraulic performance by comparison with corresponding results from Test Ll-2.

Test Ll-3 met all of these objectives except number 3. Since Ll-3 was nearly identical to Ll-3A up to the t1me of accumulator injection (22 seconds after blowdown initiation), Test Ll-3 provides a good measure of experiment repeatability. Also, since Test Ll-3 did include HPIS and LPIS injection, some indication of degraded ECC performance is provided by the Ll-3 data.

Section II of this report briefly describes the LOFT system and the facility configuration specific to this test. Section III discusses the LOFT instrumentation system 1nclud1ng the basic types of detectors utilized, the methods of obtaining certain mea~urements, and the LOFT data reduction process. Section IV summarizes the test procedures used to conduct Test Ll-3 and presents a chronology of events that occurred during the test. Section V presents the initial conditions of the test,

both specified and as measured. Section VI discusses numerous methods

employed to verify the consistency and accuracy of the data presented.

Finally, Section VII presents the data graphs and provides tables of

4

comments and supporting information necessary for the interpretation of .the data.

5

II. SYSTEM CONFIGURATION

The LOFT Facility has been designed to simulate the major components and system responses of a LPWR during a LOCA. The test assembly is comprised of five major subsystems which have been instrumented such that desirable system parameters can be measured and recorded during a LOCE. The subsystems include: (a) the reactor vessel, (b) the intact loop, (c) the broken loop, (d) the blowdown suppression system, and (e) the ECCS. System instrumentation is discussed in Section III.

The LOFT reactor vessel simulates the rea~tor vessel of a LPWR. It has an annular downcomer, a lower plenum, lower core support plates, a core simulator, and an upper plenum. The downcomer connects with the cold leg of both the intact loop and the broken loop and contains·two experimental instrument stalks; the upper plenum connects the hot leg of both the intact loop and the broken loop. The core simulator contains an experimental instrument staJk and a hydraulic orifice plate assembly to simulate the flow resistance of a nuclear core which will be installed for nonnuclear LOCE Ll-5.

The intact loop simulates the unbroken loops of a LPWR. This loop contains a steam generator, two circulating coolant pumps connected in parallel, a pressurizer, a venturi flowmeter. and connecting piping. Each circulating coolant pump is powered by a primary system motor generator (PSMG) set consisting of an ac motor coupled to an ac generator through an adjustable fluid clutch. A flywheel is connected directly to each generator shaft. For this experiment, the primary s1de steam generator inlet and outlet plenums contained square edged orifice plates sized for low resistance based on core flow area scaling. · Thus, these orifices provided a similar pressure drop at scaled flow rates around the LOFT intact loop (excluding the reactor vessel) as exists in a . LPWR operating loop. The secondary side of the steam generator was filled to a predetermined level and isolated from the remainder of the secondary coolant system. The intact loop cittulating coolant pumps

6

were used to bring the system to the initial test temperature of 540°F. For Test Ll-3,- the electrical power to the PSMG sets was terminated· within 1 second after blowdown initiation. This action left the PSMG sets electrically connected to their respective intact loop pumps such that pump coastdown characteristics were under the

. ' 2 7,500-lbm/ft inertia flywheels on the generators.

influence of the This electrically

coupled system represented the inertia and the subsequent coastdown of the circulating coolant pumps in a LPWR. When the intact loop pumps reached a speed of approximately 750 rpm, the electric.al power- to the pump motors was interrupted by opening the generator field breakers.

The broken loop simulates the broken ·loop of a LPWR. It consists basically of a hot leg and cold leg that are connected to the reactor vessel and the blowdown suppressiori tank header. Each leg consists of a break plane orifice which de·termines the break size to be simulated, a quick-opening blowdown valve (QOBV) which simulates a pipe break, a recirculation line, an isolation valve, and connecting piping. The r,edrculation lines established a small flow from the broken loop to the intact loop to maintain these loop temperatures approximately .equal prior to the blowdown. These recirculation paths are secured just prior to blowdown initiation.

Test Ll-3 simulated a 200% double-ended shear break in a cold leg of a LPWR operating loop. In this configuration, the broken loop hot leg contained, in addition to the above mentioned components, a steam generator simulator and a pump simulator. These simulators have hydraulic orifice plate· assemblies installed which have similar (passive) resistances to flow as a real steam generator and a locked rotor pump. The break flow area (break plane orifice area) in this configuration is 0.09 ft2; this is 100% of the possible break flow area in each line.

The blowdown suppression system simulates the containment back pressure of a LPWR. This system is comprised of the blowdown suppression tank header, the blowdown suppression tank (BDST), the nitrogen pressurization system, and the blowdown suppression tank spray

7

system (BDSTSS). The blowdown header is connected to the suppression tank by four suppression tank downcomers that extend inside the tank and

discharge below the water level established as a Test Ll-3 initial condition. The nitrogen pressurization system is supplied by the LOFT inert gas system and utilizes a remote controlled pressure regulator to establish and maintain the specified BDST initial pressure. The spray system consists of a centrifugal pump which discharges through a heatup heat exchanger and either three spray headers or a pump recirculation

line that contains a cooldown heat exchanger. The spray pump suction can be aligned to either the BUST or the borated water storage tank {BWST). The three spray headers have a 20-gpm, a 60-gpm, and a 220-gpm flow rate capacity and are located in the BDST along the upper

centerline.

To model the containment back pressure of a LPWR, predetermined initial conditions are established in the BDST. Thus, prior to blowdown initiation, the spray pump suction is aligned to the BDST and BDST water

is recirculated through the three spray headers. Steam is admitted to the heatup heat exchanger until the BDST water is heated to its specified temperature. Following BDST heatup, flow is secured through the three spray headers and the BDSTSS piping is cooled down using the cooldown heat exchanger in the pump recirculation line. Prior to BDST spray initiation, the spray pump suction is specified to be shifted to

the BWST so that a cooler water source is available for BDST pressure suppression. For Test Ll-3, suppression tank spray was manually initiated and adjusted to 320 gpm after accumulator nitrogen entered the

tank to establish the pressure suppression effectiveness of the BDSTSS. Therefore, the blowdown effluent was.contained within the BDST while

obtainin~ the same peak pressure as if the break was in a LPWR which was discharging into its containment vessel.

The LOFT ECCS simulates the ECCS of a LPWR. The accumulator, the

HPIS, and the LPIS were specified to be used during this experiment.

Each system was configured to inject scaled flow rates of ECC directly

into the lower plenum of the reactor vessel. To provide these scaled

flow rates, accumulator ACC-A, HPIS pump A, and LPIS pump A were

8

selected. Accumulator ACC-A was preset to inject ECC at a system pressure of 600 psig. Due to a procedural error, · however,

accumulator ACC-A and backup accumulator ACC-B failed to initiate injection. HPIS pump A was preset to inject at 17.2 gpm and to

initiate by LOCE ·control at 22 seconds after the initiation of

blowdown; LPIS pump A was adjusted to initiate by LOCE control at

35.5 seconds after the initiation of blowdown. While the above ECCS injection times and pressure represent those preset test conditions

specified in the EOS, the actual recorded parameters are presented in the test summary and Section IV.

The LOFT major components are shown.pictorially in Figure 1, and a

LOFT piping schematic, with instrumentation, is shown in Figure 2.

Reference 1 gives details of the experiment configuration and operation;

Reference 4 gives a detailed description of the LOFT system.

9

Steam Generator

Steam Generatcr Outlet OTT Flarge

Broken .1

L<lop Cold l...9g OTT !Flange

Broken Loop .. HQt Le91 [)Jll'

Fl3nge

ECC Lower Plenum Injection l,ret

+-+----- ECC Cold Leg Injection l~et

Intact Loop Cold Leg OTT Farge

EGG-A-9!9

Fig. 1 LOFT major compohents.

Suppression Tank

Borated Water Storage Tonk

4"

4" XR0-67

. ( --~~ 'r---, XR2t---69-------=-6'_' --------,

"" ~ Accumulator B ,..---------------"4',-------~--l

4"

I I I

4"

XR0-65

4" I I I I I

L_ ______ . ___________ l r-----, : Oecon.

411 ,.!." . 2

I HPI~, " I

Pump B Aux. Spray from I Purification .--------- _j

System 1

I Spray Llnel from Cold I

Leg I Pres.surizer PE-PC-4

TE-P139-

PT-P139-3,4,5

/L T-:\ P-139-'6.7.81

I I I

;~-P13;9---~~~~--~~~<5~~-c============:J~~--~

. Cycling l Backup Heaters

PE-PC-3A PE-PC-36 FE-PC-3 ME-PC-3 TE-PC-3 DE-PC-3

« Electrically '--T~ Connected

to PC- P-2

PE-PC-1 FE-PC-1

·ME-PC-1 TE-PC-1 DE-PC-1

TE-P139-28-2,29

Mechanical Connections

Alternator

~

CD J: 0 a.. u <[

E lectrlcolly ~

~!_A _______ ~, Connected ~

to PC-P -I

PT-P120-43 HPIS, II

Pump A

I I I I L

4"

4" Crossover Line

4" ECC

4"

611 x 4 11

Reducer

4"

PE-BL-1 FE-BL-1 ME-BL-1 TE-BL-1

PE-BL-2 FE-BL-2 ME-BL-2 TE-BL-2 DE-BL-2

FT-P120-85

To Suppression Tonk Pressure Control System

I ,~ ..

FE-P-138-153

4"

I FE·P·t38· 140--

3" ! 3"

•I

I I I I I

4"

4"

4"

~~m~_..J

FE-P138-139

4" Crossover Line

t. This Section is Valve and Mechanical Joint l

ANC-D-7221

Fig. 2 LOFT piping schematic (with instrumentation).

11

III. MEASUREMENTS AND INSTRUMENTATION

The LOFT instrumentation system was designed to measure and record the important events that occur during a LOCE. For Test Ll-3, 549 channels of data were recorded. Data from the thermal-hydraulic measurements (i.e., temperatures, pressures, flow rates, liquid levels, densities, pump speeds, and QOBV positions as functions of time) are of primary importance and are included in this report. Mechanical measurement data such as acceleration and strain were recorded for monitorina structurnl londs on t.hP. LOFT system but are not of primary intl::'rPc.;t·. rt<.; l.hP. r·f!~ulb are specific to the LOFT mechanical arrangement and therefore are not included.

Thermocouples and resistance temperature devices were used to sense the fluid temperatures at all major locations 'in. the system.

Pressure measurements were generally obtained with strain-gage-type transducers with pressure transmission lines connecting the transducers to the measurement points. A few piezoelectric-type transducers were u5ed Where high frequency response wa~ de~ired rather than absolute accura.c:y. FrP.P. .... fiP.ld pressure transdu<.;~rs, in which the· sensing elements w~r~ 1ns1de a bellows arrangement, were alsu used ·tu ~l·JminiiL~

connecting transmission lines and thereby produce higher frequency response without the distortion caused by the lines.

Differentiai pressures were measured by strain-gage-type transducers with double chambers. The transducers were connected to the two measur~ment points with pressure transmission lines.

Flow velocities were generally obtained by use of turbine flowmcters, which consisted of rotating vanes with magnetic blades and stationary magnetic pickup coils. Other methods of determining flow velocity included calculation by:

12

(1) Dividi.ng mass flow from venturi meters by the density and flow area

(2) Dividing momentum flux from the drag discs by the density and· taking the square root of the quotient:

Density was·measured by means of gamma densitometers (shown in Figure 3), which use the attenuation of gamma rays from a cesium-137 source to sense the mass of fluid within a pipe. The densitometers used in LOFT each have three beams (designated A, B, and C) which traverse the lower, middle, and upper parts of the pipe, respectively, for the horizontal pipe densitometers. For the steam generator discharge densitometer, where the pipe is vertical, the densitometer •s• beam is in the plane of the adjacent pipe bends. By using the logic table given in Figure 4 and special calibrations, the average density and the flow regime can be obtained, The special calibratio~s mentioned were obtained from testing with lucite and wood representations of various fluid density distributions in an actual piece of LOFT piping. These calibrations were then used to produce weighting factors to be used on each beam in combining the individual beam outputs to obt~in the average density. Experimentation showed the use -of simple weighting factors to be as accurate for average density as severa 1 more complex meth.ods of determining the fluid distribution in the pipe. The resultant weighting factors were changed as a function of the flow regime. The weighting factors used in this report were as shown in the following equations:

for stratified flow, and

p = 0.345pA + 0.40lpB + 0.254pc

for other flow regimes.

Another method used in LOFT for obtaining fluid density is by means of drag discs, which sense momentum flux, and turbine meters, which

13 \.

~---- Source

Pipino 'C' Detector

.---'c' Detector

<t_ 'c' Beam

Be om

'A' Detector ct_ '.l' Be om

ANC-1·7051

Relation of source and detector to pipe in DE-BL-1 and DE-PC-1 (view looking to-.-Jard reactor vessel).

i

I I~ C Beam

'e' Detector ~----i...,

'e; Beam ~I 'A' Becm

AN C·A-70 52

Relation of source and detector to pipe in DE-BL-2 and DE-PC-2 (view looting toward reactor vessel).

; C' Detector

LOFT Pi pi 10

'A' Beam ANC-A-70110

Fig. 3

Relatian of source and detector to pipe in ~E-PC-3 (view looking dm<~n). ·

Gamma densitometer beam configuration.

..

Input: ' PA I P8 1 Pc OS functions

of Time -

-Yes

PA : Pe = Pc within + 5°/o Homogeneous (H l

No -

' Yes Pc > Pe Annular (A l

No

-

Yes PA > Pc StrotH ied ( s)

No

-v Yes

PA < Pe Inverted Annu lor (!)

'

No

Default (0) ANC-A-7!164

Fig. ~· Gamma densitometer flow regime logic.

15 /

measure velocity .. The density is obtained from these measurements by

dividing the momentum flux by the square of velocity:

p 2 = pV -2

v

(from drag disc) ·

(from turbine meters).

This simplified approach neglects the effects of phase slip, velocity,

and the density distributions near the measurement locations.

Lif'juid levels were obtained by means of (a) differential pressure

transducers in the pressurizer, accumulators, a.nd suppression tank, and

(b) liquid detectors, which sense the conductivity of the fluid near each of a series of electrical contacts, in the reactor vessel.

Valv~· positions (analog indication from 0 to 100% of opening) were

measured. by either resistance potentiometers or . differential

transformers.

Mechanical pump speed was measured by an eddy current displacement

transducer which used a slotted metallic target attached to the top of

the pump motor shaft. The target contains six asymmetrical slots such that pump speed and direction of rotation can be determined. Pump speed

was also calculated from the PSMG set frequency. No allowance for slip

between the electrical field and the rotor was used in this latter

calculation.

Acceleration, displacement, mechanical strain, and valve off-on

indicators were sensed by accelr.rometers, linear variable differential transformers, bonded strain gages, and microswitches, respectively.

Since these are not considered of prime importance in understanding this

experiment, they are not included here. This information will he

reported in an addendum to this report if sufficient requests for the

information are received.

16

Many variables can be computed by combining measured parameters. Some of the~e variables are shown in Section VII.

The data acquisition and visual display system (DAVDS) was used to -

record the measurement data from the various instrumentation. systems on a combination of narrow-band digital recorders, medium-band multiplexed frequency modulator (FM) analog tape recorders, wide-band analog tape recorders, strip charts, and oscillograph recorders. Redundant records were. made where different uses dictated more than one recording mode or ' extra safety measures were desired for critical measurements.

A digital computer was used to collect the data at the LOFT Facility and to perform equipment calibrations and post-test data reduction and plotti.t1g. Immediately following the test, the computer was used to reduce critical channels of digital data so that a decision could be made quickly as to the success of the experiment. The digital data was transferred to magnetic tape and the tape recorded analog data was converted into digital form on magnetic tape compatable with the IBM-360/75 computer data processing programs.

The IBM-360/75 computer was used to further reduce the data. Calibration factors were first applied to produce engineering units data plots so that engineering specialists could examine each channel for discrepancies or unexpected events. After the data graphs were examined and qualified, ·they were then used to generate graphs and compute variables. Specifics of these topics are given in Section VII and a complete description of the data acquisition system and data reduction ·is given in References 8 anq 9.

figure 2 shows a piping schematic with instrument locations indicated. Table I gives the nomenclature for LOFT instrumentation designations. Figure 5 shows an isometric view of the major system components with instrument locations indicated, and Figures 6 through 12 give more specific locations for instruments located on individual components. Reference 4 should be consulted for details of instrument design and locations. (Locations, ranges, and frequency responses for

17

TABLE I

NOMENCLATURE FOR LOFT INSTRUMENTATION

Designations for the different types of transducers.

1. cv - Control Valve 2. DE - Densitometer 3. FE - Flow 4. FT· Fluw 5. LE - Level

fi.' LIT -· Lcvc 1 7. LT - Level 8. ME - Momentum Flux 9. PdE - Differential Pressure

10. PE - Pressure 11. PT - Pressure 12. RPE - Pump Speed 1 J. TE ·· Temperature 14. TT - Temperature

Designations for the different systems, except for·the nuclear core which has not been installed.

1. BL - Broken Loop 2. cs Core Simulator 3. PC - Intact Loop 4. RV - Reactor Vessel 5. SG - Steam Generator 6. ST - Downcomer Instrument Stalk 7. sv - Olowdown Suprcssion Tank

18

PT-P139-2 PT -PI39-~· PT- P139-4 FT-PI39-Z7-1 FT-PI39-27-2 FT -P 139-27-3

TE-SG-1 TE -SG-2 TE-Su-3

I !I

Pressurizer

PE-PC-4 IL T -P139-6 LT -P139-7 L T -P139-8 TE-P139-20 TE-P139-19

PCP-1-F, PCP-1-1 PCP-1-V, PCP-2-F PCP-2-1, PGP-2-V RPE-PC-1,RPE"PC-2

Fig. 5

PdE-BL-4 PdE-BV 8

PdE-BL- 3 1 PdE-BL-2 \\

DE-BL-1 \ FE-BL-1 ME-B'.-1 PE -BL-1 TE-BL-1

~

\TE-P139-28-2, TE-P139-29

Quick Opening Slowdown Valve CV-PI38-t (LVDT) PT-PI38-tt2 TE-PI38-62

ANC-C-7003

LOFT thermJ-fluids measurements instrumentation.

...

Sto 335,913

Sto 325.~~5~6 ____________ _ lerna Is Holddown

I. pring and Shim Plates

1' pper Core Support tructure low Skirt Assembly ~--- --------- -----~~Htg~~~RTf'ffi'n~~aJC1~~071

Intact LOOP

Core Simulator

Hot Leg

Care Simulator lnst rumentatian Stalk

+-+H&P~~~~---270° ECC 280°

Intact Loop

Cold Leg

Sto ~QO.OO

I Sto 286.36

Brok~n Loop Hot Leg

II Sto 264.00

Orifi<:e Plqte ~IQ.g'\~.~OO Assembly _ ___.

Sto .ZOO, 249

Sta 19t.F.lt0

Sto 168.490

SECTION A -A

Fig. 6

Sto 149.925

Sto 125.430

Sto tf3.Z47

Sto 96.437

Sto 112.650 Sto Sto 4 !50

* Core Sirnulotor Instrumentation Stalk Shown tar Relative Elev~tions only.

LOFT reactor vessel instrumentation.

20

pper Section eactor Vesse I

Support Barrel

Simulator rumentation Stalk roken Loop Cold Leg Vessel Filler Assembly Upper SectioQ

rA e PlntP. A"'emhly

e Simulator embly Housing

sel Filler Assembly

LEGEND

Thormocouples (TE's) Liquid Level Stings

er Sect ion

w Skirt Assembly rmediate Section

kirf Assembly A••eml.oly ·

r Core Support turP.

or Vessel 11om

( LE's)

Pressure (PE's 6 PdE

Oro~;~ (liS<:$ (ME's)

Turbinemeter (FE's)

'sl

t; J:C: oe> ,J-

0..

Inches above Reactor Vessel

Bottom

Jntact Loop Cold Leg I I Oowncomer I Stalk No.2

Broken Loop. Hot Leg

Core* Simulator

Stalk 1 Oowncomer Broken Loop

Cold Leg 1 I t-'Stalk No. t

Intact Loop Hot Le9

; .... .... .... .... k'l ....... "'I"'"' "' "' "' "' "' "' "' "' -·- - c;; Ui :i> ~~ 1 5 1 8~ en "' "' .... - OICDia>-..~ en"' "' .... "' 0 ~=~:~ 3 -..j

~ 1 "' .... "' 0 oa 0 0 0 0 oooooooo 0 0 0 0 0 0 0 0 0 0 0 0

220 a 1a j_a f Ia llo f_uolto lo j_o lo L

0 f 10 10 10 10~ ( 10 10 10 10 t lol lol lo I 10 10 t 1° 1° 10

I I ~ -+i,PdE-RV-4!-1---ta

0 I ntoct Loop Hot Leg

I lPE-2ST 3FF ..i-iPE-IST-3FF 210 ! : j.pE-CS-IA8B ....- PE- 1ST 3A8B

-~.J-_s-_g§T~~ --; _.;.PE-CS-2FF

I I :a-<PE-CS-IFF LE-IST-2-1 200-

r---- -- ----:,:---- --i--1= ------:::1::------I I Oowncomer

190 I ..,!.TE-2ST- t I J_ ECC Injection TE-IST-1

~--=vLE-2ST-2-2 ~E-CS-1 li rL-E-IST-2-2

180 I I E -CS-1

+¥1:-LE-2ST-2-3 E-CS -4 -~..f LE-IST-2-3 ---- r-.- -- -~-+-- --- ~------- - - --- I ~-------I I

170 lPdE-2ST-2 , I

JPdE-CS-t("'' I l '~TE- 2ST-2 TE-IST-2 -- .......... - ~~f'-1st-2-4 -- 0 -MO 00 .... ..... ,_,_ ~-- ··-··- '"~--

/l ---

160-LE-IST-2-4

_l~E-2ST·2·5 LE-IST-2-5 ---- f- -- ------ . _ . ..., ''IAJ ",. _,_ --- -...:.=---

150 I PdE-RV-1 lo Suooreulon I J-TE·2ST-3 Tank I I

I - TE-IST-3 140 ---- 1--- --T"'-ju- 2S'T=2=&-- ---------- --rt -:-.-- ----- -----

PdE-RV-3 'To Intact LOop LE-IST-2-6

I I Cold Leg I I 130 I 1LE-2ST-2-7 -~4 LE-IST-2-7 ---- t-·-- --+.-t- ------- --------- -------: ------

I I 120- I ..1-TE -2ST-4 ~ -~ TE-IST-4

- - T*'kE-2ST-2=8 -

"' LE-IST-2-6 -110 I I I

-- ---~~~~~T~~--- --H LE-IST-2-9 --- ---------- ------ r-----100 I I

I J-TE-2ST-5 lj.. TE-IST-5

lrLE-2ST-2-IO - li- 'LE-IST-2-10

-- ·-90

1---- I ILE-2ST-2-II --44 LE-IST-2 -II eo- -- t--ToFf--------- ----------- ~-=·-- ---- -----

I I I I I I I I

70- -- t'f~-~ ~~~ ~:- I~ I _..., TE-IST-6

r- t- - -- i1 7:"'~=-TS'f-~if" ·- --· -·· ... ". 60-

MOTT _rbt OTT

50 RFE-2ST-I R-FE-IST-1 .-rTI:._-L::L - - .. t.:: l::l_l,- --

40.:: ""' ~E-2ST-I ~ ij-ME-IST-1 ~

~ I I

..... I I

~

I I il-TE-!!T•T TE-ISt-t

t--- t-- -~w-fl.,t,-Z}!=I-1 ___ ---------- -t~ LE -IST=i":-'1 . -------------

A-TE-2ST-8 0 TE-IST-8

r30 r- r- T*'l='LE-2ST-I-2 - ·--·

-r-~ -LE -1ST- 4 -Z,

t-- _.f'~~T tLA.!lB-rr~2li =!} ____ ----- _ _ru~ ~A .!l B_,A.,; TE-IST 9 t---·- --I LE-2ST-I-3 LE-=-iST-t-3-

r=~ _es;-.l.H - .LEF:.r..:rr~=-2H:::!Q_ -- ...... - .. --- _ = gf._::!ST . t FF-?A.:: TE·IiT- 10 :>n , ___ ~-T LE-IsT-r-4- -----

1 E-2ST-I-~

I ··-"" ... ---~ ··- --~··•·"······-~·········-··· ··-. ·- ,.,,_,,,,

----_ ___:_ -+ ·-::rc:cc~T-!! ---------- --;4 TE-IST-11-- "91------- LE-TST-=-t-5- -----I ,LE-2ST-t-5

__ -r~rs..:2..§..T =.J2 ____ --~ TE-IST-12 tO------- ---------- r,-;------ -----I

1LE-ZST-4-6 LE- IST-1-6

·-··--· .. ~I e.J------.- ::::rE-2ST 13 -- --------·-- - :.._-+~ r!-E-=.lli ::.!.3 ___ -----

- T.lo:::J:"LE-2ST-=-i-7 LE-IST-1-7 I I l I I I -· o-

315°

Counter Clockwise ------- ANC-C-7217

212.0 209,4

200.4

196.38

IB9.3 188.4

176,4

165.:5 164.4

l!i2,4

141.3 140,4

12B,4

117.3 116.4

104,4

93.3 92.4

80.4

69.3 btl.4

47.1 45.91 45.48

33.3 32.4

~ij:~2 28.4

25.3 24.4

g!,~ 20.4

'17.3 16.4

13.3 12.4

9.3 8.4

Vapor Temper.atu re, Thermocouple TE- Pl39-19

Liquid Temperature, Thermocouple TE-P139-20

12 Electrical Heaters (4 k W each)

Fig. 7

J:oot------------Spray Inlet Line

c::::=:>-o---Pressurizer Pressure Measurement PE-PC-4

~p

Measurement for Liquid Level (3places)(typical) LT-P139-6 (CH A) LT-PI39- 7 (CH 8) LT-P139-8 (CII C l

ANC-A-7565

LOFT pressurizer instrumentation.

21

Feedwater Inlet

Strain Gao .. ( 4-3Gao• Rosettes) SE-PCi4-i

thru SE-PCt4-t2

Primary Coolant Inlet

Fig. 8

..---·Accelerometer (2) AE-PC17-1

AE-PCf7-2

2 Differential Pressure for. FHdwater Liquid Level

~----~-LT-P4-8A

LT-P4-88

Coolant Temperature Thermeoo11ple TE-SG-3

strain Gove(4-3 Gaoe RoHttes) SE-PC15-1 thru SE- PCt5-12

Coolent Ternperatlri Thtrrnocouple .(on Handhot .. )

~r-tt----lf.W...-.d-~--TE-SG-1

rimary Coolant Outlet

Pressure Transducer ANC-A-!M>I9

LOFT steam generator instrumentation.

22

Pump Speed Probe (RPE-PC-1 & RPE-PC-2)

Component Cooling Water Outlet

Component Cooling Water Inlet

3 Acceleterometers AE-PC-18-1 thru AE-PC-18-3 (pump no. 1) AE-PC-19-1 thru AE-PC-19-3 (pump no. 2)

3 Strain Gage Rosettes SE-PC-17-1 thru SE-PC-17-12 (pump no. 1) SE-PC-17-13 thru SE-PC-17-20 (pump no. 2)

Inlet

Fig. 9 LOFT irrtact loop pump 1nstrumentation.

23

Impeller (6 vanes)

Liquid Temperature,........._ i'hermoeou~le "', Tonk A: TE- P120-41 TankB: TE-PI20-27

AP Measurement for~ Liquid Level

rank A; L.tT .. Pl20 -44· TonkB: LIT- P120-30

Accumulator Tonk Pressure TankA: PT-PI20-43 Tonk B: PT- Pl20-29

Borated Water

Accumulator Flow Inlet

A: CV-PI20-42 B: CV-P120-28

Borated Water a.---Inlet

~+----_.:,tondpipe

(Jut I et ------~~

LOFT ACCUMULATOR TANK A 88

ANC-A- !5073

Fig. 10 LOFT accumulator instrumentation.

24

Ace. Vent li,,e Valvt (potentiometer} (CV- P120·39)

N2 Suppl) to Ace. A, Valve

(polonliomelor) CV-P120-38

Ace Oisc~,arve li,e Valve -----"""';(!f (level switch]· CV-P 20·47

Ace Oischaroe Bypass line Valve ----t-1ii>.;tJ (level switch) CV-PI20·48

Cold LeQ niection Pressure PT -P120-61

Cold IBQ lr,jection femperoture ( RTD) TT -P120··62 -----=,.. ..... ~ Cold lnjec:ion lsatction Valve (limit switch) CV -IP 120-90

·Intact loop Cold LoQ

LPI S Pump to Lower Plen•m Pressure

( PT ->120-64

\. LPIS Pump to LOwer Plon•m (RTO) TT->120-65

LPIS Flow

LP.IS Heotex.chanoer Ou11et

T..,poroture (TC)

T[ -Pi20- 100

LPIS Heat Ex.chanoe'

Borated water Storo;e Ta,,k

ECC·T·42

Ace. Olacharoe Isolation Valve

VA:~..._-(Ievel switch} CV- P120 -50

BWST Vo ivo CV -Pi20- 98

Note:

Elevation 4829

Elevation 4807'

4790

Veuel Wall

Brokpn Loop Reci:culotion

Far the Instrumentation Between tho BWST and tt'le Containment Vessel Wall, Consult tho Loll ECC S1stom Process Instrumentation (rioht side} Orawino.

to LPIS pump, Valve (limit switch) CV·P120·80

BWST to LPIS pump, Valve (limit switch) CV- Pi20-81

Sump

Oiachoroe Pressure

Pump ECC·P·644

Fig. 11 LOFT ECC system instrumentation (left side).

PE-SV-tt

"e" END

1 oFr N ...

·o ·o N

I o

'-ttOs,-~--~o-.....: ,___ ___ 136.5--·

l_l

·o -0 0 0 -0 -0 ·o 7o ~ <D CX) 2 ~ ! ~ ~

26

LOFT N ,....

I

"A .. END

PE-SV-12

I . I I 1-----t3G.5~-- _ , PE-SV-24

tool· I..... j ~-~ '.......-r-A

I I --= "'" _ i ..

-~S .QN,_:N 10

;;;~~:::: ;1;

0 -0 -0 -0 -0 -0 -0 -~ 0 N ~ <D CX) 0 N N N N N N .., .., ..,

Note:

Alt Dimensions in Inches

• oo VIEW A-A

180°

VIEW B-8

vacuum Relief System

VIEW C-C

Fig. 12

,....--- PT-PI38-23

B lowdown Header

Slowdown Suppression Tank

Vacuum Rei ief System Manway

TOP VIEW

LOFT suppression tank instrumentation.

~·

instruments used in obtaining data presented in this report may also be obtained from Table VI which_ is presented in Section VII.)

Instruments were calibrated before installation either by the. iristrument vendor or at the INEL. Calibration data were then correlated with other parameters to determine the functional relationships between systemmatic errors and variables other th~n those the instrument was designed to measure. These error functions were then represented by mathematical equations (usually in the form of polynomiai-s of degree five or less) and incorporated in the data reduction program.

The turbine meters arid the drag discs in the intact loop were calibrated to convert the point·measurement values to the mean values across the entire flow area. ·These calibrations were performed using the data from the single-phase variable frequency pump tests conducted

~ .

prior to blowdown initiation. Least squares curve fits were calculated for the square ~ooi of the intact loop differential pressures plotted against the pump sp~ed to confirm the adequacy of the differential pressure offset corrections. Similarly, the intact loop venturi meter data were plotted against the square root of the corrected differential pressure measurements to confirm or adjust the venturi meter offset corrections. The corrected venturi meter data were then used to calculate average velocities and momentum fluxes in the inta_ct loop and the reactor vessel. These calculated quantities were' subsequently compared to the measured turbine meter velocities and drag disc momentum fluxes to verify ·or to provide changes to the respective instrument calibration equations.

Additional calibrations were performed on specified turbine meters and drag discs to convert the point measurements to average measurements. These instruments· included broken loop turbine meters and drag discs in the intact loop and reactor vessel which were overranged during the pump frequency tests. In the intact loop and reactor vessel, the flow rates calculated using the turbine meters and their associated areas were normalized with the intact loop venturi during steady- state. (initial) conditions to determine the calibration factors for the

27·

turbine flowmeters. The flow rate for the turbine meter in the core

simulator was calculated with a core flow area equal to that of the

nuclear core to be installed for Test Ll-5. Calibration factors were then determined by normalizing this rate. These calibration factors for

flow rate with the venturi flow the turbine meters were then

squared and applied to the respective drag discs. Similar calibration f de Lur~ were deve1 oped for the broken ·1 oop tlr·dy tl i scs using the results of accumulator blowdown tests (where the accumulator flow was directed through the hrnkPn loop). Average m9asurements were then obtuined by

multiplying thP calibration factors with the respective point measurements. The additional calibration factors obtained in this manner and used in the presented data for Test Ll-3 are summarized below:

rc-o~-1 ==---- 1 '00 MF-RI-1 ------ I.UU FE~BL-2 ------ 1.00 ME-BL-2 ------ 1.00

ME-CS-1 ------ 0.0727

ME-PC-3 ------ 0.550

The presented data for average velocity and average momentum flux

are based on the following flow areas at the instrument locations:

Instrument Flow Area

FE-OL-1 and -2 ME-BL-1 and -2

FE-PC-1, -2, and -3 0.6485 ft 2

ME-PC-1, -2, and -3

FE-CS-1 1.78 ft2

ME-CS-1

FE-lST-1 and FE-2ST-l 1.52 ft2

ME-lST-1 and ME-ZST-1

28

Upper and lower error bands based on 95% (2o) confidence levels were added as overlays to the plots of certain representative instruments. These plots can be found in Section 5 of the presented data. The error band plots presented for the LOFT process instruments are valid only for steady-state measurements. These· instruments are

listed in Reference 4 and are characterized by the P ... designation in the channel~measurement identifications~

Information on the calibration factors, accuracy, and response of specific instruments is given in the LOFT Experimental Measurements Uncert~inty Analysis[lO]_ Instrument calibrations and system testing

conducted subsequent to completing the uncertainty analysis have been used to update ~he information presented and to process the data contained herein. Reference 10 is currently being revised to reflect the improved information and the.observed performance obtained to date.

29

IV. TEST PROCEDURES

In preparation for Test Ll-3, the primary coolant system was filled and vented and the system water chemistry was established to the specifications listed in Table V. The secondary coolant system, ECCS, blowdown suppression system, and supporting plant systems were configured as specified in the experiment operating specification (EOS)[lJ.

Prior to the heatup of the plant, several tests were performed on

the LOFT system. These tests included plant requalification tests, QOBV operation and seat leakage checks. pump coastdown runs, LOCE control system checks, and operational verification of newly installed 1nstrumentation. Selected system process instrumentation was ca·librated and an electrical calibration was performed on the DAVDS.

The primary coolant system pressure was hydrostatically increased to 200, 500, 1000, 1500, 2000, and 2250 psig at cold plant temperature

and zero flow conditions. The DAVDS recorded 20 seconds of data at each pressure plateau to provide information to determine the degree of sensitivity of the pressure sensing instruments. The system was concurrently inspected for leakage at the various test pressures.

ThA pl~nt w~~ hrouaht to the initial temperature of 540°F in a

stepwise manner using the work energy addition of the primary coolant pumps. During the warmup, the purification and sampling systems were

valved into the primary system to maintain water chemistry requirements and to provide a water sample at system conditions for subsequent

analysis. Isothermal conditions were obtained in the nonflowing broken loop by means of the recirculation lines back to the intact loop. Before plant temperature exceeded 200°F, the secondary side of the steam

generator was drained to the 0% power program reference level

(116 inches from the top of the tube sheet), water chemistry was

established, and the steam generator secondary side was valved out.

Concurrently with the primary plant heatup, the BDST temperature was

30

increased as the tank was pressurized with nitrogen to its specified initial conditions.

The plant was stabilized at three points during heatup: 250°F -'500 psig, 460°F - 2250 psig, and 540°F 2250 psig. At- each stabilization point a burst (20 to 30 seconds) of data was recorded

under flow and no-flow conditions for calibration checks and to determine the degree of instrument temperature sensitivity. At the 460°F stabilization point, ~ single-phase pump coastdown test was

conducted with an initial flow of 3.6 x 106 lhm/hr. At the 540°F stabiliZation point, frequency tests were performed by varying primary coolant pump frequency from 20 to.60 Hz in 10-Hz increments. Following the frequency ·tests, single-phase pump coastdown tests were conducted with initial flows of 2.15 x 106 lbm/hr and 3.6 x 106 lbm/hr. Data were recorded for about 60 seconds for each of the three pump coastdowns, and

the data were used for calibration checks. Following each pump coastdown, data were recorded for zero-flow conditions. When the plant temperat~re was stabilized at 540°F, a pressure test was performed at zero-flow conditions by varying the primary coolant system pressure from 2250 to 1450 psig and back to 2250 psig in-.200-psig increments. At each pressure plateau, approximately 20 seconds of DAVDS data were recorded to determine the degree of hot instrument pressure sensitivity. When plant conditions were again stabilized at 540°F and 2250 psig, the plant was allowed to soak for more than 6 hrs to assure isothermal conditions

for the blowdown. During this 6-hr soak an electrical calibration of the DAVDS was performed. Additionally, ECCS accumulator ACC-A was filled and pressurized to its specified values and a dry run of all the critical steps required prior to blowdown initiation was conducted.

Prior to blowdown initiation, the system parameters were checked to insure that they were within specified bands and last-minute instrument

and valve lineup checks were performed. During this period, the

initial-condition water samples were taken from the primary coolant

system, the secondary coolant system, and the BDST. The pressurizer,

steam generator, and BDST water levels were established. A computer

program ca 1 i brati on and a data integrity check o·f the DAVDS was

31

performed. The purification system, which was the primary mode of plant temperature control, was valved out. The conditions in the intact loop were established to provide 2.15 x 106 lbm/hr flow with temperature ~nrl pressure at 540°F and 2250 psig, respectively, at the time of blowdown initiation. Primary coolant pump injection flow was initiated and the

broken loop recirculation lines to the intact loop were closed.

Immediately prior to blowdown (within 60 seconds)the DAVDS was activated and data recording was started, the QOBV isolation valves were opened, and the 11re~~ur1zer heute1·s were secun~LI. Pressure fluctuations noted in the recorded data just prior to blowdown initiation are due to intermittent operation of the HPIS injection to maintain the pretest conditions. Test Ll-3 blowdown was initiated. QOBV-1 commenced opening 2.5 msec before QOBV-2 and opened to a 12-ir1ch Schedule 160 pipe area in 23 msec; QOBV-2 opened to the same flow area in 17 msec. Thus Test Ll-3 successfully s~mulated a simyltaneous 200% offset rnlrl leg shear.

Electrical power to the PSMG sets was terminated within 1 second after blowdown initiation which allowed the pumps to coast down under the influence of the flywheels and the fluid dynamic forces on the pump impe1lers. The PSMG set field breakers were tripped at 24 seconds (before the primary coolant pumps coasted down below

12.5 Hz).

FCC injection was directed vessel during blowdown. Injection

to the lower plenum of the reactor from accumulator ACC-A failed to

initiate due to an improper val_ve lineup. HPIS pu~p A was initiated by LOCE control 32.6 seconds after the initiation of blowdown and injected at a flow rate of 18.4 gpm. The specified initiation of the HPIS was 22 + 2 seconds and at a flow rate of 17.2 + 2 gpm. This discrepancy had

no detrimental effect on the test. LPIS pump A was ·initiated by LOCE control 37.5 seconds after the initiation of blowdown.

The BDST spray was manually initiated at 94.5 seconds after

blowdown and was adjusted to a total flow rate of 320 gpm. Initially,

spray flow suction was takeri from the BDST. Approximately 213 seconds

32

after blowdown initiation,· BDSTSS pump suction was shifted from the BDST to the BWST. This departure from procedure had no adverse impact on the conduct of the test. · BDSTSS flow was c~ntinued for approximately 5.7 min and then secured.

The DAVDS digital recording system obtained appr6ximately 6 minutes of· data /after simulated rupture and was secured. -The DAVDS analog system continued recording blowdown suppression tank parameters for 10 minutes after blowdown initiation and was then secured. An electrical calibration o1 the DAVDS was performed following the test completion.

A sequence of events for Test Ll-3 is provided in Table II.

33

TABLE II

CHRONOLOGY OF EVENTS FOR TEST Ll-3

Event Time After Bl owdown Ini ti:a.ti OJ;l' (:s~c-).

Ll-3 Initiation

End. of subcooled blowdown

PCS[a] pump trip

Pressurizer empty

Accumulator ACC-A injection initiation

HPIS ·injection initiation

LPIS 1njection initiation

Cnd of sdturated blowdown

PCS-BDST reached equilibrium pressure

First evidence of ECC in lower plenum

Reactor vessel lower plenum liquid full

BDST spray initiated (pump sucLiun from BDST)

BDST spray pump suction ~hffted to BWST

BDST spray completed

[a] Primary coolant system. [b] Specified in EOS to be 22 + 2 seconds. [c] Specified in EOS to be 35.5 + 2 seconds.

34

0

•1,1. 0

'" 12

Failed to initiate

32.6[b]

37.5[c]

rv50

rv50

56.3

70.6

94.5

rv213

rv436

V. INITIAL CONDITIONS

The initial conditions and pres.ented in Table III along with to the blowdown initiation. justification for their selection

tolerance bands for Test Ll-3 are the values measured immediately prior These pretest requirements and the are.specified in EOS Volume 2[l].

Only one initial condition was out of tolerance for this test: The measured intact loop flow rate was. 2.34 x 106 lbm/hr instead of the maximum 2.2 x 106 lbm/hr as specified in EOS Volume 2. This discrepancy did not have any adverse effect on the experiment.

Table IV gives the fluid temperature distribution of the primary coolant system immediately prior to ·blowdown initiation. ·As can be seen, the system temperature distribution was nearly constant, except for the pressurizer liquid and vapor space. This essentially isothermal condition was due to the greater than 6-hour soak at the initial condition temperature and pressure before the commencement of blowdown.

Table V specifies the required water chemistry for the primary coolant system, the.blowdown system. In addition, ·the these systems are presented

suppression tank, and the secondary coolant results of the water chemistry analysis for for. pre-LOCE and· post-LOCE conditions.

These analyses were required to utilize the data from the reactor vessel downcomer liquid level probes.

35

TABLE III.

LOCE Ll-3 INITIAL CONDITIONS

Parameter

Primary coolant system: Flow rate (lbm/hr) Pressure (psig)[a]

Temperature ( 0 F)

ECC accumulator: Gas volume (ft3) Water volume injected Pressure (psig)[a] Temperature ( 0 F)

Pressurizer: Steam volume (ft3)

.Water volume (ft3) Water temperature (°F)

Pressure {psig)[a]

Steam generator secondary: Water volume (ft3) Water level (in .. ) Water temperature (or)

Pressure {psig)[a]

Suppression tank: Liquid level (in. ) Gas volume (ft3) · Liquid volume (ft3)

Downcomer submergence

(ft3)

(in.)

EOS S pee ifi ed Value

2.15 + 0.05xlo6

2250 + 25 540 + 2

39 + 2.4 90.8 + 2.4 600 + 25

90 + 5

Not specified 22.4 +' 3. 5

Specified by saturation pressure 2250 + 15

Not specified 116 t 1 S1-1ed f1 P.rl by .

saturation conditions Specified by saturation conditions

50.0 + 1 Not specified 1036 + 28 16 + ~~b]

36

Measured Value

2.34 X 106

2256 540

Failed to

initiate flow

14.2 19.8 656 (vapor) 645 (liquid) 2250

121.5 116

539

945

50.8 1957 1053 17[b]

TABLE III (contdJ

Parameter

Water temperature (°F) Pressure (gas space) {psig)[a]

Differenti~l water level between downcomer interior volume and suppression tank (in.)

EOS Specified Value

188.5 + 6.5

11.9 + 2

Not specified

[a] Local barometric pressure = 12.5 psia. [b] Based on average submergence of four downcomers.

37

Measured Value

188

10

5.6

TABLE IV

PRIMARY COOLANT TEMPERATURE DISTRIBUTION AT RUPTURC

Location Detector' Temperature (uF)

Intact loop hot leg (near vessel) TE-PC-2 543

, Intact loop steam generator inlet TE-SG-1 538

Intact 1 oop steam generator outlet . TE-SG.-2 542

Intact 1 oop .co 1 d 1 eg (near steam generator outlet) TE-PC-3 542

Intact loop cold leg (near vessel) TE-PC-1 541

Reactor vessel downcomer: Instrument stalk TE-lST-2 540 Instrument stalk 2 TE-2ST-2 541

Reactor vessel lower plenum: Instrument s ta 1 k TE-lST-9 540 Instrument stalk 2 TE-2ST-9 539

Reactor vessel core simulator TE-CS-1 544

Broken 1 oop hot leg (near vessel) TE-BL-2 537

Broken loop hot leg (steam generator simulator inlet)[a] PE-BL-3 543 (~3. 9)

38

TABLE IV ( contd.)

Locc1tion [)etector Temperature (°F)

Broken loop cold 1 eg (near vessel) TE-BL-1 541

Broken loop cold leg at break plane[a] PE-BL-3 528 {~4. 7)

Intact loop pressurizer: Liquid space TE-Pl39-20 645 Vapor space TE-Pl39-19 656

[a] From saturation pressure at the end of subcooled blowdown.

39

TABLE V

WATER CHEMISTRY RESULTS FOF: TES" L 1-3

Primar~ Coolant Intact Lao~ Blowdown

Parameter S~ecifi ed Pre-LJCE[a]Post-LOCE[b]Specified

PH 9.5-10.5 1•). 11 9.81 4.0-"0.5

Conductivity ( llmho) 1-40 24.6 15.8 24-40 (025 C) em

Total solids (ppm) 25 7.5 '

Total gas (cc/kg) 100 max 32.04

Dissolved otygen (ppm) 0.10 max <0.005 4.55

Lithium (ppm) 0.2-2.2 0.7 0.6

~ Hydrazine (ppm) 0

(at <250°F} 1. 0 min <C. 01 <1. 0

Chloride (ppm} 0.15 max .::0.1 <0. 1 0.15 11ax

Dissolved solids (ppm) 25 7.5

Undissolved solids (ppm) 1.0 max <j,5 <1. 0 1. 0 max

Hardness (ppm)

Phosphate (ppm)

Gas o6

content (%) (by v lume)

[a] Sample taken upstream of the prirr•ary coolant system ion excharger. [b] Sample taken from the pressurize~.

Su~~ression Tank Pre-LOCE Post-_OCE

9.76 9.62

"13. 5 16.5

28 75.5

20.77 19.5

·:0. 1 <0. 1

~-s 75

c0.5 0.5

9

Se:ondar~ Coolant S~stem S~ecified Pre-LOCE

9.0-10.2 9. 41

56

39.9

9

0.10 max 0

1 . 0 min <0 .1

0.5 max <0. 1

500 max 39

50 max 0.9

<0. 1

15-75 35.2

VI. DATA CONSISTENCY CHECKS

As a subsequent step in the data reduction process described in ·section III, all data presented in this report were subjected to a thorough review to verify that they were consistent and reasonable. Where possible, instrument channel outputs and computed parameters were compared to test predictions, previous tests, corresponding parameter channels, and calculated quantities. In many instances, these consistency checks were _performed as data plot overlays and, therefore, the respective figure numbers are specified below as the individual topics are discussed. For other measurements, the comparisons and r~sulting calculations were performed within the company and are not included in this report. Those measurement comparisons that were determined to be within the accuracy of the particular instrument, as specified in Reference 10, were labeled as qualified engineering units data (QEUD). Specifically, several techniques have been developed and employed to perform data consistency checks on the presented data; these techniques are discussed below.

Measured system· temperatures were qualified where possible by reviewing the isothermal temperature distributions just prior to blowdown initiation and during the blowdown transient. When temperatures measuring a similar condition were within the specified accuracy of the detectors, the detector output was considered reasonable and was qualified. All primary coolant system (PCS) temperature channels were reviewed in this manner, and selected initial temperature measurements are summarized in Table IV. Selected PCS temperature channels were overlaid in Figures 135 through 146 and Figures 157 through 175 for comparison of the temperature distribution. The pressurizer liquid and vapor space, temperatures were checked for cpnsistency by comparing ~hese values with the saturation temperature for the corresponding pressurizer pressure at various· points in time. This check was valid prior to and during the system blowdown until the pressurizer emptied at 12 seconds. Similarly, steam generator secondary coolant system (SCS) temperature was examined throughout the test by comparing the measured temperature with the saturation temperature for

41

the respective SCS pressure. BDST temperature elements TE-SV-1-6 and

TE-SV-7-12 were evaluated by comparing the pretest measurements of the

thermocouples in the same horizontal stratum. Overlays of these parameters are presented in Figures 151 through 156. Figures 147 through 150 compare TE-SV-1-4 and TE-SV-7-10 in the vertical plane of the gas space in the BDST. While the data from these temperature instruments are compared for_ consistency, it should be noted that TE-SV-1-4 and TE-SV-7-10 may not represent the actual vapor space tempertaure since these instruments were designed to measure liquid temperature. TE-SV-5-6 and TE-SV-11-12 could not be compared for pretest temperature distribution in the vertical plane due to

temperature stratification in the BDST liquid. BDST temperature comparison after the initiation of blowdown was not meaningful for data consistency checks due to uneven mixin~ and condensation producin~

temperature stratification in the tank.

Pressure data were reviewed in a similar manner. During the approach to Test Ll-3 initial conditions with the primary coolant pumps secured, the PCS was raised to various specified temperatures and pressures as described in Section V. At each data point, PCS pressure

measurement detectors were compared to a 0.1% accuracy, 0 to 5000 psig pressure test gauge to verify that the slope had not statistically changed and to establish the offset of the instrument. Immediately prior to blowdown, PCS pressures were again compared to the test gauge standard to ensure that all detectors were measuring within their specified accuracy bands. During the blowdown transient, pressure data from corresponding measurement locations were compared by overlaying the data plots. These plots are presented in Figures 100 through 114. Pressurizer pressure was qualified by comparison with PCS pressure

channels and by saturation temperature as discussed above; SCS pressure was qualified by comparison of saturation temperature to the measured temperature as . presented in the paragraph on temperature te~hniques.

The BDST pressure instruments were evaluated by compariny process and

experimental pressure measurements prior to and during the blowdown

transient. Representative instrument plots are presented for this

comparison in Figures 21 through 42 and Figures 115 through 127. It

42

should be noted that the BDST experimental pressure data have all been adjusted to

\ a 0-psig initial pressure for comparison of the tank

pressure rise during blowdown. Initial BDST pressure can be obtained from the data plots of PT-Pl38-55 and.PT-Pl3R-56 in Figure 132.

Comparison of measu~ed temperature with the saturation temperature of the press~re measurement at the same location provided another method to verify PCS data consistency. This technique, however, was valid only during the saturated blowdown transient up till the time the measurement location voided of fluid. Afte~ voiding occ~rred, the measured temperature increased above the corresponding saturation temperature due to radiant heating of . the detector element by the structural system components and detector element stem conduction. Temperature detectors

' in the reactor vessel which became wetted by the ECCS lower plenum injection.displayed a measured temperature which decreased below the corresponding saturation temperature as the detector became immersed in the cooler fluid. Comparisons of saturated temperature and measured temperature are presented in Figures 257 through 264.

Data consistency checks for the differential pressure measurements were provided by ~everal basic methods. Prior to blowdown initiatiori, zero-flow data were recorded to .determine instrument offsets. PCS operating conditions were then established as specified in EOS Volume 2, and selected PCS pressure drops were compared with predicted values.. At various PCS operating conditions, intact loop flow resistance coefficients were calculated and verified to remain essentially constant and to agree with previously tabulated data. Further consistency checks were performed on the intact loop differential pressure instruments by plotting the square root of the differential pressure against pump speed using data from the pump frequency tests conducted prior to blowdown. The results of least squares curve fits performed on these plots were

then used to confirm instrument zero offsets. Both prior to and during the blowdown transient, ·differential pressure measurements were compared with the differential pressure computed by subtracting appropriate absolute pressure. measurements. Finally, pressure closure was

43

calculated for three flow loops: (a) the PCS intact loop, (b) the broken loop hot leg to the BDST, and (c) the broken loop cold leg to the BDST. The pressure closure for these three loops is defined. in Table VII and presented for loop (a) in Figure 246. Investigation of these data plots revealed that the algebraic sum of the differential pressures in the two broken loops was not zero on the blowdown transient and remained positive. lt is believed that this deviation is ca·used by a velocity head and two-phase flow effects at the measurement loca·tions and system components in the flow loop for which a differential pressure

measurement ~id not cx1st. rurther invesliydtiun of these results is needed to support the supposition and account for observed discrepancies.

Three 5,Y5tcm revel measut·em~nt.:-. wPrP 1mrortant for lest Ll 3: (a)

HOST liquid level, (b) pressurizer coolant level, and (c) reactor vessel cuuldflt 1evel. BOST liquid level was evaluated by comparing two independent level measurements which are plotted as an overlay in Figure 66. Similarly, pressurizer level was reviewed by redundant level measurements which are presented for comparison in Figures 67 through 6Y. It should be noted that level instrument LT-Pl39-7 showed an unexpected level increase at 40 seconds; further investigation will be necessary to resolve this occurrence. The reactor vessel liquid level probes were verified to be indicnting satisfactorily by performing a pretest conductivity calibration with the vessel liquid full and under cold and hot plant conditions.

Primary coolant pump speed measurements were checked for

consi~tency by comparison with pump speed as calculated from the PSMG frequencies. This check was valid prior to and during the blowdown transient until the PSMG fielq breakers were opened at 24 seconds. These comparisons were overlaid in Figures 239 and 240. Prior to test· initiation, the pump speed was further checked, along with the intact loop flow rate and pump differential pressure, by reviewing the agreement with the manufacturer's pump performance curves. Pump run voltages and currents were evaluated prior to the initiation of blowdown by calculating the pump electrical horsepower input, the pump water

44

~ .. ~ . .

'.

..:·

horsepower, and finally the combined pump efficiency .. These calculated efficiencies were then compared to previously recorded efficiencies determined during pump requalification tests.

To evaluate the PCS average fluid densities, calculations were performed by two independent methods using the gamma densitometer and drag disc turbine flowmeter outputs as described in Section III. To ensure that the gamma densitometer measurements were accurate for these calculations, the individual beam densities were compared to the known density of the PCS just prior to blowdown initiation. Additionally each densitometer gamma source was stowed in iti lead cask to obtain an essentially infinite density data point for each densitometer calibration ·curve. These known density values were then used to adjust

·the instrument electronics to give the correct readings from the gamma densitometers. As a final pretest check on the densitometer calibrations, a high ·and low calibration tungsten shim of known density

--was inserted in each individual densitometer beam. DAVDS data were then taken and reviewed for these measurement channels in each shim position.

Several techniques were employed to verify the validity of the measured data from the turbine meters, the drag discs, and the intact loop mass flow rate venturi meters. In particular, the broken loop turbine meters and drag discs were calibrited as discussed in Section III. The intact loop venturi meter data were examined by perfor~ing least squares curve fits for the computed venturi meter velocities plotted against the square root of the differential pressure transducers in the intact loop. The results of these data consistency checks for this test indicated discrepancies in the intact loop mass flow rates measured by the venturi meters. New venturi meter calibration equation offsets were therefore derived by using the above curve fitting technique with the variable-frequency single-phase test data obtained prior to blowdown initiation. These corrected venturi meter mass flow rates were then used to calculate average velocities and momentum fluxes in the intact loop and the reactor vessel. These values were subsequently used to correlate the outputs of the turbine meters and the drag discs. Finally, the measured average turbine meter

45

velocities and drag disc momentum fluxes were confirmed or adjusted to produce consistent data in the pump frequency tests. As an independent check, the turbine met~r and drag disc data were used to calculate fluid density as specified in Section III. These values were then compared to the known single-phase density prior to blowdown. This analysis was performed on all the turbine meters and drag discs in the intact loop and the reactor vessel with .the exception of ME-PC-3 and ME-CS-1 and those instruments that failed as listed in Table VI. ME-PC-3. and ME-CS-1 were overranged during the pump frequency tests, and data con~i5tcncy wns verified ~y ~erform1ng the pretesL· ~ctl ibrat1ons dis

cussed in Section III.

The computed parameter, mass flow rate per system volume, was calculated by five different methods at various lr1r~tions in the intact loop, broken loop, and the reactor vessel. A list of the measu~ement

panimet~t~, IHeasurement locations, and the calculation methods used are summarized in Table VII. Comparison of the calculated results obtained by each method at a particular measurement location was utilized to provide the data consistency checks for this computed parameter. It should also be noted that these comparisons provided a redundant check of the individual instruments used for each computation. Mass flow rate per system volume could not be calculated for any method or at the respective locations using ME-PC-2 or the average density computed from DE-PC-1 due to the failure of ME-PC-2 and DE-PC-lA. For purposes of comparison, however, mass flow rates per system volume were calculated using the chordal density from DE-PC-lB instead of the average density for that location. Although they are not overlaid, selected results calculated by the various methods are presented for each location in Figures ?21 through 236 for comparison.

The mass flow rates per system volume were also calculated for the pressurizer as defined in Table VII. Consistency was verified by (a) calculating each parameter using two similar but independent sets of input data ana comparing results and (b) by integrating the mass flow rate with time and comparing the total mass ejected with the known mass

46

in the pressurizer prior to blowdown initiation.

pres~nted in Figure 237.

The results are

System fluid velocities were evaluated during the blowdown. transient by utilizing two independent methods. Velocities were measured directly by the turbine meters and were subsequently calculated. using the gamma densitometers and drag disc as discussed in Section III. Data consistency checks were performed by comparing the turbine flowmeter velocities for representative system locations with the respective calculated vP.locities, To provide reliable data for these velocity checks, the gamma densitometers, the drag discs, and the turbine flowmeters were calibrated prior to test initiation as discussed in Section III and in this section. Fluid velocities could not be computed at the locations using MC-PC-2, and the . average density was computed from DE-PC-18 due to the failure of ME-PC-2 and DE-PC-lA.

As a redundant approach to verify the validity of Test Ll-3 data, selected instrument parameters were overlaid with plots from (a) the expe~iment prediction for Test Ll-3[2], (b) the Semiscale counterpart test {S-Ol-3)[ll], (c) the LOFT nonnuclear Test Ll-2[6], and (d) the

LOFT nonnuclear Test Ll-3A[ 7J. Parameters of interest in these comparisons included broken and intact loop average densities, pressures, temperatures, fluid velocities, and computed mass flow rates per system volume. The differential pressure measurements across selected PCS components were also examined. The results of these comparisons are not included in this report.

Several additional methods are being developed to reconcile inconsistancies in the presented data. The mass flow rates through the break planes can be calculated by each of five different methods and then integrated with respect to time. Comparisons are then made between the resulting total mass ejected from each integral and the total mass of water initially in the PCS, including the mass of water injected by the ECCS. The five methods presently utilized to compute mass flow rates are:

47

( 1 ) M = (11 densitometer 11 X 11 drag disc 11

)112 X A

(2) M = (11 densitometer 11

) X ( 11 turbine meter 11) X A

(3) M = (11 drag disc 11 /"turbine meter 11

) X A (4) M ::: Constant X (d 11 BDST level 11 /dt) (5) M = Constant X {L'>P 11 l4 11 to 5 11 reduction 11 X 11 densitometer 11

)112.

To date, ar1 anulysis has l.u:en performed using broken lo~p data from Tests Ll-1, Ll-2, LJ-3, and Ll-3A to investigate the integrated mass flow rate JJ<;ina Methods 1 through S ~I.Juve. The genera'! shape of the graphs of the rnass flow integral as a function of time were similar for each experiment, although the magnitudes were different. The rnagnitudes of the integrals, however, were generally ordered the same. That is, Method 3 was highest, Method 1 was second, Method 4 was third, Method 5

was fourth, and Method 2 was lnwP.<;t, Method~, usinq the RnST levQl change with time, was Llle most erratic, probably due to pressure vnrintion5 on the lev~l ueleclurs caused by waves and blowdown turbulence within the BDST. Further calculations using the mass of the water in the suppression tank, however, provided the best check on the integrated mass flow from the system.

A correction technique was formulated based on the assumption that the densitometer density was correct and that observed deviations in the mass balances were due to variations in the measured momentum flux and the measured velocity. The ratio of the integral from mass flow computed by Method 1 and the BDST mass change was used to determine a correction factor K1. Similarly, a constant K2 was calculated for the turbine meter from Method 2. ·As a check, Method 3 was used to compute a mass flow integral with the drag disc data corrected by a factor equal to l/K1

2 Then the correction factor for the turbine meter was calculated by comparison with the BDST mass change. The resulting factor compared well with the previously calculated K2. A similar correction constant was calculated for Method 5, again using the mass change in the BDST as a reference.

The results of this analysis for all four tests were then used to produce a set of correction factors for the mass flow rate data

48

/

calculated by Methods 1, 2, 3, and 5. When these correction factors are . applied to the individual test data, however, unresolved discrepancies

are present in the results. It is believed that these discrepancies are caused by the ·effect of two-phase flow at the measurement locations. Therefore, more detailed analysis needs to be performed to make the system mass balance a valid data consistency check.

I .

The corre~tion factors resulting from the above analysis are listed below along with method designation and the figure containing the applicable. mass flow rate graph. These graphs should be multiplied by the respective correction factor to produce a more consistent mass balance.

Method Correction Factor Applicable Figure No<.:

( 1 ) 1 0. 778 222 and 225

(2) 2 '1.417 223 and 226

(3) 3 0.443 221

(4) 5 0.917 224 and 227

' It should be noted that these results have been applied only to the broken loop measurements. An analogous technique will be applied to the intact loop but as yet has not been performed.

49

VII. DATA PRESENTATION

The data presented in this report include selected pertinent

thermal-hydraulic data from LOFT Test Ll-3. The data have been divided into four categories: qualified engineering units data (QEUD), un1nterpreted data, yuud data-not qualified~ and channel failed. The "lJI:.UlJ" designation was applied to measurements that have been compared to other measurements and have been found to be within the accuracy of the instrument. These data checks are discussed in detail in Sect1on VI. lhe "uninterpreted data" designation was applied to measurements in which the instruments did not fail but the data are not in a readily usable form. The "good data-not qualified" designation was . .

applied to measurements that appeared to be reasonable but no compnrnhle measurement for cross-checking was recorded.

The data were processed to the extent of converting the data to engineering units, combining measurements to produce computed parameters, and overlaying graphs of corresponding parameters at several locations to facilitate comparison. Point values of momentum flux from the drag discs and velocity from the turbine flowmeters have been conVerted to average values by using the intact loop venturi meter ns discussed in Section III. Data from the drag discs, the turbine flowmeters, and the gamma densitometers were filtered with a 4-Hz filter prior- to 1Jr·esentat1on. Numerous other instrument channel outputs were also Fi ILer·ed prior to presentation. These channels are indicated in Table VI and on the individual plots along with the filter used. Measurement uncertainties for each instrument were reported in

Reference 10 and are subsequently being revised as dictated by in situ testing and calibrations. These uncertainties have been used to produce error band plots [plots of data with upper and lower bounds of the 95% (2cr) confidence levels overlaid]. For the drag discs and gamma densi

tometers, uncertainty analyses have been performed for the point

measurements only. Further analyses will be required before average value uncertainties can be reported.

50

For LOFT Test Ll-3, the instrumentation system performed well. Of 549 instrument channels recorded during this experiment, only 37 iristruments failed. Many of the i~Struments (such as accelerometers and strain g~ges) were used to measure system loads or contributed little·or nothing towar~ understanding what occurred in this test. Thus, data from only 199 of the instrument detectors recorded are included in th1s report.

Table V_I lists the sensors that were intended to be reported for Test Ll-3. Tt gives the detector 1 ocation, range, and frequency response along with the figure number where the data can be found. This table also contains a 11 COmmentS 11 column which gives information reflecting on the usability of the data.

Table VII lists the parameters that were computed from the sensor outputs and other factors; such as"geometrical constants. This table also gives the equations used to compute these parameters, the figure number on which the data can be found, and comments which may reflect on the usefulness of the data.

The data are presented in graphical form, and are arranged two plots per page. The data plots are further divided into five major sections with the individual plots in each section being presented i.n alphanumeric order to facilitate comparison and location of desired parameters. These data sections include:

1. Test Ll-3 Measured Parameters-- Short-Term Plots (Figures 14 through 42) .' . This section contains the detector outputs, including overlays, which ~ere specifically designed for the short-term transient and, therefore, do not exceed 1-second duration.

2. Test Ll-3 Measured Parameters -- 70-Second Plots (Figures 43 through 175).

51

3. Test Ll-3 Measured Parameters -- Long~Term Plots (Figures 176 through 212). This section contains selected detector outputs, including overlays of 175-sec and 500-sec duration.

4. Test Ll-3 Computed Parameters (Figures 213 through 269).

5. Test Ll-3 Erro~ Hand Plnts (Figures 270 through 312). This section contains error band plots for several representative instrument types, l"llnges, anLI fr·equency responses. These error bands are based on 95% (2o) confidence levels.

Time zero for each plot is the average of the times at which each of the QOBVs opened to 17% of its full sleeve travel. This definition for time of blowdown initiation (T

0) was used since (a) a flow area does

not exist through each QOBV until the valve sleeve clears the huddle ·chamber at 17% of its full travel and (b) QOBV-1 commenced opening 2.5

msec sooner than QOBV-2. Determination of T0

, along wit~ valve opening ti~e, is shown pictorially in Figure 13. It should be noted that, while this definition of time zero is adequate for measurment comparisons using time scales on the ~rder of several seconds, the user may wish to utiliz~ a different time zero definition for evaluation of shorter time phenomena. The data are presented prior to the defined time zero to allow for such a comparison.

Pressure data presented in this report are in gauge pressure (psig); barometric pressure at the time of test execution was 12.5 psia.

The scales selected for the graphs were chosen to provide an overview of the test and do not refl~ct the obtainable resolution of the data.

The volume of data contained in this report is large, and although every effort was made to prevent it, an error may have found its way into the report. In the event a user detects an error, prompt notification would be appreciated so that other users may be notified.

52

0

>

20

-- CV-P138-15

---- CV-P138-1

66

12"SCH 160 Pipe

Area Opening

17 '" "

'- " " /

"

/

/ /

/

" "

"---- ---

" " "

Notes

(I) To=(T1 +T2 )/2

(2) CV-P138-1 Opening Time

TQOBV-1=T4-T2 -

(3) CV- P138--15 Opening Tim

TQOBV-15=T3- Tl.

ANC ·A -9429

Fig. 13 Determination df time of rupture (T0

) and valve opening time.

53

TABLE VI

ME~SURED PARAMETERS FOR LOFT T~ST Ll-3

Range Freguenct Res~onse PARAMETER Data. Da,tc

System Acqui s iti on1 · DataUa] Hg. Detector Location Detector System Detector ~yste11 No .• Measurement Conments

VALVE OPENING

Broken Loop Broken loop cold leg betweer 0-100% 0-100% 35 Hz SOD pps 14 QEUD.

CV-Pl38-l break plane and suppressio• tank. 15

Broken Loop Broken loop hot leg betwee• 0-100% 0-100% 35 Hz SOD pps -14 QEUD.

CV-Pl38-15 break plane and suppressio• tank. 16 270

CHORDAL DENSITY (J1 Broken Loop Broken loop cold leg at DT- 0.5-62.4 0.5-62.4 1,000 Hz 1, C•OO Hz QEUD. Filtered to ·4 Hz for +==-

43 DE-BL-lA flange. Beam line 14° 21 min lb/ft3 lb/ft3 10 Hz 50 pps 176 0 to 70 sec plots onl~.

from -lB line [CW looking 271 toward reactor vessel (RVll

Broken Loop Broken loop cold leg at OTT 0.5-62.4 0.5-62.4 1,000 Hz 1 ,COO Hz 43 QEUD. Filtered to 4 Hz for

DE-BL-18 flange. Beam line through f lb/ft3 lb/ft3 10 Hz 50 pps 176 0 to 70 sec plots only. of pipe 45° from vertical · (CCW looking toward RV).

Broken Loop Broken loop cold leg at OTT 0.5-62.4 0.5-62.4 1 ,000 Hz 1 ,COO Hz 43 QEUD. Filtered to 4 Hz for

DE-BL-lC flange. Beam line 22° 7 mi~ lb/ft3 1 b/ft3 10 Hz 50 pps 176 0 to 70 sec plots only.

from -lB line (CCW looking toward RV).

Broken Loop Broken loop hot leg at OTT flange. 0.5-62.4 0.5-62.4 1,000 Hz 1 ,COO Hz 4<1 QEUD. Filtered to 4 Hz for

DE-BL-21\ Beam line 14° 21 min from -213 lb/ft3 1 b/ft3 lO Hz 50 pps U.7 0 to 70 sec plots only.

line (CCW looking toward R\).

Broken Loop Broken 1 oop hot .1 eg at OTT flange. 0.5-62.4 0.5-62.4 1,000 f-\Z 1 ,COO Hz 44 QEUD. Filtered to 4 Hz for

DE-BL-28 Beam line through ~of pipe 45° lb/ft3 lb/ft3 10 H.z ~.o pps 177 0 to 70 ~ec plot~ only.

from vertical (CW coking toward RV).

TABLE VI (contd.)

Range Freguencl Res~onse PARAMETER Data Data

System Acquisition Data[ a] Fig. Dete"ctor Location Detector System Detector System No. Measurement Comments

CHORDAL DENSITY

Broken Loop Broken loop hot leg at OTT 0.5-62.4 0.5-62.4 1,000 Hi 1 ,000 Hz 44 QEUD. Filtered to 4 Hz for

DE-BL-2C ·flange. Beam line 22° 7 min lb/ft3 lb/ft3 . 10 Hz 50 pps 177 0 to 70 sec plots only • from -2B line (CW looking toward RV).

Intact Loop Intact loop cold leg at OTT 0.5-62.4 0.5-62.4 1 ,000 Hz 1,000 Hz Channel failed. DE-PC-lA flange. Beam line 14° 21 min lb/ft3 lb/ft3 10 Hz 50 pps

from -lB line (CW looking away (J'I from RV). (J'I

Intact Loop Intact loop cold leg at OTT 0.5-62.4 0.5-62.4 1,000 Hz l,OOO Hz 46 QEUD. Filtered to 4 Hz. OE-PC-lB flange. Beam line through~ of 1 b/ft3 lb/ft3 10 Hz 50 pps

pipe 45° from vertical (CC 1 ook i ng away from RV).

Intact Loop Intact loop cold leg at OTT 0.5-62.4 0.5-62.4 1,000 Hz 1 ,000 Hz 46 QEUO. Filtered to 4 Hz.

OE-PC-lC flange. Beam line 22° 7 min 1 b/ft3 lb/ft3 10 Hz 50 pps from -lB line (CCW looking away from RV).

Intact Loop Intact loop hot leg at OTT 0.5-62.4 .0.5-62.4 1 ,000 Hz 1 ,000 Hz 47 QEUD. Filtered'to 4Hz.

OE-PC-2A flange. Beam line 14° 21 min 1 b/ft3 1 b/ft3 10 Hz 50 pps t'rom -2B line (CW looking away from RV). ·

Intact Loop Intact loop.hot leg at OTT 0.5-62.4 0.5-62.4 1,000 Hz 1.000 Hz . 47 QEUD. Filtered to 4Hz.

DE-PC-2B flange. Beam line through E of lb/ft3 lb/ft3 10 Hz 50 pps pipe 45° from vessel (CCW looking away from RV).

TABLE VI (contd.)

Ran~ Freguenct Res~~nse PARAMETER Data Data.

System Acquisition Data[a] Fig. Detector Location Detector System Detector System No. Measurement Comments

CHORDAL DENSITY

Intact Loop Intact loop hot leg at DT- O.S-62.4 0.5-62.4 1,000 Hz 1,000 1-z 47 QEUD. Filtered to 4 Hz.

DE-PC-2C flange. Beam.line 22° 7 min 1 b/ft3 1 b/ft3 10 Hz 50 pps from -2B line (CCW looking away from RV).

Intact Loop Steam generator (SG) outlet at 0.5-62.4 0.5-62.4 1,000 Hz 1,000 1-z 48 QEUD. Filtered to 4 ~z.

DE-PC-3A DTT flange. Beam line 14c 21 min lb/ft3 lb/ft3 10 Hz SC• pps

(J1 from -3B line (CCW looking down).

"' Intact Loop SG outlet at DTT flange. 0.5-62.4 0.5-62.4 1,000 Hz 1,000 'rz 48 "QEUD. Filtered to 4 Hz.

DE-PC-3B Beam line 65° from flange E 1 b/ft3 lb/ft3 10 Hz 5C pps (CW looking down).

Intact Loop SG outlet at DTT flange. 0.5-62.4 0.5-62.4 1,000 Hz 1,000 Hz 48 QEUD. Filtered to 4 Hz.

DE-PC-3C Beam line 22° 7 min from -2B E lb/ft3 lb/ft3 10 Hz SC pps (CW looking down).

FLUID VELOCITY, All turbine meter measure-ments are unidirectional.

AVERAGED

Broken Loop Broken loop cold leg at DlT 7.5-150 0-190 9 Hz 1 ,'000 HZ 50 Uni nterpreted da.ta. Filtered

FE-BL-1 flange. ft/sec ft/sec SC pps 52 to 4 Hz for 0 to 70 sec plot 178 only. Plot corrected to 272 avera£'€.

Broken Loop Broken loop hot leg at DTT 7.5-150 0-190 9 Hz 1 .tOOO liz 51 Uninterpreted data. Filtered

FE-BL-2 1 flange. ft/sec ft/sec 5C pps 52 to 4 Hz, plot corrected to average.

TABLE VI ( contd.)


System Acquisition Data[a] Fig. Detector Location Detector System Detector System No. Measurement Comments

FLUID VELOCITY, AVERAGED

Reactor Ve.ssel Core simulator in instrument l. 5-30 0-60 9 Hz 1,000 Hz 53 Uninterpre-ted data. Fil te~ed FE-CS-1 stalk above orifice. ft/se-c ft/sec 50 pps to 4 Hz, plot corrected to

average.

Intact Loop Intact loop cold leg at OTT 7.5-150 0-180 9 Kz 1 ~000 Hz 54 Uninterpreted data. Filtered FE-PC-1 flange. ft/sec ft/sec 5C pps 57 to 4 Hz, plot corrected to

average •. (.11 ....... Intact Loop Intact loop hot leg at OTT 7.5-150 0-200 9 Hz 1 ,000 Hz 55 Uninterpreted data. Filtered

FE-PC-2 flange. ft/sec ft/sec 50 pps 57 to 41H i, p -~ ot corrected to average.

Intact Loop SG outlet at OTT flange. 7.5-150 0-210 9 Hz 1,000 rlz 56 Unirterpreted data. Filtend FE-PC-3 ft/sec ft/sec 50 pps 57 to 4Hz, ~lot cotrected tc

average.

Reactor Vesse 1 Downcomer stalk 1' 47.1 in. l. 5-30 0-60. 9 Hz 1 ,000 Hz 58 Uninterpreted data. Filte-red FE-lST-1 from RV bottom. ft/sec ft/sec 50 pps 60 to L Hz, plot corrected to

273 average.

Reactor Vessel Downcomer stalk 2' 47-1 in. 1.5-30 0-64 9 Hz 1,000 Hz 59 Uni~terpreted data. Fi 1 tered FE-2ST -1 from RV bottom. ft/sec ft/sec 5) pps 60 to 4 Hz ior 0 to 70 sec plot

179 only. P1ot corrected to average.

FLOW RATE

Emergency core Accumulator A in 6-in. 1 i ne 0-60 in. 0-2000 gpm 5 Hz ~ pps QEU'). Net presented •. ACO:L-Cooling System downstream of orifice. muhtor P.CC-A injection

FT-Pl20-36-l fai~ed to initiate.

TABLE VI (contd.t

Ran~ Freguencl Res~nse PARAMETER Data Data

System Acquisition i:Jata[a] Fig. Detector Location Detector System Detector System No. Measurement Comments

FLOW RATE

Emergency Core Accumulator A in 6-in. 1 i ne 0-600 in. 0-600 gpm 5 Hz :o pps Chaimel failed. Cooling System downstream of .orifice.

FT-Pl20-36-5

Emergency Core LPIS pump A in 4-in. 1 i ne 40-800 g.pm 0-400 gpm 5 Hz :o pps 61 IQEUD. Cooling System between heat exchanger and 184

FT-Pl20-85 orifice. 275

c:.n co Emergency Core HP IS pump A discharge. 2-30 gpm 0-30 gpm 5 Hz 5() !PPS 62 ()EUD. Cooling System 276

FT-Pl28-104

Slowdown Suppres- Suppression tank spray flo·,; 0-100 gpm 0-100 gpm 7 Hz !JO IPPS 180 ~ni~t~~~:~~d ~~~~ ~~~~ io to

sion Tank Spray rate in 60 gpm header. System +0 94 sec to 175 sec. 0

FE-Pl38-138

Slowdown Suppres- Suppression tank spray flow 0-400 gpm 0-400 gpm 7 Hz 50 pps 181 QEUD after the initiation of

si on Tank Spray rate from pump discharge. 274 spray flow at !v T + 94 sec. 0

System FE-Pl38-139

Slowdown Suppres- Suppression tank spray flo~ 0-300 gpm 0-300 gpm 7 Hz 50 pps 182 QEUD. Recorded fi ow rate be-

sian Tank Spray rate in the 220 gpm header. tween T and T + 1 5 sec due

System to mechgnical ~hock.

FE-Pl38-140

Slowdown Suppres- Suppression tank spray flOW! 0-150 gpm 0-150 gpm 7 Hz 5:> pps 183" ~EUD after the initiation of

sian Tank Spray rate in the spray pump spray f]ow at"-· T0

+ 94 sec.

System recirculation line. FE-Pl38-153

TABLE VI (contd.).

Range Freguenct Res~onse PARAMETER Data Data

System Acquisition Uata[a] Fig. Detector Location Detector System Detector System No. Measurement Comments

FLOW RATE

Intact Loop Intact loop hot leg venturi 0.5-5 0-5 5 Hz 1,000 Hz 63 QEUb for initial conditions FT-Pl39-27-l flowmeter (right side mlbm/hr mlbm/hr 50 pps only; data 10t corrected for

facing SG). density changes after T0.

Intact Loop Intact loop hot leg venturi 0-760. 0-760 5 Hz 1,000 Hz QUED for initial conditions FT-Pl39-27-2 flowmeter (left side in. H2o in. H20 50 f.lPS only. Channel failed after

facing SG). T0 (diigital). <..n \.0 Intact Loop Intact loop hot leg 0.5-5 0-5 Hz. 50 Jps 63 QEUD ~or initial conditions

FT-Pl39-27-3 venturi flowmeter (bottom). mlbm/hr mlbm/hr 277 only; data not-corrected for densi:y changes after T0.

LIQUID LEVEL

Reactor Vessel Downcomer 1 with stings 0-162 in. -1-+1 v 0.7 Hz 1,000 Hz 64 QEUD. LE-lST-1 between 200.4 in. and 8.4 in. and -2 above RV bottom.

Reactor Vessel Downcomer 2 with stings 0-162 in. -1-+ 1 v 0. 7 Hz l,COO Hz 65 QEUD. LE-2ST-2~2 channel f~Hed.

LE-2ST -1 between 200.4 in. and 8.4 in. and -2 above RV bottom.

Secondary Coolant SG secondary 1 evel. -143-+57 -143-+57 3 Hz 50 pps 70 Good data - not qualified. ')ata System in. H.20 ~ in. H20 1,000 Hz display instrument ringing from

LT-P4-8B T0 tc "' 5 sec.

0"'1 0

PARAMETER System

Detector

UQUID LEVEL

Emergency Core Cooling System

LIT-Pl20-44

Location

Accumulator A.

Slowdown Suppres- Slowdown suppression tank ·evel sian Tank on north end of tank.

LT-Pl38-33

Slowdown Suppres- Slowdown suppression tank ·evel sian Tank on south end of tank.

LT-Pl38-58

Intact Loop LT-Pl39-6



~10NENTU~1 FLUX, AVERAGED

Broken Loop M~-BL-1

Pressurizer level on southeast side.

Pressur-izer level on south~~oest

side.

Pressurizer level on north side.

Broken loop cold leg at DTT flange.

Detector

0-120 in.

0-150 in.

0-132 in.

0-75 in.

0-75 in.

0-75 in.

2.0-50 lQ3lb/ftse~

TABLE VI (contd.)

Range Data

Acquisition System

0-120 in.

0-132 in.

0-132 in.

0-75 in.

0-75 in.

0-75 in.

-460-+460 l03lbm/ftsec2

Frequency Response

Detector

5 ~-z

5 f-z

5 f-z

5Hz

5 H.:

" oJ H~

35 Elz

Data [Jata[a] Fig.

System No.

~-0 PJS

1,000 Hz 66 50 pps 185

204

1,000 Hz 66 50 pps 185

205 27G

1,000 Hz 67 5D P~·s

l,OOC Hz 68 50 p~s

50 PJ:S 69 .279

l ,000 Hz 71 50 pps 73

136 280

Measurement Convnents

QEIJD. Not presented. AccumLlator ACC-A injection failed to initiate.

QEUD. Data display instrument rinaing from T to ~ T + ~: 5 sec. 0 0

QEUD. Data display instrument rinoing from T to ~ T + 2.'5 .. sec. 0 0

QELID from T to T + 13 sec. Uninterpretgd dat9 after T + 13 sec. 0

QE_D from T to T + 13 sec. Uninterpretgd dat~ after T

0 + 13 sec.

QEJD from T to T + 13 sec. Un i1nterpretgd da t9 after T

0 +

i3 sec.

Un'nterpreted datj. Filtered to ~ Hz for 0 to 70 sec plot. Unfiltered for 0 to 175 sec plot. Plot corrected to 3verage. Data temperature sen;itive after ~ T + 50 sec.

0

TABLE VI (contd.)

Range Freguenc~ ResQonse PARAMETER Data Data

System Acquisition Oa-:a[a] Fig. Detector Location Detector System [•etector System No. Measurement COI!Illents

f·10MENTU~1 FLUX, AVERAGED

Broken loop Broken loop hot leg at OTT 2.0-5.0 -420-+460 1,000 Hz 72 Uninterpreted data. Fil-~1E-BL-2 flange. l03lb/ft-. l03lbm/ft- 35 Hz 50 pps 73 tered to 4 Hz for 0 to

sec2 sec2 · 70 sec plot; unfiltered for 0 to 190 sec plot. Plot corrected to average.

Reactor Vessel Core simulator stalk above 200-3,500 -20-+20 l,OJO Hz 74 Uninterpreted data. Fil ter,ed 0"1 ME-CS-1 orifice plates. l b/ft-sec2 1 o3l bm/ft- 3!: Hz· 50 pps to 4 Hz, plot corrected to

sec2 average for 0 to 70 sec.

Intact Loop Intact loop cold leg at OTT 2.0-50 -510-+510 l ,000 Hz 75 Uninterpreted data. Data tern-NE-PC-1 flange. l 031 b/ft- l03lbm/ft- 35 Hz 50 pps 77 perature sensitive after T

sec2 sec2 + 22 s~c. Filtered to 4 Hz~ Plot corrected to average.

Intact Loop Intact loop hot leg at OTT 200-3,500 -2~-+28 l ,000 Hz Channel failed (digital). f~E-PC-2 flange. lb/ft-sec2 10 lbm/ft- · 3S Hz 50 pps

sec2

Intact Loop SG outlet at OTT flange. 2.0-5.0 -440-+440 l,COO Hz 76 Unin~rpreted data. Data ME-PC-3 l03lb/ft- 1 o3l bm/ft- 35 Hz 50 pps 77 temperature sensitive after

'sec2 sec2 T0 + 22 sec. Filtered to 4 Hz. Plot corrected to average.

Reactor Vessel Downcomer l, 45.~ in. above 200-3,500 -19-+19 1,000 Hz 73 Uninterpre:ed data. Filtered ME-lST-1 RV bottom. l b/ft-sec2 -·· l03lbm/ft- 35 Hz 50 pps 281 to 4 Hz, plot corrected to

sec2 averaqe.

TABLE VI (contd::

Range Freguencl Respohse PARAMETER Data

Oc.tc.la] Data

Sy:;tem Acquisition Fig. Detector Location Oetector System Dete-ctor Sy~.te-m llo. Measurement Comments

MOMENTUM FLUX. AVERAGED

Reactor Vessel Downcomer 2. 45.5 ; n. above 200-3.500 -19-+19 l .coc Hz· 79 Uninterpreted data. Filtered ME-2ST-l RV bottom. lb/ft-sec2 l o3l bm/ft- ~5 Hz SJ PI=S 187 to 4 Hz for 0 tJ 70 sec; un-

sec2 filtered for 0 to 175 sec; plot corrected to average.

ELECTRICAL FREQUENCY CT'I Intact Loop Intact loop pump l. 0-75 Hz 0-75 Hz l • OG)() Hz 5) IPPS 238 QEliD. N

PCP-1-F 239

ELECTRICAL CURRENT

lntact Loop Intact loop pump l. 0-1.000 amps 0-1.000 amps 500 pps QE~D. Not presented. PCP-1-I

ELECTRICAL VOLTAGE

Intact Loop Intact loop pump l. 0-600 v . 0-600 v 500 pps QE_D. Not presented . PCP-1-V

ELECTRICAL FREQUENCY

Intact Loop Intact loop pump 2. 0-75 Hz 0-75 Hz 1 .oca Hz 50 pps £•38 QEUD. PCP-2-F 240

TABLE VI (contd.)

Range Freguenc,t Resf!onse PARAMETER Data

Data[aj Data

System Acquisition Fig. )

Detector Location Detector System Detector System No. Measurement Comments

ELECTRICAL CURRENT

Intact-Loop Intact loop pump 2. 0-1,000 amps 0-1,000 amps 500 pps QEUD. Not presented .. PCP-2-I

ELECTRICAL VOLTAGE

Intact Loop Intact loop pump 2. 0-600 v 0-600 v 500 pps QEUD. Not presented. PCP-2-V

~ DIFFERENTIAL w PRESSURE

Broken Loop Broken loop hot leg from flange 0-50 psid -50-+50 E.O Hz '50) pps 80 Uninterpreted data. Filtered PdE-BL-1 in front of SG simulator psid 282 to 4 Hz.

to pipe in front of reflood assist bypass system tee.

Broken Loop Broken loop cold leg from flange o-1,500 psid -50-+50 60 Hz 500 pps 81 QEUD. Filtered to 4 Hz. PdE-BL-2 in front of spool piece to pipe psid 283

in front of reflood assist by-pass system tee.

Broken Loop Broken loop cold leg across 0-1,500 psid -1,500- 1 .2 Hz 5C pps 82 QEUD. PdE-BL-3 break plane. +1 ,500 psid 284

Broken Loop ~Broken loop hot leg across 0-1,500 psid -1,500- 1 .2 Hz 50 pps 82 QEUD. PdE-BL-4 break plane. +1 ,500 psid

Broken Loop Broken loop hot leg across 0-1,500 psid -1,500- 1.2 Hz 1 ,.000 Hz 83 QEUD. · PdE-BL-5 pump simulator. +1 ,500 psid 50 pps

TABLE VI (contd. I

Range Freguencl Re~~onse PARAMETER Data Data

System Acquisition Data[a] Fig. Detector Location Detector System Detector System No. Measurement COITIIlents

DIFFERENTIAL PRESSURE

Broken Loop Broken loop hot leg acro~s 0-50 psid -50-+50 3.5 Hz ~0 pps 84 QEUD. PdE-BL-6 SG simulator outlet flanre. psid 285

Broken loop Broken loop hot leg acr~s 0-100 psid -50-+50 3.5 Hz 1,000 H;;; 85 QEUD. PdE-BL-7 SG simulator. psid EO pps

Broken Loop Bro"ken loop hot leg acr~s 0-50 psid -50-+50 3.5 Hz !:() pp s 86 QEUD. Filtered to 4 Hz.

"' PdE-BL-8 SG simulator inlet flange. psid +=-

Reactor Vessel RV between core simulator :!:_ 50 psid -25-+25 2'. 3 Hz 50 pps 87 OEUD. Filter:d to 4 Hz. PdE-CS-1 instrument stalk and psid

downcomer 2, 24.5 in. frJm \ RV bottom.

Intact Loop Intact loop cold leg acr·J:SS 0-1qo psid -100-+100. 0.7 Hz 1,000 Hz 88 CEUD. PdE-PC-1 primary coolant pumps. psid 5J pps 286

Intact Loop Intac~ loop across SG. 0-100 psid -100-+100 3.5 Hz 5.J pps 89 QEUD prior to T . Uninter-. 0 0

PdE-PC-2 psid 287 preted data' after T . Unex-plained long-:erm p8sitive offset.

Intact Loop Intact loop hot leg piping, :!:_ W psid :!:_ 10 psid 2.3 Hz 5) pps 90 QEUD. Filtered to 4 Hz. PdE-PC-3 RV to venturi. 288

Intact Loop Intact loop hot leg pipi!l·~. :!:_ 10 psid :!:_ 10 psid 2 3 Hz 5·0 pps 91 QEUD prior to T0

. Uninter-

PdE-PC-4 venturi to SG. preted data after T . Unex-plained long-term nggative offset. Filtered to 4 Hz.

PARAMETER System

Detec_tor

DIFFERENTIAL PRESSURE '

Intact Loop Pd~-PC-5

Intact Loop PdE-PC-7

Reactor Vessel PdE-RV-1

Reactor Vessel PdE~RV-3

Reactor Vessel PdE-RV-4

Location

Intact loop cold leg primary coolant pumps to RV nozzle,

Intact loop cold leg RV inlet to broken loop cold

· leg RV in 1 et.

Between downcomer stalk 1 and blowdown suppression tank.

)

Intact loop cold leg inlet to bottom of downcomer.

Upper plenum to the R~ outlet nozzle in the intact loop hot leg.

Slowdown Suppres- Suppression tank across the sian Tank vacuum breaker line.

PdE-SV-·9

Reactor Vessel PdE-2ST.-2

Intact Loop PdT-Pl39-30

Downcomer 2 between 209.4 in. and 24.5 in. above RV bottom.

Across RV just beyond intact loop inlet and outlet nozzles.

TABLE VI (contd.)

Range Frequency Respo1se

Detector

+ 10 psid

+ 10 psid

Data Acquisition

System

+ 10 psid

+ 10 psi d

0-1,500 psid -1,500-

+ 10 ps id

+ 10 psi d

0-25 psid

0-50 psid

+1 ,500 psid

~ 10 psid

+ ·10 psid

-100-+100 in.

-25-+25 psid

0-50 psid

Detector

2.3 Hz

2.3 Hz

1 .2 Hz

2.3 Hz

2.3 Hz

5 Hz

60 Hz

5 Hz

Data [Jata[a] F. lg.

System No. Measurement Comments

50 pps

50 pps

50 pps

50 pps

50 pps

50 pps

50 pps

50 pps

92 QEUD prior to T0 . Uninterpreted date after T . Unexplained long-term nggative offset. Filtered to 4Hz.

93 QEUD. Filtered to 4 Hz.

94 QEUD. Differential press~re 289 exceeds instrument range

prior to T0

.

95 QEUD. Filtered to 4Hz.

96 QEUD prior to T ; uninterpreted data after T 0Unexplained long-term pogitive offset.

97 QEUD. Good data - not

98

99 290

qua 1 Hied.

QEUD prior to T ; uninterpreted data after T

0. 0Unexplained

long-term negative offset. Filtered to 4 Hz.

QEUD-

TABLE VI (contd )

Range F reguenc~ Res~onse PARAMETER Data Data

System Acquisition Data[ a] Fig. Detector Location Detector System Jetector System No. Measurement Comments

PRESSURE

Broken Loop Broken loop cold leg at D\r D-3,000 psig 0-3,000 psig >!iiOO -lz l,OJO Hz 17 QEUD. PE-BL-1 flange. 50 pps 100

l 01

Broken Loop Broken loop hot leg at o:-r 0-3,000 psig 0-3,000 psig >5(•0 -lz l,DJO Hz 18 q::uo. PE-BL-2 flange. 5J Jps 100

102 291

0"1 Broken Loop BrakeD loop hot leg just 0-3,000 psig 0-3;ooo psig >~CO Hz 1.0•)0 Hz Q.::uo. 0"1 18 PE-BL-3 upstream of SG simulator. 50 Jps 102

Broken Loop Broken loop cold leg at inlet 0-3,000 psig 0-3,000 psig >~CO Hz 1.ooo Hz 17 OEUD. PE-BL-4 of spool piece. 50 pps 101

Broken Loop Broken loop hot leg at OL:let 0-3,000 psig 0-3,000 psig >~00 Hz 1,000 Hz 18 C•EUD. . PE-BL-6 of SG simulator. " 50 pps 102

Broken Loop Broken loop cold leg at certer 0-3,000 psig 0-3,000 psig >~00 Hz 1 ,000 Hz 17 CEUO. PE-BL-8 of spool piece. 50 pps 101

Reactor \les~el Core simulator stalk above 0-3,000 psig 0-3,000 psig 4!: Hz l ,000 Hz 103 . CEUD. PE-CS-lA orifice plate (wide ranged- 50 pps 108

3,000 psi). 112 292

Reactor Vessel Core simulator stalk abo~ 0-200 psig 0-200 psig 45 Hz 1,000 Hz 104 QEUD. Pressure .beyond ins tru-PE-CS-1 B orifice plate (narrow ranred- 50 pps 188 ment range until T

0 + 31 sec.

200 psi). 293

Reactor Vessel Core simulator stalk above 0-3,000 psig 0-2,500 psig 4,lJO Hz 1,0(10 Hz 20 Q[UO to T + lJ sec. Instru-PE-CS-lFF orifice plate.

' 50 ~·ps lll ~nt temp~rature sensitive

after ~ T0

_ + lJ sec.

PARAMETER System

Detector

PRESSURE"

Reactor Vessel PE-CS-2FF

Intact Loop PE-PC-1

Intact Loop PE-PC-2

Intact Loop PE-PC-3A

Intact Loop PE-PC-3B

Intact Loop PE-PC-4

Blowdown Suppression System

PE-SV-01

Blowdown Suppression System

PE-SV-2

I

Location

Core simulator stalk_above .orifice plate.

Intact loop cold leg·at OTT flange.

Intact loop hot leg at OTT flange.

SG outlet at OTT flange, wide range (0-3,000 psi).

SG outlet at DTT flange, narrow range (0-200 psi).

Intact loop pressurizer vapor space.

Blowdown suppression tank bottom under downcomer 4 (north end), 180° from t~p vertical (CW looking ~rth).

Blowdown suppression tank across from downcomer 4 (north end), 112.5 from top vertical (CW lookirig north).

TABLE VI (contd.)

Range Frequency Resporse

Detector

0-3,000 psig

0-3,000 psig

Data Acquisition

System

0-2,500 psig

0-3,000 psig

0-3,000 psig 0-3,000 psig

0-3,000 psig 0-3,000 P.Sig

0-200 psig 0-200 psig

0-3,000 psig 0-3,000 psig .r

0-100 psig 0-100 psig

0-l.DO psig 0-100 psig

Detector

4,100 Hz

>500 Hz

>500 Hz

>500 Hz

">500 Hz

>500 Hz

500 Hz

500 ·Hz

Data Uc:ta[a] Fig.

Sy~.tem No.

1 ,000 Hz 20 50 pps . 114

294 295

l,OJO Hz 19 50 pps 105

107

Measurement C011111ents

QEUD to T + 10 sec. Instrument tempgrature sensitive after ~ T + 10 sec. 0 .

QEUD.

1,000 Hz 19 QEUD. 50 pps 105

1,000 Hz 50 'PPS

50 pps

1,000 Hz 50 pps

1,000 Hz 500_ pps

500 pps

107

19 105

106 188

19 107

21 32

115 125

23 32

QEUD.

QEUD. Pressure beyond instrument range until T

0 + 31 sec.

QEUD.

QEUD. Fil :ered to 60 Hz .. All BDST pressure instrument initial values are adjusted to 0 psig. Use PT-138-56 to obtain the initial pressure for all [!>~-SV-] except PE-S~-30, -31, -45, and -46.

QEUD.

TABLE VI (cortd.)

Range F r·eguencl Response PARAMETER Data Data

System Acquisition Jata[a] Fig. Detector Location Detector System Detector System No. Measurement Comments

I?RESSURE

Slowdown Suppres- Slowdown suppression tank c.r.ro5s 0-100 psig 0-100 psig 500 1-z 1,000 Hz 22 QEUJ. All SDST Pressure instru-sion System from downcomer 1 (south 5CO pps 36 ment initial values are adjusted

PE-SV-3 end), 157.5° from top v~rtical 116 to •) psig. Use PT-Pl38-56 to (CW looking north). 189 obtain the initial pressure

206 for all [PE-SV-] except PE-SV-30, -3J, -45, and -46.

Slowdown Suppres- Slowdown suppression tark ccn:o5s 0-100 psig 0-100 psig 500 Hz 500 pps 24 QEL'D.

"' sion .System from downcomer 1 (south 36 (X) PE-SV-4 end), 112.5° from top vertical

(CW looking north).

Slowdown Suppres- Slowdown suppression tark P-erd 0-100 ps ig 0-lOJ psig 500 Hz 500 pps 31 ' QELD. sion System (north end), 10° from tank

PE-SV-1 0 horizontal ~ (CW looking we~t) (vertex of ngle at intersecticn of downcomer 4 E and tank hori-hori zonta 1 E) .

Slowdown Suppres- Slowdown suppression tank 8-end 0-100 psig 0-100 psig ' 500 1Hz 500 pps 30 IQEUD. Filtered to 60 Hz.

sion System (south end), 10° from tank PE-SV-11 horizontal ~ (CCW looking west}

(vertex of ngle at intersec.tioo of downcomer 1 E and tank E;.

Slowdown Suppres- Slowdown suppression tan'k A-e:'ld 0-100 psig 0-100 psig 500 Hz son pps 31 QEUO.

sion System (north end), 45° from tank PE-SV-12 horizontal ~ (CW looking w~t)

(vertex of ngle at intersection of downcomer 4 E and tali< t.:ri-zontal E).

TABLE VI (contd.)

Range Freguenc~ Res~onie

PARAMETER Data Data System Acquisition liata[a] Fig.

Detector Location Detector System Detector· System No. M~asurenent Comments

PRESSURE

Blowdown Suppres- Blowdown ~uppression tank B-end 0-100 psig 0-100 psig 5JO Hz 500 pps 30 QEUD. All BDST pressure instru-

sian System (south end), 45° from tank ment initial values are adjLsted

PE-SV-13 horizontal ~ (CCW looking west) to 0 psig. Use PT-Pl38-56 t~ (vertex of ngle at intersection obtain the initial pressure for of downcomer 1 E and tank hori- all [PE-SV-] except PE-SV-30, zontal E). -31, -45, ~nd -46.

Blowdown Suppres- Blowdown suppression tank-header 0._ 100 psig 0-100 psig !:00 Hz 500 pps 29 QEUD. ~ sian System above downcomer 4r 327° from top 117 1.0

PE-SV-14 vertical (CW looking nqrth). 127 296 297

Blowdown SuRpres- Blowdown suppression tank across 0-100 psig 0-100 psig 500 Hz 500 ,PPS 28 QEUD.

sian System from downcomer 4, 230° from 33

PE-SV-15 top vert i.ca 1 (CW looking north). . Blowdown Suppres- Blowdown suppression tank across 0-100 psig 0"-100 psig 500 Hz 5CO pps 28 QEUD.

sian System from downcomer 1, 230° from 36

PE-SV-16 top vertical (CW looking north). .,

Blowdown Suppres- Blowdown suppression tank, 0-100 psig 0-100 psig 500 Hz 500 pps 27 QEUD.

sian System 54-1/2 in. nor~h of down- 35

PE-SV-17 ·comer 3 E; 327° from top 118 vert i ca 1 ( CW 1 ook i ng north). 126

B1owdown Suppres- B1owdown suppression tank header 0-100 P.S i g 0-100 psig 500 Hz 500 pps 29 Un-i nterpreted data.

sian System above downcomer 1. 119

PE-SV-18 127

TABLE VI (contd.)


System Acquisition Oata[a: Fig. Detector Location Detector System Detector System No. Measurement Comments

PRESSURE

Slowdown Suppres- Slowdown suppression tank t-ot tom, 0-100 psig 0-100 psig 5CO Hz 1,000 H;: 21 QEUD. All SDST pressure instru-sion System 54-l/2 in. north of down- 500 pps 34 ment initial values are adjusted

PE-SV-22 comer 3 E· 120 to 0 psig. ·Use PT-Pl38-56 to· 125 obtain the initial pressure for 189 a1l [PE-SV-] except PE-SV-30,

-31, -45, and ~46.

Slowdown Suppres- Slowdown suppression tank 0-100 psig 0-100 psig 500 Hz 500 pps 23 QEUD. sion System 54-l/2 in. north of down- 34

PE-SV-23 comer 3 E,ll2.5° from top -....J 0 vertical (CW looking north).

Slowdown Suppres- Slowdown suppression tank bottom, 0-100 psig 0-100 psig 500 Hz 500 pps 21 QIEUD. sion System 136.5 in. north of down- 31

PE-SV-24 comer 3 E·

Slowdown Suppres- Slowdown suppression tank, 0-100 psig 0-100 psig 50D Hz 500 pps 23 QEUD. sion System 136.5 in. north of down-

PE-SV-25 comer 3 E• 112.5° from tQ~:' vertical (CW looking nortt).

Slowdown Suppres- Slowdown suppression tank bo~tom, 0-100 psig 0-100 psig 500 Hz 1,000 Hz 22 QEUD. sion System 54.3 in. south of down- 500 pps 121

PE-SV-26 comer 2 E· 125 207

Slowdown Suppres- Slowdown suppression tank b:>ttom, 0-l 00 psi g 0-100 psig 500 Hz 1,000 Hz 22 QEUD.

sion System 136.5 in. south of down- ~-00 pps 30

PE-SV-27 comer 2 [·

Slowdown Suppres- Slowdown suppression tank~ 0-1DO psig 0-100 psig 50) Hz 500 pps 24 QEUD.

sion System 54.5 in. south of down-PE-SV-28 comer 2 E· 112.5° from to.:

vertical (CW looking nort~)~

TABLE VI (contd.)


System Acquisition Date[ a] Fig. Detector Location Detector System Detector SystEill No. Measurement Comments

PRESSURE

Slowdown Suppres- Slowdown suppression tank, D-100 psig 0-100 psig 500 Hz 500 pps 24 QEUD ... \11 SCST pressure inst~u-sion System 136.5 in. south of down- ment in~tial values are adjusted

PE-SV-29 comer 2 E• 112.5° from top to 0 psig. Use PT-Pl38-56 to verti c'a 1 ( CW 1 ooki ng north). obtain the initial pressure f~r

all [PE-SV-] except PE-SV-30. -31, -45, and·-46.

Slowdown Suppres- Slowdown suppression tank header 0-3,ooa psig 0-3,000 psig 100 Hz 500 ~·PS 37 Good data - not qualified. -.....J sion System snubber (en~).

PE•SV-30

Slowdown Suppres- Slowdown suppresston tank header 0-3,000 psig 0-3,000 psig 100 Hz 500 pps 38 Good dcta -not qualified. sipn System snubber (end) .

PE-SV-31

Slowdown Suppres- Slowdown suppression tank bottom 0-100 psig 0-100 psig 500 Hz l,OOO.Hz 22 QEUD. sion System under downcomer 2. 500 pps 122

PE-SV-43 125 208

Slowdown Suppres- Slowdown suppression tank bottom 0-100 psig 0-100 psig 500 Hz l,OOJ Hz 21 QEUD. sion System under downcomer 3. 500 pps 20S

PE-SV-44

Slowdown Suppres-'Slowdown suppression tank header 0-3,000 psig 0-3,000 psig 100 Hz 500 IPPS 39 Good d:ita -not qualified. sion System snubber (bend).

PE-SV-45

Slowdown Suppres- Slowdown suppression tank header 0-3,000 p;ig 0-3,000 psig 100 Hz 500 pps 40 Good dlata - not qualified. sion System snubber (bend).

PE-SV-46

TABLE VI (co1td.)

Range Freguenct Res~onse PARAMETER Data

[ atala] Data

System Acquisition Fig. Detector Location Detector System Jetector S:. stein No. Measuremen: Comments

PRESSURE

Slowdown Suppres- Slowdown vacuum relief sys~em 0-100 psig 0-100 psig 50C Hz SOC• ~·ps 41 QEIIJD. All SDST pressure instru-sian System rupture disc standpipe. memt initial values are adjusted

PE-SV-54 to 0 psig. Use PT-Pl38-56 to obtain the initial pressure for al- [PE-SV-] except PE-SV-30, -31 , -45, and -46.

""'-1 Slowdown Suppres- Slowdown suppression tank lt•Op, 0-100 psig 0-100 psig 500 -lz 5DC r;ps 27 - QEIJD.

N sian System 6 in. north of downcomer 33 PE-SV-55 4 E· 123

126 190

Slowdown Suppres- Slowdown suppression tank across 0-100 psig 0-100 psig 5CO Hz 500 pps 26 QE_D. sian System from downcomer 4, 45° f~om 33

PE-SV-57 top vertical ( CW 1 oak i n~1 north) ..

Slowdown Suppres- Slowdown suppression tank across 0-100 psig 0-100 psig 500 Hz 500, p~s 25 QEUD. sian System from downcomer 4, 67.5° 32

PE-SV-58 from top vertical (CW looki1g north).

Slowdown Suppres- Slowdown suppression taNk, 0-100 psig 0-100 psig 500 Hz 500 pJS 26 QEI!ID. sian System 63.5 in. north of down~ 35

PE-SV-59 comer 3, 45° from top vertical (CW looking north:.

Slowdown Suppres- Slowdown suppression tank 'to)p 0-100 psig 0-100 psig 50) 1-2 500 pps 27 QEUJ. sian System above downcomer 1. 36

PE-SV-60 124 ~26 090

....... w

PARAMETER System

Detector

PRESSURE

Slowdown Suppression System

PE-SV-61

Location

Bl owdown ,suppress ion tank across from downcomer 1 67.5° from top vertical (CW looking north).

Slowdown Suppres- Bellows between broken loop sion System and blowdown suppression tank

PE-SV-70 header.

Reactor Vessel PE-lST-lA

Reactor Vessel ~E-lST-lB

Reactor Vessel PE-lST-lFF

Reactor Vessel PE-1ST-3A

Reactor Vessel PE-1ST-3B

Downcomer stalk 1, 24.5 in. above RV bottom, wide range (0-3,000 psi).

Downcomer stalk 1, 24.5 in. above RV bottom, narrow range (0-200 psi).

Downcomer stalk 1, 21.6 in. above RV bottom ..



TABLE VI (contd.)

Range Frequency Response

Detector

0.:.100 psig

Data Acquisition

System

0-100 psig

0-500 psig 0-500 psig

0-3,000 psig 0-3,000 psig

0-200 psig 0-200 psig

0-3,000 psig 0-2,500 psig

0-3,000 psig 0-3,000 psig

0-200 psig 0-200 psig

Detector

' 500 Hz

30 Hz

3C Hz

30 Hz

4,100 Hz

47 Hz

47 Hz

Data [lat .[a] F. .. lg.

System No.

500 ~ps 25 36

Measurement Comments

QEUD. All BDST pressure instrument initial values are adjusted to 0 psig. Wse PT-Pl38-56 ta obtain the initial pressure toall [PE~SV-] except PE-SV-30, -31, -45, and -46.

500 pps 42 QEUD .

1,000 Hz 108 QEUD. 50 pJs 129

50 pps 109 QEUD. Pressure beyond i nstr J-

1 ,000 Hz 111 50 pps

ment range until ~ T0

+ 31 s~c.

QEUD (jigital) toT + 10 sec. Instrunent temperat8re sensit~ve after " TR + 10 sec. Channel failed (a aiog).

1,000 Hz 108 QEUD. 50 ~·ps

50 pps 110 QEUD. Pressure beyond instrunent range until ~ T

0 + 30 sec.

PARAMETER System

Detector

PRESSURE

Reactor Vessel PE-lST-3FF

Reactor Vessel PE-2ST-lA

Reactor Vessel PE-2ST-lB

Reactor Vessel PE-2ST-lFF

Reactor Vessel PE-2ST-3FF


PT-Pl20-43


PT-Pl20-54


PT-Pl20-83

Location

Downcomer stalk l, 212.1 in. above RV bottom.



Downcomer stalk 2, 21.6 in. above RV bottom.

Downcomer stalk 2, 212.1 in. above RV bottom.

Accumulator A, 27 in. above water outlet.

Emergency core cooling injection into lower plenum.

LPIS pump A discharge line.

TABLE VI (cortd.)

Range =requency Response

D•etector

Data Acquisition

System

0-3,000 psig 0-2,500 psig

0-3,000 psig 0-3,000 psig

0-200 psig 0-200 psig

0-3,000 psig 0-2,500 psig

0-3,000 psia 0-2,500 psig

0~1,000 psig 0-1,000 psig

0-3,00b psig 0-3,000 psig

D-1,000 psig 0-1,000 psig

Detector

4, lC•O Hz

30 rz

30 rz

4,1GO Hz

4, l ({) Hz

5 Hz

5 Hz

5 Hz

Oat a Oata[a] Fig.

System No. Measurement Comments

1,000 Hz 50 pps

20 lll 113

QEJD to T + 10 sec. Instrument te~peratu?e sensitive after "' T

0 + 10 sec.

l,moo Hz 112 QEUO. 50 pps

50 pps Channel failed (digital).

1,000 Hz Channel failed (digital 50 pps and analog).

1,000 Hz ll3 QEUD toT + 10 sec (digital). 50 pps 114 lnstrumen£ temperature sensi-

tive after "' T + 10 sec. Ch~nnel failed0 (analog).

50 pps QEUD. Not presented. Accumula:or ACC-A injection failed to initiate.

50 pps

50 pps

128 Good data - not qualified. 129 191 298

130 Good data - not qualified. 192 299

TABLE VI (contd.)


System Acquisition Uata[a] Fig. Detector Location Detector System Detector System No. i"'·easurement Comments

PRESSURE

Blowdown Suppres- Blowdown header, 35 in. south 0-200 psig 0-200 psig 5 Hz 50 pps 131 QEUD. Initial pressure value sion System of downc.omer 1, 5° from adjusted to 0 psig. Use

PT-Pl38-23 bottom vertical (CCW looking PT-Pl38-56 to obtain the south). initial pressure.

Blowdown Suppres- Blowdown suppression tank top, 0-100 psig 0-100 psig 5 Hz 1 ,C•OO Hz 132 QEUD for imitial conditions sion System 48 in. north of downcomer 1. 50 pps 193 only.

PT-138-55 209 300

"'-J (.11

Blowdown Suppres- Blowdown suppression tank top, 0-100 psig 0-100 psig 5 Hz 1,000 Hz 132 QEUD for initial condition5 sion System 49 in. north of downcomer 2. 50 pps 193 only.

PT-Pl38-56 209

Blowdown Suppres- Spray pump BS-P-83 discharge 0-500 psig 0-500 psig 5 Hz 50 pps 194 QEUD. sion Tank Spray pressure. 302 System

PT-Pl38-136

Blowdown Suppres- Spray system cool down heat 0-500 psig 0-500 psig 5 Hz 50 pps 194 QEUD. sion Tank Spray exchanger outlet pressure. System

PT -Pl38-151

Broken Loop Broken loop cold leg QOBV inlet 0-2,000 psig -2,000 - 5 Hz 1,000 Hz 15 QEUD analog data only.

PT -Pl38-lll between isolation valve and QOBV. +2,000 psig 500 pps 301

Broken Loop Broken loop hot leg QOBV inlet .0-2,000 psig -2,000 - 5 Hz 1 ~000 Hz 16 QEUD analog data only. PT-Pl38-112 between isolation valve and QOBV. +2,000 psig 5CO pps

Intact Loop Intact 1 oop hot leg at venturi 0-3,000 psig 0-3,000 psig 5 Hz 1,000 Hz 133 QEUD except during sub-PT-Pl39-2 on bottom. 5(1 pps cooled blowdown.

TABLE VI (co.ntd. :•

Ringe Freguenc~ Res~:mse

PARAMETER Data Data System Acquisition Jata[a] Fig.

Detector Location Detector System D2tector SJstetl No. Measurement Comments

PRESSURE

Intact loop Intact loop hot leg at verturi 0-3,000 psig 0-3,000 psig 5 Hz l ,'000 Hz 133 QEUD for initial condi-PT-Pl39-3 on left side when looking toward 5C ~ps tions. Uninterpreted data

SG. after T . ' 0

PUMP SPEED

Intact loop Intact loop pump l speed. 0-4,500 rpm 0-10,000 rpm 3.5 Hz 50 ~ps 134 QEUD. RPE-PC-1

'-1 en Intact loop Intact loop pump 2 speed. 0-4,500 rpm 0-10,000 rpm 3.5 Hz 50 ~ps 134 QEUD.

RPE-PC-2 303

TEMPERATURE

Broken loop Broken loop cold leg at on 32-2,300°F 0-600°F 1 .a Hz 50 pps 135 QBUO while instrument immersed. TE-Bl-1 flange. 195 Data display h!Jt wall effects

after ~ T0

+ 53 sec.

Broken loop Broken loop ~ot leg at OTT 32-2,300°F 0-600°F 1.3 Hz 50' pps 135 QEUD while ins~rument immersed. TE-Bl-2 flange. 195 Data display hot wall effects

304 after~ T0

+ 40 sec.

Broken loop Reflood assist bypass syst:m 32-2,300°F 0-600°F l .8 Hz 50 pps 135 QEUO. TE-Bl-3 near CV-Pl38-7l.

Broken loop Broken loop cold leg warm-Jp 32-2,300°F 0-600°F 1.! Hz 50 p:>S 136 Go:>d data -not qualified.

TE-Cl-1 line.

Reactor Vessel Core simulator in instrume1t 32-2,300°F 0-1 ,300°F 1 .& Hz . 50 pJS 137 QEJD while instrument immersed.

TE-CS-1 stalk above orifice plate. 196 Data display hot wall effects after ~ 102 sec.

TABLE VI (confd.}

Range Freguenct Res~onse PARAMETER Data Data

System Acquisition Data[ a] Fig. Detector Location Detector System Detector System No. Measure~nt Comments

PUMP SPEED

Broken Loop Broken loop hot leg warm-up 32-2,300°F 0-600°F 1.8 Hz 50 pps 136 .Good data - not qualified.

TE-HL-2 line.

TEMPERATURE

Intact Loop Intact loop cold leg at OTT 32-2,300°F 0-1 ,300°F 1 .8 Hz 1,000 Hz 138 QEUD while instrument immersed.

TE-PC-1 flange. 50 pps 197 Displays hot wall effects after "' T

0 + 30 sec.

""-J ""-J Intact Loop Intact loop hot leg at OTT 32-2,300"F 0-1 ,300°F 1 .8 Hz 50 138 QEUD while instrument immersed.

' Jps

TE-PC-2 flange. 197 Data display hot wall effec~s after "'T

0 + 135 sec.

Intact Loop Intact loop at SG outlet 32-2,300°F 0-1,300°F 1 .8 Hz 50 pps 138 QEUD ~hile instrument immersed.

TE-PC-3 OTT flange. 197 Displays hct wall effects after "' T

0 + 30 sec.

Emergency Core Accumulator A temperature. 0-200°F 0-200°F ., Hz 50 pps QEUD. Not presented since •

Cooling System accumJlator ACC-A injection

TE-Pl20-41 failej to initiate.

Slowdown Suppres- Slowdown suppression tank bottom, 50-300°F 50-300°F 7 Hz 50 pps 139 Uninterpreted data. Thermo-

sion System 24.0 in. north of downcomer 1 . 305 couple located in a stagnant

TE-Pl38-22 fluid zone.

Slowdown Suppres- Slowdown suppression tank top, 50-400°F 50-400°F 1 .8 Hz 50 pps 140 Good data - not qualified.

sion System 51 in. south of downcomer 4. 306

TE-Pl38-34

.Broken Loop Broken loop cold leg QOBV inlet. 32-1400°F 50-650°F 1 .8 Hz 50 pps .141 Good data -not qualified .

TE-Pl38-62 307

TABLE VI {contd.)

ltange iFreguenct ReSJ.!Onse PARAMETER Data

Oata[a] Data

System Acquisition_ Fig. Detector Location Detector Syste11 Detector System No. Measurement Comments

TEMPERATURE

Broken Loop Broken loop cold leg isolati:m 50-650°F 50-650°F 0.06 Hz 50 pps 141 Good data - not qualified. TE-Pl38-63 valve inlet. 308

Broken Loop Broken loop hot leg isolation 5Q-65Q°F 50-650°F 0.06 Hz 50 pps 142 Good data not qual ifi ed. TE-Pl38-65 valve inlet.

Broken Loop ~roken loop hot leg QOBV inl:t. 32-l4Q0°F 5Q-650°F 1 .a Hz 50 pps 142 Good data - not qualified.

........ TE-Pl38-66 (X)

Slowdown Suppres- Temperature of spray in the 0-400°F 0-400°F 7.Kz 50 pps 199 Good data- not qualified. sion Tank Spray 60 gpm header. 309 System

TE-Pl38-l4l

Slowdown Suppre~- Temperature of spray at spray 0-400°F 0-400°F 7 ftz 50 pps 198 Good data - not qualified. sion Tank Spray pump BS-P-83 discharge. System

TE-Pl38-l42

Slowdown Suppres- Temperature of spray in the 0-400°F 0-400°F 7 ftz 50 pps 199 Gbod data - not qualified. s ion Tank Sp_ray 220 gpm header. System

TE-Pl38-l43

Intact Loop Pressurizer vapor temperature, 600-700°F 600-700°F 7 Hz 5o pps 143 QEUD for initial conditions TE-Pl39-l9 34 in. above the heater rods. on~y. Temperature below

instrument range after 23 sec.

Intact LoGp Pressurizer liquid tempera:ure, 50-7006 F 50-700°F 71-tz 50 pps 143 QEUD for initial conditions

TE-Pl39-20 14 in. above heater rods. 310 oniy.

PARAMETER System

Detector

TEMPERATURE

Intact Loop TE-Pl3g-2g

Intact Loop TE-Pl3g-32

Intact Loop TE-Pl3g-33

Intact Loop TE-SG-1

Intact Loop TE-SG-2

Location

Intact loop cold leg just upstream of OTT flange.

Intact loop hot leg in elbow near venturi.

Intact loop hot leg in elbow· near venturi.

Intact loop cold leg SG outlet.

Intact loop hot leg SG inlet.

Secondary Coolant SG secondary side. System . TE-SG-3

Slowdown suppression tank, 12 in. north of downcomer 1,

Slowdown Suppression System

TE-SV-1 21 in. east of tank E• 107.2 in. from t~nk bottom.

Slowdown Suppres- ·slowdown suppress-ion tank, 12 sion System north of downcomer 1, 21 in.

TE-SV-2 east of tank E,93.0 in. from tank bottom.

in.

Detector

-330 -+l,l30°F

-150 +700

TABLE VI (contd.)

Range Freguency Response Data

Acquisition System Detector

0.06 Hz

0.06 Hz

0.06 Hz

0.35 Hz

0.35 Hz

•).07 Hz

.1.8 Hz

1.8 Hz

Data [Jata[a] F. lg.

System No. MeasurEfllE!nt Corrrnents

50 pps 144 QEUD for initial conditions only.·

1,000 Hz 145 50 pps

1 ,000 Hz 145 50 'PPS

50 pps 146 311

QEUD for i~itial conditions only.

QEUD for initial conditions only.

QEUD for initial conditions only.

50 pps 146 QEUD for initial conditions only.

50 pps

1,000 Hz 50 pps

1,000 Hz 50 pps

1

149 QEUD for initial conditions only.

147 151 200 210

147 152 200 210

QEUD while instrument immers,~d. Designed to measure liquid · temperature.

QEUD while instrument immersed. Designed t) measure liquid temperature.

TABLE VI (cJntd.)

Range Freguencl Res~onse PARAMETER Data

Data[a] Data

Systetl Acquisition Fig. Detector Location Detector System Detecr.or System No. Measurement Comments

TEMPERATURE

Blowdown Suppres- Blowdown suppression tank, 12 in. -150 - 0-400°F l.E Hz 1,000 Hz 147 QEUD while. instrument immersed. sian System north of downcomer 1, 21 in. +700°F 50 pps 153 De;igned to measure liquid

TE-SV-3 east of tank E• 74.7 in. from 200 te11pera ture. tank bottom. 210

Blowdown Suppres- Blowdown suppression tank, 12 in. -150 - .0-400°F 1.E Ht 1,000 Hz 148 QEUD while instrument immersed. sian System north of downcomer 1, 21 in. +700°F 50 pps 154 De·;igned to measure li~uid

TE-SV-4 east of tank E• 57.2 in. from 201 te11perature. (X) tank bottom. 211 0

Blowdown Suppres- Blowdown suppression tank, 12 in. -150- 0-400°F 1 .8 Hz 1,000 Hz 148 QEIDD for digital channel. sion System north of downcomer 1, 21 in. +700°F 50 P~·S 155 Channel failed for analog.

TE-SV-5 east of tank E• 39.0 in. from 201 tank bottom. .

Blowdown Suppres- Blowdown suppression tank, 12 in. -150 0-400°F 1.8 Hz 1 ,OOC· Hz 148 QEUD. sion System north of downcomer 1, 21 in. +700F 50 p~s 156

TE-SV-6 east of tank E• 14.7 in. from 201 tank bottom. 211

312

Blowdown Suppres- Blowdown suppression tank, 12 in. -150 - 0-400°F 1.8 Hz 50 PJ:S 149 QEUD while ·instrument irrmersed. sian System north of downcomer 3, 21 in. +700°F 151 De~.igned to measure 1 iquid

TE-SV-7 east of tank E• 107.2 in. from ,202 teraperature. tank bottom.

Blowdown Suppres- Blowdown suppression tank, 12 in. -150 - 0-400°F 1.8 Hz 50 pps '!49 QELID while instrument immersed. sian System north of downcomer 3, 21 in. +700°F 152 De~igne9 to measure liquid

TE-SV-8 east of tank E• 93.0 in. from :202 teraperature. tank bottom.

TABLE VI (contd.l


System Acquisition Data[ a] Fig. Detector Location Detector System Detector System No. Mea-surement Convnents

TEMPERATURE

Slowdown Suppres- Slowdown suppression tank, 12 in. -150- 0-400°F 1 .8 Hz 1,000 Hz 149 QEUD while ir.strument immersed .. sian System rtorth of downcomer 3, 21 in. +700°F 50 pps 153 Designej to ~easure liquid

TE-SV-9 east of tank E• 74,7 in. from 202 temperature. tank bottom.

Slowdown Suppres- Slowdown suppression tank, 12 in. -150- 0-400°F 1.8 Hz l,OOC Hz 150 QEUD while instrument immersed-. ' sian System north of downcomer 3, 21 in. +700°F 50 p~s 154 Designed to measure liquid

co TE-SV-10 east of tank E• 57.2 in. from 203 temperature. tank bottom. . 212

Slowdown Suppres- Slowdown suppression tank, 12 in. -150 - 0-400°F 1 .8 Hz 50 Pr•s 150 QEUD. sian System north of downcomer 3, 21 in. +700°F 155

TE-SV-11 east of tank E• 39.0 in. from 203 tank bottom.

Slowdown Suppres- Slowdown suppression tank, 12 in. -150 - 0-400°F l.B Hz 50 pps 150 QEUD. sian System north of downcomer 3, 21 in. T]00oF 156

TE-SV-12 east of tank E• 14.7 in. from 203 tank bottom. ·

Reactor Vessel Downcomer 1, 189.3 in. from 32-2,300°F 0-1 ,300°F 1.8 Hz 50 pps 157 QEUD. TE-lST-1 RV bottom. 162

Reactor Vessel Downcomer 1., 165.3 in. from 32-2,300°F 0-1 ,300°F 1.8 Hz 50 pps 157 QEUD~

TE-lST-2 RV bottom. 163

Reactor Vessel Downcomer 1, 141.3 in. from 32-2,300°F 0-1 ,300°F 1.8 Hz 50 PJS 157 QEUD. TE-lST-3 RV bottom. 164

Reactor Vessel Downcomer 1, 117.3 in. from 32-2,300°-F 0-1 ,300°F 1 .8 Hz 50 p;JS 157 QEUD. TE-lST-4 RV bottom. 165

TABLE VI (corotd.)

Range Freguenct Res(!onse PARAMETER Data Data

System Acquisition Dita[a: Fig. Detector Location Detector System [•etector System No. Measurement Comments

TEMPERATURE

Reactor Vessel Downcomer 1, 93.3 in. fr011 32-2,300°F 0-1,300°F 1 .8 Hz 50 rpps Qhannel failed (digital). TE-lST-5 RV bottom.

Reactor Vessel Downcomer 1, 69.3 in. fr011 32-2,300°F 0-1,300°F 1.8 Hz 50·JPpS 158 QEUD. TE-lST-6 RV bottom. 166

Reactor Vessel Downcomer 1, 33.3 in. fr011 32-2,300°F O-l,300°F 1.8 Hz 50 pps Olannel failed {digital).

(X) TE-lST-7 RV bottom.

N Reactor Vessel Downcomer 1, 29.3 in. fro11 32-2,300°F 0-1,300°F 1 .8 Hz 50 pps 158 !;t:UD.


Reactor Vessel Downcomer 1, 25.3 in. fro11 32-2,300°F O-l,300°F 1 .8 Hz 50 pps 158 !;t:UD. TE-lST-9 RV bottom. 169

Reactor Ves?el Downcomer 1, 21.3 in. fro11 32-2,300°F 0-1 ,300°F 8 Hz 50 pps 158 c;t:Uri. TE-lST-10 RV bottom. 170

Reactor Vesse 1 Downcomer l, 17.3 in. from 32-2,300°F. 0-1,300°F 8 Hz 50 pps 159 QEUD. TE-lST-11 RV bottom. 171

Reactor Vessel Downcomer 1, 13.3 in. from 32-2,300°F 0-1 ,300°F 1 8 Hz 50 pps 159 QEUD. TE-lST-12 RV bottom. li2

Reactor Ves se 1 Downcomer 1 , 9.3-in. from 32-2',300°F 0-1,300°F 1 8 Hz 50 pps 159 QEUD.


Reactor Vessel Downcomer l, 45.9·in. from 32-2,300°F 0-1 ,300"F 8 Hz 50 pps 159 QC:UD.

TE-lST-14 RV bottom (inside of OTT). 174

Reactor Vessel Downcomer 2, 189.3 in. from 32,2,300°F 0-1,300"F 8 Hz 1 ,OJO Hz .. C1annel faile~ (digital).

TE-2ST-l RV bottom. 50 CJps

TABLE VI (contd.)

Range Freguenci: Res~onse PARAMETER Data Data

System Acquisition Data[ a] Fig. Detector Locati qr,t Detector System Detector System No. Measurement Comments

TEMPERATURE

Reactor Vessel Downcomer 2, 165,3 in. from 32-2,300°F 0-1,300°F 1.8 Hz 5C pps 160 QEU[). TE-2ST-2 RV bottom. 163

Reactor Vessel Downcomer 2, 141 .3 in. from 32-2,300°F 0-1 ,300°F 1 .8 Hz 1,000 Hz Chame 1 failed (digital). TE-2ST-3 RV bottom. 50 pps

Reactor Vessel Downcomer 2, 117.3 in. from 32-2,300°F 0-1,300°F 1 .8 Hz 50 pps 160 QEUC. TE-2ST-4 RV bottom. 165

00 w Reactor Vessel Downcomer 2, 93.3 in. from 32-2,300°F 0-1,300°F 1 .8 Hz 1,000 Hz Charnel fa i1 ed (digital) ..

TE-2ST-5 RV bottom. 50 pps

Reactor Vessel Downcomer 2, 69.3 in. from 32-2,300°F 0-1 ,300°F 1 .8 Hz 50 pps Channel f3iled (digital). TE-2ST-6 RV bottom.

Reactor Vessel Downcomer 2, 33.3 in. from 32-2,3G0°F 0-1,300°F 1 .8 Hz 1,000 Hz lEO QEUD. TE-2ST-7 RV bottom. 50 pps 167

Reactor Vessel Downcomer 2, 29.3 in. from 32-2,300°F 0-1,300°F 1 .8 Hz 5) pps Charme 1 failed (digital).

TE-2ST-8 RV bottom.

Reactor Vessel Downcomer 2, 25.3 in. from 32-2,300°F 0-1 ,300°F l .8 Hz 1,COO Hz 160 QEUD. TE-2ST-9 RV bottom. 50 pps 169

Reactor Vessel Downcomer 2, 21'.3 in. from 32-2,300°F 0-1,300°F 1.8 Hz 50 pps 161 QEU).

TE-2ST-10 RV bottom. 170

Reactor Vessel Downcomer 2, 17.3 in. from 32-2,300°F 0-1 ,300°F 1 .B Hz 1 ,000 Hz Cha>1nel fa i 1 ed (digital)

TE-2ST -11 RV bottom. 50 pps

TABLE VI (co1td.)

Range F reguencl 'Res~ons e

PARAMETER Data Uata[a]

Data System Acc.u i. sit ion Fig.

Detector Location Detector System De-tector ' System No. Measuremen-:. Conunents

TEMPERATURE

Reactor Vessel Downcomer 2, 13.3 in. from 32-2,300°F 0-1,300°F l.E Hz 50 P~·S 161 QEUD. TE-2ST-12 RV bottom. 172

Reactor Vessel Downcomer 2, 9. 3 in. from 32-2,300°F O-l,300°F 1.8 Hz 5o p~s Chc.nnel failed (digital). TE-2ST -13 RV bottom.

Reactor Vessel Downcomer 2, 45.9 in. from 32-2,300°F 0-1 ,300°F 1.8 -lz 50 p~s 161 QELID. TE-2ST-14 RV bottom. 174

Emergency Core Lower plenum injection·in ~-in. 50-650~F 50-650°F . O.Ol Hz 50 P!=S i75 Gocd data -not qualified. co Cooling System line upstream of injection poi1t. ~

TT-Pl20-65

[a] pps points per second sample rate of the ·cliCJital ~ystem.

CX> (.]'1

PARAMETER Location

Detectors

DENSITY, AVERAGE

Broken Loop Cold Leg DE-BL-lA (p A) DE-BL-lB (pB) DE-BL-1 C (pC)

Broken Loop Hot Leg D E- B L- 2A ( p A ) DE-BL-2B (pB) DE-BL-2C (pC)

Intact Loop Cold Leg DE-PC-lA (pA) DE-PC-lB (pB) DE-PC-lC (pC)

Intact Loop Hot Leg DE-PC-2A (pA) DE-PC-2B (pB) DE-PC-2C (pC)

Intact Loop Steam Generator Outlet

DE-PC-3A (pA) DE-PC-3B (pB) DE-PC-3C (pC)

TABLE VII

COMPUTED PARAMETERS FOR LOFT TEST Ll-3

Units

1 bm/ft3

1 bm/ft3

1 bm/ft3

1 bm/ft3

Calculation Meth6d

Density, Average P = KlpA + K2pB + K3pC

where: PA' PB' Pc = average den-sity along gamma densitometer beam lines A, B, and C. For stratified flow,

Fig. No.

45

45

p = 0.437pA+0.417p 8+0.146pC. __

For other flow regines, P = o.345pA+0.40lp8=0.254pc.

49

49

Remarks

The individual beam densities were filtered with a 4 Hz filter prior to ~eing used ir the averaging calculation.

Not presented. DE-PC-lA failed.

TABLE VII (contd.~

PARAMETER Location Fig.

Detectors Units Calculation Method No. Remarks

FLOW REGIME AND DENSITY 1 bm/ft3 Homogeneous flow regimes c.re Rapid fluctuation back and indicated by (H) when forth between flow regimes

Broken Loop Cold Leg 1 bm/ft3 PA = PB = Pc· 213 usually indicated slug flow.

DE-BL-lA (p A) The logic table and math-DE-BL-lB (pB) Annular flow regimes are ematical model for this DE-BL-1 C (pC) indicated by (A) w1en regi~e have not yet been

Pc > p B. d~veloped.

Broken Loop Hot Leg 1 bm/ft3 214

DE-BL-2A (p A) Stratified flow regimes are . Broken loop hot leg should 0? DE-BL-2B (pB) indicated by (S) w1en be inverted annular ~ DE-BL-2C (pC) PA > PC' after , ... 24 sec.

Intact Loop Cold Leg 1 bm/ft3 Inverted annular flow regimes Intact loop fOld leg not pre-

DE-PC-lA (pA) are indica ted by (l) wren sented due to failure of DE-PC-DE-PC-lB (pB) PA < PB· lA. DE-PC-1 C (pC)

. Unmodeled flow regimes are Intact Loop Hot Leg

l-bm/ft3 indicated by default (C) 215 Intact loop hot leg should be DE-PC-2A (p A) when none of the above .condi ti o.ns stratified after ~18 sec. DE-PC-2B (pB) are satisfied. DE-PC-2C (pC)

ENTHALPY Btu/1 bm Enthalpy = H = hf + xf~ow hfg Data before T is invalid due to the sa~urated fluid

Broken Loop Cold Leg 216 assumption. PE-BL-1 ( p: hf' hfg) psig:Btullbm

PARAMETER Location

Detectors

ENTHALPY (contd.)

Broken Loop Hot Leg PE~BL-2 (P: hf' hfg)

Intact Loop Cold Leg PE-PC-1 (P: hf' hfg)

Intact Loop Hot Leg

Units

Btu/lbm

psig:Btu/lbm

psi g: Btu/1 bm / .

PE-PC-2 (P: hf' hfg) psig:Btu/lbm

Intact Loop, Steam Generator Outlet

PE-PC-3A (P: hf' hfg) psig:Btu/lbm

MASS FLOW RATE/SYSTEM VOLUt~E

Broken Loop Cold Leg Type A:

FE-BL-1 (v) 2 . ME-BL-1 (p v )

Type B: FE-BL-1 (v) PE-BL-1 {P: p£)

ft/sec 2 1 bm/ft-sec

ft/sec psig:lbm/ft3

TABLE VII (contd.)

Calculation Method '

where:

h = f saturated fluid enthalpy from ASME steam tables using the pressure at the measurement location

= latent heat of vaporization from the ASME steam·tables using the pressure at the· measurement location

xfl ·OW = fl o.w qua 1 ity (see 11 QUALITY' FLOW"

Mass

m = A

entry in this table).

flow rate/volsys Type A =

p v2 A v x volsys

t~ass flow rate/vo\ys Type B =

[(1 - <a>)/(1 - x)] p£ VA m = --------=----~:...._-8 volsys

. ?ig. No.

2T7

218

219

220

Remarks

Data before T is invalid due to s~tura~ed fluid. assumpti :>n.

The output f~om the drag discs, the turbine flowmeters, and the gamma dernsitometers were filtered ~o

2 21 4 Hz prior to perfqrmi ng calculations. The measured point values. for .the fluid velocity and momentum flu~ from the.turbin~rlowmeters and the drag discs, respectively, were converted to average values prior to performing the calculations. ·

00 00

PARAMETER Location

Detectors

MASS FLOW RATE/SYSTEM VOLUME (contd.)

Type C: ME-BL-1 (pi) DE-BL-1 (p)

Type D: · FE-BL-1 {v) DE-BL-1 (p)

Type E: PDE-BL-2 {t~P) DE-BL-1 (p) ·

Broken Loop Hot Leg Type A:

FE~BL-2 ( v) 2 ~1E-Bt"-2 (pv )

Type B: FE-BL-2 (v) PE-BL-2 {P: p£)

Type C: ME-BL-2 (pi) DE-BL-2 (p)

Units

ft/sec 3 1 bm/ft

psid 1 bm/ft3

ft/ sec ·) lbm/ft-!:ec·-

ft/sec psi g: 1 brr./f:3

? 1 bm/ft3sec'-l bm/ft

TABLE VII (contd.)

Calculation Methoj

r1ass flow rate/volsys Type C =

m = [p(pv2)]l/2 h C volsys \

Mass .flow rate/volsys TYpe D =

m = p v A 0 volsys

l1ass flow rate/volsys Tjpe E =

m ='p [(Kt~P)/p]l/ 2 A E vol sys

where:

p = average fluid demsity at measurement location

p = Q,

saturated 1 iquid· density from ASME steam tables ·

/

rto.

2.~2

:223

:224

Remarks

Broken loop co~d leg Type B mass flow rate/system volume not r:resented.

Not presented.

Not presented.

--TABLE VII (contd.)



MASS ~LOW RATE/SYSTEM lbm/ft3-sec 2 ! -pV =momentum flux [ME ... ]

VOLUME (contd.) <a> = void fraction (see

Type D: 11 VOID FRACTION 11 entry 226 FE-BL-2 (v) ft/sec 3 in this table) DE-BL-2 (p) lbm/ft

Type E: 227-PDE-BL-1 {l'lP) psid DE-BL-2 (p) · 1 bm/ft3

00 Intact Loop Cold Leg A = flow area for the 1.0 Type A: measurement location 228

FE-PC-1 (v)2 ft/sec 2 ME-PC-1 (pv ) lbm/ft-sec

Type B: 229 FE-PC-1 (v) ft/sec - - 2 -PE-PC-1 (P: pt) psig:lbm/ft3 A . = 0.6485 ft in the

plpes plane of the DTT~ Type C:

lbm/ft~sec 2 K = conversion constant 230 Type C and Type D mass

2 ME-PC-1 (pv ) ' flow rate per- system DE-PC-1 (p) lbm/ft v = velocity of fluid at volume were calculated

measurement location using _DE-PC-lB since Type D: [FE ..... ] 231 DE-PC-lA failed and

FE-PC-1 (v) ft/sec 3 av~rage density co~ld DE-PC-1 (p) 1 bm/ft X = flow quality (see not be calculated.

II QUALITY,_ FLOW" this -Intact Loop Hot Leg tab 1 e).

Type A: Not presented; ME-PC-2 FE-PC-2 (v)2 ft/sec 2 failed. ME-PC-2 (pv· ) 1 bm/ft-sec

TABLE VII (contd.)


Detectors Units Calculation ~ethod r~o. Remarks

MASS FLOW RATE/SYSTEM 1 bm/ft3 -sec VOLUME (contd.)

Type B: 2.32 FE-PC-2 (v) ft/sec PE-PC-2 (P: .P_e) psig:lbrD/ft3

Type C: 2 ' ME-PC-2 (pv ) 1 bm/ft3sec- Not presented; ME-PC-2 OE-PC-2 ( p) 1 bm/ft failed.

Type 0: 233 1,() FE-PC-2 (v) ft/sec 3 0

OE-PC-2 (p) 1 bm/ft


Type_ A: Not pr:sented. FE-PC-3 (v)2 ft/sec -')

ME-PC-3 (pv ) 1 bm/ft-sec

Type B: 2~:4

FE-PC-3 (v) ft/sec 3 PE-PC-3A (P: p1

) p s i g : 1 brr/ f:

Type C: 2 ? 2~5

ME-PC-3 (pv ) 1 bm/ftjsec._ OE-PC-3 (p) 1 bm/ft

Type 0-: 2~6

FE-PC-3 ( v) ft/sec 3 OE-PC-3 (p) 1 bm/ft

TABLE VII (contd.)

PARAMETER Location Fig:

Detectors Units Calculation Me~hod No. Remarks

MASS FLOW RATE/SYSTEM lbm/ft3-sec VOLUME ( contd. )

Pressurizer psig:lbm/ft3 Mass flow rate/vols pres- Not presented.

PE-PC-4 ( P: Pg) surizer = ys · . dL L T -Pl39-6 {l~P) m = -0.067269 dT

dpg

PE-PC-4 (P: Pg) ' 3 0.011677 crt

psig:lbm/ft dpL 237 LT-Pl39_;8 {t~P) psid 0.011026 crt

1.0 where: p = density of saturated g steam corresponding

to the pressure from PE-PC-4

PL = density of saturated liquid remaining in pressurizer corre-sponding to the pres-sure from P~ PC-4

L = 1 evel in pressurizer in inches.

PUMP SPEED, ELECTRICAL rpm

Intact Loop, Primary Coolant Pump 1 Pump speed, electrical = 238 Pump 1 PSMG set field

PCP-1-F Hz NG = 60 (PSMG frequency). 239 breakers were opened at ·-v24 sec.

1.0 N

PARAMETER Location

Detectors PUMP SPEED, ELECTRICAL rpm (contd.)

Primary Coolant Pump 2 PCP-2-F

PUMP MOTOR SLIP

Intact Loop, Primary Coolant Pump

RPE-PC-1

Primary Coolant Pump 2 RPE-PC-2

PUMP ELECTRICAL HORSEPOWER

Intact Loop, Primary Coolant Pump 1

Hz

None

rpm

rpm

hp

PCP~l-I (I 1) amp

PCP-1-V (V1) V

Primary Coolant Pump 2 PCP-2-I (I 2) amp

PCP-2-V (V2 V

TABLE VII (contd.)

Calculation ~ethod

Pump motor slip =

NG- (RPE-PC-1! -2)

Spurn~ = NG

where: NG = pump speed, electrical

(see "PUMJ SPEED! ELEC~ TRICAL" above).

Pump electrical horse~ower =

p . = 0. 001 3 2 ( V l I l ) ehp1

p· = 0.00132 (V2I2) ehp2

Fig. No.

:238 240

241

242

242

~:emarks

Pump 2 PSMG set field breakers were opened. at "-24 sec.

Pumps 1 and 2 PSMG set field breakers were opened at "-24 sec.

TABLE VII (contd.)



PUMP ELECTRICAL HORSE- hp POWER, TOTAL

Intact Loop, Primary Coolant Pump electrical horsepower = 243 Pumps 1 and 2

PCP-1-I (!1) amp p = 0.00132(V1I1 + V2I2) ehptot

PCP-·1-V ( v 1 ) v PCP-2-I (I 2) amp where:

1.0 w PCP-2-V (V2) v I 1, I are the instantaneous

curre~t values as defined in-Column 1

V , V are the instantaneou$ v6lta~e values as defined in Column 1.

PUMP WATER HORSEPOWER hp Pump water horsepower =

Intact Loop,. Pwhp = Ap Vt~P (0.2618) 244 Primary Coolant Pumps and 2 where:

PdE-PC-1 (t~P) psid Ap =_ 0. 6485 ft2

FE-PC-3( V) ft/sec

PARAMETER Location

Detectors

PUMP EFFICIENCY

Intact Loop, Primary-Coolant Pumps 1 and 2

PRESSURE, CLOSURE

Broken Loop Cold Leg PDE-RV-1 (P1) PDE-BL-2 ( P 2) PDE-BL-3 ( P 3)

Units

None

psid

· psid psid psid

TABLE VII (cant~.}

Calculation Methcd Primary coolant pump efficiency =

:, = Pwhp/Pehp tot

·where:

Pwhp = pump water horsepow~r (s'ee "PUMP WATER HORSEPOWER" in this table).

P h = pump electr~cal e Ptot

horsepower total {see "PUMP ·ELECTRICAL HORSEPOWERD in this table).

Pressure, closure =

n Pl - E

i=2 P.

1

Remarks

245

TABLE VII (contd.)

PARAMETER Location Fi·~.


PRESSURE, CLOSURE (contd.)

Broken Loop Hot Leg where: Not presented. POE-RV-1 ( P1) psid P and P. are the PDE-BL-1 ( P ) psid dlfferenfial· pressure POE-BL-4 ( P2) I psid readings for each calcu-POE-BL-5 (P~) psid lation as assigned in POE-BL-6 ( P 5) psid Column 1.

1.0 PDE-BL-7 (P6) psid

<.T1 PDE-BL-8 (P8) psid

Intact Loop 246 PDE-PC-1 ( P1) psid PDE-PC-2 (P2) psid PDE-PC-3 (P3) psid PDE-:PC-4 (P4) psid PDE-PC-S ( P ) psid PDT-Pl39-305(P6) !2-S i d

QUALITY, STATIC None Quality static =

Broken loop Cold Leg xstatic = 1 - [(l-<a>)(p1/~)]

247 PE-BL-1 (P: P1 , Pg) psig:lbm/ft3 where:

<a> = void fraction (see Broken Loop Hot Leg

ps 1 g: 1 bm/ft3 11 VOID FRACTION 11 entry). 248

PE-BL-2 (P: p1

, pg). ·

TABLE VII (contd.)



QUALITY, STATIC (contd.) None PQ, = saturated liquid Static ~uality data are re-density from the ASME stricted between values of

Intact Loop Cold Leg psig:lbm/ft3 steam tables us;ng 249 0.0 and 1.0 in the computer

PE-PC-1 (P: pi, Pg) the pressure at :he program. measurement locc:ion

I.ntact Loop Hot Leg psig;lbm/ft3 250 Static quality in the intact

PE-PC-2 (P: pi, pg) p = average density ~rom loop cold leg was calculated gamma densitometer. using DE-PC-lB since DE-PC-lA

Intact Loop, Steam failed and average density Generator Outlet

psi g: 1 bm/ft3 . 251 could nat be calculated.

PE-PC-3A (P: pi, Pg)

1.0 QUAL! TY, FLOW None Qua 1 ity, flow = Flow quality data are restricted 0'1

(Lockhart and Martinelli 1 between values of 0.0 and 1.0 in Correlation) xflow = (1 + N) the computer program.

Broken Loop Cold Leg p-si g: 1 bm/ft3 1/P 1/P 252

PE-BL-1 (P: Pi' Pg) N = {1/A) [(1-<a>)/<c>] TE-BL-1 (T: lli' llg). °F: 1 bm/ft-hr

Broken Loop Hot Leg ( ) -Q/P ( I '-R/P 253 PE-BL-2 (P: p.Q,, pg) psi g : 1 bm/ft 3 Pg/p.Q, lliJllg•

TE-BL-2 (T. ll.Q,' llg) °F: 1 bm/ft-hr \\'here:

Intact Loop Cold Leg 3 254 Flow qua·. i ty was ca 1 cul a ted using PE-PC-1 (P: p.Q,, Pg) psig:lbm/ft <::t.> = void fraction (see DE-PC-lB since DE-PC-lA failed TE-PC-1 (T: ll.Q,' llg) °F: 1 bm/ft-:hr "VOID FRACTI011' e111try) and average dens.-=i ty caul d not

be calcu-ated. Intact Loop Hot Leg

psi g : 1 bm/ ft 3 pl = saturated liquid 255 PE-PC-2 (P: p.Q,, pg) density from the.ASME TE-PC-2 (T. ll.Q,~ llg) °F: 1 bm/ft-hr steam tables u~·ng

the pressure at the measurement location

PARAMETER Location

Detectors Units

QUALITY, FLOW None (Lockhart and Martinelli Correlation) (contd.)


psig:lb~/ft3 PE-PC-3A (P: p~, p ) TE-PC-.3 (T: ~~' ~g) °F: 1 bm/ft-hr g

\.0 ""-~

TEMPERATURE, SATURATION OF

Broken Loop Cold Leg PE-BL-1 psig (TE-BL-1) OF

Broken Loop Hot Leg PE-BL-2 psig (TE-BL-2) OF

"

TABLE VII (contd.)

Fig. Calculation Method No.

Pg = saturated yapor den-sity from the ASME steam tables using the temperature at the measurement location 236

~~ = saturated liquid vis-cosity from tempera-ture

~g = saturated vapor vis-cosity from tempera-ture.

Lockhart and Martinelli Coefficients:

A = 0.28 p = 0.64 Q = 0.36 R = 0.07

Saturat~on temperatures are taken from ASME steam tables for measured pressures. 257. Temperatures are measured by the detectors in parentheses.

258

Remarks

Saturation temperature data are not valid prior toT . TE-BL-1 displays ho~ wal9 effects after ~53 sec.

TE-BL-2 displays hot wall effects after ~40 sec.

0

TABLE VII (contd.)


Detectors Units Calculation Methcd ·~a. Remarks TEMPERATURE, SATURATION OF (contd.)

Intact Loop Cold Leg 2:39 TE-PC-1 displays hot wall PE-PC-1 psig effects after ~30.sec. (TE-PC-1) OF

' Intact Loop Hot Leg 260 PE-PC-2 psig (TE-PC-2) OF

1.0 Intact Loop, 261 TE-PC-3 displays hot wall co Steam Generator Outlet effects after ~30 sec.

PE-PC-3A psig (TE-PC-3) OF

Reactor Vessel, 262 TE-CS-1 has ~4°F high Core Simulator offset at T

0.

PE-CS-lA psig ( TE-cs=-1) OF

Downc.omer 263 Instrument Stalk

PE-lST-lA psig (TE-lST-9) OF

Down comer 264 Instrument Stalk 2

PE-2ST-1A · psi g (TE-2ST-9) OF

TABLE VII (contd.)

PARAMETER Location F'ig.

Detectors Units Calculation Method rJo. Remarks -

P~, - p

VOID FRACTION None Void fraction = Void fraction data are p - Pg restricted between.the Jl,

Broken Loop Cold Leg 265 values of 0.0 and 1.0 in PE-BL-1 (P: PJI,' Pg) psig the compu:er program. DE-BL-1 (p) 1 bm/ft3 where:

Void fraction for the in-Broken Loop Hot Leg

~

p = saturated liquid den- 256 tact loop cold leg was PE-BL-2 (P: pJI,, pg) psig Jl, s i ty from the .~SME calculated using chordal

1.0 DE-BL-2 (j;) 1 bm/ft3 steam tables u5ing the density measu~·ed by 1.0 pressure at the measure- DE-PC-lB due to the

Intact Loop Cold Leg ment location 267 failure of DE-PC-lA. All PE-PC-1 (P: PJI,' pg) psi g subsequent calculations DE-PC-1 (p) 1 bm/ft3

Pg = saturated vapor density using void fraction at this from the ASME steam location were al5o computed

Intact Loop Hot Leg tables using the pres- 268 using DE-PC-13. PE-PC-2 (P: pJI,, pg) psig sure at the measurement DE-PC-2 (j;) 1 bm/ft3 location

Intact Loop, Steam p = average density from 2.69 Generator Outlet gamma densitometer.

PE-PC-3A (P: pJI,, p ) DE-PC-3 (j;) g

psig 1 bm/ft3

-; '7 .

THIS PAGE

WAS INTENTIONALLY

·. LEFT BLANK

1. TEST L1-3 MEASURED PARAMETERS--,

SHORT-TERM PLOTS (1 SECOND OR LESS}

This section of presented data consists of Figures 14 through 42.

101

;= u 0..

:z 8 1-.... ... 0 0..

.... > ~ >

;= u 0..

:z 8 1-.... •n

~ ... > _. < >

100.

.........---8' -.;;;;:

/ /

75. / / /. • PSFT~~8 CV-P138-001 i/

7, ~ PSFTO~~g CV-P138-015 J

50. 7

// '/ .)

-· ,.../~

25. / I "

I J .... I

'1/

o. """"" -/

-25.

-0.02 o.oo 0.02 o.o .. o.oe 0.08 0. 10

TIME AFTER RUPTURE (SEC)

Fig. 14 Valve opening (%) for broken loop QOBV, cold leg valve (CV-Pl38-l), and hot leg valve (CV-Pl38-15).

100. 2500 .

~ -~ / 1 I \ / e PGFTW715 P~~P138-111 2000

\ / o PSFT~It8 CV-PI38-00 -··· ... I <.!)

I I --.

I .PI ..

I

.... "' 0..

60. 1500 "' ~ ., ....

I .• 0:: 0..

iJ 1000

I /\. ........... ..... . I ~ ......... h.. .-. -I ' /_ i -.__..... \........- ...

o. 500

-0.02 o.oo 0.02 o.o .. 0.06 0. 08 . 0. I 0

Fig. 15 TIME AFTER RUPTURE (SEC)

Valve opening (%) for broken loop cold leg QOBV (CV-Pl38-l) and cold leg QOBV inlet pressure ( PT -P138-111).

102

;:: u a.

:z 8 !:: "' 0 a. ...., > .... < :>.

<!l -"' ~ ...., a:: => "' "' ...., a:: a.

100. 2500 -· -- ...,-r........- • PGFTW716 PT-PI38-112 ...._ I D PSFTQ~~g CV-PI38-015

\ p

' I 1/ 2000

f <!l 1\ I

\ I -"' a.

\ J ~ l 50. ....,

1500 a:: =>

"' 1/ "' ...., a:: a. ,

I I 1000

.1

./ L.r"' -- ~ 0. 500

-0.02 o.oo 0.02 o.o~ 0.06 0.08 0: I 0

TIM£ AFTER RUPlURE (SEC)

Fig. 16 Valve opening (%) for broken-loop hot leg QOBV (CV-Pl38-15) and hot leg QOBV inlet pressure (PT-Pl38-112).

noo.

...... rl

2000.

1!500.

1000.

500.

-0.02

Fig. 17

··e 1108Ttel3 P£-BL-001 : o.:"PoeTW'723 PE-8L-OO'f

._... '~A. P08TW'725 PE-&L-008 ~~\

IF ~ ~· IJ v ~

\1 ~ .. hA.. ~ ~£

v LA ~ .. ""\

It\ ~ I'-\. 1 lA ..

... ""'-.

.. J '111\1' ~ . . WIO\ ~ , __

if" • .. Jl' -~ -- ... ........ ~I ._ -~-.,

"" ...... ~ ,

o.oo 0.02 o.o .. o.oe o.oa 0.10 0.12


Pressure in broken loop cold leg (PE-BL-1, -4, and -8) {filtered to 250Hz).

103

<.!l ~

V> 0..

<.!l ~

V> 0..

2500.

[J

2000.

1500.

1000.

500.

-0.02

\ ~ l ~ -\ UC\ ~ ~ II\ { ~ ::![ ' \ - 'T \~ -~ .-""' __. ,.: '-. - • ~

\ ' ' ~ la

o.oo 0.02 o.o .. o.oe


• PG8T .. I .. P£-IL-002 a PG8TW'7H P£-IL·-ooJ • PG8TW'72't ~-ooe

....

' '-.. ... -. o.oa 0.10 0.12

Fig. 18 Pressure in broken loop hot leg (PE-BL-~. -3, and -6) (filtered to 250Hz).

2500.

2000.

1!'500. ,_____

1000.

500. -0.02

_.._

~~

"'-lit"\ ...... ~·~ .... '\.

"' r-.... I\..,.... " ... ""'\..• ~' ~

... " ........ !}., '

o.oo 0.02 o.o'+ o.oe TIME AFTER RUPTURE (SEC)

...._

• POPTW727 P£-PC-001 a POPTH808 P£-PC-002 6 POPT .. 08 P£-PC-OOJA 0 POPTW738 P£-PC-OOit

.............. ~ ...._.__, -

""'''I;; -.........

0.08 0. I 0 0. 12

Fig. 19 Pressure in intact loop cold leg, hot leg, steam generator outlet, and pressurizer (PE-PC-1, -2, -3A, and -4) (filtered to 250Hz).

104

/

<!I .... V'> c..

w

"" => V'> V'> w

"" c..

<!l .... V'> c..

w

"" => V'>

·~ "" c..

2500.

2000.

1500.

1000.

500.

-0.02

- i\'-~

--

o.oo

• POCT~7 PE-CS-OOIFF a POCT~8 PE-CS-002FF 6 POOTH850 PE-IST-003FF

1'-.. ......... ~ a--..; ... ~ ~

·""''III ~ ~ ~

1 ill.

' ~ -iiiiii;

0.02 O.Oit 0.06 0.08 0. 10 0. 12


Fig. 20 Pressure in rea~tcr vessel core simulator instrument stalk and downcomer instrument stalk 1 (PE-CS-lFF and -2FF and PE-lST-3FF) (filtered to 258Hz).

ItO.

30.

20.

I 0.

o. -o. 1

Fig. 21

• PGTT0088 PE-5~-001 a PGTTOIOI PE-SV-022 6 PGTT0103 PE-SV-021t 0 PGTT0112 PE-SV-Oitlt

It IN 1\. n all ~

/i' J 1\J

u !I :~ N!' ,_, ~ ul I' -.mJ.

j Jr/QW'!Y '+' I

4 .. I .NOTE: INITIAL SLOWDOWN SUPPRESSION

TANK PRESSURE ADJUSTED TO 0 PSIG, PE-SV-1 FILTERED TO

j 6~ HZ.

I I ... 1 I

o.o 0. I 0.2 0.3 0.'+ 0.5 o.6 o.7 o.e 0.9


Pressure in blowdown suppression tank bottom, 180° from top vertical reference (PE-SV-1, -22, -24, and -44).

105

~ -<I) a.

..... "" ::> <I) <I) .... "" a.

<.!) -<I) a.

~ =' ~ .... "" a.

!50.

'tO.

30.

20.

10.

o. -o.a

Fig. 22

so.

20.

10.

o. -o.a

Fig. 23

• POTTDIII PE· .,.. .. ~-a POTTOI05 PE-SV-028 6 PGTTDOIO PE-SV-001 0. -•niiDe- --;,

...

~l g JJl

-~~- .al\ .. ...

fl NOTE: INITIAL BLOWDOWN SUPPRESSION TANK PRESSURE ADJUSTED TO 0 PSIG.

j I I I o.o o. l 0.2 0.3 o ... 0 .!5 o.e 0.7 o.8 o.e

TIME AFTER RUPTURE (SEC) '

Pressure in blowdown suppression tank bottom, 180° from top vertical reference (PE-SV-3, -26, -27, and -43).

o.o

• P8TT0088 ra.·-.,· . .,.,. a P8TTOI02 PE-sY-021 • !'"V••utllt ~-sv-on

& ,... ~ -- ...

..d

t NOTE: INITIAL BLOWDOWN SUPPRESSION

rJ TANK PRESSURE ADJUSTED TO 0 PSIG .

...t

0. I 0.2 0.3 O.'t 0.!5 o.e 0.7 0.8 0.9


Pressure in blowdown suppression tank submerged, 112.5° from top vertical reference (PE-SV-2, -23, and -25).

106

~ -"' ~ "" "" =>

"' V'l

"" "" Q.

<.!1 -"' Q.

"" "" =>

"' V'l L.o,J

"" Q.

••

2o.

10.

o. -0.1

. -

~ r -o.o o.a

·,

• Nnoo81 PE-SY-OOit D NTTDI07 PE-SY-028 A NTTDI- P£-SY-0211

.....M..

"J' .... ,. ~-..._ - ~

, .....

NOTE: INITIAL SLOWDOWN SUPPRESSION TANK PRESSURE ADJUSTED TO 0 PSIG.

0.2 o.s o ... o.s o.e o . ., o.a 0.8


Fig. 24 Pressure in blowdown suppression tank submerged, 112.5° from top vertical reference (PE-SV-4, -28, and -29).

JO.

20.

10.

o. -o.a

Fig. 25

• NTTDI21 PE-SY-081 D NTTDII8 PE-SY-058

-~ V"

fA 1/ --NOTE: INITIAL SLOWDOWN SUPPRESSION

- TANK PRESSURE ADJUSTED TO 1 0 PSIG.

1 /

o.o 0. I 0.2 0.3 o ... 0.5 o.e 0.7 o.a o.e TIME AFTER RUPTURE (SEC),

Pressure in blowdown suppression tank vapor space, 67.5° from top vertical reference (PE-SV-58 and -61).

107

<!I -V') 0..

w

"" :::> L'l V') .... "" 0..

<!I -V') 0..

w

"" :;;, V') ,,., .... "" ~

so.

n.

10.

o. -o. 1 o.o

.

j , 17

0. I

~ ~ ~

I r

0.2 o.:s o ... TIME AFTER RUPTURE (SEC)

• P8TTDI17 P£-SY-057 a ~T!DII8 PE-SY~058

....... ..... ~

--

NOTE: INITIAL SLOWDOWN SUPPRESSION -TANK PRESSURE ADJUSTED TO 0 PSIG.

o.e 0.1 0.8 n.R

Fig. 26 Pressure in blowdown suppression tank vapor space. 45° from top vertical reference (PE-SV-57 and -59).

10. • POTT0118 P£-SY-085

------ a POTTD018 PE•SY-017 6 POTTOIIO PE·SY-080

20. ... r_ -- r\.... ~

I ~A ~ --

II. 7 --- IJ ~ -,________

10.

J 1 NOTE: INITIAL SLOWDOWN SUPPRESSION

17 TANK PRESSURE ADJUSTED TO -0 PSIG.

o. -0.1 o.o O. I 0.2 0.3 O.'t 0.5 o.e 0.7 o.a 0.8

Fig. 27


Pressure in blowdown suppression tank top, oo from top vertical reference (PE-SV-17, -55, and -60).

108

~ -11'1 ~

..... a:' => V> V> ..... "" ~

-t,O -V> ~

..... "" => V> V> ... "" ~

30.

za.

10.

o. -0.1 o.o

.. 1111 ! ~

~

0 .•

--

.._

ll ~ ,..-_;- -J. -,..... .... -r.J ,.

' 1/ •

0.2 0.3 o ... TIME AFTE~. IIIIPTIIRE (SEC)

• P8TT0087 PE-SV-015 a P8TT0081 P£-SV-018

'

- ........ ~ ~ -

_.,. •••-n•••

NOTE: INITIAL BLOWDOWN SUPPRESSION TANK PRESSURE ADJUSTED TO 0 PSIG.

0.5 o.e 0.7 o.a 0.9

Fig. 28 Pressure in blowdown suppression tank submerged, 230° from top vertical reference (PE-SV-15 and -16).

50.

'tO.

30.

20.

10.

A o. -o. 1 · o. o

Fig. 29

. • POTTOHe PE-SV-OI't a PGTTOIOO PE-SV-018 -- . . -··.- - ... -.

~ " I~ ~- ~ ~ 4

-x.., " ~ - ~ .~

...-..::;

NOTE: INITIAL BLOWDOWN SUPPRESSION TANK PRESSURE ADJUSTED TO 0 PSIG.

0 .. I 0.2 0.3 o ... 0.5 o.e 0.7 o.a 0.11


Pressure in blowdown suppression tank header (PE-SV-14 and -18).

109

~ -<1'1 0..

..... ... ;;.., <1'1 <1'1 1...•! a: 0..

~ -<1'1 ~

..... a: :::> <1'1 <1'1 ..... a: 0..

30. • POTT0093 PE-SV-011

~----1r-----+------~------~------+-------~--D POTT0095 PE-SV-013

~----1r-----+----t---~----11------+------~- 6 POTTO I 06 --~~ -SV-:()2_7

20.

~ .... ~-

I J J-----1r-----fiiH,_.,vt+------+------+----____;' NOTE: INITIAL SLOWDOWN SUPPRESS I ON J TANK PRESSURE ADJUSTED TO

j r 0 PSIG, PE-SV-11 FILTERED TO

_,_ .I 601HZ. I I 0 ..... ~~ .. ~--~----~--~----L---~--~~--~--~ -o. 1 o.o

Fig. 30

JO.

20.

10.

o. -0.1 o.o

Fig. 31

0. I 0.2 0.3 0.1+ 0.5 0.6 0.7 u.s


Pressure in blowdown suppression tank B-end submerged along vertical centerline (PE-SV-11, -13, and -27).

0.9

• POTT0012 P£-SV-010 D POTT~ P£-SV-012 6 POTTOIOJ P£-SV-0~

.1.1 JIA I , l!'

J.J ~ l L .. -- :---~ I ~ i./ -

~ - -

J NOTE: INITIAL SLOWDOWN SUPPRESSION

7 TANK PRESSURE ADJUSTED TO 0 PSIG.

---:17 .I I -

0. I 0.2 0.3 0.1+ 0.5 o.e 0.7 0.8 0.9

TIME AFTER RUPTURE (SEC) )

Pressure in blowdown suppression tank A-end submerged along vertical centerline (PE-SV-10, -12, and -24).

110

~ -"' ~ w

"' => "' "' w

"' 0..

~ -"' 0..

w "' => "' "' w "' Q.

'+0.

30.

20.

I 0.

o. -o. 1 o.o

Fig. 32

sa.

n~

a a.

a. -a.a a.a

Fig. ·33

- -

• PGTT0088 PE-SV-001 D PGTT0088 PE-SV-002 6 PGTTOIIS PE-SV-058

I 1\. ., ~ ,.

I

J I. ' J .. na..~. DA a A ~ n..,awr1 .... ~ ••AA'- ~~

A V' - yw ... \,J

II' 4 ., NOTE: INITIAL SLOWDOWN SUPPRESSION

TANK PRESSURE ADJUSTED TO 1..,. 0 PSIG, PE-SV-1 FILTERED TO

I I 60 HZ. . .

..Ill. I/ I I I I

0. I 0.2 0.3 0.'+ 0.5 o.e 0.7 o.a 0.9


Pressure _in blowdown suppression tank in a transverse plane, 316.5 in. from B-end reference (PE-SV-1, -2, and -58).

• NTTDII7 IP£-sY-0117 a NTTDII8 IP£-s¥-08 A NTTDOe'7 IP£-s¥-015

II

~ r• ~ -- 1-

~ ~_/ -- --- ~ ...__ I& --......., ... ~ ---'1

1

J NOTE: INITIAL SLOWDOWN SUPPRESSION , TANK PRESSURE ADJUSTED TO 0 PSIG.

....1 I

a. a 0.2 0.3 o ... 0.5 o.e 0.7 o.a o.a TIME AFTER RUPTURE (SEC)

Pressure in blowdown suppression tank in a transverse plane, 316.5 in. from B-end reference (PE-SV-15, -55, and -57).

111

<.!) .... V'l 0..

......

"" ::> V'l V'l ...... "' 0..

<.!) .... V'l e; LLI

"" :::::> V'l V'l ......

"' Q.

JO.

20.

10.

o. -o. 1 o.o

rig. 34

JO.

20.

10.

o. -o. 1 o.o

Fig. 35

• NTTDIOI P£-SV-022 D NTT0102 P£-SV-023

' t .. l~

......,. ~ - ...__ ....

·y ._ ~ .... - ...._

r I

~ r 7 NOlE: INITIAL SLOWDOWN SUPPRESSION

1 TANK PRESSURE ADJUSTED TO 0 PSIG.

_.1.

0. I 0.2 0.3 o ... 0.5 o.e 0.7 o.a 0.9


Pressure in blowdown suppression tank in a transverse plane, 263 in. from B-end reference (PE-SV-22 and -23).

• P8TTDII8 P£-SV-058 D PeT~ P£-SV-017

_..J ,.... ,..

~

I --, J NOTE: INITIA,L SLOWDOWN SUPPRESSION

T TANK PRESSURE ADJUSTED TO 0 PSIG.

iJ I I I O. I 0.2 0.3 o ... o.s o.e 0.7 0.8 o.sa


Pressure in blowdown suppression tank in a transverse plane, 263 in. from B-end reference (PE-SV-17 and -59).

112

(.!' -V)

~ .... "' ~ V) V) .... "' 0..

30.

-... --

o. -o. 1 o.o

Fig. 36

2100.

2000.

1800.

1800.

1'700.

-0.1 o.o

Fig. 37

• P8fnDOIO P£-SV-003 D P8ff0081 P£-SV-OOit a NJTDaaa P£-sv-oel "' Nff0120 PE•SV-080 • PWTTUII-- ~~ :1e

~ I....~

II - ....,_. ,. r 1\ .....

' ~ H4 lJ

'j • NOTE: INITIAL BLOWDOWN SUPPRESSiON

l ., TANK PRESSURE ADJUSTED TO 0 PSIG. --0. I 0.2 0.3 o ... o.e 0.7 o.a

TIME AFTE_R RUPTURE (SEC)

Pressure in blowdown suppression tank in a transverse plane, 28.5 in. from B-end reference (PE-SV-3, -4,· -16, -60, and -61).

o.e

r : ··: : 'P8TTOI08 P£-SV-030

""

I ... .. --

I l J• \1\.1\ - .

r I'"' -I

'

0.1 o.a o.3 o ... 0.5 o.e 0.7


Pressure in blowdown suppression tank header snubber (end)(PE-SV-30).

113

o.a o.e

"" a: :::>

'·" "' "" a:· n

~ .... V>

~

"" a: :::> V> VI ..... "" 0..

2500. POTTDIIO PE-SY-OJI

~

---2250.

2000. . 1 ,

\ .. 1\t\J -v-

1 v

\

1750.

-o, a o.o o.a 0.2 o.~ · Q.~ o.e o.e o.7 o~e o.e TIME AFTER RUPTURE (SEC)

Fig. 38

I !SO.

100.

,o .

o. .....

-so .

Pressure in blowdown suppression tank header snubber (end) (rE-SV-31).

POTTDIIJ PE-SY-a-5 ---·- -·-·

'

-·---· -

v .. . ... ~ ... "\ .""" \ I ~ ~ ~ "W """ • n I V'

\ll m v rJiTT

. -0.1 o.o 0.1 0.2 o.J O-~ o.s o.e o.7 o.e o.e TIME AFTER RUPTURE (SEC)

Fig. 39 Pressure in blowdown suppression tank header snubber (bend) (PE-SV-45).

114

<!>· -VI 0..

.... "" ::> VI

~ "" 0..

~ -"' 0..

.... "". ::>

"' "' .... "" 0..

'750. POTTDIIIt P£-SV-Oite . - .. -·

500.

250.

o. J I I" ~ -'\..I' -

-no. -o. 1 o.o 0. I 0.2 0.3 o ... 0.5 o.e 0.7 0.8 0.1


Fig. 40 Pressure in blowdown suppression tank header snubber (bend) (PE-SV-46).

30.

20.

10.

o. -o. 1

Fig. 41

POTTDII5 PE-SV-051t

' .-

A / ---r---1\ / -

'

J NOTE: INITIAL BLOWDOWN SUPPRESSION TANK PRESSURE ADJUSTED TO

I 0 PSIG.

J

o.o 0. I 0.2 0.3 o ... 0.!5 o.e 0.'7 o.a 0.9


Pressure in blowdown vacuum relief system rupture disc ~tandpipe (PE-SV-54).

115

<.!> ..... "' Q.

.... "" ~ "' "' ...... 0! "-

.: NTtDIU -PE~SV-070

~ 1\ 7 ~

50. 7 " l I \. ..

T '\.. I"\_

--~ - .... ---~

25. -·--

r;r .....

o. -o. • o.o o.a 0.2 o.:s o... ·o.s o.e - o.7 o.a o.a

Fig. 42


Pressure in bellows between broken loop and blowdown suppression tank header (PE-SV-70).

116

(

2. TEST L1-3 MEASURED PARAMETERS -

MEDIUM - TERM PLOTS (-10 TO 70 SECONDS)


117

.., : 1-"-..... ::E .., _, >-1--Vl ., ..... 0 _, < 0

"' 0 ::z:: '-'

.., i<

t-"-..... :E .. _,

>-1-

Vl a 0 _, < 0 a: 0 ::z:: u

!50.0

ltO.O

"" ~~lt • DEBFO'OOI DE-BL-OOIA

-a DEBF'D002 DE-BL-0018 • DEBFD003 DE-BL-OOIC

-30.0

20.0

10.0

o.o

f\ ;: .. Ia.. - ,. --- -

-ao.o o.o 10.0 20.0 :so.o ltO.O !50.0 10.0 70.0

Tli~E AFTER RUPTURE (SEC)

Fig. 43 Density in broken loop cold leg, chordal density (DE~BL-lA, -lB, and -lC) (filtered to 4Hz).

!50.0 • DEIFOOOit DE-BL-002A

'tO.O

.A - • a DEBF000!5 DE-BL-0028 ~ JJ A DEBFOOOI DE-BL-002C

30.0 \

20.0 -~ ~ ...

~ l Vi - .. 10.0 ~ _a

~ A'l , .L.. ,.. ._ "¥ -o.o

J

-10.0 o.o 10.0 20.0 30.0 ltO.O !50.0 ao.o 70.0


Fig. 44 Density in broken loop hot leg, chordal density (DE-BL-2A, -2B, and -2C} (filtered to 4Hz).

118

"" : 1-LL ...... "" = >-~ VI :z ...., 0

...., <.!) c(

"" ...., > c(

"" .. .. 1-LL ...... ::E

"" = >-1-

~· ...., 0

-' c( 0 'o< 0 X u

"o.o

... o.o

~ • OOBCOOOI DE-IL-001 ._.

~ a OOBCD002 OE-IL-002

~ 411

, ~

1\ It!

30.0 ... \

20.0 ·\ ~ .

~1, k.

10.0

. ·l ~ . ~ A ~ ~

o.o

-10.0 o.o 10.0 20.0 30.0 ltO.O 150.0 eo.o 70.0


Fig. 45 Density in broken loop, average fluid densities (DE-BL-1 and -2) (filtered to 4Hz) .

. 50 .o

ltO.O

--$t • OEPF0008 OE-PC-0018 a OEPFD008 OE-PC-OOIC r\

l

' 30.0

20.0

10.0 ... ,&, '

r\Jfi o.o "

.a.. •• 1. r- .... r--

-10.0 o.o 10.0 20.0 30.0 ltO.O !50.0 eo.o 70.0


Fig. 46 Density in intact loop cold leg, chordal density (DE-PC-lB and -lC) (filtered to 4Hz).

. 119

..,

... ... ...... .... ....... :E co --'

>-t: "' :z .... • --' < 0

"" 0 ::r: u

M ... ... ...... .... ....... ::E co --'

>-!::::; •n -.... 0

.....i < 0

"" 0 ::r: u

50.0 ' . . ...ll • OEPFOOIO OE-PC-002A ...... ~ a DEPFOOII DE-PC-0028

'+0.0 6 OEPFOOI2 DE-PC-002C

30.0

ao.o I ~ I .I ·•\

10.0 ~

.~. ~ .... .J If\ - J ~ ~ L -- ~ .. -o.o

-lo.o o.o ao.o 20.0 30.0 '+0.0 50.0 eo.o 70.0

TTMf. AFTER RUPTURE (SEC)

Fig. 47 Density in intact loop hot leg, chordal density (DE-PC-2A. -26, and -2C:) (filtered to 4Hz).

50.0 _....... • DEPFOOI3 DE-PC-003A

'+0.0

-.., ,.,., .. l a OEPFOOI'+ DE-PC-0038 1\ 6 OEPFOOI5 DE-PC-OOSC

~ ,

30.0

20.0

-

10.0 ... ~ ~ ....

~ o.o ...

-10.0 o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o 70.0


Fig. 48 Density in intact loop at steam ge.nerator outlet, chordal density (DE-PC-3A, -3B, and -3C) (filtered to 4 Hz). ·

120

;:;; i<

"' 1-... ..... a> :::! >-~ V'> :z .... c:> .... <..!> ·ce

"" ... > <

~

u .... V'>

~ ... ~

~ -u 0 .... .... >

50.0 I.. •• OOPCOOIO OE-PC-002

ltO.O

- lrlla. a OOPCOOI3 OE-PC-003

1\ <

'1

30.0

20.0

10.0 \. ~ ... J ~

o.o llr ~ I

.., ~ ~ ~

-10.0

o.o 10.0 20.0 30.0 ltO.O !50.0 eo.o 70.0 TIME AFTER RUPTURE (SEC)

Fig. 49 Density in intact loop, average fluid densities (DE-PC-2 and -3) (filtered to 4 Hz).

150.0 VE8K01t51 .FE-BL-001

__.JI ~V\r ~ ~to.. _}_ )j V\

100.0 If I A'/ \A

Ill l

111 50.0 J

IAAI

""""" ' I / ,..,.

--'-A o.o

i

NOTE: REFER TO SECTION III IN TEXT ON TURBINE CALIBRATIONS. --

-50.0

-10. o. I 0. 20. 30. '+0. 50. 60. 70. TIME AFTER RUPTURE (SEC)

Fig. 50 Average fluid velocity in broken loop cold leq at OTT flange (FE-BL-1) (filtered to 4Hz).

121

~

U· ... VI -1-.... r.:: -u 9 ... >

u ... VI -1-....

!: u 0 -I ... >

30.0

20.0

IQ.Q

o.o -10.

NOTE:

·-

I

J

Fig. 51

150.0 I

I i

100.0 I I

__;__

' 1

50.0 '

REFER TO SECTION III IN aJ lft"'- V£81(0't52 FE -BL -002 TEXT ON TURBINE CALIBRATIONS.

h vv r• \ j

M IIU ff ----11

i

! ! I I

!

I I I I --I ,~ .. - I' ~~ .. I f I

--· or ft._. - '\. I \

I \ \ "~ ! M...J ~

o. I 0. 20. 30. '+0. 50. 60. 70.


Average fluid velocity in broken loop hot leg at OTT flange (FE-BL-2) (filtered to 4Hz).

• ·vEBK0'+51 FE-BL-001 0 VEBK0'+52 FE-BL-:002

I ,.f/lJ¥\r ~~ II J ~ V\

'' i ~ .l. i ' .,.II

"' .. : AT ~ l i • I

i I nn I -' i J i i fAA/ ~--~---·- f---~- ---- r-v i I 1-a,.,

i ' / v- ~~v -- "" t\ f1"-"'-~ i J. "" \ ' I

0.0 i 7 t:l'll ~ '-..-I

r- -I ! i

! ! i ' ' I NOTE: REFER TO SECTION III IN

~-! ' TEXT ON TURBINE CALIBRATIONS.

-50.0 '

-10. 0. 10. 20. 30. '+0. 50. 60. TIME AFTER RUPTURE (SEC)

Fig. 52 Average fluid velocity in broken loop cold and hot legs at OTT flanges (FE-BL-1 and -2) (filtered to 4 Hz).

122

70.

~

u .... VI ...... ..... ... ~ -u 0 ...J .... >

u .... VI ...... ..... ... ~

~ -u 0 ...J .... >

ao.o

8.0

~ 6.0

4.0

2.0

o.o -ao.o

~ ~

o.o

---

I I Y£CTD't53 J:E-CS-00 I I I I I

NOTE: REFER TO SECTION III IN TEXT ON TURBINE CALIBRATIONS.

, I

·- ~" .... -.... ~

~ "L ...... \ \. t..N "- u 10.0 20.0 30.0 ltO.O 50.0 eo.o 70.0


Fig. 53 Average fluid velocity in reactor _vessel core simulator instrument stalk (FE-CS-1) (filtered to 4 Hz).

30.

20. ~~ I 0.

o. -10. o.

I tvEP!O .. s .. FE·Pc·ooa I I I I I I


M n ~ J .. ~ r ~M~

, "'

It

' Jt. \.a {'~ ..

\ ~ ~k '~ " 10. 20. 30. ItO. 50. 60. 70.


Fig. 54 Average fluid velocity in intact loop cold leg at OTT flange (FE~PC-1) (filtered to 4Hz).

123

u ..... VI ....... 1-u.

t: ~ ..J ..... >

u ..... VI ....... 1-~ >-t:; u 0 ..J ..... >

30.0

20.0 ~-

10.0

o.o -HJ.O

..

- 4 ,.,

o.o

\Ill l '4~ 1\ iO.O

YEP!D~55 ~£-PC-002 J I I T I T


~ l \ 1\

2(·.0 30.0 .. o.o ,.. ~o.o ao.o 70.0

11Ml AHI::R RUPTURE (SEC)

Fig. 55 Average fluid velocity in intact loop hot leg at DTT flange (FE-PC-2) (filtered to 4Hz).

30.0

20.0

11 1 I

10.0

o.o -10.0

I

ll Jll

\ \

o.o 10.0

iVEPfD~5B ~E.:.PC·003 I I I I I I


lJ II'

\ "-20.0 30.0 ltO.O · !50.0 eo.o 70.0


Fig. 56 Average fluid velocity in intact loop steam generator outlet at DTT flange (FE-PC-3) (filtered to 4Hz).

124

u ...... "' ...... 1-... > !: .., 0 ....I ...... >

u ...... VI ...... 1-... ~

> 1--u 0 ....I ...... >

30.

20.

I 0.

o. -10.

~~ ~

"'

o.

ftl. ·~M -~ ,, , ... ' -~ )\

10.

• VEPT~~ FE:PC-001 o VEPT~55 FE-PC-002

A1VEPrD'ter FEIPC-r03

r I r I I NOTE: REFER TO SECTION III IN

TEXT ON TURBINE CALIBRATIONS.

•• ..

.~ '1 ~

I , ~ ·~ • .... \ .. ,,~

~~. i ,. --~ •

I \J l.: ~ . ... ~ 1 ~ -~ 20. 30. .. o. 50. 60 . 70.

liME AFTER RUPTURE (SEC)

Fig. 57 Average ·fluid velocity iti intact loop cold leg, hot leg, and steam generator outlet at DTT flanges (FE-PC-1, -2, and -3) (filtered to 4Hz).

12.5 ~~~~ ~57 FE ) ST ·.00 I

I I I I I

10.0 I ·-. NOTE: REFER TO SECTION III IN .. · TEXT ON TURBINE CALIBRATIONS.

7.5

5.0

2.5 A ru 1..1! M I . \ r.1 I

\ I 1m 1\.J\

o.o " r,. '-N " lJU\. IP\ " ... ""

-2.5

-10.0 o.o 10.0 20.0 30.0 .. o.o 50.0 60.0


Fig. 58 Average fluid velocity in reactor vessel downcomer stalk 1, 47.1 in. above reactor vessel bottom (FE-lST-1) (filtered to 4Hz).

125

70.0

u .... VI ....... 1-.... ~ -u 0 -' ..... >

~

u ..... VI ....... 1-.... ~

r-IJ 0 -' ..... >

12.!5 r-~---y--~--,---~--r-~~~--~--~--~--.---~~~-.~~ t---t---t--+--t---f--+--+--+--I----J1- vESTOit!58 F"E-2ST -00 fL I I I I • I I

t---t--+--+-+-+--...._---1--f--+ NOTE: REFER TO SECTION III IN ~ TEXT ON TURBINE CALIBRATIONS. ~

10.0 IL • -!!. ... 7.!5

!5.0

,, 2.5 .A1 tr

-, 1 na IIW ,11

I I tllllr I \ • Ill WlfV'I l.& 1\ 1\

-2.!5 ~~--_.--~--~------._--~_. __ _. ______ ~ __ ._ __ ~--~~---'

-10.0

Fig. 59

o.o 10.0 20.0 30.0 ~+o.o 50.0 eo.o TIME AFTER RUPTURE (SEC)

Average fluid velocity in reactor vessel downcomer stalk 2, 47.1 in. above reactor vessel bottom (FE-2ST-l) (filtered to 4Hz).

70.0

12.5 • VEOT F"E-.IST-001

a YEST~It!58 1 F"E-~ST-~OI 10.0 I

NOTE: REFER TO SECTION III IN f'ltff TEXT ON TURBINE CALIBRATIONS.

7.5

5.0

.... , 2.5 .11 " II .II , ... 1

'Mil- ll 11'1, JllW A • II I , .. , Ill! .A IV\

'- ~ I~ '-A. 'U...'\1 ... -o.o

-2.5

-10. o. 10. 20. 30. '+0. 50. eo. TIME AFTER RUPTURE (SEC)

Fig. 60 Average fluid velocity in reactor vessel downcomer _stalks 1 and 2, 47.1 in. above reactor vessel bottom (FE-lST-1 and FE-2ST-l) (filtered to 4 H~).

126

70.

150.0 I l l l FVFT0'+61 FT-Pl20.:...o85": I ! I ! i

·--I j I

- 1--·

I I ! I l Pt( I --· : ! _! ! / ! 100.0 I ! I :E ! J a. -~ !::. I I v

UJ ---:-- -+--- ·-~

~ i ; I I i --~

3 0 i i -' r----:· .... I I

50.0

1---·-,.- - -· i I ' ! ! i __ .!" ____

-···· !-. -·· .. ....... i-- -· I '-i I

---~ ., I ! i l o.o

. -I 0. o . 10. 20. 30. '+0. 50. 60. 70.

TIME AFTER RUPTURE (SEC) I Fig. 61 Flow rate in ECCS LPIS pump A discharge (FT-Pl20-85).

30.00 FYFT0087 FT-P

1

128-10'+

20.00 1\.

:E a. e UJ t- 10.00 ~ 3 0 -' ....

o.oo

NOTE: INITIAL OVERSHOOT IS DUE TO AUTOMATIC SPEED CONTROL.

-10.00

-10. o. 10. 20. 30. '+0. 50. 60. 70. TIME AFTER RUPTURE (SEC)

Fig. 62 . Flow rate in ECCS HPIS pump A discharge (FT-Pl28-104).

127

~

"' :<: ..... iii -' ~. ..., ..... ~ 3: 0 -' ....

3.0 ..

2.0

I .0

o.o -ao.

Fig. 63

• F'MF'T(*i!fl F"T~PIIG-a7-l -~-F'..-;aoo~o F"T-PllSI-27-3

. I I -.- .. I I I I I

NOTE: FLOW RATE UNCORRECTED FOR _

IW" DENSITY CHANGES.

-·--~ ...... ., -

"'

~ - ''fl!l' - - - ....

o. I 0. 20. 30. '+0. !50. eo. 70.

riME AFTER RUPTURE (SEC)

Flow rate in intact loop hot leg venturi (FT-Pl39-27-l and -27-3).

128

N 1.0

z .... _. ... > ... _. 0 .... ::> ::? _.

LIQUID LEVEL P~OB~ Hl BLmiDOWN DATA TEST

-zoo~~t-·· •xxx xxxxx------------_..,._ .,.._ --,---lila. 4 oxxxxxx 176.4 •xxxxxxxxxxxxxx

-164.4 •xxxxxxxx··-··x-· -------''------~-

152.4 •xxxxxxx xxxxx 140.4 •xxxxxxxx x

--1-2 8;; ,, .. • X XXXX XXXX XX -x· 116.4 •xxxxxxxxxxx l~4.4 ~XXX~AXXXXXX XXX

--··92;. 4··-• X XXXX XX-···· x··-···--··------------·---80.4 •xxxxxxxxxxxxx x 68.4 •xxxxxx

lt-3 09/10/76

----'-·----

-------·--·-----------

--3Z··tv·-* x :o:xx xxxx xxxxxxxx x-· -x- -------- ----·-----------xxxxxxx-x-xxxxxxx-xxxxxxx xx----28.4 ~xxxxxxxxxxxxxxxxxxxxx xxxx xxxxxxxxxxxxxxxxxxxxxxxxxxxxxx 24.4 *XXXXXXXXXXXXXXXXXXX X X XX X X X X XX X XXXXXXXXXXXXXXXXXXXXXXXXlXXXXXXXXXXX

--iO·• 4--• X XX XX XXXY. XXX XXX XX XXX XXX-X·--XX---X-------XX -X-·-·X-·-· XXX XX XXXX XX XX XXX XX:o; XXXXXXXX XXX X X )(XXX.li.X X XXXXXXX xx--16.4 •xxxxxxxxxxxxxxxxxxxx xxxxxx x x x xx xxxxxxx- xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx~xxxxxxxxxxx 12.4 •xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx~xxxxxxxx~xxxxxxxxxxxxxxxxxxxxxxxxxxxxxx

--a·.-4-•xxxx-xxxxx·x-x·xxxxx-x-xxxxx-x-xx·xxx-xx-x-x-x-x-x-xx-xxx·xxxxxxxx-xxxxxxxxxxx-xx-xx-x-xu.x·xx·xx·xxx-xx-)(·xxx-xxx-,cx-x·x·xxxxx--••---------•---------•---------•---------•---------*---------•---------~----~----$---------•---------• 0.0 10.0 20.0 30.0 40.0 50.0 60.0 7J.O 80.0 90.0 100.0

Fig. 64


Liquid level in reactor vessel downcomer instrument stalk 1, bubble plot (LE-lST-1 and -2).

...... ..... > ..... ...... c ..... => CT ..... ......

LIQUID LEVEL ,PROBE #2 BLO~DOWN DATA TEST L1~3 .09/10/76 ------------·-------------- ---------------- -----------------------------zoo~-4--.,xxxxxxx ···- _!._. _____________ _

176.4 ~xxxxxxxx xxx x 164.4 •xxxxxxx x

--15·2·.4- •xxxxxxx·· ·--xx---x 140.4 '~'XXXXXX

128.4 •xxxxxxxxxxxx x -·He,.4-•XXXXXX x·x··-···-------

104.4 *XXXXXXXXXXXXX 92.4 •xxxxxxxxx

--tw.4 •xxxxxxxxxxxxxx·----· bd.4 *XXXXXXX

J ----------·-·---· ------

------·- ·-----

32.4 *XXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXX -.z 8. 4 .,.. X XX XX XX XX XX XX XX X X------------------------------·-·----·-·---------·---.. - . . X XX XXX X XX X XX: X X X X X X XX X XXX X XXX X X

24.4 •xxxxxxxxxxxxxxxxx xx x xx xx x x xxxxxxxxxxx~xxxxxxx:xxxxxxxxxxxxxxxxxx 2G.4 •xxxxxxxxxxxxxxxxxxxx x x xx x x x x xxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxxx

---!. t.;; 4-• X XX XX XXXX >:X XXX XXX XXXX.<.<X:XXXXXXX-XXX XXXXX·xx-XX XX·XXX·XXX X)iXXXX >J: XX XX XXX XX XX X X XXX.>:XX XXX XXX X XXX X XXX XXX XXXX XX ----·· 12.4 *XXXXXXXXXXXXXXXXXX XXXXXXXXX X X X XX XXXX XXXXXXX~XXXXX~XXXXXXXXXXXXXXXX)XXXXXXXXXXXXXXXXXXXXXXXXX

8.4 *XXXXXXXXXXXXXXXXXXXXX~XXXXXXXXXXXXXXXXXXXXXXXXXX~XXX~XXXX>>XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX ------·· ··---------· ---------· ----------· -·-·----------··--·;,.,·--------··-- -------·------· -·-·----·-·--· ----------·-·- -·-----·.-.·-· ------·----. -·-

o.o 10.0

Fig. 65

20-Q 30.0 40.0 so.c 60.0 70.0


liquid. level in reactor vessel dm•mcomer instrument stalk~' bubble plot (LE-2ST-l and -2).

90.0 1 oo.o

:z --' .... :> .... -' 0 ~· ::> e -'

:z -... .... :> w -' 0 -::> e -'

7U.O

65.0

60.0

55.0

50.0

"+5.0

"+0.0

-10.0

Fig. 66

!50.

.. o.

30.

20.

10.

o. -10.0

Fig. 67

'• UtFT0~66 LT-Pi38-033 0 UtFT0039 LT-PI38-058

1

I; 1. ,, ..

• II , ...

...

NOTE: DATA DISPLAY INSTRUMENT RINGING BETWEEN T

0 AND

T0

+ 2.5 SEC. I I

o.o 10.0 20.0 30.0 "+0.0 50.0 60.0 70.0


Liquid level in blowdown suppression tank (LT-Pl38-33 and -58).

L~r~e7 LT-Pi3e-ooe

\ NOTE: DATA ARE QUALIFIED UNTIL \ "' T0 + 13 SEC. \ \ \ \ \ \

\ \ \ \ \ \

'-""""'

o.o 10.0 20.0 30.0 ltO.O !50.0 60.0 70.0


Liquid level in pressurizer, southeast side (LT-Pl39-6).

131

:z

_, w > w d c -"' 0 -_,

-:z -_, w >

"" _, o· ::::> 0 -_,

50.

'+0.

30.

.:o.

I 0.

o. -10.0

Fig. 68

!50.

'+0.

30.

20.

I 0.

0.

-I 0.

LHrTOO'+O LT-P139-007

\ NOTE: DATA ARE QUALIFIED UNTIL

\ "' T0 + 13 SEC. -

I

\ -____ ,_. ~·~

\ ..• ··--- -- ·-·····-··

\ 'N ~ ""\.. A

\ ...

I \ 7 ~ f7

o.o 10.0 2o.o 3o.o '+O.o ~o.o 6o.o 7o.o

liME AH~K RUPTURE !SEt)

Liquid level in pressurizer, southwest side (LT-Pl39-7).

I

LT-Pi3sa-ooe LPW8001tl

-··

\ NOTE: DATA ARE QUALIFIED UNTIL

\ "' T0 + 13 SEC.

\ \

~ J

\ \

"' o. I 0. 20. 30. '+0. 50. 60. 70.


Fig. 69 Liquid level in pressurizer, north side (LT-Pl39-8).

132

!!1.

'+·.

3.

2.

z I

..J .... > o . .... ....J T 0 ... :::> -I 0' ... ....J

-2.

_.3.

-'+.

-5.

-10.0

Fig. 70

7!000.

"' !0000. .. .. u .... VI

I .... ... ...... ::E

"" = 2!000. X :::> ....J ... ::E :::> .... z .... 25 ::E o.

-nooo. -10.

Fig. 71

'·-,,.; ..... A 0

~-PO~'+ ll I' I 1

NOTE: DATA DISPLAY INSTRUMENT RINGING FROM T0 TD T0 + 5 SEC.

.... ~ .... ~ .... - - .....

---

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0 TIME AFTER RUPTURE !SEC)

Liquid level in steam generator secondary coolant system (LT-P4-8B).

ttF'BF'D!22 te-IL-001 I I I I I

NOTE: DATA ARE TEMPERATURE - SENSITIVE AFTER~ T0 +

50 SEC. REFER TO SECTION III IN TEXT,ON DRAG DISC CALIBRATIONS.

1\aa l IN"W IV\1 la

I\.. A .. ""ll.A. y '\M \r\. ..

"""' ---o. 10. 20. 30. ItO. !0. eo. 70.


Average momentum flux in broken loop cold leg at OTT flange (ME-BL-1) (filtered to 4Hz).

133

-N

"' "' u ..... VI

I 1-"-...... ::E cc ....0

>< :::> ....0 "-

~ 1-.. ...... ~ ::E

N .. "' u ...... VI

I 1-"-...... ::E cc ....0

;...: :::>

Li.!

~ 1-:z .... ~ ::E

JOOO.

2000. -~

1000· ·.

o. ...

-aooo. -ao.

Fig. 72

'75000.

50000 .

25000.

o.

-nooo. -10.

I I tFIF'DRJ IC-IL-002 ... ~ I I I I I

rt'1 NOTE: REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS.

J \ I~ ~ ~ I "' \.N \.

l ,.AJ""

ll\ 1\. l " \I \..r v \. ~

" ~ - r\:

""\: ~-·

~ ---

-·-- - -· .. ~ ......... , .... , ···"""•··-

o. 10. 20. 30. 'tO. eo. eo. '70. TIME AFTER RUPTURE (SEC)

~~er~ge momentum flux in broken loop hot leg at DTT flange (ME-BL-2) (filtered to 4 Hz).

• tFIF'DR2 IC-IL-001 a tFIF'DRJ IC-IL -002 1----.- r- I I

NOTE: REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS.

- lt.aa

b I~ ~ Ia

~· 'Wlll -- ~

Yl "' .. """ ~--~~ """

o. 10. 20. 30. ItO. 50. eo. '70. TIME AFTER RUPTURE (SEC)

Fig. 73 Average momentum flux in broken loop cold and hot legs at DTT flanges (ME-BL-1 and -2) (filtered to 4 Hz).

134

750.

- 500. "' ... « (..) ..... "' I ...... ... -. :E a> ...J

>< 250. :::> ...J ... ~ ...... .:z: ..... ! :E o .

I

-· -250.

-10.

. Fig. 74

ltOOOO.

30000.

"' ... ... (..) ..... "' I ...... ...

20000 . ...... :E .., = . >< 3 ... ~ 10000 . ...... :z: ..... ! ·x

o. \

-10000.

-10.0

Fig. 7 5

I MFC ~0524 ME:-CS :.90 I I I I I I I

NOTE: REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS.

r---A -J \

- ~·

I& --

..... ·- . . r---

.LJ. .... 11' ..., ..,

\. .,...

• . -

' o. 10. 20. 30. 40. 50. 60. 70.


Average momentum flux in reactor vessel core simulator stalk (ME-CS-1) (filtered to 4Hz).

~F"~.Tp.525 1 I'IE-!. . .l i ·op~-I I I.

NOTE: DATA ARE TEMPERATURE SENSITIVE AFTER T0 + 22 SEC. REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS .

•

•• IIIII -.

'

o.o 10.0 20.0 30.0 40.0 50.0 60.0 ·70.0 TIME AFTER RUPTURE (SEC)

Average· momentum flux in intact loop cold leg at OTT flange (ME-PC-1) (filtered to 4Hz).

135

lfOOOO.

30000. N .. .. u w Vl

I 1-LL. 20000 . ...... E

"' -'

>< "' -' I.A~ .. E 10000. "' ... :z ..... ~ E

o.

-10000.

-10.0

Fig. 76

ltOOOO.

30000. N .. .. u w Vl

I 1-LL. 20000 . ...... E

"" -'

>< "' -' lL

~ IOOQO. :z w il5

·E

o.

-10000.

-10.0

Fig. 77

-J-"!~PJD_'O't~ 11E,;-PC NOTE: DATA ARE TEMPERATURE

SENSITIVE AFTER T0 + 22 SEC. REFER TO SECTION I II IN TEXT ON . DRAG DISC CALIBR~TIONS.

I

............ , ... . --~·-·· f--·· • ......... ···"·-··- ......... - -

0 .o. 10.0 20.0 30.0 lfO.O 50.0 60.0 70.0


Average momentum tlux in intact loop steam generator outlet at OTT flange (ME-PC-3) (filtered to 4 Hz).

• 11F-PToS2S 11E-PC-OO I

D 11F~JQ~~~ 11E;PC-p0~-·

NOTE: DATA ARE TEMPERATURE • SCNSITIVE AFTER T0 + . 22 SEC. REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS.

.. . ..

~ r- ., I

J , ... ~ ---

o.o 10.0 20.0 30.0 lfO.O 50.0 60.0 70.0


Average momentum flux in intact loop cold leg and steam generator outlet at OTT flanges (ME-PC-1 and -3) (filtered to 4 Hz).

136

N • • u ..... Vl

I ... .... ..... ::E ul

.::! >< ~ ~ .... ::E ~ ... z ..... ::E 0 E

N' • • u ..... Vl

I

t;: ..... E

"" ~

5000. 1 L L~.Pi051t~ HE ~ .1 !?. .. :;_OJU_

• I

REFER T~ SECT1ION I ;I IN +EXT NOTE:

DRAG DISC CALIBRATIONS.

I ' 2500.

1 _u '

o . ~ 1Ull.. ...... La... ... ....J I rwu rrr " .....

-2500.

-10.0 o.o 10.0 ~o.o · 30.o ltO.O 50.0 60.0 TIME AFTER RUPTURE (SEC)

Fig. 78 Average momentum flux in reactor vessel downcomer stalk 1, 44.5 in. above reactor vessel bottom (ME-lST-1) (filtered to 4Hz).

70.0

5000 .

• 1 ~t_st_p_s.~~ HE;2sr)~9..!

I I I I I I

NOTE: REFER TO SECTION III IN TEXT ' ON DRAG DISC-CALIBRATIONS.

' 2500.

I

•• w·~ .lk .~L. ...L

0. ....... ..... ...U.a. ll. ~ ~~~ -.~ r.

WJII II i'

'

-2500.

-10.0 o.o 10.0. 20.0 30.0 ltO.O 50.0 60.0 TIME AFTER RUPTURE (SEC)

Fig~ 79 Average momentum flux in reactor vessel downcomer stalk 2, 44.5 in. above reactor vessel bottom (ME-2ST-l) (filtered to 4Hz).

137

70.0

Q ~

en ~ LLI

"" ::::> en en LLI

"" 0..

...J < .... ~-· :z LLI

ffi .._ ::= Q

0 -en ~ LLI

"" ::::> en en LLI

"" 0..

' < ... 1-:z .., "" LLI .._ ::= Q

5.0

2.5

o.o ·-·-

-2.5

-10.0

Fig. 80

300.

200.

100.

POBT0052 PDE-BL-001

I--

,1~1 II

I .... , ~ ~~. ,T

r''""" •• "11 ••• 'ttl ~I I .. 11 I

jL

............ ..... ' ... ···-·

o.o 10.0 20.0 30.0 ~0.0 50.0 60.0 70.0 TIME AFTER RUPTURE (SECl

Differential pressure in broken loop hot leg across 14-to-5-in. contraction (PdE-BL-1) (filtered to 4Hz).

POBT0053 POE-BL-002

-"" -----~---~-,...4.- -~,..,...._ ,-~---~--1---+--~1---+--~

~-+-~~~-+-4-~1---+-4-~~-~-~~-

0.

-100. ~_.--~--~_.--~~~_.--~--~_.--~--~_.--~--~~

-10.0

Fig. 81

o.o 10.0 20.0 30.0 ~o.o 50.0 60.0

TIME AFTER RUPTURE (SECl

Differential pressure in broken loop cold leg across 14-to-5-in. contraction (PdE-BL-2) (filtered to 4 Hz).

138

70.0

c -"' ... ..... "' :::> V)

"' ..... "' 0..

...J.

~ 1-z ..... "' ..... ... ~ c

c -"' 0..

..... "' :::>

"' "' ..... "' 0..

...J s .... z ..... "' ..... ... ~ c

500.

• 1Poelco5~ PO~-BL~003

o POBT005'+ POE-BL-00'+

'+00.

300.

200.

tOO.

o. -10.0

""*-

IJ r

""'

o.o

\ ~ ...... .

' ·- -·-

~ ~ ~~~ ~~

~ l \... ~

~

~ II..

~ ~

, ... 10.0 20.0 30.0 '+0.0 !50.0 80.0


Fig. 82 Differential pressure in broken loop across break planes (PdE-BL-3 and -4).

'+00.

70.0

POBT00!56 POE-BL-005

350. ~

...,.._ ~

\. 300.

\ 250. \

\ -200. \.

\

' 150. i I i\ -~

100. l \. ' ~ !..

50. i " ' I .......... I

0.

-10.0 o.o 10.0 20.0 30.0 '+0.0 50,0 80.0


Fig. 83 Differential pressure in broken loop hot leg across pump simulator (PdE-BL-5).

139

70.0

0 .... VI Q.

.... "" ::> VI VI .... "" Q.

...J

:3 .... :z .... "" .... ... !!; Cl

c .... ·VI Q.

.... "" ::> VI VI .... "" ..

I

:!; .... :z .... .,. .... ... !!; 0

30.0 POBT~057 POE-BL ·006

I

20.0

.... 10.0 """"'"

''I ... ... "" "'" ' ~ ~ ....... -·········

o.o .........

-10.0

-10.0 o.o 10.0 i:!O.O 30.0 40.0 !50.0 eo.o 70.0 'I'IME 1\HiR RUPTURE (&EC)

Fig. 84 Differential pressure in broken loop hot leg across steam generator simulator outlet flange (PdE-BL-6).

'+0.0

30.0

20.0

10.0

o.o

-10.0

-10.0

Fig. 85

.';"Uti I IU::)tl r-uc.:·DL ·~07 ... •• ..

• • "'. I . I

r

o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o TIME AFTER RUPTURE (SEC)

Differential pressure in broken loop hot leg across the steam generator simulator (PdE-BL-7).

140

70.0

/

-o -'VI

~ .... 0:: :::> VI

~· .... 0:: Q..

...J :!; 1-::z .... 0:: .... .... := c

c -VI Q..

.... 0:: :::> VI VI .... 0:: Q..

...J :!; 1-:z .... 0:: .... .... := c

5.0 P08T0059 POE-BL-008

2.5 ·-

1:--- f-

~-

~ L...

o.o ~ nM Jtlw- rrtvt ~ 'rtJV ~ ·- lA .A

~ --~·· -···-···- -·-- .. ~ ..... - ... ·- . ·-·~ . ..

-2.5

-10.0 o.o 10.0 20.0 30.0 '+0.0 . 50.0 60.0 TIME AFTER RUPTURE (SEC)

Fig. 86 Differential pressure in broken loop hot leg across steam generator simulator inlet flange (PdE-BL-8) (filtered to 4Hz).

10.0

......

70.0

POCT0060 POE-CS-001

~

5.0

o.o

-5.0

-10.0

Fig. 87

. M. ...

-

l

'"' ~ ., ....-

' ~

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 TIME AFTER RUPTURE (SEC)

Differential pressure in reactor vessel core simulator to downcomer instrument stalk 2, 24.5 in. from reactor vessel bottom (PdE-CS-1) (filtered to 4Hz).

141

I

70.0

Q ~

VI 0..

w

"" ~ VI VI w

"" 0..

..... ::5 1-:z w

"" w .... ~ Q

Q ..... VI 0..

w ... ~ VI VI w "" C!.

~ ... :z w .. w .... != Q

20.0

25.0

~ POPT0081 POE-PC-001

15.0

10.0

5.0

o.o

-~.o

-10.0

Fig. 88

115.0

.. .. ·-10.0

'---

5.0

o.o

I -5.0

-10.0

Fig. 89

, I

~ ~

'-... ...._ ... !'

o.o 10.0 20.0 30.0 ltO.o 50.0 60.0 TIM! A~T!~ RUPTUR! (5!C)

Differential pressure in intact loop cold leg across pr1mary coolant pumps 1 and 2 (Pdc-P~-1).

l 70.0

POPT0062 PO~PC-002 I I I I I

NOTE: DATA ARE QUALIFIED FOR INITIAL CONDITIONS ONLY;

lPYtl ~ONTAIN UNINTERPRETED LONG-TERM OFFSET.

L !1

... ·-

~

' iLa. .• ... ,.... , ... .,. , .... .. &1,

~-.... ..... II"

o.o 10.0 20.0 30.0 1+0.0 50.0 60.0 70.0


Differential pressure in intact loop across the steam generator (PdE-PC-2).

142

5.0

c .... VI 0.. ...... 2.!5 ... a: ::::> VI ..., ... a: 0..

...J

~ 1-:z ... a: ... o.o ..... := 0

-2.5

-10.0

Fig. 90

. · 2.

-c 1 .... VI 0.. .A ..

-.., ... a: ::::> VI VI ... a: 0..

...J o . ~ 1-:z ... a: ... ..... := 0 r--

-1 .

-2.

-10.0

Fig. 91

~ -

POPT0063 POE-PC-003

r\_' 1

...... ... "' I' -- I""'

~- -

o.o 10.0 20.0 30.0 . ItO .0 50.0 so.o TIME AFTER RUPTURE (SEC)

Differential pressure in intact loop 'hot leg p1p1ng from reactor vessel outlet to the flow venturi ( PdE-PC-3) (filtered to 4 Hz) •

·I-

70.0

POPT0061t POE-PC-OOit I I

NOTE: OATA ARE QUALIFIED FOR INITIAL CONDITIONS ONLY; · CONTAIN UNINTERPRETED LONG-TERM OFFSET.

.u .l ,..,, . ·lL_

11*\J l"'f

" ~ ~ ~ ... r-

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 TIME AFTER RUPTURE (SEC)

Differential pressure in intact loop hot leg p1p1ng from flow venturi to steam generator inlet (PdE-PC-4) (filtered to 4 Hz).

143

70.0

:::: V> 0..

.... gs V> V> .... a: 0..

...J

~ !2 .... a: .... ~

!!; c

c -V> 0..

3.0

2.0

I

~ I. 0

o.o

-I. 0

-10.0

Fig. 92

POPT0065 POE-PC-005 ~ I

NOTE: DATA ARE QUALIFIED FOR INITIAL CONDITIONS ONLY; CONTAIN UNINTERPRETED LONG-TERM OFFSET.

.•. l

··n ' --

-··--- .

II. N "'""'- - .......

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0 TIME AFTER RUPTURE (SEC)

Differential pressure in intact loop cold leg primary coolant pump discharge to reactor vessel inlet nozzle (PdE-PC-5) (filtered to 4Hz).

··-.. I ···I""-

-2.5 ~_.---L--~--~~--~--~--~--~~--_.--~--._~~_.--~

-10.0 o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o TIME AFTER RUPTURE (SEC)

Fig. 93 Differential pressure in intact loop cold leg reactor vessel inlet·to broken·loop cold leg reactor vessel inlet (PdE-PC-7) (filtered to 4Hz).

144

70.0

.·

r

0 .... V>

~ .... "" :::>

~ .... "" .... -' :!; ... :z ..... "" .... .....

. !;!:; 0

8 V>

£:. .... "" :::> V> V> .... "" .... -' :!; ... :z .... "" .... ..... !;!:; 0

2500.

2000.

1!500. 1--···

1000.

!500.

o. -10.0

...

T' 0 -·~· .. ' ··-

-....: -.......

o.o 10.0

- ~-·

~ORTp0-11 POE-RV-001 ' . ' -

NOTE: DIFFERENTIAL PRESSURE BEYOND INSTRUMENT RANGE BEFORE T 0 •

........... ~

. "-

' .......

........... -~ 20.0 30.0 '+0.0 50.0 60.0 70.0

-TIME AFTER RUPTURE (SEC)

Fig. 94 Differential pressure in reactor vessel downcomer stalk 1 to the blowdown suppression tank (PdE-RV-1) •

... 3.

2.

I .

o.

-I .

-2.

-3.

-'+.

-10.0

Fig. 95

PORTOO&Q POE-RV-003

,,.... 1 .. -. ~

r'k • - r--~

' l/ "- ~ It" .

o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o TIME AFTER RUPTURE (SEC)

Differential pressure in reactor vessel intact loop cold leg inlet to downcomer stalk 2 (PdE-RV-3) (filtered to 4Hz).

145

70.0

0 .... <I) 0-

..... !!!! <I) <I) ..... "' 0-

...... ;:= 1-:z ..... "' ..... "-!:!:; 0

0 .... <I) 0-

..... "' ~ <I) <I) ..... "' 0-

...... ~ 1-:z ..... "' .., "-!:!:; 0

5.0 [POR~007Q ,..u-; -ru~IJOit . .

NOTE: DATA ARE QUALIFIED FOR INITIAL CONDITIONS ONLY; CONTAIN UNINTERPRETED LONG-TERM OFFSET.

2.5

• o.o

-2.5

•10.0

Fi 9. 96

••

-so .

-···

-···

,

o.o 10.0 20.0 30.0 'tO, 0 50.0 eo.o TIME AFTER KUI'fUKE. (Sf.l:l

Differential pressure in reactor vessel upper plenum to the int~~t loop hot leg reactor vessel outlet nozzle (PdE-~V-4) •

'70.0

I ~ - -~

~ r

•• ••• ... 10 . so . eo. '70 •


Fi 9. 97 Differential pressure in blowdown suppression tank across vacuum breaker line (PdE-SV-9).

146

c -,,., ~ ..... IX

i;l "' ..... IX 0..

...J

~ 1-:z ..... IX ..... "-!:!; c

c -"' ~ ..... IX ~ V') V') ..... a: 0..

...J

..: i:= :z ..... a: ..... "-!:!; c

~OST~073 POE~2ST-002

NOTE: DATA ARE QUALIFIED FOR INITIAL CONDITIONS ONLY; CONTAIN UNINTERPRETED

·o.o

. u ·~-..

LONG-TERM OFFSET .

" _ . ., ~ ll~aa. --~ / -

" /

"" / -2.5

-· ... _, .•. .... ~-

-5.0

-10.0 o.o 10.0 20.0 30.0 .. o.o 50.0 IISO.O TIME AFTER RUPTURE (SEC)

Fig. 98 Differential pressure in reactor vessel downcomer stalk 2, between 209.4 and 24.5 in. above reactor vessel bottom (PdE-2ST-2) (fi)tered to 4 Hz).

10.0 PO 'TOO 7'+ PpT-P:I39-r'l30 ..... .111....1 I

5.0

o.o

-5.0

-10.0

Fig. 99

I

~ ~

r--

o.o 1(1.0 20.0 30.0 '+0.0 50.0 60.0 TIME AFTER RUPTURE (SEC)

Differential pressure in intact loop across the reactor vessel inlet and outlet nozzles (PdT-Pl39-30).

147

70.0

~ -"' ~ w "' ""' "' "' w "' 0..

~ -"' 0..

w "' ~ "' "' ~ "" 0..

2500.

2000.

1500.

1000.

500.

o. -10.

0

1---

....

0 0 10.

• PGBT0075 PE-BL-001 D PGBT0076 PE-BL-002

-·- f-·

"' .... .........

g

""'- ....... ~

iW'&-

20. 30. 40. 50. 6.0. 70. TIMF AFTnl JIIJIITUR[ (SEC)

Fig. 100 Pressure in broken loop cold and hot legs (PE-BL-1 and -2).

2500.

2000.

1500.

1000.

500.

o. -10.

1\.. --o.

.

- .... "' ~

~ ...

10.

• PG8T0075 PE-BL-001 D PG8T0078 PE-BL-OOif A POBTOOBO PE-BL-008

-

r-...

"" ....... 1'1!1.. .....

...... loo. .........

-.....;;; ["..... ra.-.

20. 30. 40. 50. 60. 70.


Fig. 101 Pressure in broken loop cold leg (PE-BL-1, -4, and -8).

148

~ -VI a..

UJ

"" ::::> VI VI UJ

"" a..

<.!1 -VI 0-

UJ

"" ::::> VI

~ "" 0-

2500.

2000.

1500.

1000.

500.

o. -10.

---- -· .. ·~- -· -·

--

T l

I

o. I 0.

•-PGBT0076 PE.-I::fL-OOc? 0 P08T0077 PE-BL-003

6 P08T0079 PE-BL-006

--····

'

~ ---~ ~

"""''': ~ ~ -~

20. 30. '+0. 50. 60. 70.


Fig. 102 Pressure in broken loop hot leg (PE-BL-2, -3, and -6).

2500. POCTOOBI PE-CS-00 l A.

2000.

1500.

1000.

500.

o. -10.

- 1-o.

o. I 0.

-

........

' """

............. .......... ....._

20. 30. '+0. 50. 60.


Fig. 103 Pressure in reactor vessel core simulator instrument stalk, wide range (PE-CS-lA).

149

70.

<!I ..... VI 0..

.... ~ VI VI .... 0:: 0..

<!I

VI 0..

'" 0::

~ VI .... .. 0..

300.

200.

100.

o. -10.

--

-

o. 10.

fGCr~ P£~.fs-_QJU-f-

1 NOTE: DATA ARE BEYOND INSTRU-

\ MENT RANGE UNTIL T0 + 31 SEC. -

1 \

\ \

' ' '\ '

.

20. 30. ItO. 50. eo. '70. .

TIME AFT~R RUPTURE (tEC)

Fig. 104 Pressure in reactor vessel core simulator instrument· stalk, narrow range (PE-CS-lB).

noo.

aooo.

1'500;

1000 .

500.

o. -10.

·-

·-

- .......

o. 10.

• POPT0083 P£-PC-001 a POPT0081t P£-PC-002 A POPT0085 P£-PC-OOJA

. -- -- .

-- --.

..........

"""-~

"' .............. --.

20. 30. '+0. !50. eo. '70. TIME AFTER RUPTURE (SEC)

Fig. 105 Pressure in intact loop cold leg, hot leg, and steam generator outlet (PE-PC-1, -2, and -3A).

150

<!> -~ .... "" :::>

"' "' "" "" 0.

<!> -"' ~ .... "" :::> V>

"' .... "" 0.

300.

eoo.

100.

o. -10. o. I 0.

·-

P10PTqOB6 PE-f:!C-oq3B

\ NOTE: DATA ARE BEYOND INSTRU-

\ MENT RANGE UNTIL T0 + 31 SEC.

\ \

1\ ... ._.... -.,,.. ....

\ \ r\

'\

""' 20. 30. ItO. 50. 60. 70.


Fig. 106 Pressure in intact loop steam generator outlet, narrow range (PE-PC-38).

2500.

2000.

1500.

1000.

500.

o. -10.

1\c ~

'

o.

'\..· ~

' \ l ~

\ \ A

......

I 0.

• POPT0083 PE-PC-001 a PGPT008'+ PE-PC-002 A PGPT0'+62 PE-PC-OOI_t

\. ~

-....

""" ~ ""'111:

""' ~ 20. 30. ItO. 50. 60. 70.


Fig. 107 Pressure in intact loop cold leg, hot leg, and pressurizer (PE-PC-1, -2, and -4).

151

~ -"' 0..

..... .. ~

"' "' ..... Ct! 0..

<.!J -"' 0..

..... Ct! .J II\ VI ..... Ct! 0..

2!500. • Pocrooal ~cs..:ooiA a PODTD~8~ PE-IST-OOIA A ~Ut~7!5 PE-IST-003A

2000.

1!500.

1000 .

soo.

o. -10.

~·

o. 1 0.

"' ... ""' • ...

' ~ . 20. 30. 1+0 . !50. 60.

TIM~ AFTER RUPTURE (SEC)

Fig. 108 Pressure in reactor vessel downcomer instrument stalk 1 and core simulator (PE-CS-lA and PE-lST-lA and -3A).

·-

i! 70.

300. POOT01~1+ PE-15]-0018

\ NOTE: DATA ARE BEYOND INSTRU-

200.

100.

0.

-10. o. 1 0.

\ \ \

\ \ \

1\.

.

20. 30. ItO.


MENT RANGE UNTIL T0 + 31 SEC.

_.,

'\

""' 50. 60.

Fig. 109 Pressure in reactor vessel downcomer instrument stalk 1, 24.5 in. above reator vessel bottom, narrow range (PE-lST-18).

152

70.

/

300.

~ Pootof2e PE-I:sr-o1o3B I ~. I

\ I

DA~A ARE1

BEYO;D INS+RU-·NOTE:

i MENT RANGE UNIT T0 + 30 SEC.

250.

200. \ <..!> -~/ -· •.. ..... "" ::::>

"' "' ..... "" 0..

<..!> -"' 0..

...... "" ::::>

"' "' ..... "" 0..

1\ \

150.

~ '\

100.

1'-...........

5o:

o. -10.0 o.o 10.0 20.0 30.0 &tO.O 50.0 60.0 70.0

2500.

2000.

1500.

1000.

500.

o. -10.

TIME AFTER RUPTURE (S£C)

Fig. 110 Pressure in reactor vessel downcomer instrument stalk 1, 209.4 in. above reactor vessel bottom, narrow range (PE-lST-38).

• POCT~3 PE-c&-001~~ a ~~5 PE-IST-001~ A PODTOe&te PE-IST-D03F~

I . I I I I -NOTE: INSTRUMENTS DISPLAY

TEMPERATURE SENSITIVITY AFTER ~ T0 + 10 SEC.

""""' • """" ........ ~ --....

-o. 10. 20. 30. ItO. 50. eo. 70.


Fig. 111 Pressure in reactor vessel core simulator and downcomer instrument stalk 1 (PE-CS-lFF and PE-lST-lFF ~nd -3FF).

153

·-~ V) 0...

w § V) V) w c:r:: 0...

<.ll -V) 0...

.... c:r:: :::> V) V) ~

c:r:: ...

2500:

2000.

1500.

1000.

500.

0.

-10.

-

........ , ... _ ··~·~-

o. I 0.

. • POCTDOBI PE-CS-OOIA a PGSTOI+77 PE-2ST-OOIA.

-

,...,.,. .. """"" • ..

"""" ~ ~

20. 30. ItO. 50. eo. 70.

TIME AFTER RUPTURE !SEC)

Fig. 112 Pressure in reactor vessel core simulator and downcomer -instrument stalk 2 (PE-CS-lA and PE-2ST-1A).

2500.

2000.

i~OO .

1000.

!!500.

o. -ao. o. 10.

• PODT~e PE-IST-OOJFF a PGST~B PE-2ST-OOJFF . . •

NOTE: INSTRUMENTS DISPLAY TEMPERATURE SENSITIVITY AFTER ~ T0 + 10 SEC.

- -

- --

--

~ • ~

........:: ..... ......... ~

-=

20. 30. ItO. 50. eo. 70.


Fig. 113 Pressure in reactor vessel downcomer instrument stalks 1 and 2 (PE-1ST-3FF and PE-2ST-3FF).

154

<; -Vl c..

w 0:: ::::> Vl Vl ...... 0:: c..

<!I -Vl c..

...... 0:: ::::> Vl Vl w 0:: c..

noo.

2000.

1500.

1000.

500.

o. -ao.

r-'

-

•'''""""

o. 10.

• • I _. I

• POCT~~ PE-CS-002FF D POST~& PE-2ST-003FF

NOTE: INSTRUMENTS DISPLAY JTEMPERATURE SENSITIVITY

AFTER ~ T0 + 10 SEC.

~ • -....

"""'''i! .... -- .... -

20. :so. ~o. 50. eo. 70.


Fig. 114 Pressure in reactor vessel core simulator and downcomer instrument stalk 2 (PE-CS-2FF and PE-2ST-3FF).

50.0

'tO.O

30.0

20.0

10.0

o.o

-10.0

-10.0

Fig. 115

POTTD088 PE-SV-001

~ ,_. ._..,

k..

/ "'" -/ ,

r /_

"" lit I'

' NOTE: INITIAL SLOWDOWN SUP-

PRESSION TANK PRESSURE IS ADJUSTED TO 0 PSIG.

j_ _I .L _I_ _j_

o.o 10.0 20.0 30.0 'tO.O 50.0 60.0 70.0


Pressure in blowdown suppression tank bottom under downcomer 4, 180° (PE-SV-1) (filtered to 60Hz).

155

~ "' "· ...... "" :::>

"' "' ...... p< P-,

@ ..... "' ... '" p< -VI

"' ...... 0: ...

50.0 POTTOO&O PE-SV-003

~to.o . .- -

L 1 .

30.0 L L

J L ......... , ...... .~-···· ~-

20.0 I ~

~ 1\ ...,j ,. 1 ....

lO.O ................. ., .... ,.,,H, .. ~, _.,._

·-

o.o NOTE: INITIAL BLOIWOWN SUP-


-10.0 I I I I I

-10. o. I 0. ?.0. 1+0. liO. eo. 70.


Fig. 116 Pressure in b1owdown suppression tank across from duwm;umer 1, 157. 5'-' ( PE-SV-3).

50.0 POTT0096 PE-SV-0 lit.

ltO.O ~ ........

r""--. -/ -30.0 /

/'

20.0 .;~

~ it'

10.0

o.o NOTE: INITIAL BLO\~DOWN SUP-


-10.0 I I

-10. 0. I 0. 20. 30. ItO. 50. 60. 70.


Fig. 117 Pressure in b1owdown suppression tank header above downcomer 4, 321° (PE-SV-14}.

156

~ -V'> 0..

.... "" ~ V'> V'> .... "" 0..

<.!l -"' 0..

.... "" ~ V'> V'> .... "" 0..

5,P.O

'+0.0

30.0

20.0

-· 10.0

0.0

-10.0

-10.

Fig. 118

50.0

'+0.0

30.0

20.0

10.0

o.o

-10.0

-10.

o.

POTTD099 PE-SV-017

....., - "-, "" -~

L , ~

J L

/

IV'

NOTE: INITIAL BLO\~DOWN SUP-PRESSION TANK PRESSURE IS ADJUSTED TO 0 PSIG •

I I . I

I 0. 20. 30. '+0.· 50. 60. 70.

llME AFTER RUPTURE (SEC l

Pressure in b1owdown suppression tank 54.5 in. north of downcomer 2, 327° (PE-SV-17).

--~,. --. r--.. ...._ lo-...

v POTTDIOO PE-SV-018

/ )'

~ ~

\...1 ;""'

l

NOTE: INITIAL Bl.:OI~DOWN SUP-PRESSION TANK PRESSURE

. IS ADJUSTED TO 0 PSIG.

o. 10. 20. 30. '+0. 50 . . 60. 70.


Fig. 119 Pressure in b1owdown suppression tank header above downcomer 1 (PE-SV-18).

157

<!l -VI 0..

...... "' => VI VI ... ex 0..

<!l -VI 0..

...... "' ~ ..., ...... "' 0..

50.0 NTTDIOI P£-sv-022 ·

-- ro-... -ltO.O

" " -··-·

30.0 ,

I

~ I

20.0 1£ ~

I

I r 10.0 . -

o.o -NOTE: INITIAL BLOt~DOWN SUP-PRESSION TANK PRESSURE : IS ADJUSTED TO 0 PSIG. _

-10.0 . • L _.a.

-10. o. 10. ao. 30. &tO. so. eo. 10.

TIME AFTER RUPTUR~ (S~C)

Fig. 120 Pressure in b1owdown suppression tank bottom 54.5 in. north of downcomer 3, 180° (PE-SV-22}.

ao.o POTT0105 PE-SV-028

~

'tO.O ~ - -f IL

30.0 ,

' . I,

_, f

20.0 ~ .L

I L \ .Mil ..

10.0

o.o NOTE: INITIAL BLOI~DOWN SUP-

PRESSION TANK PRESSURE IS ADJUSTED TO 0 PSIG .

-10.0 ._.ll ..L

-10. o. 10. 20. 30. ItO. 50. 60. 10.


Fig. 121 Pressure in b1owdown suppression tank bottom 54.3 in. north of downcomer 2, 180° (PE-SV-26}.

158

"" .... Vl

~ w

"' => Vl Vl w "' 0..

"" .... Vl 0..

w "' => Vl Vl w.

"' 0..

so.o -·

'tO.O

30.0

20.0

10.0

o.o

-10.0

-10.

Fig. 122

so.o

'tO.O

30.0

20.0

10.0

o.o

-10.0

-10.

---POTTOIII PE-SV-O't3

_, -~

/ ./ ,

~ ./ --_L

·--

I

Jr 1\ ...-.....

--

NOTE: INITIAL SLOWDOWN SUP-PRESSION TANK PRESSURE· IS ADJUSTED TO O.PSIG . . .

o. I 0. 20. 30. ItO. 50. eo. 70.


Pressure in b1owdown suppression tank bottom under downcomer 2, 180° (PE-SV-43}.

POTTOIII!S PE-SV-055

-__... ,

" .<II

.I

L I

/ ......

l/

tiOTE: INITIAL BLOt~DOWN SUP-PRESSION TANK PRESSURE· IS ADJUSTED TO O.PSIG.

o. 10. 20. 30. ItO. 50. 80. 70.


Fig. 123 Pressure in b1owdown suppression tank top 6 in. north of downcomer 4, 0° (PE-SV-55}.

159

<.!l -V'l ... -..... "" :::::> V'l V'l ..... "' "-

L~ -V'l a.. .... ..... "" :::::>

"' !::] "' ~

50.0 POTT0120 PE-SV-060

ltO.O ~ ~ ..,. / -_,

30.0 ~ I

~ J

20.0 I./ -··---_,

v 10.0

\

o.o ' NOTE: INITIAL BLO\~DOWN SUP-

PRESSION TANK PRESSURE

-10.0 IS. ADJUSTED T~ 0 PS/G·

-10. o. I 0. 20. 30. ItO. 50. 60. 70.


Fig. 124 Pressure in b1owdown suppression tank top above c1ownr.omf!r 1, 0° (PE-SV-60).

50.0

ltO.O Jj -

~ -30.0

20.0

~ , , • POTTDOIB PE-SY-001

... a POTTDIOI PE-SY-OU

~ A POTTDIOS PI-SY-018 0 POTTDIII PE-SY-:-1111

-_ .. , 10.0

o.o · NOTE: INITIAL BLOHDOWN SUP-PRESSION TANK PRESSURE ' IS ADJUSTED TO 0 PSIG. PE-SV-1 DATA ARE FIL-TERED TO 60 HZ.

• I . . -ao.o -ao.o o.o 10.0 20.0 30.0 50.0 eo.o 70.0


Fig. 125 Pressure in b1owdown suppression tank bottom (PE-SV-1, -22, -26, and -43).

160

~ VI 0..

w a: :::> VI VI .... "' 0..

<.!1 ... VI 0..

.... "' :::> VI VI w

"' 0..

!50.0 I I I

ltO.O -~ ~ --~

--·- ·-· •.. • I .. POTT0088 P£-SV-017 30.0

~ 0 POTTOil6 PE-SV-0!5!5

" A POTTOI20 PE-SV-060 ... .. 20.0 _, ..... .,

10.0

~----

o.o NOTE: INITIAL BLOWDOWN SUP-


-1o.o . . --10.0 o.o 10.0 20.0 30.0 ltO.O !50.0 60.0 .70.0


Fig. 126 Pressure in b1owdown suppression tank top (PE-SV-17, -55, and -60).

!50.0 -IG:

~ ---. II....._ -""""- ~

• POTT0086 PE-SV-OIIt [gJ a POTTOIOO PE-SV-018

~to ._o

30.0

~ ~

, ~ ~

20.0

,. -

10.0

o.o NOTE: I Nl TIAL BLOWDOWN SUP-

PRESSION TANK PRESSURE·-

-10.0 I I S

1 ADJU~TED T~ 0. PS

1IG.

-10. o. - I 0. 20. 30. ItO. !50 .. eo. 70.


Fig. 127 Pressure in b1owdown suppression tank header above downcomers 4 and 1 (PE-SV-14 and -18).

161

<!) ..... V)

~ ... a: ::. V) V) ... a: ...

<!) -V) C>.

... a: :,::, V) V) ... "" CL.

600. PGFTDi 35 PT-PI2!):Q_~~

r--

501).

'+00.

300.

200.

100.

o. -10.

2500.

eooo.

1500 .

1000.

500.

o. -10.

i"'\

\ 1\

\ \

\

\ ··-'

\

" N -.....;;;;;,:

o. I 0. 20. 30. '+0. 50. 60. 70. TIME AfTER RUPTUR~ (!!C)

Fig. 128 Pressure in ECCS lower plenum injection line (PT-Pl20-64).

• POFTO.I35 PT-PI20-05'+ D POOT0'+5'+ PE-IST-OOIA

-

"

7

··--· ·-·

i"e.... ............ ...

"' -...;~ ~ ~

o. I 0. 20. 30. '+0. 50. 60. 70.


Fig. 129 Pressure in ECCS lower plenum injection line and lower plenum (PT-Pl20-64 and PE-lST-lA).

162

~ -VI .,_ ,~

.... "' => VI VI .... ~-

~ -VI c..

.... "' ~ VI .... "' c..

220.0

21!5.0

210.0

20!5.0

200.0

19!5.0

-10.

-

o. I 0.

I POFTOi37 PT-Pi20-083-j_ .. ...

...

·- ··-• ~

• -" 'Ia •• IW ...... .. -20. 30. ItO. !50. 60. . 70.


Fig. 130 Pressure in ECCS LPIS pump A discharge -(PT-P120-83).

!50.0 ...,.,o•• 1PT-Pa38·,;o23 ..

'tO.O / .,..- --..

t-- .._

/ -30.0 /

II' ~

20.0 /

&J ,F

10.0

' o.o II NOTE: INITIAL BLOWDOWN SUP-

PRESSION TANK HEADER -PRESSURE IS.ADJUSTED TO 0 PSIG.

-ao.o -ao. o. ao. 20. 30. 'tO. !50. eo. 70.


Fig. 131 Pressure in b1owdown supp.ression tank header 35 in. south of downcomer 1 (PT-P138-23).

163

A <..!) -V'l 0..

... 0:: ::::> V'l

~ 0:: 0..

·~ '·" ~ ... 0: ::::> VJ V'l .... g:

eo.

eo.

ItO.

so.

20.

I 0.

o. -10.

··-

r-

-, ~

rf 1

o.

~ / • POFT01t71t PT-PI38-055

A a POFT0125 PT-PI38-056

/ ' & .,.

~

I 0. 21). ItO, 50. 60. "10.


Fig. 132 Pressure in blowdown suppression tank top (PT-Pl38-55 and -56).

2500.

2000.

1500.

1000.

500.

o. -10. o.

-..... --

10.

• POFTOit78 PT-PilQ-002 D POFT0127 PT-PilQ-003

~ ~ ~ ~ -.; ~ ~ .......

--..; ~

20. 30. ItO. 50. 60. 70.


Fig. 133 Pressure in intact loop hot leg venturi (PT-Pl39-2 and -3).

164

~ "-"" c .... .... "-

.V')

"-~ "-

"-<!I .... c

.... 0< :::> 1-< 0< ..... "-ffi 1-

2000. ; • SRPT~78 AP£-PC-001 ' - "' ;·a SRPT~78 AP£-PC-002 ..

" 1500. ' Ill. ' ... ~

1000. .....

"""' ... - ...

"--.,... ~

500. ""''I! q == --.... I . ....., .... . ..........

o. ' ...

-500.

-10. o. 10. 20. 30. ItO. 50. eo. 70. TIME AFTER RUPTURE (SEC)

Fig. 134 Pump speed for intact loop pumps 1 and 2 (RPE-PC-1 and -2).

600.

500 .

'tOO.

300.

-10.

.. ..

0. 10.

• TEBT0178 TE-BL-001 0 TEST0179 TE-BL-002 6 TE8TD180 TE-BL-003

~ ~

~ \.. NOTE: DATA ARE QUALIFIED

WHILE INSTRUMENT IS '\ IM~1ERSF,D. DATA DIS-

1'- PLAY HOT WALL EFFECTS AFTER "' 40 SEC.

" 1\.. ""-h ~

. ~ ~ L

..... b.... ..... ,;A ~ -"' I"-. I ~ fL'

20. 30. ItO. 50. 60. 70.


Fig. 135 Temperature in broken loop cold leg, hot leg, and reflood assist bypass system (TE-BL-1, -2, and -3).

165

;: <!) w e w 0:: :::> .... < 0:: w 0..

~ 1-

... <!) w e w 0:: :::> 1-< 0:: w 0.. E w ,...

550. • T£81:0181 TE-CL-001 a TEBT0183 TE-HL-002

500.

't50.

&tOO.

3!50.

300.

-iO. o.

"' ~ \ \

) r\:

'" ~ \

'"- ., ~ ... '

Ill

"

I 0.

-.~ .. .................. '

"' " "' ""' "' ""'\.. "' " Ia.... """ii ..... -.........

20. 30. &tO. 50. 60.

liME AfflR RUI'rUKI:: iSH;)

Fig. 136 Temperatute in broken loop cold leg and hot leg wanuup 1_1 nes {TI::-CL-1 ~nd TE-HL-2).

eoo.

-~

70,

TECTD'tBO TE-CS-001

!500.

&tOO.

300.

-10.

--

r--.....

o. I 0.

-

"" f'-" '\. -.' .... ~ ... -,

~ ~

1\.. .....

20. 30. &tO. 50. . eo. TIME AFTER RUPTURE (SEC)

Fig. 137 Temperature in reactor vessel core simulator instrument stalk (TE-CS-1).

166

70 .

i:

"' ..., e ..., c:: ::::> t-C( c:: ..., ~ ..., t-

i:

"' ..., c

..., c:: ::::> t-C( c:: ..., 0-:E: ..., t-

.

eoo.

500·

'tOO.

3oo. -10.

-~

o. 10.

• TEPTOI85 TE-PC-001 a TEPTOI88 TE-PC-002 6 TEPTOI87 T~-PC-003 l _l l I

NJTE: ~ATA A1RE QUlLIFIE~

I' WHILE INSTRUMENT IS

~ IMMERSED. DATA DIS-PLAY HUT WALl, EFFECTS

-~ AFTER "' 3D SEC.

~~ ......

1'-J ,~ L_ n... ~ll ~ ~ -"-

l~ ...........

" ~ --~

" ~ ....._, _.

20. 30. ItO. 50. eo. 70.


Fig. 138 Temperature in intact loop cold leg, hot leg, and steam generator outlet (TE-PC-1, -2, and -3).

aeo. ' TEF"TD501 TE-PllB-022 -

~ ~ i"""'"

150. lo""

v /

1/ ~

1'+0 . /

/ v

/ , 130. /

~

/ ./

120.

-10. o. I 0. 20. 30. '+0. 50. eo. 70.


Fig. 139 Temperature in blowdown suppression tank 1 i quid at tank bottom (TE-Pl38-22).

167

..... <!I w 0

w a: ~ t-< a: w 0. ::E w t-

~ <!I w e w a: ~ t-< a: w 0. ::E .... I-

280. TE~T~g TE-P138-03'+

270.

280.

250.

2'+0.

230.

220.

210.

200.

190.

180.

-10.0

·-

.7 .,.,-/

o.o 10.0

-I .......... /

1/ ~

/

7 -

I I

7 7

20.0 30.0 '+0.0 50.0 eo.o TIME AFTER RUPTURE (SEC)

Fig. 140 Temperature in blowdown suppression tank vapor at tank top (TE-Pl38-34).

\

7CJ.o

550. • TE~TD1SMS TE-P138-062 a TE~T0187 TE-P138-083

500.

'+50.

'+00.

350.

JOO. -10.

'

o.

""'iiiitiL

I'll.

""' Ia.

'

10.

.........._ ~

r""'oo..

"- ...... ..... ~ - ........._

llil::

""' ~""'\;...

1"" T "\.:

~

~

-..... ........ ~ -

20. 30. '+0. 50.


Fig. 141 Temperature in broken loop cold leg QOBV inlet and isolation valve inlet (TE-Pl38-62 and -63).

168

...

-eo. 70.

)

1: ::tl Q

.... 0:

. => 1-« 0: .... c.. ::E .... .....

1: <!l .... e .... 0: => 1-< 0: .... c.. ::E .... 1-

lt!50.

ltOO.

3!50.

300.

-10.

~

o.

'\..

"" "\. '" .:\. .... ._

' ~

'

I 0.

·-

• TEF'TOIQS TE-PI38-965 a TEF'TOISI9 TE-P138-065

~ _)l_

'\..

' '"'\.

' \.. ~ ' "'- '-

A 1'- ' -

..... :".. ~

"""""' .... ~ .A ~ ..., ~ -

20. 30. ItO. !50. eo. 70.

TIME AFTER RUPTURE {SEC)

Fig. 142 Temperature in broken loop hot leg QOBV inlet and isolation valve inlet (TE-Pl38-66 and -65).

700.

8!1).

eoo.

!5!50.

!500.

lt!50.

ltOO.

-ao.

Fig. 143

• TEF'T0201t TE-P138-018 a TEF'T020!5 TE-P138-020

I I I

I I I -- . . . - ....... NOTE: TEMPERATURE IS BELOW i""o..' INSTRUMENT RANGE AFTER ... L " T 0 + 24 SEC . .

"' '" .. '" '"

~

"' • 1'-'-

"""""" .... .....

o. 10. 20. 30. ItO. !50. eo. 70.

TIME AFTER RUPTURE {SEC)

Temperature in intact loop pressurizer vapor and liquid (TE-Pl39-19 and -20).

169

,

..

... <..!> ... e ... a< :::> ..... < a< ... 0..

ffi .....

... <..!> -... e ... a< ~

!;( a< ... 0.. ::E ... .....

sso. TEFT0207 TE-PI38-028

-' ' ~ soo. '" . ..

'· \.. ' ..

' ' 'tSO . "-

"- --...

'tOO· -10. o. 10. 20. 30. ItO. so. eo.


Fig. 144 Temperature in intact loop cold leg upstream of OTT flange (TE-Pl39-29).

r--

70.

sso. • TEFT0520 TE-Pl38-032

-.. a TEFT02SO TE-P138-033

soo.

'tSO.

'tOO.

3SO.

I 300.

-10.

.

o. I 0.

.......... "11....

"'IIIo.

' "' ""-'

20. 30. ItO.


' ' .. ' ... ~

"""" ......

so. eo.

Fig. 145 Temperature in intact loop hot leg in elbow near venturi (TE-Pl39-32 and -33).

170

~ ......;;;;

70.

.... CJ ... e ... a:: :::> 1-< a:: ... 0.. ::E: ... 1-

.... <!) ... c

... a:: :::> ... < a:: ... 0.. ::E: ... 1-

550.

525.

500 .

't7!5.

'tiiO.

't2!5.

-10.

Fig. 146

i ..._

,~ """'-~ r-...

llio. ...... ... " ~ - :--~

" -,. ~ ~

r-.. ... ....... ~

r""'a. ~

• TEGTD!503 TE-S0-001 D TEGTD!50't TE-S0-002

·A TEGTD!50!5 TE-S0-003

o. I 0. 20. 30. 'tO. !50. eo. 70.


Temperature in steam generator intact loop cold leg, hot leg, and secondary side (TE-SG-1, -2, and -3).

27!5. ~~~~----+---~---4----~---~~----+---~-• TETT0!50e TE-SY-001 ~~~~---+---~---4-~~---~~---+---~-D TETT0!507 TE-SY-002

6 TETTD!508 Tl -SY-003

2!50 .

22!5. l\

\ IIJ ""

MK.r' 200. Jtl'f

...'J v-

-

N I.

~ :::..:: ~ - I~ l\f ..,. t n;; W:l'" ir\1""'

NOTE: DATA ARE QUALIFIED -WHILE INSTRUMENT IS IMMERSED. -

17!5. L-~---L--~~~_.--~--._~--~--~~--~----~~-*--~

-ao. o. I 0. 20. 30. 'tO. !50. eo. TIME AFTER RUPTURE (SEC)

Fig. 147 Temperature in blowdown suppression tank B-end thermocouple stalk {TE-SV-l, -2, and -3).

171

70.

.... <.!> w e w

"" ::::> 1-

~ w Q_

i!J 1-

;:;: <.!> w 0

w

"" ::::> 1-

"" "" w Q_

:E w 1-

27!1.

2!10.

22!1.

200.

175.

-10. o.

J 41

" JJ"

I 0.

"' ~ a.. ia..4 ...... • ItT .. \1 ' 'Jl -

l ... ~ -ill I J I' o,JIJ ~ -1\j ll r •

Ill .I ..rr

"" /4, ~

,.) NOTE: DATA ARE QVALJ.FIED ..,.. WHILE INSTRUMENT IS IMMERSED.

• rE 'ti)Soa TE-SY-~Oit a TETTD510 TE-SY-00!1 6 TETTD511 TE-SY-OOe

20. 30. ItO. 50. eo. 70.


fig. 148 Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-4, -5, and -6).

eso.

225.

200.

175.

-10.

... .. ......

o.

A Jl ~-

I 0.

l t ,....J. iW .... -.J~ •...4-MI ~ ... -..

~ ...... ... 1' ~ ~- ... .- ""-~~if/~: ,

~ " .. ,,. llATA ARF C)IIAI TrTEn -

II" IIIII NOTE:

WHILE INSTRUMENT IS _

~ IMMCR!JCD.

• TETT0512 TE-SY-007 a TETT0513 TE-SY-008 6 ·-.:_oe -- -TET lit T~'";tY"'!'U•

20. 30. ItO. 50. eo. 70.


Fig. 149 Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-7, -8, and -9).

172

... <.!> UJ 0

UJ

"' ::::> 1-< "' UJ a.. ::E UJ 1-

;:: <.!> UJ 0

UJ

"' ::::> 1-< "' UJ a.. ::E ..... 1-

2'75.

aeo.

225.

200.

17e.

-10. o.

I 9 I w- ·-. .. "" II " I -

,_ J"W ~ ~

(]' l II JU' ¥ ~ ~

aJl IT r.7il' ~ • ~I""'·•

~

NOTE: DATA ARE QUALIFIED _ WHILE INSTRUMENT IS IMMERSED. -

·e r&TTJdl! TE-5V-Cl10 D TETTO!I8 TE-SV-011

·a T£TTI)517 TE-SV-012

10. 20. 30. ItO. eo. eo. 70. TIME AFTER RUPTURE (SEC)

Fig. 150 Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-10, -11, and -12) •

. ., ...

2eo.

22e.

100.

17e.

-10.

l rw"""'

o.

.n ~ 11r • r..r JIJ

l 0.

• TET TE'"'SV-001 1"1 T~T1 DIU TIE-SV-110'7

~ ~ * A... \1 ,..,....

JtJ ll' I ~ ~:f

I W)ll' ... ~ J-,J ~

NOTE: DATA ARE QUALIFIED WHILE INSTRUMENT IS -IMMERSED. .-

eo. 30. ItO. eo. eo. '70.


Fig. 151 Temperature in blowdown suppression tank 107.2 in. from tank bottom (TE-SV-1 and -7).

173

.... <.D .... e .... "" :::> ..... cr. '"' .... <>-lE: .... .....

;: ffi e .... ~ ..... < "" ..... <>-lE: .... .....

no.

118 .

200 •

178.

-ao. o.

I

J -~

10.

I 'Wit _.. _ ..... ..

rw ..... ......

,J '

~

NOTE: DATA ARE QUALIFIED -WHILE INSTRUMENT IS

I I IMMERfED. I I -

• TE rTbeoi TE-"sv-o'oa a TETTOSIJ TE-SV-008 . . - .

eo. JO. 'tO. !50. eo. 70.

TIME AFTER RUPTUR~ (SEC)

Fig. 152 Temperature in b1owdown suppression tank 93.0 in. from tank bottom (TE-SV-2 and -8).

250.

225.

200.

175.

-10.

---

o.

1\

AJ 1

..... ~ 1--' ~ ...

10.

' .AI ~ }.

~ w~ \ .,A ~ .......... ""-f I ~

_., If-"" :~ ~ - Ia_,

,_ .... ..,.,

~ -~ I IV' ~

14 ~ ~ ~ '\ ,. -~ II"""'

"


i I I I I

i • 'rEr-losoa TE~SV-003

I 0 1 TET1051~ TE-SV-009 -I I

20. 30. '+0. 50. 60. 70.


Fig. 153 Temperature in b1owdown suppression tank 74.7 in. from tank bottom (TE-SV-3 and -9)~

174

i: <.!> ..... e ..... a:: => 1-< a:: ..... a.. E ..... 1-

"-<.!> ..... e ..... a:: => !;( a:: ..... a.. E ..... 1-

. ., .. ISO.

··~·

100.

. ., .. -ao.

..... ,..

o.

•

Ia If . 11

11'1'

Ia. •• iiJll ~ I ~

I 0. 10.

' ,.. ·-~ -' "

>

I

NOTE: DATA ARE QUALIFIED • WHILE INSTRUMENT IS • IMMERSED.

• TITTDSOI h -;. .;:.

a TETTDSI TE~Iv-~10 I _l I

10. ItO. eo. 10. TIME AFTER RUPTURE (SEC)

Fig. 154 Temperature in b1owdown suppression tank 57.2 in. from tank bottom (TE-SV-4 and -10) •

. , .. 180.

••••

100.

. ., .. -ao. o.

....

A~ Ill I~

10.

•J n r u• .... ~

ll' I..IU II._ I, INM•

J.l't"lr' ~' •

u

eo. 30. ItO.


~ ~

r.-' -"" ~


• ·~, ,ug·ao TE-av-ooe D

1 TETIDS18 TE;IV•Oll

so. eo. 'JQ.

Fig. 155 Temperature in b1owdown suppression tank 39.0 in. from tank bottom (TE-SV-5 and -11).

175

.... <.!) .... c

.... 0: j: < 0: .... a.. :£ .... .....

.... <.!) .... ,.....

w ,.. ::0 ..... < rv .... a.. :£ w .....

275.

250.

225.

200.

175.

-10. o.

lVI ,.l IlL

... ~Ill\ l..l n~ IIIII ~ 'I lift IIV v•

I 0.

• TETT0511 TE:..sv-ooe o TETT0517 TE-SV-012

--"' ~

r::r ... - """

rJ.~ ~ ""'- ........., ~ r -, .. ~ J. If I ~

1 '".l ,rr 11 -~

..J ~

NOTE: DATA ARE QUALIFIED WHILE INSTRUMENT IS -IMMERSED • -• .

20. 30. '+0. 50. 60. 70.

l'lME AFTER RUPTURE (SEC)

Fig. 156 Temperature in blowdown suppression tank 14.7 in. from tank bottom (TE-SV-6 and -12).

600.

500.

'+00.

300.

eoo.

-10.

-

o. I 0.

• 'rEOTb518 TE-IST-001 a TEOT02U TE-IST-002 6 n::oroeae TE-a.sr-oo3 0 TEOT0213 TE-IST~OO~

" ----...

' ~ ' ~

' ~ ~ .... -

"'""""""" ....

20. 30. '+0. 50. 60. 70. TIME AFTER RUPTURE (SEC)

Fig. 157 Temperature in reactor vessel downcomer instrument stalk 1 (TE-lST-1, -2, -3, and -4).

176

L: <.!) ...... e ...... "' i= < "' ...... 0.. :E ...... 1-

eoo.

300.

200.

-10.

Fig. 158

600.

500.

'+00.

300.

200.

-10.

• TEOT021!5 TE-IST-008 a TEOT0217 TE-IST-008 6 TEOT0218 TE-IST-008

- lo TEOT021SJ TE-IST-010 ~ ~ ~ ~

' ' " ~ ll ....

"""" ... .......

~ -...'

o. I 0. 20. 30. '+0. !50. eo. 70.

TJMF AFTER RUPTURE (S~C)

Temperature in reactor vessel downcomer instrument stalk 1 (TE-lST-6, -8, -9, and -10).

• TEOT0220 TE-IST-011 a TEOT0221 TE-IST-012 A TEOT0'+59 TE-IST~OI3 0 TEOT0223 TE-IST-01'+ -............ -~---

~ ~

" li! ' ..

' .. ... ~ ... .,.,

' ,._ ~

~

!""-~

o. I 0. 20. 30. '+0. 50. 60. 70.


Fig. 159 Temperature in reactor vessel downcomer instrument . stalk 1 (TE-lST-11, -12, -13, and -14).

177

..... <.!) .... c

..... c<

i= ..: c< ..... c.. :::E ..... ....

;: t.!) .... c

..... !:!! .... ..: c< ..... c.. :::E ..... -....

800.

500.

'+00.

300.

eoo. -10.

. ..

-

o. l 0.

• TEST022'+ TE-2ST-002 D TEST0228 TE-2ST-00'+ A TEST0229 TE-2ST-007 0 TEST0231 TE-2ST-009.

~ '-. ..

"' " ' ._ '-

"'- -- ~

""- ...

"" ~ -·-. ~

20. 30. '+0. 50. 60. 70.

TIM[ AF-TER P.UPTUP.I:: ( SI::C)

Fig. 160 Temperature in reactor vessel downcomer instrument stalk 2. (TE-2ST-2, -4, -7, and -9).

800.

eoo.

ltOO.

31:\0.

eoo. -ao.

---

o. 10.

• TES1"02R TE..!2ST-OIO· a TEST0238 TE-2ST-OIIt: & TEST~~ TE-25T-DI2

............

'-lil

" ' ~ "' " II .... ~,... -......

~ '-. ..._ ~ ~

20. 30. '+0. 50. 80. 70. TIME AFTER RUPTURE (SEC)

Fig. 161 Temperature in reactor vessel downcomer instrument stalk 2 (TE-2ST-10, -12, and -14).

178

-LL..

<!I ... e ... 0:: => I-< 0:: ... 0.. ::E ... I-

500.

450.

400.

350.

300.

-10.

- -.......

o. 10.

'rEOT0518 TE-lST-001

f'.. "'-.

\. \.

:\. .... --- ~-

\: \.

I' \.

\.

' ' '\.

~ .......... ····· ..

20. 30. 40. 50. 60. 70. TIME AFTER RUPTURE (SEC)

Fig. 162 Temperature in reactor vessel downcomer instrument stalk 1, 189.3 in. from reactor vessel bottom (TE-tST-1).

LL..,

<!I ... c

... 0:: ::> I-< 0:: ... 0.. ::E ... I-

600. • TEOT0211 TE-IST-002 a ,TEST022't TE-2ST-002

500.

400.

300.

200.

-10. o. 10.

~ ~

"" ~ lll

"" --,. ~

lliL

' ........

20. 30. 40. 50. 60.


Fig. 163 Temperature in reactor vessel downcomer instrument stalks 1 and 2, 165.3 in. above reactor vessel bottom (TE-lST-2 and TE-2ST-2).

179

70.

..... t:J .... e .... "' ::::>

~ "' .... Q.

E .... 1-

~ t:J .... e .... "' ::::> ,... < ...: ..... . .:.. E ..... 1-

eoo. TEOTD212 TE-·IsT-003

500.

'tOO.

300.

-10.

- -.........

o. I 0.

" r\. '\ I' ' \. ' ~

' '""" " 20. 30. ItO. 50. eo.

TiM~ AfH.II RIII'TURE (SFC)

Fig. 164 Temperature in reactor vessel downcomer instrument stalk 1, 141.3 in. above reactor vessel bottom {TE-1ST-3).

70.

eoo. • • TEOT02 a3 TE.: I ST .:OOit a TEST0228 TE-2ST-001t

500.

ltOO.

300.

200.

-10.

-

o. 10.

"""'-.. ~ ~

!'...

"" ""'" """ 1'-

'"' ~ .....

20. 30. ItO. 50. eo. TIME AFTER RUPTURE (SEC)

Fig. 165 Temperature in reactor vessel downcomer instrument stalks 1 and 2, 117.3 in. above reactor vessel bottom (TE-lST-4 and TE-2ST-4).

180.

70.

-.... <.!' ..... e ..... "" :::> 1-< "" ..... a.. ::E ..... 1-

;:: <.!' ..... e ..... "" :::> 1-< "" ..... a.. ::E ..... 1-

~oo.

eoo.

'+00.

300.

-10. o.

-,.._

I 0.

TEOT0215 TE-IST=008

'

K 1\.

' 1\ ... . .

" '" " ' -

' "" "" 20. 30. '+0. 50. 80. 70.


· Fig. 166 Temperature in reactor vessel downcomer instrument

800.

500.

'+00.

300.

200.

-10.0

Fig. 167

stalk 1, 69.3 in. above reactor vessel bottom (TE-lST-6).

TEST)2H TE-2ST-007

' ' ' i'o..

" r\. ........ ~

" ............

o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o 70.0


Temperature in reactor vessel downcomer instrument stalk 2, 33.3 in. above reactor-~essel bottom (TE-2ST-7).

181

.... <.!I ..... e ..... "' ::::> 1-o:r: "' ..... ,_ :..: ..... 1-

L: <.!I ..... !::::! ..... a:: ~ < .... ~ ::E ..... 1-

eoo.

500.

'+00.

300.

-10.0

-~

o.o 10,0

TEOTb217 TE~IST-008

~ r\.

'\ 1'\.

' "\.

" "\. ~

"!I.. ""'

20.0 30.0 ltO.O eo.o eo.o 70.0

TIME AFTER RUPTUR~ (StCl

Fig. 168 Temperature in reactor vessel downcomer instrument

eoo.

soo.

'tOO.

300.

eoo. -10.

stalk 1,· l9.3 in. above reactor vessel bottom (TE-1ST-8).

• TEOTOI!18 TE-lST-008 Q TEST023l TE-esT-008

"""-~

'81. ["-. ~~

"-~

- I'--... .., -··- ·-

-.... ~

o. 10. eo. 30. 'tO. so. eo. 70. TIME AFTER RUPTURE (SEC)

Fig. 169 Temperature in reactor vessel downcomer instrument stalks 1 and 2, 25.3 in. above reactor vessel bottom (TE-1ST-9 and TE-2ST-9).

182

.: ..., ..... e ..... "' :::> I-< "' ..... Q.

::E ..... I-

.: ..., ..... e ..... "' :::> I-< "' ~ ::E ..... I-

eao. • TEDTDel8 TE-IST-DID a TESTD!Je TE-2ST-OID'

r-

SOD. """"' ~ "' ...

~ l

..oo. ' l "" ·--"' ~ .......... 300.

~ ....

200.

-ao. o. 10. 20. 30. .. o. TIME AFTER RUPTURE (SEC)

-

so . eo.

Fig. 170 Temperature 1n reactor vessel downcomcr in!itrument stalks 1 and 2, 21.3 in. above reactor vessel bottom (TE-lST-10 and TE-2ST-10).

'70.

eoo. TEDT0220 TE-lST-011

soo.

.. oo.

300.

200.

-ao. o. 10.

........... ~

' "\..

"' i"-. " "\..

~

"""""" ........ ~

20. 30. ..o. so. eo. TIME AFTER RUPTURE (SEC)

Fig. 171 Temperature in reactor vessel downcomer instrument stalk 1, 17.3 in. above reactor vessel bottom (TE-lST-11).

183

-~

'70.

.... <.!) .... e .... !5 ...., c(

"" .... 0.. ::E .... 1-

~ ·o.!J ....

Q

.... "" ~ c(

"" .... 0.. ::E ,,, 1-

eoo.

500.

&tOO.

300.

200.

-ao.

r-

o. I 0.

• TEOT0221. D TEST0231t

""""'-

' .,. ~

11

' • ' .. ... ,.

-...... -"-

20. 30. &tO. 50.

TIME AFTER nUPTUnC (SEC)

TE-IST-012 TE-2ST-Ol2

• I\\.. - .-~

..

60. 70.

Fig. 172 Temperature in reactor vessel downcomer instrument stalks 1 and 2, 13.3 in. above reactor vessel bottom (TE-lST-12 and TE-2Sf-12).

eoo.

500.

'tOO.

300.

200.

-10.

r--

o. I 0.

' I"-

' ' " " "

' ~ -

20. 30. 'tO.


TEOTO&t59 TE-IST-013

"'" ....... "" ' -- -

50. 60. 70.

Fig. 173 Temperature in reactor vessel downcomer instrument stalk 1, 9.3 in. above reactor vessel bottom (TE-lST-13).

184

.... Cl .... e .... a: ~ ..... < ·a: .... 0..

ffi .....

.... Cl .... e .... a: ::> ..... < a: .... 0..

ffi .....

eoo. • TEOT0223 TE-IST-OIIt a ~~ST0238 TE-2ST-OI~

$00 .

'tOO.

300.

-10. o.

..... ~

~"' .r.·•

10.

" ~ ~

) ." .,. '\.

--all

"-~ ... "- . ..

20. 30. ItO. so. eo. TIME AFTER RUPTURE (SEC)

Fig. 174 Temperature in reactor vessel downcomer instrument stalks 1 and 2, 45.9 in. above reactor vessel bottom in DTTs (TE-lST-14 and TE-2ST-14).

70.

'tOO. TEF'TD2'tl TT-Pl20-08S

3SO.

300.

2SO.

200.

-10.

-

'

o. I 0.

"'

20. 30. ItO.


~

' ' \ \ \

~

' ' 1\. '\.

so. 80.

Fig. 175 Temperature in ECCS lower plenum injection line (TT -Pl20-65).

185

" 70.

~~ '7 .

THIS PAGE

WAS INTENTIONALLY

·. LEFT BLANK

3. TEST L1-3 MEASURED PARAMETERS --

LONG - TERM PLOTS (175- AND 500-SECOND PLOTS)


187

.., .. .. 1-.... -E

"' ...J

.... ,_ -VI

"" w 0

...J < 0

"' 0 ::t: u

>,_ ..... VI :z w 0

...J < 0

"' 0 ::t: u 10

0

- 1 -25

Fig. 176

I ..

Fig. 177

DE-BL-1A DE-BL-16 DE -BL-1C

TIME AFTER RUPTURE (SEC) EGG-A-372

Density in broken loop cold leg, chordal density (DE-BL-lA, -18, and -lC).

DE-BL-2A DE-BL-28

•..••••••. DE-BL-2C

175

TIME AFTER RUPTURE (SEC) ~GG-A-368

Density in broken loop hot leg, chordal density (DE-8L-2A, -28, and -2C).

188

~ t) 0 --' ...... >

FE-BL-1


0~------~------~------~~DA~~~-----L------~~----~------~ -25 0 175 .


Fig. 178 Fluid velocity in broken loop cold leg at OTT flanges (FE-BL-1).

189

EGG-A-671

-<..> ..... .. ,

8

FE-2ST-1


;;:r ~ 4

2

0

-2 ~------~~----~------L-------L-------L-------L-------L-----~ -:.1!:> u to 1UU 1ou 1/o

TIME AFTER. RUPTURE (SEC) EGG-A-911

Fig. 119 Fluid velocity in reactor vessel downcomer instrument stalk 2, 47.1 1n. above reactor vessel bottom {FE-2ST-1).

190

9 ...

10 --~-

NOTE: DATA ARE QUALIFIED AFTER T + 94 SEC ONLY. DATA A~E UNINTERPRETED PRIOR TOT +"94 SEC DUE TO MECH~NICAL NOISE.

FE-P138-138

-25 7!i 176 TIME AFTER RUPTURE (SEC) ·eGG-A-390

Fig. 180 Flow rate in blowdown suppression tank spray system 60-gpm header (FE-P138-138).

FE-P138-139

~~25~----~----~~----~~----~----~~----~~----~~----,~75

TIME AFTER RUPTURE (SEC) EGG-A·385

Fig. 181 Flow rate in blowdown suppression tank spray system pump discharge (FE-Pl38-139).

191

UJ 1-

~ 3 0 _. .....

.::E Q.

e w 1-

~ 3 0 _. .....

FE-P138-140

NOTE: RECORDED FLOW RATF. BETWEEN !n AND !a + 15 SEC DVE TO

- Mtt:HANicAL SHOCK.

0~----~~--~----~~--~~----~----~~--~~--~ -25 75 100 175 TIME AFTER RUPTURE (SEC) EGG-A-377

Fig. 182 Flow rate in blowdown suppression tank spray system 220-gpm header (FE-Pl38-140).

120 .....----1---...--1 --,--,--1~--..,.,----,.,--__,1,--------.

FE-P138-153 100 f- -

00 ~ -

~ -60

40 ~ -

-

I I I I . 1\ I I ~L25~----~oL-----~2!5~----~5o~----~7!5~--~,~oo~----~1~25~----~,5~o~--~175

Fig. 183

EGG-1\·389 . TIME AFTER RUPTURE (SEC)

Flow rate in blowdown suppression tank spray system pump recirculation line (FE-Pl38-153) .•

192

:z: .... _, w > ..... _, 8 :::>

8' _,

)

FT-P120-85


Fig. 184 Flow rate in ECCS LPIS pump A discharge (FT-Pl20-85).

Fig. 185

-·- LT-P138-33

---- LT-P138-58

NOTE: DATA DISPLAY INSTRUMENT RINGING FROM" T0 TO T0 + 2.5 SEC.


Liquid level in blowdown suppression tank (LT-Pl38-33 and -58).

193

EGG-A-371

N ... ... ::.:l· VI

I 1-u. ...... ~

I

""' >< ::::> ...J u.

::£ =-1-z: ..... !5 ~

N ... ... u ..... "' I 1-u.

~ ...J

50

ME-BL-1

40

NOTE: DATA ARE TEMPERATURE

30 SENSITIVE AFTER~ T0 + 50 SEC. REFER TO SECTION III IN TEXT ON DRAG DISC CALIBRATIONS.

20

10

0 1---.....---~

-10L-------L-______ L_ ______ L_ ______ i_ ______ i_ ______ L_ ____ ~~----~

-25 0 25 7fi 100 125 160

TIME AFTER RUPTURE (SEC) · EGG-A-973

Fig. 186· Momentum ·flux in the broken loop cold leg at DTT flange (ME-BL-1).

5 r-------r-------r---~~r-------r-------r-------.-------r-----~

4

3

ME-2ST-1

NOTE: REFER TO SECTION III IN ·TEXT ON DRAG DISC GALIBRATIONS.

~- 2

0

-1

-25 0 25 50 7!i 100 125 150 175

• TIME AFTER RUPTURE (SEC) . EGG-~-97o Fig. 187 Momentum flux 1n reactor vessel downcomer 1nstrumen~

stalk 2, 44.5 in. above reactor vessel bottom (ME-2ST-l).

194

::e V) Q.

..... "" :::> V) V) ..... "" Q.

300r-----r-,----r-,----~.----~,----~,----~,----~,----~

-·-·--·-·-.

250 r-

200 -

150 -

100 -

50-

0 I -25 0

Fig. 188

50

oa----

'

l I 25

Pressure in

NOTE: DATA INITIAL VALUES ARE ADJUSTED TO 0 PSIG.

-

- PE·CS-18 --·- PE-PC·3B

-

-

L I l 125 150 HS

EGG-A-378

simulator instrument loop steam generator

- PE-SV-3 -·- PE-SV-22

-10~-----±-----~----~--~~---~~---~---~~----~ -25 . 50 75 100 HS TIME AFTER RUPTURE (SEC) EGG-A-387

Fig. 189 Pressure in blowdown suppression tank across from · downcomer 1, 157.5°, and bottom 54.5 in. north of downcomer 3, 180° (PE-SV-3 and -22).

195

;..... <!J -VI 0..

o~--..

--- PE-SV-55 -.- PE-SV-60

Note: Data Initial Values Adjusted to 0 psig.

. -1U~----~------~------~----~~----~~--~~~----~~--~ . - -25 175

..

·<!J -. VI ... -

TIME AFTER RUPTURE (SEC) EGC3-A·380

: Fig. 190 Pressure in blowdown suppression tank top north of. downcomer 4 and above downcomer 1 (PE-SV-55 and -60).

soor------T-----~--~~~----~r-----~-------r------,-~~~

PT-P12Q-64

TIME AFTER RUPTURE (SECl EGG-A-384

Fig. 191 Pressure in ECCS lower plenum injection line · (PT-P120-64).

196

.-<..!> -V'l ~

""· -V'l .,_ ...... "" ::>

- V'l V'l ...... "" ~

PT-P120-83

195~----~------t.o----~~----~----~~----~~--~~----~ -25 50 75 . 100 175


Fig. 192 Pressure in ECCS LPIS pump A discharge (PT-P120-83).

·- PT-P138-55 -·- PT-P138-56


Fig. 193 Pressure in b1owdown suppression tank top 48 in. north of downcomer .. 1 and 49 in. north of downcomer 2 (PT-P138-55 and -56).

197

<!I .... VI c.

... a: ~ VI VI w a: c.

-... <!I w e w a<

fi ... w 0.. ::E w 1-

- PT-P138-136 -·-- PT-P138-151

1\. ·--·-· .. _.,-

17~~3~--+---....,r----~:w------w .. ==""'-=-... =,~,11:::-:., ..... -=-=---~~-.,..-~:---~,.,!'i

Fig. 194 TIME AFTER RUPTURE (SEC)

Pressure in blowdown suppression pump discharge and coo1down heat (PT-Pl38-136 and -151).

EGG-A-369

tank spray system exchanger outlet

55o~-----?-----~---~---~~---~---~---,-~--__,

500

450

350

300

'/ . '/ \ . \.}

-·- TE-BL-1 --- TE-BL-2

NOTE: DATA ARE QUALIFIED WHILE INSTRUMENT IS IMI>IERSED. DATA DISPLAY HOT WALL EFFECTS AFTER "' 40 SEC.

250~----~~----~~----~----~~----~b.-----~~----~~-~~ - 5 75 175


Fig. 195 Temperature in broken loop cold leg and hot leg (TE-BL-1 and -2).

198

-I

... <!I ..... Q

.....

450

~ 400 -..; a: ..... 0..

ffi ,_

300

TE-CS-1

NOTE: DATA ARE QUALIFIED.WHILE INSTRUMENT IS UIMERSED. DATA DISPLAY HOT WALL EFFECTS AFTER~ 102 SEC .

25~~25~----~------~~----~~----~~----~~----~~----~~-----1~75

... <!I ..... Q

TIME AFTER RUPTURE (SEC) EGG·A-380

Fig. 196 Temperature in reactor vessel core simulator

NOTE:

instrument stalk (TE-CS-1).

- TE-PC-1 ......... TE-PC-2 --·- TE-PC-3 ---· ,...,..:-. .

/"''__,.,· .

. /·

r f· . '"" .

\

\ .. ~

DATA ARE QUALIFIED WHILE INSTRUMENT.IS IMMERSED. DATA DISPLAY HOT WALL EFFECTS AFTER~ 30 SEC.

·-·

--···--··········-·· ..... -. .....,-. ..... .... .... ·.,.-----····


Fig. 197 Temperature in intact loop cold leg, hot leg, and steam generator outlet (TE-PC-1, -2, and -3).

199

..... <!l a·

TE-P138-142

..... 150 ~ 1-< a:: ..... 0..

ffi 1-

..... <!l ..... 0

w a:: .. ~ a:: ... 0.. ::E ..... 1-

~2~5~----~~~~~~--~~----~----~~----~~----~~----~175

Fig. 190 TIME AFTER RUPTURE (SEC) EGG-A-379

Temperature in b 1 ow down SUIJ~H'ess·i uu tank spray system pump discharge (TE-P138-142).

---·- TE-P138-141 TE-P138-143

125~---------------------------------------

·---·---·---·---·---·-----

- 109 5 175 TIME AFTER RUPTURE CSECl EGG-A-388

Fig. 199 Temperature in b1owdown suppression tank spray system 60-gpm header and 220-gpm spray header (TE-P138-141 and -143).

200

.... <..!1 .... c

.... <..!1 .... c

.... "' :::::> 1-< a: .... 0.. ::E .... 1-

-·- TE-SV-1 .......... TE-SV-2

--- TE-SV-3

NOTE: DATA ARE QUALIFIED WHILE INSTRUMENT IS IMMERSED.

16q2~5~· --~~~----~~----~~----~~----7100~----~b-----~~----~17~5

240

Fig. 200 TIME AFTER RUPTURE (SEC) EGG-A-374

Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-1, -2, and -3).


----- TE-SV.-4 -·- TE·SV-5 ........ TE-SV-6


Fig. 201 Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-4, -5, and -6).

201~

w

"" :::> I< "" ...... 0-

~ 1-

...... <!I ...... 0

...... "" :::> 1-< "" ...... 0-

ffi 1-

--- TE-SV-7 -·- TC-;J\(-0 ····~ ... -~ TE~sv-9


loU~-----~~~~±-----~~---~~==~~~------~~----~~----~ -:l'5 50 175 TIME AFTER RUPTURE (SEC) EGG-A-375

Fig. 202 Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-7, -8, and -9).

280~--~~---,-~-~------r~-----r------~------,-----~,


--~ TE-SV-10 TE-SV-11

-·········· TE-SV-12 ...... .

160~------~-----~------~------~------~~----~~----~n-----~ -25 100 175

TIME AFTER RUPTURE (SEC) EGG-A-37€.

·Fig. 203 Temperature in blowdown suppression tank A-end thermocouple stalk (TE-SV-10, -11, and -12).

202

z -.... ..... ... ,.. ... ..... s ~

~ .....

z -..... ... ,.. ... ..... 0 -~ a -.....

''1.0-;~~b-~-~- -- --- - -···- --- ·-- ---.-----

:.t-+---1-,>~·· -+-+--+-+--+---+--+--f---+-J~~· . . dr~~: (i~· -

~ La

60.0

50.0

.. T

i

! I

I_ ~F'T"593 .LT -PI_ ~-B-t!3,3 ~o.o ~~~~~~~--~--~~._._._~~~--------~~------~

70/0

60.0

50.0

~o.o

0. 1 oo. __a_o_o_,_ ..3Jl.(L_ ~oo. 5oo. T.IME AFTU .. RUPTURE. (SEC\

Fig. 204 Liquid level in blowdown.suppression tank north end (LT-Pl38-33).

l.;"n~g~ \_T-:-_P_I38~-~~L -,

.... .. ... ... lit" r-'

taN! .,, rr I

-

I

i

j I I i

o.. 100. 200. 300. 400. 5(l0.

TIME AFTER RUPTURE (SEC) Fig. 205 Liquid level in blowdown suppression tank

south end (LT-Pl38-58).

203

';j -V'> c.

! ~.J

"" => ~ .... "" c.

~ -V'> c.

.... "" => V'> V'> .... "" c.

60.

50.

1+0.

30.

20.

10.

o. o.

J l

I 1/

'\,11'1

r I '\.

If If

:

, .... , .•. ....... ~.~

-·.

' f"""o, ....... /

1\ ~

\ / ' \

I i I I l ' I

!

'!_tll'lo!'"d. ·~

100.

~ ~ I ~ I I I I

POTTI'tl558 P£-SY-003

-l.o-""

\ '\. ··-- -

~

' /

""' I .......

""' II'

"'

'

NOTE: DATA INITIAL VALUES ARE -ADJUSTED TO 0 PSIG. -

I --

200. 300. 1+00. 500. TIM[ A~T[R RUPTURE (S!C)

Fig. 206 Pressure in blowdown suppression tank across from duwnCOirn::r· 1, 157.5n (PE-SV-3).

60.

50.

'+0.

30.

20.

I 0.

0.

o.

-

I

I 1/

:

I" I \.

IT

: '

'

Fig. 207

"

T T T T T I T T T I T

POTTft6&1t PE-SV-026

!

'

I -"" I I--' ..,

II v I I / \ '

I \ 1/ i ! \.I +-' ' --p.. \ I --' I . I

I I I """'"' I i ! "'-- /

' i I I I

I ' I I I

NOTE: DATA INITIAL VALUES ARE -ADJUSTED TO 0 PSIG. -

"T

100. 200. 300. 1+00. 500.

TIME AFTER RUPTURE (SEC) Pressure in blowdown suppression tank bottom 54.3 in. south of downcomer 2, 180° (PE-SV-26).

204

<!I ~· "' a..

.... "' :::>

"' "' .... "' a..

<!I -"' a..

.... "' :::>

"' "' .... "' a..

'

eo.

50.

'+0.

30.

20.

I 0.

o. 0.

60.

50.

'+0.

30 .

20.

I 0.

0.

o.

I . • POTTI1668 PE-SV-0'+3 a POTTI1669 PE-SV-Oiflf

1--

• ~ " ..

1!1.. "'I! ..,. -"'-1 -.. ""' /

'/' /. \\.. .... 1- \. .,.,...

\'-" ::"'.. _/ :;..-

"' ......... l!o ../ v -1 ... """ 1r~

~ uo... ...... r1 '-· --··· ........... ..... . ,.,_ --

NOTE: DATA INITIAL VALUES ARE --

"""- ADJUSTED TO 0 PSIG. --J

100. 200. 300. '+00. TIME AFTER RUPTURE (SEC)

Fig. 208 Pressure in b1owdown suppression tank bottom under downcomer 2 and under downcomer 3, 180° (PE-SV-43 and -44).

~~~... • POF'TI1615 PT-P138-055 11' ~" 1 a POF'TI16U5 PT-P138-056 • -" ~ .. ._Ill., ~ rL

....... ..... -..... ../ .,. '7' '\\

u .. ~

rr ~ /

"1lii.: r-o... ~

"' ~ /A ~ ..... !loL ....... M

.J .... ... , """

-

"'"

NOTE: DATA INITIAL VAlUES ARE -ADJUSTED TO 0 PSIG. -

I

100. 200. 300. lfOO. 500. TIME AFTER RUPTURE (SEC)

Fig. 209 Pressure in b1owdown suppression tank top 48 in. north of downcomer 1 and 49 in. north of downcomer 2 (PT-P138-55 and -56).

205

~

1.&.

<.!1 ..... e ..... !5 ..... < a: ..... <>. %: ..... .....

~ <.!1 ..... e ~ :::> I

~ ..... <>. E ..... .....

250. • TETTI1658 TE-SV-001

IJlAI ... a TETTI1659 TE-SV-002 ,., ~

... ~ I"'" 6 TETTH660 TE-SY-003 ,.,.., .,. l I I I I I I I I ~ ~ (Y Iff 'l I 225.

~ 1,_ M I I I I I I I I I ,., ., NOTE: DATA ARE QUALIFIED WHILE

• ll. INSTRUMENT IS IMMERSED •

200 .

4 175.

150.

0.

275.

250.

.225.

200.

175.

o.

a lN ~

I ll .. " ~ ~ 11 L I '1ft: ... ~ ,. ~ ~J' ~ r_~ ~ ~ • ~"Y fll it...

.,.....

'..:; .... " -100. 200. 300. lfOO. 500.

TIME AFTER RU~TURE I~£Cl

F·ig. 210 Temperature 1n b1owdown suppression tank B-end thermocouple stalk (TE-SV-1, -2, ~nd -3),

• TETTI1661 TE-SY-00'+

a TETTI1663 TE-SY-006

ru. lllo.. .... 1 -- !'-.... - .. ll'r ._

, __ ... -~ ~ •• .~~~~ L.A. •"-

Jj .. • I, Lnn'!Lt I" Ill ,. l ' r.ll 4 ' . •

·--

'

NOTE: DATA ARE QUALIFIED WHILE INSTRUMENT IS IMMERSED .

I I • 100. 200. 300. &tOO. 500.


Fig. 211 Temperature in blowdown suppression tank B-end thermocouple stalk (TE-SV-4 and -6).

206

..... <.!1 LLI e LLI

"" :::> ..... < "" .. LLI 0. E LLI .....

r

C!7!5.

C!!50.

C!C!!5.

C!OO.

17!5.

o.

TETTH&e7 TE-SV-010

F# -"1111. 1-""""' ""' ~ ~

-

..


I I I I I I I I I

100. 200. 300. !tOO. '!500. TIME AFTER RUPTURE (SEC)

Fig~ 212 Temperature in blowdown· suppression tank A-end thermocouple stalk (TE-SV-10).

207

~- . '7 .

THIS PAGE

WAS INTENTIONALLY

LEFT BLANK

4. TEST Ll-3 COMPUTED PARAMETERS


209

60 58 !)t)

54 52 50 48 H. 46 AA 44 .A 42 .A 40 AS

- 38 :.

_ .. ' .... :, :..- •• <dl !-}~ ..

. ( .:.~.

H = Homogeneous

S = Stratified

A= Annular

I = Inverted Annular

c:.., 36 s ~ 34 s ..8 32 .:::. 30 >- 28 !::::; 26 ~ 24 ~ 22

20 18 16 14 12 10 8 b 4 2 0

0

s. SSI.

II ·r ·u

·r ir

IS ·Isss

SSSSSASSS S ~SSSSSSSSSSSSSSSSSSISSSSSSSSSSSSS~

10 20 30 40 50


Fig. 213 Flow regime and average density in broken loop co 1 d 1 eg.

210

60

60 58 56 !54 52 50 48 H HH 46 .H ..

44 ss 42 ·sssss 40 s

.-. 38 ss ~ 36 ~ 34 ..8 32 .:::. 30 i: 28 ...... 26 . ~ 24 ~ 22

20 18 16

. 14 12 10 8 6 4 2 0

0 10

. ~

. . s

s. s. s~

~ .S s:

H = Homogeneous

S = Stratified

A = Annular

NOTE: Flow regime should be stratified after rv 24 seconds .

. s s s ·s ·ss· .AAA

AAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAS

20 30 40 50 60


Fig. 214 Flow regime and average density in broken loop· hot leg.

--""-- .

211

60 58 66 54 52 50 48 HH. 46 HHH, .H. 44 H A 42 40

M 38 .jJ 36 .,_ ......... 34 E .u 32 ..-- 30 >- 28 1-....... 26 (/)

z 24 LLJ Cl 22

20 A 18 16 14 12 10 8 6 4 ? 0

0

AAAAA AAAA·AAAAS

H = Homogeneous

S = Stratified

A = Annular

NOTC: rl ow rt!~f"i rm::! s huu 1 d be stratified after '" 18 seconds.

ss. s ·s

·!J. ·. ASAS AAAAAAA:; 'sssA. __ . .A.

AAAAAAAAAAASAAAAAAAASAAAS A

10 20 30 40 50


Fig. 215 Flow regime and average density in intact loop hot leg.

212

60

. ~ c:c _. .._ ;;J .... c:c

>-<>-_. < :J: .... :z ....

~ c:c _. .._

1250.

1000 .

750.

500.

-10.

1250.

i= I 000. c:c

750.

500.

-10.

-

EN81(007!» PE-BL-1-EN ..

J\ r- -~

' ,A

r " I"' II .I ~

If l ~w ~

V\\ . l

r_ t'

I / NOTE: DATA BEFORE T~ ARE INVALID

./ DUE TO SATURA ED FLUID ASSUMPTION. -

o. 10. 20. 30. '+0. 50. . 60. 70 .


Fig. 216 Enthalpy in broken loop cold leg.

_E_N_BK0078 PE-BL-2-EN ····-·.

fV ~ .. I~

\ ll .aL '-..tAl 'I ~r

., r

~ I'

1'\J J_ NOTE: DATA BEFORE Ty ARE INVALID

DUE TO SATURA ED FLUID ./ ASSUMPTION.

- -··-- ··- ··-

o. I 0. 20. 30. '+0. 50. 60. 70.


Fig. 217 Enthalpy in broken loop hot leg.

213

:::;: co -' -:::::> .... m

>-CL. -' < "' .... :z ....

~ co -' -:::::> .... co

,.. CL. -' < ::t: 1-:z ,,,

1250.

1000.

750.

500.

250.

1250.

1000.

750.

500.

-10.

ENPK0083 PE-PC-1-EN , ..

L l -·

1 I . r--~

I .. - - tlOTt: DATA ARE INVALID PRIOR TO

Tp DUE TO SATURATED FLUID AJSUMPTION. DATA WERE CALCULATED USING CHORDAL DENSITY FRDr~ DE-PC-lB.

o.o 10.0 20.0 30.0 ltO.O 50.0 60.0 70.0

TIME A.I"TER RUPTURE !SEC l

Fig. 218 Enthalpy in intact loop cold leg.

ENPK0081t PE-PC-2-EN .. - ··-

r wr h. ... a.

I •• ··~ l,4 1.

~ IMtN Ia

, ~,IL.t J' I . u ~

11'

I

•• - ---

ll \~ NOTE: DATA BEFORE Ty ARE INVALID

DUE TO SATURA ED FLUID ASSUMPTION.

o. I 0. 20. 30. ItO. 50. 60. 70.


Fig. 219 Enthalpy in intact loop hot leg.

214

~ "" .... ·-:::J .... "" >-0.. .... <( X .... :z .....

u ..... VI

I .., .. .. .... .... ....... ::E

"" .... ..... ~ .... 0 >

15 .... VI >-VI ....... 3: 0 .... .... VI VI

~

1250. tNrkooos rc ·- rc- 3-.:..tN

aj

tv• , 1000. ~

IJ ~·

750.

I NOTE: DATA BEFORE Ty ARE INVALID

DUE TO SATURA EO FLUID

500.

-10. o.

~

10.

I

20. 30. '+0. TIME AFTER RUPTURE (SEC)

,. ASS~MPTI 0~. I

50. 60.

Fig. 220 Enthalpy in intact loop at steam generator outlet.

!5.0 F'E81<0'+!51 F'E-1'1E-BL-001

'+.0

3.0 -. NOTE: REFER TO TEXT IN SECTION v ON MASS BALANCE. DATA

2.0

\ Ia I ARE IRRATIC BEFORE Te

J\t:!\, \A a AND AFTER Tg + 50 SE 111A. DUE TO DIVI ION BY

' NUMBERS NEAR ZERO.

II .... w ••

VI I .0

11 r "1 II

la u ~ u ~

o.o o.o 10.0 20.0 30.0 '+0.0 50.0 60.0


Fig. 221 Mass flow rate per system volume in broken loop cold leg calculated from FE-BL-1 and ME-BL-1.

215

70.

' \ \A

1

70.0

u ... VI

I <"'> .. .. ...... ..... ...... ::E 0:0 -'

... !!5 -' 0 > ::E ... ...... VI >-VI ...... :X 0 -' ..... VI VI < ::E

u ... VI

I <"'> .. .... ...... ..... ...... ::E

"" -'

... !§ -' 0 > ::E ... ...... VI ,_ VI

~· 0 -' ..... VI VI < ::E

5.0 F'RBIC0002 ttE-OE-BL-001

'+.0

!.0

It

'" .. 2.0 ' V\

l NOTE: REFER TO TEXT IN SECTION 1\ua, A.. ON MASS BALANCE. DATA

1 . 0

' '~ VALUE PRIOR TO T IS \a' DUE TO SMALL INS9RUMENT "'\ft OFFSET.

"""-"""" ·v -o.o

o.o 10.0 20.0 30.0 'tO.O ~o.o 00,0 7Q.Q TIME AFTER RUPTURE (SEC)

Fig. 222 lv1ass flow rate per system volume in broken loop cold leg calculated from DE-BL-1 and ME-BL-1.

5.0 F'OBF'0'+51 F'E-OE-BL-001

'+.0

3.0

2.0 I. ·~

1 . 0

1.. NOTE: REFER TO TEXT IN SECTION \...,. ON MASS BALANCE. ,..._ " ~

""'lA

o.o o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0


Fig. 223 Mass flow rate per system volume in broken loop cold leg calculated from DE-BL-1 and FE-BL-1.

216

u ... "' I .., .. .. 1-...... ....... ::E a:> ...J

... !!5 ,J 0 >

ffi ...... "' >-

"' ....... :z 0 ...J ......

"' "' ~

;:; ... "' I .., .. .. 1-...... ....... ::E a:> ...J

.... !5 ...J 0 > ::E ... 1-

"' >-

"' ....... ~ ...J ......

"' "' ~

5.0

... o

3.0

a.o

1.0

o.o -10.

L.a....

~

o. 10.

....

\

' .... " ~ ~

C!O. 30. 'tO.


FTBICOOOC! POE-OE-&L-01

NOTE: REFER TO TEXT IN SECTION ON MASS BALANCE.

---1 - I I 50. eo. 70.

Fig. 224 Mass flow rate per system volume in b·roken loop cold leg calculated from DE-BL-1 and PdE-BL-2.

1.0 FRBKD003 HE-OE-BL-OOC!

0.8 L 9\,. ... ""'\: 1...

' 0.6 \ \

' \ \

0.'+ II.. \A

a

0.2

]\ NOTE: REFER TO TEXT IN SECTION f I

r,1 \1 ON MASS !lALANCE.

' ' "' .• 1111 a 1""'- ~ .r , ....... o.o .... Ill I "'--

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0 TIME AFTER RUPTURE (SEC)

Fig. 225 Mass flow rate per system volume in broken loop hot leg calculated from DE-BL-2 and ME-BL-2.

217

u ... II')

I

"" ... ... ..... "-....... ::E

"" ...J

... ~ ...J 0 > ::E ... ..... ~ ~ ~ ...J "-II') VJ

~

u ... '1 "" ... ... ... "-...... ::E

"" ...J

... ~ ...J

~

ffi ..... "' >' "' ...... 2 • ...J "-II') VJ

~

1.0 ~08~0'+52 ~E-OE-BL-002

'

o.s

o.e '\ ~

'r'l O.'+ ... I -

111 \ II r I NOTL R£FER TO T~XT IN 5[CTION

o.a l I II 'I ON MASS BALANCE.

I

' \J "\ ·- "'\j ~ o.o o.o 10.0 20.0 30.0 '+0.0 50.0 eo.o 70.0


Fig. 226 Mass flow rate per system volume in broken loop hot leg calculated from DE-BL-2 and FE-BL-2.

1.0

o.a

o.e

0.'+

o.e

o.o -10.

l ....

l!l~ o.

r-4\ ~ L~ -

10. 20. 30. '+0. TIME AFTER RUPTURE (SEC)

,., --- ·0'2 r-w.· ... -

NOTE: REFER TO TEXT IN SECTION ON MASS BALANCE. DATA VALUE PRIOR TO T IS DUE TO SMALL INS~RUMENT OFFSET.

-

50. 60. 70.

Fig. 227 Mass flow rate per system volume in broken loop hot leg-calculated from DE-BL-2 and PdE-BL-1.

218

u ..... V'>

I .... .. .. 1-..... ...... ::E

"' _, ..... ~ _, S! ~· 1-V'> >-V'> ...... 3 0 _, ..... V'> V'>

~

u ..... V'>

I ..., .. .. 1-..... ...... ::E

"' _, ..... ; _, 0 >

ffi 1-V'> >-V'> ......

·3 0 _, ..... V'> V'>

~

3.0

l ... ·-· ~&If F'E -HE~~ ;~O I_ r-

J\ ,a a. " \f rtvr l 2.r' ' 1

\

' ~ \. "1

1.0

o.o

!all f\A NOTE: REFER TO TEXT IN SECTION l1j • 91 All\

ON MASS BALANCE. DATA .. a ARE VALID ONLY UNTIL To v ,_V\ + 8 SEC; DATA AFTER

T9 + 8 SEC ARE AFFECTED B THE TEMPERATURE

I""\_ SENSITIVITY OF ME-PC-1. ~

..

V\ .&

rt M ll

-1.0

\ J ~ ... ~ \ II ' -

o.o I o .. 0 20.0 30.0 ltO.O 50.0 eo.o 70.0


Fig. 228 Hass flow rate per system volume in intact loop cold leg calculated from FE-PC-1 and ME-PC-1. ·

3.0

2.0

"V

I . 0

o.o

-1.0

Fig: 229

F'QPK0083 PE-PC-1-F'Q

" \ l :-~~

\ s;.-·· ·,.~

\ IVVV '

1 \.

I"'

NOTE: REFER TO TEXT IN SECTION ON MASS BALANCE. DATA PRIOR TO T ARE NOT VALID DUE Yo THE SATURATED FLUID ASSUMPTION.

o.o 10.0 20.0 30.0 ltO.O 50.0 80.0 70.0


Mass flow rate per system volume in intact loop cold leg calculated from FE-PC-1, PE-PC-1, and DE-PC-1~.

219

~ VI

I M

t ~ ... ...... E

"" ...J

~ ...J 0 > E w tli >-VI ...... :31: 0 ...J ... ~ ~

'-' w

"' I M ... ... ~ ... ...... E "'l

w ;5 =' 0 .... ~ ~ VI >-VI ...... :31: 0 ...J ... VI VI

~

3.0

"' F'RPKOOO'+ HE-OE-PC-001

,A I ~ V' 'VVJ l

2.0 \ \

~

-"'U"'"'

l ........ _.

-~

1.0

" ··-··~ .... ·- .... - .... -~

____ ,

' \. ....... ~ ~ ~

o.o NOTE: REFER TO TEXT IN SECTION

ON MASS BALANCE. DATA WERE CALCULATED USING CHORDAL DENSITY FROM

-1.0 DE:PC-1B.

o.o 10.0 20.0 30.0 '+0.0 !50.0 60.0 70.0

TIME AfTER RUPTUR[ (SEC)

Fig. 230 Mass flow rate per system volume in intact loop cold leg· calculated from DE-PC-lB and ME-PC-1.

3.0 F'Of)f:"0'+5'+ F'E-DE-PC-001

r\ •A " _a -"V lfV'' l

2.0 \

' ' -~·

I. 0

\ \..

vow- I""\. o.o NOTE: REFER TO TEXT IN SECTION

DN MASS BALANCE. DATA WERE CALCULATED USING CHORDAL DENSITY FROM DE-PC-1B.

-I. 0

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0


Fig. 231 Mass flow rate per system volume in intact loop cold leg calculated from DE-PC-lB and FE-PC-1.

220

u ... II)

I .., .. .. ..... ... ....... ::E ... ~

... !!!; ~ 0 >

ffi ..... II)

>-II) ....... :X 0 ~ ... V) V)

~

u ... V)

I .., ... .. ..... ... ....... ::E ... ~

... !i ~ 0 >

ffi ..... V) ,... VI ....... :X 0 ~ ... VI V)

~

3.0 c-· f"QPI(OOG't ~-PC-2-FO!

2.0 lA .A

..~

rv. 1.0

o.o \-. """ NOTE: REFER TO TEXT IN SECTION ·- . ·-····-··· -· ON MASS BALANCE. DATA

PRIOR TO T ARE NOT VALID DUE 9o THE SATURATED FLUID ASSUMPTION.

~ l. 0 I .

o.o 10.0 20.0 30.0 &tO.O 50.0 80.0 70.0


F1g. 232 Mass f.low rate per system volume in intact loop hot leg calculated from FE-PC-2 and P~-PC-2.

3.0 FO?FO&t55 FE-OE-PC-002

A lA .. ... ,,. ... 2.0

. J''lt

l. 0

o.o t ""' -

NOTE: REFER TO TEXT IN SECTION ON MASS BALANC~.

-1.0

-10. o. I 0. 20. 30. &tO. 50. 80 .. 70.


· ·. Fig. 233 Mass flow rate per system volume in intact loop hot leg calculated from DE-PC-2 and FE-PC-2.

221

(..) ...... V>

I .., .. • ..... ..... ...... :E a::o -'

~ -' 0 > :E ...... ..... V>

~ ...... ~ -' ..... V> V>

~

(..) ...... V>

I .., • .. ..... ..... X' a::o ~ ...... !5 -' i z: !:!! V> >-V> ...... ::0: 0 -' ..... V> V>

~

3.0 ~QPK0085 PE-PC-3-~Q

2.0

~ ~ ~~ ~ . l . 0

' ' '

' o.o \.: .. NOTE: REFER TO TEXT IN SECTION

ON MASS .BALANI>E. DATA PRIOR TO T ARE NOT VALID DUE ~0 THE SATURATED ; FLUID ASSUMPTION .•

···I . 0 ..

o .. o I 0. 0. 20.0 30.0 a.o.o 50.0; oo.o TIME AFTER RUPTUR~ (SEC)

Fig. 234 Mass flow rate per system volume in intact 1 oop, st_eam generator outlet calculated from FE-PC-3, PE-PC-3A, and DE-PC-3 ..

70.0.

3 .. 0 ~RPK0006 HE-OE-PC-003

AI lal~ I"LJII ~~

2.0 1 Ill

,- ~-·,- .. .. . .. . --

'(

1 • n ·". . ---- - ·--- ~ ----- -----· . ..

\ ~ I-.

o.o

NOTE: REFER TD TEXT IN SECTION ON MASS BALANCE.

-1.0

-10. . o. l 0 . 20. 30. ItO. 50. 60. 70.


Fig. 235 Mass flow rate per system volume in intact loop steam generator outlet calculated from DE-PC-3 and ME-PC-3.

222

u ... V'l

I .., • • 1-.... ...... ::E

"" ..J

... !i ..J 0 >

C5 1-V'l >-"' ...... 3 0 . ..J .... "' V'l

~

~ "' I .., • • I-.... ...... ::E

"" ..J

... !i ..J 0 >

C5

3.0 -f"oPf"Dif58 F'E-OE-PC-003

l1a r '\ I -

2.0

\ -

I. 0

o.o i\..._

- ' ........

NOTE: REFER TO TEXT IN' SECTION ON MASS BALANCE.

-I. 0

-10. o. 10. 20. 30. ItO. 50. eo. TIME AFTER RUPTURE (SEC}

Fig. 236 Mass flow rate pe·r system volume in intact loop steam generator outlet calculated from DE-PC-3 and FE-PC-3.

0.3

0.2

70.

:;:; 0.1 >V'I ...... ~ ..J .... V'l

"' ~ 0 1---"' NOTE: CALCULATIONS WERE NOT

PERFORMED BEYOND TO + lB SEC. ·

-0.1L------L------~------L-----~-------L------~------L-----~ -10 0 10 20 30 40 50 60 70

TIME AFTER RUPTURE (SEC} EGG-A- 505

Fig. 237 Mass flow rate per system volume in intact loop pressurizer calculated from LT-Pl39-8 and PE-PC-4.

223

:E 0.. rx:

c ...... ...... "· en 0.. :E: :::> 0..

~ rx: ~

c ..... ...... 0.. en 0..

~ 0..

2000 .

1!500.

1000.

eoo. ·10.

..

..

o.

\.

' " .. '-. ~

""' •

10.

e PCP-1-F o PCP-2-F

lk

' ~ ..... - r--

'

ao. 30. . 'tO. . .so. TIME AfTER RUPTURE (5EC}

Fig. 238 Pump speed, electrical, in intact loop primary coolant pumps 1 and 2 •

. 2000. e PCP-1-F o RPE-PC-1

!'- ·---- .. ··-· W\.

1!500. ' "" """ .,.,_

·1000. ..._,_ llr..

.. -- .. .. I'\..

!500. ,._

....... .... lliloL ~ ...

....... ... o.

..,._

-!500.

-10. o. 10. 20 .. _30. 'tO. 50._· 60. 70.


Fig. 239 Pump speed, electrical and mechanical, in intact loop primary coolant pump 1.

224

if IX

c LU LU 0..

"' 0..

!i 0..

2000.

1500.

1000.

500.

o. -to.

~-- -- ~

~ ""\ ..

o.

\.

' ... ' .. 1111..

tO.

e PCP·2-F --a:~- o RPE-PC-2 ·-- ----

-

111. ~ - _,...

~

~ .....

~ ..... .... .... ~ ... ~-

I

I

20. JO. 'tO. eo. 80. 70.


Fig. 240 Pump speed, electrical and mechanical, in intact loop primary coolant pump 2.

1.5 e PCP-1 SLIP c PCP-2 SLIP .. ··- ,-·-

" _. -II ~ ""' .........

•

1.0

0.5

o.o ..

-o.e -ao. o. ao. 20 . . 30. 'tO. so. ao. 70.


Fig. 241· Pump motor slip in intact loop primary coolant pumps 1 and 2.

225

"' ...... 3 0 0.. ...... "' "' 0

"' -' ex: ~ "' f-u ...... -' ......

"' ...... ::.: 0 0.. ...... "' "' 0

"' -' ;3 ~

"' f-u ...... -' w

-' ex: f-0 1-'-

125.0 • PCP-I o PCP-2

100.0 ~ •• ~ -:1..

Ia.

75.0 .Ia

1\. I'M

• 50.0 •

~\

25.0 • ~ o.o ~

-25.0

-10. o. I 0. 20. 30.


Fig. 242 Pump motor inidividual electrical horsepower in intact loop primary coolant pumps 1 and 2.

200.0 ~ ....

' 1!50.0 ' ll u 'I

100.0 ''l

!50.0 Ji ~ ~ -....

" -o.o ~

-!50.0

-10. o. 10. 20. 30.


Fig. 243 Pump motor total electrical horsepower in intact loop primary coolant pumps 1 and 2.

226

'+0.

'+0.

"" LLI ..,. 0 ~ LLI V>

"" 0 :I:

"" LLI 1-<C 3 _. <C 1-0 1-

>-L) z ~ L)

......

...... LLI

~ :i:

2

·100.

ao.

eo.

'+0.

20.

o. -1o.o

II 1

IIU II

II ' lL MJJr

I

..

, .. 1/ I

r.J. -,u

, o.o 10.0 20.0 30.0


Fig. 244 Pump total water horsepower in intact loop primary coolant pumps 1 and 2.

I. 0

o.e

0.6

O.'+ n

""' .I.IW ol ... 1U I 1.111

T

ll L

0.2 [1, .111'1

"I" \I I

..o.o

-.

I ~ o.o \o.

1ft r

-0.2 __IIL_ft I • I

-10.0 o.o 10.0 20.0 30.0


Fig. 245 Pump combined efficiency in intact loop primary coolant pumps 1 and 2.

227

'+0.0

<!> -VI c..

w

"' :::;> VI

"' w

"' c..

>-I--...J ...: ::::. 0

8 I--c I-V>

3.

2.

f--·- .....

I

0. --T

"""" I····

I . I II ~ I .a I I -•-a

-I ...

I'' IT ''T TT ,..., T

I -. 'I

1·----·- I -2.

-3.

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0

TIME AfT(R RUPTUR[ (5[C)

Fig. 246 Pressure, closure, in intact loop (filtered to 4 Hz).

1.0

' 0.8

o.e

.~: , O.'t

J~ 1111

tl .,_ r• ~

..

' l/ ~

0.2

...

---;-:~

"fWII """"T

70.0

~,..

1/ v QIIICD0'75 PE-IL-1-QS o.o

o.o 10.0 20.0 30.0 ltO.O 50.0 eo.o 70.0


Fig. 247 Static quality in broken loop cold leg.

228

>" ::; -' :§ 0'

~ 1-

~ VI

>-1---' < ::::>. 0'

~ 1-

~ VI

1.0

0.8

-o.e

o ...

0.2

o.o -ao.

1.0

0.8

0.6

0.'+

0.2

-

I

\ II .., \ ..Jl_.:..~ AI

V' ., 1""'"11 .. • ·-

N

/ ~ ' I I

, ,. P£-a.-e~os

o. ao. eo. JO. ItO. so. . eo. 70.


Fig. 248 Static quality in broken loop hot leg.

!r QSPK0083 PE-PC-1-SQ

-J

·-

1- ~ NOTE: DATA WERE CALCULATED

} USING CHORDAL DENSITY FROM DE-PC-lB. . I I

a.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0


Fig. 249 Static quality in intact loop cold leg.

'

229

>-1--...J < ::> 0

u ,: ~ "'

>-1--..... ~ 0

" 1-< 1-V)

1.0

o.e

o.e M~ O.lt ......

" ~ II ·w !1 .. fi

fl. ~ ,.. "\ atl rr

"J ... o.a

...., :-2-SQ

j -o.o o.o 10.0 20.0 30.0 !50.0 eo.o '70.0

TIME AFTER RUPTUR~ (SEC)

Fig. 250 Static quality in intact loop hot leg.

1.0

:N II I II I I I L 1~008!5 ~-~-3~~

o.e I

o.e ··- II

o ... ~

j I

0.2

I o.o J

o.o 10.0 20.0 30.0 ltO.O !50.0 eo.o '70.0 TIME AFTER RUPTURE (SEC)

Fig. 251 Static quality in intact loop at steam generator outlet.

230

>-!::: ...J < ::::> CT

::0: 0 ...J ...

>-!::: ...J < ::::> CT

::0: 0 ...J u.

I. U

0.8

o.&

o ...

0.2

o.o -10.

I. 0

0.8

0.6

0.'+

0.2

o.o -10.

"' ff' ..... ";

.)'

~~ J .N ·vy.

-OGBKD075 PE-BL-1-QG . -- . -=--- ~- ..

• ~ I

jl L

,r

o. 10. 20. 30. ItO. 50. 60. 70.


Fig. 252 Flow quality in broken loop cold leg.

r I~ .. 1-\ • l. &;'-.& " .. aa

~ .,

""' ""l"' r

., QG8K0076 PE-8~-2-QG

A.

\j

J II'

o. I 0. 20. 30. '+0. 50. 60. 70.

TIME AFTER RUPTURE !SEC)

Fig. 253 Flow quality in broken loop hot leg.

231

1.0

o.a

~ o.e -...J c( :::> 0'

7. 0 ...J .... o ...

>-!:; ...J c( :::> a ~ ..J ...

0.2

o.o

1.0

o.s

o.e

0.'+

0.2

o.o -10.

r

11 OOPKDOIJ P£-PC-1·00

-t----

I ----+ ....

i i

. -- --· I ---~--I- -

l .,....

I NOTE; DATA WERE CALCULATED

] USING CHORDAL DENSITY FROM DE-PC-18.

o.o 10.0 20.0 JO.O '+O.o 50.0 eo.o 70.0

TIME AFTER RUPTURi (SiC)

Fig. 254 Flow quality in intact loop cold leg.

~r, ~~ I

' "' rJ" 'IIIII"''

~ ~ ~ ' ~ ,. QGP1<008'+ PE-PC-2-QO

I y ' ..

~

o. I 0. 20. 30. '+0. 50. 60. 70.


Fig. 255 Flow quality in intact loop hot leg.

232

>-t:; ...J < :::::> 0

3 0 -' ...

... <!> ... e ... a: :::::> !;:( a: ... Q.

Q ......

1.0

aN QOPK0095 PE-PC-3-QO

0.8

o.s

0.'+

0.2

o.o -10.

1

o.

I ~

.I I

I 0.

-

. -

-- --

20. 30. '+0. 50. 60.

TJME AFTER RUPTURE (SEC)

Fig. 256 Flow quality in intact loop at stea~ generator outlet.

700. • TE8T0178 TE-SL-001

' -- -D TE8C0178 TE-PE-SL-1 \L 1-3 COPERA:

I~ ~

600 . NOTE: DATA DISPLAY HOT WALL

70.

EFFECTS AFTER ~ T0 + 53 SEC .

500.

'+00.

300.

-10.

1-

-.

o. 10.

~r-.,.

~ ~

" ~ I' ....,

1'-. -t-..

20. 30. '+0.


_..A _,... ,. -.... J.

50. 60.

Fig. 257 Saturation temperature in broken loop cold leg overlaid with TE-BL-1.

233

--

-

70.

.... <!! ... "" ... "" :::> ,_ cC a: ..... 0.. ::E .... ,_

....

..!J ... e ... "" :::> ,_ cC

"" ... 0.. ::E ..... t-

700.

600.

500.

'+00.

300.

-to.

Fig.

700.

·-600 .

1-

500.

--'--f-·

'+00.

300.

-10.

-

-

o.

258

-

o.

. ~ .. TEBTO I 7g"· TE -BL- o"o2 I .. ·a TEBCD179 TE-PE-6L-2,LI-3 COPERA

.

--- --

NOTE: DATA DISPLAY HOT WALL EFFECTS ---AFTER~ T0 + 40 SEC. ---- .. --- ..

r-.. ~--· ·--~ -·

" ._ lx ...... .. v .,__ -- I-'"'

r-...~ .......

""' 1.0. 20. 30. '+0. 50. 60. 70.

TIM~ ArT£R RUPTURE (5[C)

Saturation temperature in broken overlaid with TE-BL-2.

loop hot 1 eg

•

1

TEPTOIBS TE~PC-001 l I

0 T~P.C0185 TE-PE-PC-lill-3 COPERA

-·

NOTE: DATA DISPLAY HOT WALL EFFECTS -

~ . AFTER ~ T

0 + 30 SEC . -

~

"'Ia. ~ ' [',

a..• ..._ " -~ -X - -~ ·-

....,~

10. 20. 30. '+0. 50. 60. 70. TIME AFTER RUPTURE (SEC)

Fig. 259 Saturation temperature in intact loop cold leg overlaid with TE-PC-1.

234

LL

<.!) ...., e ...., 0:: ::::> ..... <( 0:: ...., 0.. lE: ...., .....

~ <.!) ...., c

...., IX ::::> ..... <( 0:: ...., c.. lE: ...., .....

700. • TFPTOiAS "''E:_:PC-OUc I 0 TEPC0186 TE-PE-PC-2 Ll-3 COPERA - ·- --·-· ·,--·

600.

500 . ~

"-"" i'-

" 400. ' ' " '' ... ____ .• ···-··-r...

..... ~

300.

-10. o. 10. 20. 30. 40. 50. 60.

. 700.

600.


Fig. 260 Saturation t~mperature in intact loop hot leg overlaid with TE-PC-2 .

• TEPT0187 TE.:.PC-003 I o TEPC0187 TE-PE-PC-3A;L1-3 COPERA

-

.... ~ .. -

70.

- NOTE: DATA DISPLAY .HOT WALL EFFECTS -

500 .

'+00.

300.

-10. o. 10.

'"' AFTER ~ T0 + 30 SEC .

"-'I

I"'--"1:1 .A... ...,..

'"\-.. ~ ~ ---..

l ~ ~ ~

20. 30. 40. 50. 60.


Fig. 261 Saturation temperature in intact loop steam generator outlet overlaid with TE-PC-3.

235

-

-

70.

;:

"" w c

w

"" :::> ,. ... "" w

" 2: w 1-

;: .., w c

~ :::> ,... ~

"" w c. ~ ....

700.

GOO.

'!>UU.

'+00.

300.

200.

-10.

. ..

-- - --

.. .. .... .... .. --~ ...

o.

. .. ...

-- -

-

··- ... -

10.

• TECTO'+BO TE-CS-001 I I I

0 TECCO'+BO TE-PE-CS IAL.I-3 COPERA

i -- --·---·

I - . ·-· -··-- ·--·· NOTF: flEVTATION IS DUE TO A "' 4°F

TEMPERATURE OFFSET IN TE·CS·l

.... ~ AT T

0 •

Ia. ~ .. ~

"" ""'"' a..u.

"'' '& ~ 1-

" I'-. ~

'b.. ... . ... . .... --- ·····-·- -- ~ "V"

20. 30. '+0. 50. 60. 70.


Fig. 262 Saturation temperature ~n r~act~r ~essel core simulator instrument stalk overla1d w1th IE-C~-1.

700.

600.

500.

'+00 .

300.

200.

-10.

1--

f-·

1---t-

.

... -..

o. I 0.

.. I . T T r • TEOT0218 TE-IST-009 I I I

0 TEOC0211 TE-PE-IST-IA Ll-3 COPERA

-

r-.... !'Is.

-..;,

""' ..... ''-. ..

"""-1~

....... ID-._ ..........::

20. 30. '+0. 50. 60.


Fig. 263 Saturation temperature in reactor vessel downcomer instrument stalk 1 overlaid with TE-lST-9.

236

""'

70.

La~

<.!> .... e w a:: ~ ~ < c< .... 0.. ::0:: .... ~

:z 0 -~ u < c< ... c -0 >

700.

600.

500.

'+00.

300.

-10.

1-~

i•

I

~

-N<O- '"' ........ ..

0. 10.

• TEST0231 TE -25 T- 009· I I I

' 0 TESC0519:E-PE-2ST-I~LI_-3 COPERA

·- ........ "

~ ~

--1"- ' .. ~ -' 11

" ~~ ~ 20. 30. '+0. 50. 60.


Fig. 264 Saturation temperature in reactor vessel downcomer instrument ?talk 2 overlaid with TE-2ST-9.

1.0 ~

,.......

70.

7 VDBICDO'N P£-81.-1-VF' o.e

J ~

I o.e

I I

o ... ..

J 0.2

) ~

o.o o.o 10.0 20.0 JO.O ltO.O 50.0 eo.o 70.0

· TIME AFTER RUPTURE (SEC)

Fig. 265 Void fraction in broken loop cold leg.

237

:z 8 1-u < a:: .... c -"" >

:z 8 1-u < a:: .... e 0 ::-

1.0

o.e

o.e

o ...

0.2

o.o -ao.

1.0

o.e

0.6

Q.lot

0.2

o.o

!\.~ r VD81C0071 PE-k-2-VF

.. ......,

J

I

~ ~ ..

/ .I

o. 10. 20. 30. 50. eo. '70.

TIME AFTER RUPTURE (SEC}

Fig. 266 Void fraction in broken loop hot leg.

M') VDPKD083 PE-PC-1-VF

l~ ~ rv A.

I - ~·

I i I i

I I I ! I j i

I I

i i '

i I I ·r-

I

I NOTE: DATA WERE CALCULATED USING

}!I I CHORDAL DENSITY FROM DE-PC-lB.

I I I I I I

o.o 10.0 20.0 30.0 '+0.0 50.0 60.0 70.0

TIME AFTER RUPTURE (SEC}

Fig. 267 Void fraction in intact loop cold leg.

238

1.0

o.a

o.e :z 0 -~ c..> < "" ..... o ... s 0 >

0-2

o.o

1.0

o~a

:z o.e s ~ c..> < "" .....

r 0 -0 .O.It >

o.a

. o.o

~ { \ ..

~ ~ ~ aj

r VOfiiC008It P£-PC-2-VF

~

J -

o.o 10.0 20.0 10.0 ~to.o '50.0 eo.o 70.0 ' TIME AFTER RUPTURE (SEC)

Fig. 268 Void fraction in intact loop hot leg.

/ :,VOPICDOeS .PE-Pc-1-VF L --··-·- ·-·-- ···-.

.. . ---.

J

'

L I

o.o 10.0 20.0 10.0 ltO.O so.o eo.o TIME AFTER RUPTURE (SEC)

Fig. 269 Void fraction in intact loop at steam generator outlet.

239

'

70.0

-, . ., .

THIS PAGE

WAS INTENTIONALLY

·. LEFT BLANK

SlO

ld Q

NVS ~0~~3

£-1

1S31

5. TEST Ll-3 ERROR BAND PLOTS


241

1-u 0..

z 0 -~ Vl 0 .... .... > ..... < >

.., .. ~ LL ...... ~ .....

>-t.. Vl :z .... 0

..... < 0

"" 0 ::.:: u

12!5. "

100. ---~ ~ ~

-~ ~

7!5. /~_/ • PSFTI)It'tlit CV-PIH-01!5

ff,.

rH a UPPRBNO ~ r7

6 LNRSNQ. AI F/~

!50. /.F/ .,,, ., .. . ... '• --- ...... """' Irk

/}

ff/·· .. 2!5.

,, ~

-.

/L.

o. "//

-2!5. . . . .

-0.02 o.oo 0.02 o.o ... , o.oe o.oa o.ao IIMI:. lifTER RUP:t'URf (SEC)

Fig. 270 Valve opening (%) in broken loop hot leg QOBV with, error bands (CV-Pl38-15).

50. o.

~~. .. OEBTOOOI DE 81;--00IA

II" "1 a UPPRBNO 6 LWRBNO

'+0.0 .. I~

30.0

·-

20.0 "' . ''t(" -··. -·· 0

10.0 "' ~ >

~ ,_ ..... .~ . o.o ..

-10.0

•.

.'

-I 0 0 o. I 0. 20. 30. '+0. !50. 60. 70.


Fig. 271 Chordal density in broken loop cold leg with error bands (DE-BL-lA) (filtered to 4Hz).

242

--150.

• YEB"TO't!S I F'E-BL-001 II

a uPPRBNO p.,~ ~! ,~ ~i.L A LwAeNo .dill ~~ ~~ ~~ I I

_ _j ~ ~lJJ. -~ ~~ I i

i I l ~ I .-.. 100. I ' I ! ! <..> .... Cl) ........ 1-u.

~ ..... u 0 -I .... >

..... u .... Cl) ........ 1-u.

> !::::; <..> 0 -I .... >

50.

NOTE: REFER TO SECTION Ill IN -- ---+-TEXT ON TURBINE CALIBRATIONS.·, ! i I

···-~-·-- 1-·-'-·- ~- ; -· . -~ -·-·- ----!---

r---+ I I 11&1 I I i i I ----r--- -·

~ ~· I I I -~- I : _J.

I ~ N I ' I I ' ....... IJ:

..J . .,_ .. i ~ !A,.., IJ I

:~ ,Jj ~

-A .. ._., ~ ... ~ -~

~ ~ ~ -o. -10. o. 10. 20. 30. 1+0. 50. 60. 70.


Fig. 272 Average velocity in broken loop cold leg at OTT flange with error bands (FE-BL-1) (filtered to 4Hz).

15.0 • YEOT01+57 F'E-IST-001 a UPPRBNO A LWRBND

10.0 .A4Vt ~ aA JIM .. NOTE: REFER TO SECTION III IN •• 'Jd't TEXT ON TURBINE CALIBRATIONS. ..&

Ill' r·~ ,.

5.0 ~~ .Jil ·--

~ r v· ~1 I lA l ~! '-',( .J. A

\..}JJ ~ ~ , 1\. ~ II \1 \ ...

• u rn •• ' \. I~. ' \.-r~, w. .. l\ __ .A. N\

-

o.o -10. o. I 0. 20. 30. 1+0. 50. eo. 70.

TIME AFTER RUPTURE (SEC) ,

Fig. 273 Average velocity in reactor vessel downcomer instrument stalk 1 with error bands (FE-lST-1) (filtered to 4Hz).

243

~

::£ c.. ~ w 1-

:a 3 0 ...J u.

3 0 ...J u.

100.

'7S.

•o.

"·

- - -" - ····- - . - - -II -t---+--+--+--+---+--+--+--+---1-- -•' ~--:~_ n-Pa•-•• t--+--+--+---f--+-+----if---+--+-___;· a "''••iD t-~-+----t---t--t--+---11'--+-+-~-, &·. L.,._

J, • ....

o. -ao. o. 10. eo. so. . so. ao. -70~

TIME AFTfl! RIIPTIIRF (SFt \

Fig. 274 Flow rate in blowdown suppression tank spray system pump discharge with error bands (FE-Pl38-139).

ISO. • F'WTO'Iel F'T-PIH-oes

a "''•.o .. &L...._., ~ ::::.. ..

r I . _l j_ I ~ --r-

I I I / --NOTE: ERROR BANDS ARE UNDEFINED ./

100. DURING THE TRANSIENT. ; fl'

......

~ ·- ·-!10.

o.

-so. i

-ao. o. 10. eo. so. eo. TIME AFTER RUPTURE {SEC)

Fig. 275 Flow rate in ECCS LPIS pump A discharge with error bands (FT-Pl20-85).

244

. ~

--

::E D..

e w 1-

~ 3 0 ..... Lo-

,. 2 ::z:: ...... iS ..... ~ .... 1-

~ 3 0 ..... Lo-

30.0 -

• ~V~T0087 F"T-Pl28-101t 0 UPPA8NO 6 LWA8NO

-

20.0 .. " -

'

10.0

o.o

NOTE: ERROR BANOS ARE UNDEFINED DURING THE TRANSIENT .

-10.0 .•. ·-·-· ··- .. - .. ----. -

-ao.o o.o 10.0 20.0 30.0 ltO.O eo.o eo.o 70.0


Fig. 276 Flow rate in ECCS HPIS pump A discharge with error bands (FT-Pl28-104).

3.

2.

I .

o. -10.

Fig. 277

• F"HF"80020 F"T-P139-27-3

D UPPRBNO fa' LWABNO -.,..

NOTE: ERROR BANDS ARE DEFINED PRIOR TO T

0 ONLY.

·---- -·

LA ."

- - - - - - -o. 10. 20. 30. "+0. 50. 60. 70.


Flow rate in intact loop hot leg venturi with error bands (FT-Pl39-27-3).

245

z -...J

~ LoJ ...J

0 -:::> CT -...J

z

...J LoJ > LLI ...J

0 -:::> CT -...J

70.0 r-~----~~--r-~--~--~--~~~----------------------~

65.0

60.0

55.0

50.0

e L"FT0038 LT-PJ38-058 a UPPRBNO 6 LWRBNO

~5.0 ~~--_.------~~----------------~--~--~--------_.--~ ··10. o. 10·. 20, 30. ~0. 50. 60.

TIME AFTER RUPTURE (SECi

Fig. 278 Liquid lev~l in blowdown suppression tank south end with error bands (LT-Pl38~58),

~o.

70.

- • L"FBOO~I LT-P139-008 a UPPRBNO 6 LwRBNO

30.

t----+--+---tlH--+----l--+--+---+--1-- NOTE: ERROR BANDS ARE UNDEFINED -AFTER T0 + 13 SEC. . -

20.

I 1 v.

, l---+--+·--l-----t--+---1f---+--+---t--t--f--+---t--+---t

0.

-10. o. I 0. 20. 30.


~0. 50. 60.

Fig. 279 ~iquid level in pressurizer north side with error bands (LT-Pl39-8).

246

70.

"' ... ... u ... V>

I I-u. ...... ::e:: "" -' ><:

>< => -' ... ::E => I-z ... ~ :E

"' ... ... u ... V>

I I-LL ...... :E

"" -' ><:

>< => -' LL

:E => I-z ... ~ :E

100, • MFBT0522.ME-BL-OOI D UPPRBNO

f- A LI.IRBNO 75. -- [ I j_ I I

I I I [

- I I I I I ·-NOTE; REFER TO SECTION III IN TEXT

ON DRAG DISC CALIBRATIONS. 50.

I

1---f-J

"· I, I~

25 . I ':\A ~ :~ ., .... •,t'l ~ i\ II ··~ J ftJ LIA t-Ill ,

~ . .- ..... vr ~ ~-. .. ..~~ ~ .... ~ • AJ4 ' \ ... I''Y""'t --,.. 11 "'- ... lrll .A.

-.... ~

o. '~'-- .... ~

~

-25.

-I 0. o. I 0. 20. 30. 40. so. 60. 70 ..


Fig. 280 Momentum flux in broken loop cold leg at OTT flange with error bands (ME-BL-1) (filtered to 4Hz).

7.:5 • ~OT~5 HE-IST-001 a UPPAINO A LWAINO

!5.0

2.!5 • ~l

NOTE: REFER TO SEC~ION III IN TEXT ON DRAG DISC CALIBRATIONS.

I

-- --

..._ .iJ\.; ... n.. .A . .... o.o ~- "l¥"' lt lo.A.. ~ _ ..

... J'\ ~A "'

... .. - -~ .A ....

~ .. ~ IJJf¥ ll"'_!_- -"' -...

-ao. o. I 0. 20. 30 .. ItO. 50. 60. 70.


Fig~ 281 Momentum flux in reactor vessel downcomer instrument stalk 1 with error bands (ME-lST-1) (filtered to 4Hz).

247

0 ..... v> ~ ..... "' :::> v> v> ..... "' 0..

-' < -.... :z ..... "' ..... "· ~ 0

0 ..... v> e:. ..... "' :::::>

'" v> ..... "' 0..

-' ~ I-:z ~ ..... .... := 0

!5.0 .,I\-:?;., • P08T0052 POE-IL-001 "j .... a UPPI8G

• I A UIBG

.. lit 2.!5 I .l

~· it

.I JL

o.o - -

-2.!5

-10. o. I 0. 20. 30. '+0. !50. 60. 70.

TIMi AFTER RUPTURE (SEt)

Fig. 282 Differential pressure in broken loop hot leg at 14-to-5-in. reduction with error bands (PdE-BL-1) (filtered to 4Hz).

300. • POBT0053 POE-BL-002 a UPPABNO 6 LWABNO

200 .

l(l(l tJl ~

~ lilllo.. -...... c.

-100.

-I 0. o. I 0. 20. 30. litO. 50. eo. TIME AFTER RUPTURE (SEC)

Fig. 283 Differential pressure in broken loop cold leg at 14-to-5-in. reduction with error bands (PdE-BL-2) (filtered to 4 Hz).

248

_._

70.

0 .... "' Q.

...... "' ~ "' "' ...... "' Q.

....J := 1-z ...... "' ...... .... .... ... 0

..... 0 .... "' Q.

.... "' ~ "' "' ......

"' Q.

....J

:::5 ...... z ...... "' ...... .... !!; 0

soo.

ltOO.

300.

200.

100:-

o.

'"100·

-10.

.... ~

o.

• POBTOOH 110£-BL-003 a UPPRBHO

.a L......n .... ~ ..... .. ~ ....

r-.a -~

=»-----""" ~ !'Ill.

ao. 20. 30. . ItO. so. eo. 70. TIME AFTER RUPTURE (SEC)

Fig. 284 Differential pressure in broken loop cold leg across break plane with error bands (PdE-BL-3).

lQ.

• ~,ooe., POC-a-ooe 1 a .,.," • ., ... .....,

20.

! i

I i

10.

II i ; ,.,... "I -~ ---···--

l ' :

' : .... ( ..,

~ -,.._ Q.

. -10.

-10. o. 10. ao. JO. ItO. so. eo. '70. TIME AFTER RUPTURE (SEC)

Fig. 285 Differential pressure in broken loop hot leg across steam generator simulator outlet flange with error bands (PdE-BL-6) (filtered to 4Hz).

249

c .... V'l 0..

.... "' ;:;)

"' "' .... "' 0..

-' ~ ,_ z ~ .... ..... ~ n

c ..... "' ~ .... "' ;:;) V'l V'l .... "' 0.

-' ~ 1-z w

""' .... ..... ..... .... c

30. t-·- f----·- ---- +----- t--+-----1--+---- t------ -+ • POPTD08 I PDE-PC-00 I --·+---1t-·- 1---- ---1---~- ---- ---~---J...- D UII'PRIND 1-·

----+--~--1----+--1- A LWR8ND 1 ... , .. ...... , IT''• ••••r--t----- ---1---- -~----'---+----1~-- --- ,__. -r--

i 20 .

f----

l 0. f--·

·--· 1--- - ~-- -----~ ~--+--- ------f· +--~--+--_-+-_ ----+-_ ..=-_+ =r.= =--::=~ := -=--=~~~:l~-~- ::=~~F---~-

-+-------1+--- ---1----· f--+ -- 1--·-- --- -----·-t --. -·- -----

-~-If----·· "111=1+--i---- ...... .. ---- = =-f.--~ ~= f-~3-= ----~ ~=--

-o.

-10.

-ao. o. 10. ao. JO. 'tO. so. eo. '70.

TIME AFTER RUPTVRE (SEC)

Fig. 286 Differential pressure in intact loop cold leg across primary coolant pumps 1 and 2 with error bands (PdE-PC-1).

18.0 • POPTDOal POE~PC-002 a uPPRINO .. , A LWR&ND

·----

10.0

·-5.0

~ ~ - ..... .... .... - ..... r--

o.o

-s.o -ao. o. 10. eo. JO. 'tO. so. eo. '70.


Fig. 287 Differential pressure in intact loop across steam generator with error bands_(PdE-PC-2).

250

c -VI 0..

~ VI VI ..... EE ...J

~ 1-:z ..... ot! ..... "-~ c

c -VI 0..

..... ot! ::> VI VI ..... ot! 0..

...J

~ 1-:z ..... ot! ..... "-~ c

3.0 • POPTOOIJ POE-PC-OOJ

·-·---f- a uPPRBNO

• LWA&NO --- --- -··-·- ---

2.0 I , t ·-1-· " ---

._

1.0 ,. ~

o.o ~ ~ "it'R ~ ... ...- ~ .. ... -· '& v- -- .. .. _ . .....!

-a.o -10. o. 10 . . 20. JO. ItO. !50. eo. '70.


Fig. 288 Differential pressure in intact loop hot leg reactor vessel outlet to flow venturi with error bands (PdE-PC-3).

2!500. • PORTD0'71 POE-AY-001 a UfiPABNO

·~ooo. • LWR8NO - -

1!500 . --NOTE: ERROR BANDS ARE DEFINED -

AFTER T0 ONLY. --1000 . I

-.........

....... soo. ....

"11IL. roo...

~ --o.

-soo. .

-10.0 o.o 10.0 20.0 30.0 ~to.o !50.0 eo.o '70.0


Fig. 289 Differential pressure from reactor vessel downcomer stalk 1 to blowdown suppression tank with error bands (PdE-RV-1).

251

~ -V')

~

"' "' :::> V') V')

"' "' 0..

...J

~ 1-:z ..... "' w lA. ~ Q

~ -V') 0..

"' "' :::> V') VJ

"' "' 0..

10.0 .-.. ... • POf:T00'71t POT-PIJSI-030 ...... a UPPRBNO ...... 6 LWRBNO ....

oo,_,,_

!5. 0

··-

···-·. --l ·-· ...

.. ··- .... - """"a" - - - -

C).O ~ ... -.....- - - - ~

....... f- ~- ---

r· ....

........ i

-s.o -10. o. lO. 20 .. :so. ItO. so. eo. '70.

TIM!: AFTF.R RIIPTIIRF. (SF,C)

Fig. ?90 OiffP.rential pressure in intact loop across the reactor vc~scl inlet and outlet nozzles with error bands (PdT-Pl39_:30).

2500.

2000.

1soo.

1000.

500.

o. -10. o. 10.

.. ~ """'''IL

......... .... _......... ~

20. 30.


• POBT00'78 PE-BL-002. a uPPR8NO 6 LWR8ND .. - -·---

---

ItO. so. eo. '70.

Fig. 291 Pressure in broken loop hot leg with error bands (PE-BL-2).

252

c:; -V) ... ·"' ""' ::::>

V) V)

"' ""' ...

2SC)O.

2000.

1!500.

1000.

!500.

o. -ao.

-· . ---; r-

-·

.. -

r---· --· -·--r-- -·

o. I 0.

-

• POCTD081 P£-CS-OOIA a uPPA8ND

• L~ ..

-·-

,.:

~ ~ 'IIlii. ~ I -...

"""'' ~

eo. JO. ItO. !50. eo. '70. >


Fig. 292 Pressure in reactor vessel core simulator instrument stalk, wide range, with error bands (PE-CS-lA).

<!> -V) 0..

"' ""' ::::> V) ._, "' ""' ...

JQO.

200.

100.

o. -10.

--·

---+-j

·---+·-____ j__ I ---t-

·-··- --·-

-··- r-··-.

-.---- -

------___ .J ___

I I" i

o.

I • POCTOOH PC~~s~ooaa

F - - - a . uPPA81C) .. l • LWA8ND ·.';'

-··· _., -·-·t--

I ____ \ ! I f--·· t ·-·

l ' ····-

i I .. ~-- +- ··- I

i 1 ., ··- -···:-+--··· -1 \ -·--+- t--

I

' ; ·-······-·

; " I

" .. ___ _.. __ i '' I -·- ---·-- -· -I

---·t i '

NOTE: PRESSURE IS BEYOND INSTRU----~- -MENT RANGE PRIOR TO To +

i 31 SEC.

10. eo. 30. ItO. !50. eo. '70.

TIME AFTER RUPTUR£ (SEC)

~ig. 293 Pressure in reactor vessel core simulator instrument·stalk, narrow range, with error bands (PE-CS-18).

253

c:D ~

V')

0..

... ~ V') V') w

"" 0..

2500.

2000.

1!500.

I 01)0.

soo. -0.02

• POCTH8~8 PE-CS-002FF a UPPR8NO

~ A LWR8NO

~~ ~ .... ~ ~ ...

~ ... k ~L ~

'l:: ~ ·- .......

o.oo o.o2 o.o~ o.oe o.oa 0. I 0 o. 12

TIME AFTER RUPTURE ISECl

·Fig. 294 Pressure in reactor vessel core simulator instrument stalk, short-term plot, with error bands (PE-CS-2Ff).

<!:1

V')

0..

... "" -, V') V') ... "' 0..

2500.

2000.

1500.

1000.

500.

o.-ao. o. I 0.

.. r--.... .. ....... -loo..

20. 30.


• POCT~~ PE-CS-002FF o UPPRBHO

•• LWR&ND

I I I I I I T T

I

NOTE: ERROR BANDS ARE UNDEFINED AFTER T0 + 10 SEC.

I

~o. 50. eo. 70.

Fig. 295 Pressure in reactor vessel core simulator instrument stalk, 70-second plot, with error bands (PE-CS-2FF).

254

<!I -v>. D..

w 0: ~ v> v> w 0: D..

<!I -v> D..

w

!3 "' v> w 0: D..

...

50.0 • PGTT0096 PI::-SV-01'+ o UPPRBND

'+0.0 A LWRBND

~ ~ ~ I 30.0

Q,lr' ~ ~ ~ ~ .... ~~~ vy: ~ ~ """'-. ra.. Ia..

~ -20.0

V' I~ ........ r.... I.a.

._ I-.,.,... .

rtt.. ~ .. .....

10.0 I

o.o ~' ~ NOTE: DATA INITIAL VALUES ARE

ADJUSTED TO 0 PSIG.

-10.0 l I I I I I l

-0.10. o.oo 0.10 o.2o o.3o o.'+o o.5o o.eo o.7o o.ao o.ao

Fig. 296

50.0

'tO.O

30.0

20.0

10.0

o.o

-10.0

-10.0


Pressure in blowdown suppression tank header above downcomer 4, short-term plot, with error bands(PE-SV-14).

~ ~ -. / ~ - --

/ / ~ _.... - ---"/ ~ --~

/'_.~ 'l • POTT0088 PE-SY-OI't

~ "" ... ,r/ D UfiPAatG • L.WI8tD

~ ~..,. ,

J

~ ,.,.

NOTE: DATA. INITIAL VALUES ARE ADJUSTED TO 0 PSIG.

I I _l l I -o.o 10.0 20.0 30.0 'tO.O 50.0 eo.o 70.0


Fig. 297 Pressure in blowdown suppression tank header above downcomer 4, 70-second plot, with error bands (PE-SV-14).

255

~ -V)

~ ... 0! :::> V) ... ...... a: Cl..

s V)

Cl.. .,... ...... a: til V) ...... a: Cl..

'7SO.

• PvTDIJS PT-PII0-0811t a uPPRIIC) A -LWR8ND . . ... --··- ···- ----- - -.. --- .

~ "'1 soo. --\ NOTE:. ERROR BANDS ARE UNDEFINED·

lit AFTER T0 + 22 SEC.

---- ··- -

\ \

eso. 1\. .. '

I

' ' --- -o. -10• o. 10. eo. 30. litO. so. ao. '70.


Fig. 298 Pressure in ECCS lower plenum injection point with error ·bands (PT-Pl20-64).

eso. •• POI'TDI3'7 PT-PII0-083

-eoo.

1----

ISO.

100.

-10.

--·

---

·-

o.

- --- -- -..

~ - 1-

Ill' - - - r-. ~ - I•

-

10. eo. 30. TIME AFTER RUPTURE (SEC)

. ; a uPPRIIC)

• LMR8tt0 ·- . ----- - ...

[,. r-.-_ ..... r...,;. r-- ... -~ .,..

1-..--

'tO. so. ao.

Fig. 299 Pressure in ECCS LPIS pump A discharge with erro,r bands (PT-Pl20-83).

256

. --

'70.

(

<!J

V) 0..

..... IX :::> V) V) ..... IX 0..

<!J .... V) 0..

..... 0:: :::> V) V) .....

. IX 0..

•

. •

60.

50.

40.

30.

20.

I 0.

o. -IQ.

-

-

r ~J -

1 ...

o.

·-·

~ I"'"

/ 1

~-

~ ~

I 0. 20. 30.


.__, ~

• POF'T0474 PT-PI38-055 • D UPPRBND

A LI.IRBND

i I I I I I 1NOTE: I ERRO~ .BANcis ARE

1 UNOEF

1INED

AFTER TQ.

I

I I

40. !50. 60. 70.

Fig. 300 Pressure in blowdown suppression tank top with error bands ( PT -Pl38-55).

2500.

2000.

1500.

1000.

500.

o . -0.02

~ ~ "\.

W\......a-~.A ~......t

o.oo

• POFTW715 PT-PI38-III

a UPPRBNO ~A LWRBNO -

I I I I I I I I I I I I

NOTE: ERROR BANOS ARE UNDEFINED AFTER T0 + 0.03 SEC.

A ./A._ -.,... /A.

.._ f-""' ./ './-"" ./' r"

0.02 o.o~t o.oe o.oe 0. 10

TIME AFTER RUPTURE (SEC)·

Fig. 301 Pressure in broken loop cold leg QOBV inlet, short-term plot, with error·bands (PT-Pl38-lll).

257

<!I .... "' "" ..... a: =' .,., "' ..... "" ""

::£

"" tY.

1""1 ..... ..... 0.. Vl

0.. ~ :::> 0..

320.

310.

300.

2gQ,

280.

270.

260.

-10.

--~- ...

~

-..

" ... ,. ~

rr ... . ..... ~

--~

·w

o. I 0.

....... -~

..,/ ~ r- ....

,I r

v • POF' T 0 I'+ 3 PT-P138-136 0 UPP~SNO

6 LW~BNO

' l I NOTE: ERROR BANDS ARE UNDEFINED

AFTER Tq.

'

20. 30. ~0. 50. 60. 70.

TII~E Arrcn nuroTunE (SiC)

Fig. 302 Pressure in blowdown suppression tank spray system pump discharge with error bands (PT-Pl38-136).

aooo.

ISOO.

1000 .

SQO.

o. -10.

... 1'-

' l

o.

• SRPTOit.,. RPC-PC-OM· . a UPP•G- , . ·--~

• .. L .... . :_!~.-{·.· ..

····· .- -~ .....

...::.

~

' Ill. '- ·~

~~ (

' l"-. ~

~ I

~ I 1

10. eo. 30. so. eo. 'PO.


Fig. 303 Pump speed in intact loop operating pump 2 with error bands (RPE-PC-2).

258

(

-u..

"' ...... 0

...... o< :::> 1-< o< ...... a.. :E ...... 1-

L:

"' ...... 0

...... o< :::> 1-< o< ...... a.. z: "' 1-

550.

500.

'+50.

'+00.

350.

300.

-I 0. o.

--..:: ~ ...... ~~

I 0.

• II. a "--"" 6 I~

~ ~ ~'\

"'\.X\ .NOTE: "',}

1.\.'\.

.. ,,~ "" -~ ··-~ ~ !IlK

'~ '~ ~

""'\111

~

20. 30. '+0.

TIME AFTER RUPTliRF. (SEC)

TEBT0179 TE-BL-002 UPPRBND LWRBND

I I I I I I I I

F.RROR RANI)$ ARE liNOEFIIIED AFTER T0 + 40 SEC.

~ .Mrt'"

v _.. .... r

~o. so. 70.

Fig. 304 Temperature in broken loop hot leg with error bands (TE-BL-2).

uso.

1~0.

1'+0.

130.

120.

110.

-10.

Fig. 305

-~

-.... ,....

, ~ .,. .,

IIJ

,...,.,.,. • TE~T0501 TE-PI38-022

.A v a UfiPR&IC)

/ A LYI8NO W" I

./ •• 1 I I ~ I I I I I

~ NOTE: ERROR BANDS ARE UNDEFINED J AFTER T0. -

.. -

o. I 0. 20. 30. '+0. ~o. eo. 70.


Temperature in blowdown suppression tank liquid at tank bottom with. error bands (TE-Pl38-22)·.

259

..... <.!1 ..... e w "" => ..... ..: "" ..... Q.

::E ..... ...

;;: <.!1 ..... e w IX :;, ... < "" ..... Q.

::E ..... .....

275.

2!50.

22!5.

200.

17!5 ..

•IQ.

...

o.

.•--•1•'>••

_,. -~ ~

ao.

/_ .. ./ ., • TEF"TD2 .. 8 TE~Pll8-0J1t

/ a uPPRIND L • LNRBND . . ... I

I I I 1 , NOTE:' ERROR BANDS ARE "uNDEFINED

I AFTER TQ . . ---- ·- 040 --- -· ·- .

~ . ..... -- .

en. ~o. ~o. !SD. 1'11:1. 70-


Fig. 306 Temperature in blowdown suppression tank vapor at tank top w1th error bands (TE-Pl38-34).

550.

500.

450.

400.

350.

300.

-10.

f--

Fig. 307

• TEF"TOI86 TE-P138-062 0 UPPRSNO A LWRBNO

'-• NOTE: ERROR BANDS ARE UNDEFINED '- AFTER TQ. "'--.

........ _ ~ .. ...

..... '- ·-

1"'1 "'- ....

"--"' """ --.. --

o. I 0. 20. 30. 40. 50. eo. 70.


Temperature in broken loop cold leg at QOBV inlet with error bands (TE-Pl38-62).

260

~ <.!1 .... c

.... a: ::::> ..... < a: .... 0.. lE .... .....

~ <.!1 .... e .... a: ::::> ..... < a: ....

. 0.. :z: .... .....

_j

!52!5.

• TEF'T0197 n:-Pl3B-063 o UPPRBNO

500. A LrRB~O

I I .......... ~- I I I I

"""''l I I I I

'+75.

~ NOTE: ERROR BANDS ARE ·uNDEFINED

' _AFTER T0

. '

"-' I'll.

'-I

'+50. '-"" '-

="" .... '+25.

..... ... ......,.,_ ~ ~

'tOO.

-I 0 .. o. l 0. 20. 30. '+0. 50. 60. 70.

TIME AFTER RUPTURE (SEC) .

Fig. 308 Temperature in broken loop cold leg isolation valve inlet with error bands (TE-Pl38-63).

1!50.

100.

!50.

o. -10.

Fig. 309

• TEF"T0201 TE-Pil8-11tl :a UPPR8ND

6 La,t~BND ..

"':" "':" "':" "':" "':" "':" "':" "':"

o. I 0. 20. 3(1. ItO. !50. eo.

TIME AFTER·RUPTURE (SEC)

Temperature in blowdown suppression tank spray system 60-gpm header with error bands (TE-Pl38-141).

261

"':"

70.

... <!I .... c

.... "" :::> ..... ~ .... D. :IE; .... .....

~ <!I .... L..l

.... ,... :::> ..... < a:. .... D. ::E .... .....

700.

650.

eoo.

550.

500.

'+50.

'+00.

-10.

---·

r---

·--···-·1-· .. ·-·--............ , t-~~

---·

==t== r----

o.

- ........... .... " ... -

Ill.. ··-...... " --

-· --- I "Ill

" -·----t----- ------ .... .-~,- 1=-=-- -- " '

--1- ! ·------ --

I 0. 20. 30.

TlMi: ~.HER. P.i.JPTIJP.E (SFI::)

• TEF"T0205 TE-P139-020 0 UPPRBND A LI.IRBND

~

NOTE: ERROR BANDS ARE UNDEFINED AFTER TQ.

··---·

lt.. -.,._

"""'- ... -'+0. 50. 60. 70.

Fig. 310 Temperature in intact loop pressurizer liquid with error bands (TE-Pl39-20).

sso.

en.

-soo.

't'7S .

'ISO.

't2S.

-10.

Fig. 311

• TCOTDSOJ TC-S0-001 a uPPRilC) - - • i"""oa.. a LWR8ND

ra.. I -· Ill. I I I I I '- I I I I I

] NOTE: ERROR BANDS ARE UNDEFINED "- AFTER TQ. ..

r.. ·-... ·-·-- -· ~

........ --"""-

1-.. ~ ....,..,.

~ ....... ..

o. 10. ao . JO. 'tO. so. eo. '70. . TIME AFTER RUPTURE (SEC)

Temperature in intact loop cold leg at steam generator inlet ~lenum with error bands (TE-SG-1).

262

. ••

..

L: <!> ...... c

...... IX ::::> ..... < "' w c.. ::E ...... .....

2'7S.

no.

en.

eoo.

1'7S.

-ao.

II ~

o.

' r•

t.t~ .JII u·•\! ~ ' • II

1-

10. eo. 10.


• rtnosaa Tc-sv-ooe a U'P•tD &L....,

--- r- r . ---.

~ ~. -1-"' ~~

·-

.

so. eo. '70.

Fig. 312 Temperature in blowdown suppression tank B-end thermocouple ·stalk with error bands (TE-SV-6).

263

VIII. REFERENCES

1. T. K. Samuels, Conformed Copy of LOFT Experimental Operating Specification, Volume 2, Nonnu.clear Test Series Ll Experiment 3 and 3A, NNE Ll-3 dn~ 3A, Aerojet Nuclenr Compnny. EOS Volume 2. NNE Ll-3 and 3A Revision 2 (September 1~76).

2. J. R. White, Experiment Prediction for LOFT Experiment Ll-3, Aerojet Nuclear Company, EP Ll-3 (June 1976).

3. J. R. Chappell, Quick Look Report on Loss of Coolant Experiment. Ll-3, Aerojet Nuclear Company, QLR-76-4 (July 1976).

4. H. C. Robinson, LOFT System and Test Description (Loss of Coolant Experiments Using a Core Simulator), TREE-NUREG-1019 (November 1976).

5. J. R. Chappell, Experiment Data Report for LOFT Nonnuclear Test Ll-1, TREE-NUREG-1025 (December 1976).

6. H. C. Robinson, Experiment Data Report for LOFT Nonnuclear Test Ll-2, TREE-NUREG-1026 (December 1976).

7. G. M. Millar, Experiment Data Report for LOFT Nonnuclear fest Ll-3A, TREE-NUREG-1027 (December 1976).

8. F. S. Miyasaki, Digital Data Acquisition Program, ANCR-1250 (August 1975).

9. N. L. Norman, LOFT Data Reduction, ANCR-1251 (August 1975).

10. G. L. Biladeau et al, LOFT Experimental Measurements Uncertainty Analysis, Aerojet Nuclear Company, LTR 141-39 (September 1975).

264

·•

11. S. N~ Zender, Experimental Data Report for Semiscale MOD-1 Test S-01-03 (Isothermal Slowdown with Core Resistance Simulator), ANCR-1195 (March 1975).

265

'I

l.

)

ac Ace. BL BDST BDSTSS BWST CL cs DAVDS DC de Deg. DP OTT ECC ECCS EOP EOS ESF

FF Fig. FM Freq. ·

a FTS2 g

gpm HL HPIS hr HX Hz in. INEL Instr. lb

lbm LOCA LOCE LOFT

IX. LIST OF ABBREVIATIONS AND ACRONYMS , I

Alternating ~urrent Accumulator Broken Loop Blowdo~n Suppression Tank Slowdown Suppression Tank Spray System Borated Water Storage Tank

Cpld Leg Core Simulator Data Acquisition and Visual Display System Down comer Direct current Degree Differential Pressure Drag Disc-Turbine Flowmeter Emergency Core Cooling or Coolant Emergency Core Cool~nt System Experimental Qperating Procedure Experimental Operating Specificat1on Engineered Safety Features Degrees Fahrenheit Free Field Figure FrPf111Pnr.y Mnclulator Frequency Feet Feet-second2

Acceleration due to gravity Gallons per minute llot Leg

High-Pressure Injection System Hour Heat Exchanger Hertz Inch ( s) Idaho National Engineering I ~hnr~tory

Instrument Puund(s) Pounds mass Loss-of-Coolant Accident Loss-of-Coolant Experiment Loss of Fluid Test

·)

267

LP LPIS LPWR msec MW

N2 p

PC PCP PCS PCT ppm pps psi psi a psid psig PSMG QEUD

QOBV RABV RMS rpm RTD RV scs sec SG Snuh. TAN Temp. UP JJSec v

v volsys p

p

<>

Lower Plenum Low-Pressure Injection·system Large Press~rized Water Reactor (~1000 MW) Milliseconds Megawatt Nitrogen Pressure Primary Coolant · Primary Coolant Pump Primary Coolant System Percent Parts per million Points per second Pounds per square inch Pounds per square inch - absolute Pounds per square inch differential Pounds per square inch - gauge Primary System Motor Generator (Sets) Qualified Engineering Units Data Quick-Opening Slowdown Valve · Reflood Assist Bypass Valve Root Mean Square Revolutions.per minute Resistance Temperature Detector Reactor Vessel Secondary Coolant System Second(s) Steam.Generator Snubber Test Area North Temperature Upper Pl_enum Microseconds Velocity Volt(s) Volume of system Density Average density Density of saturated vapor Density of saturated liquid Averaged over a specified cross-sectional are.a

DISTRIBUTION RECORD FOR TREE-NUREG.,-1 065 ' - ~ • ' • . j •

lnternal Distribution

1 - Chicago Patent Group - ERDA 9800 South Cas·s Avenue ·

2-4 -

5 -6 ...,

] -·

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A.r96nne, ~ 1 1 i:noi s: ·6'04,39<

A. T. Mo~phew. Classifi-cation and Technical Information Officer Idaho Operations o·ffice - ERDA Idaho rall~. IQ 6J40l

R. J. Beers., ID

P. E. ~ i ttene,ker '· ID

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R. E. Wo.od, ID

~..., H. P~ Pearson, Supervi~or Technical· Information

10-19 .,._ INE.L Techni ca 1 Library

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External Oi~tribution

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