NEDO-24542 79NED1 01
CLASS I AUGUST 1979
,ft 4*
i~I~V, ~i.~ m% A
MARK I CONTAINMENT PROGRAM
MONTICELLO T-QUENCHER THERMALI O
H NOTICE
HFILES ARE OFFICIAL RECORDS OF THE
r DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN
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DEADLINE RETURN DATE
RECORDS FACILITY BRANCH
MIXING TEST FINAL REPORT TASK NUMBER 7.5.2
B. J. PATTERSON
7910170 ?
GENERAL * ELECTRIC
NEDO-24542 79NED101 Class I
August 1979
EU TO REACTORIOCE FILES ,
MARK I CONTAINMENT PROGRAM
MONTICELLO T-QUENCHER THERMAL MIXING TEST
FINAL REPORT
Task Number 7.5.2
B. J. Patterson
Reviewedl
M. E. Tanner, Manager Safety/Relief Valve Programs
P. P. Stancavage, Manager Containment SRV Performance Engineering
Approved: _
P. W. Ianni, Manager Containment Design
- P. W. Marriott, Manager Containment Engineering
NUCLEAR ENGINEERING DIVISION * GENERAL ELECTRIC COMPANY SAN JOSE, CALIFORNIA 95125
GENERAL* ELECTRIC
Vrw- r'I 1{qvLc-1qy
NEDO-24542
DISCLAIMER OF RESPONSIBILITY
Neither the General Electric Company nor any of the contributors
to this document makes any warranty or representation (express
or implied) with respect to the accuracy, completeness, or
usefulness of the information contained in this document or that
the use of such information may not infringe privately owned
rights; nor do they assume any responsibility for liability or
damage of any kind which may result from the use of any of the
information contained in this document.
NEDO-24542
TABLE OF CONTENTS
Page
ABSTRACT ix
1. INTRODUCTION 1-1
1.1 Background 1-1
1.2 Test Objective 1-2
2. SUMMARY OF PRINCIPAL OBSERVATIONS 2-1
3. TEST PROCEDURE 3-1
4. INSTRUMENTATION 4-1
5. DISCUSSION OF RESULTS 5-1
5.1 Description of Phenomena 5-1
5.2 Instrumentation and Test Data Summary 5-1
5.3 Results 5-2
6. REFERENCES 6-1
APPENDICES
A. POOL TEMPERATURE TRANSIENTS A-1
B. POOL TEMPERATURE TRANSIENTS WITH RHR POOL COOLING B-1
C. SRV STEAM FLOW RATE C-1
iii/iv
NEDO-24542
LIST OF ILLUSTRATIONS
Figure Title Page
1-1 Monticello T-Quencher 1-3
1-2 T-Quencher Hole Pattern (Arm 1) 1-4
1-3 T-Quencher Hole Pattern (Arm 2) 1-5
1-4 Quencher Installation 1-6
1-5 Monticello Plant Configuration. 1-7
1-6 Locations of RHR Suction and Discharge Piping in Monticello Torus 1-8
4-1 Pool Water Temperature Sensor Locations in Torus 4-4
4-2 Pool Water Temperature Sensor Location - Bay C 4-5
4-3 Pool Water Temperature Sensor Location - Bay B 4-6
4-4 Pool Water Temperature Sensor Location - Bay H 4-7
4-5 Pool Water Temperature Sensor Location - Bay E/F 4-8
4-6 Pool Water Temperature Sensor Location - Bay D/E 4-9
4-7 Pool Water Temperature Sensor Location - Bay D 4-10
4-8 Pool Water Temperature Sensor Location - Bay D 4-11
4-9 Pool Water Temperature Sensor Location - Bay G/H 4-12
4-10 Block Diagram of DS-83 Scanner System 4-13
5-1 Measured Versus Calculated Bulk Pool Temperature Test Without RHR 5-5
5-2 Measured Versus Calculated Bulk Pool Temperature Test With RHR 5-6
5-3 Maximum Temperature of Water Feeding the T-Quencher Test Without RHR 5-7
5-4 Maximum Temperature of Water Feeding the T-Quencher Test With RHR 5-8
5-5 Average Bay D Temperatures, Test Without RHR 5-9
5-6 Average Bay D Temperatures, Test With RHR 5-10
5-7 Bay Average Temperature, Test Without RHR 5-11
5-8 Bay Average Temperature, Test With RHR 5-12
5-9 Bay Average Temperature, Test Without RHR 5-13
5-10 Bay Average Temperature 5-14
A-1 Bay C Temperatures, Test 1 A-1
A-2 Bay B Temperatures, Test 1 A-2
A-3 Bay H Temperatures, Test 1 A-3
NEDO-24542
LIST OF ILLUSTRATIONS (Continued)
Figure Title Page
A-4 Bay E/F Temperatures, Test 1 A-4
A-5 Bay D/E Temperatures, Test 1 A-5
A-6 Bay D Temperatures, Test 1 A-6
A-7 Bay D Temperatures, Test 1 A-7
A-8 Plant Sensor Temperatures, Test 1 A-8
A-9 Bay C Temperatures, Test 2 A-9
A-10 Bay B Temperatures, Test 2 A-10
A-11 Bay H Temperatures, Test 2 A-11
A-12 Bay E/F Temperatures, Test 2 A-12
A-13 Bay D/E Temperatures, Test 2 A-13
A-14 Bay D Temperatures, Test 2 A-14
A-15 Bay D Temperatures, Test 2 A-15
A-16 Plant Sensor Temperatures, Test 2 A-16
B-1 Bay C Temperatures, RHR Cooling B-1
B-2 Bay B Temperatures, RHR Cooling B-2
B-3 Bay H Temperatures, RHR Cooling B-3
B-4 Bay E/F Temperatures, RHR Cooling B-4
B-5 Bay D/E Temperatures, RHR Cooling B-5
B-6 Bay D Temperatures, RHR Cooling B-6
B-7 Bay D Temperatures, RHR Cooling B-7
vi
NEDO-24542
LIST OF TABLES
Table Title Page
3-1 Test Initial Conditions 3-3 3-2 Test Limiting Conditions 3-3 4-1 Sensor Specifications 4-2 4-2 Recording System Specifications 4-3
vii/viii
NEDO-24542
ABSTRACT
This document presents the results of the Monticello T-Quencher
Thermal Mixing Test that was performed in November 1978. The
objective of the test was to evaluate the effectiveness of a modi
fied T-quencher design (holes in one endcap) and a modified
residual heat removal (RHR) return system (90-degree elbow and
10-inch by 8-inch reducing nozzle at the end of discharge line) on
thermal mixing of the water in the pressure suppression pool
during safety/relief valve (SRV) discharge. Results of the test
show that the modified RHR discharge system yLelds a marked
improvement in thermal mixing over the modified T-quencher design.
ix/x
NEDO-24542
1. INTRODUCTION
1.1 BACKGROUND
An in-plant testing program was conducted at the Monticello Nuclear Generating Station of Northern States Power in December 1977 to evaluate the loads and pool thermal mixing characteristics resulting from a safety/relief valve (SRV) discharge through a T-quencher device. An additional test (extended SRV discharge) was conducted at Monticello in February 1978 to gather more data on the thermal mixing phenomena observed in the pressure suppression pool when one loop of the residual heat removal (RHR) system was operating in the recirculation mode. Test results1 showed the difference between the average discharge bay temperature and the calculated bulk pool temperature to be 430F for the test without RHR and 380F for the test with RHR. These two tests will be referred to as the "previous tests". In order to investigate other methods to enhance thermal mixing in the pool, modifications were made to the T-quencher design previously tested and also to the RHR return lines in the pool. This report describes the tests that were performed in November 1978 to evaluate the effectiveness of these modifications.
The original T-quencher device consisted of two arms (each approximately 9-1/2 feet long) perforated with holes on the front and back sides of the arms. The arms were attached to the ends of a ramshead-type device similar to those previously installed in the Monticello plant on the end of the safety/relief valve discharge line (SRVDL).
The modified T-quencher device (shown in Figures 1-1, 1-2 and 1-3) is similar to the previously tested T-quencher except that 40 holes in one arm of the device were relocated from the arm of the T-quencher to the face of the endcap. The purpose of the steam discharge through the endcap was to induce pool water circulation in the direction of discharge and hence to increase thermal mixing in the pool, as indicated by a decreasing bulk pool to average bay temperature differential. The quencher was supported at the ramshead fitting and at the midspan of the quencher arms as shown in Figure 1-4. These supports were connected to a 14-in. pipe support, which in turn was attached to the torus ring girders. Figure 1-5 illustrates the Monticello plant configuration.
1-1
NEDO-24542
The original RHR system consisted of four 20-in. suction lines (located at
45-degree, 135-degree, 225-degree and 315-degree azimuth) and two vertically
oriented 10-in. discharge lines at 74-degrees and 299-degrees azimuth. The
RHR system was modified by installation of a 90-degree elbow with a 10-in. by
8-in. reducing nozzle at the end of the existing discharge lines. These
revised discharges were oriented tangentially to impart circumferential flow to
the suppression pool. Figure 1-6 illustrates the RHR suction and modified
discharge piping in the Monticello torus.
1.2 TEST OBJECTIVE
The objective of the Monticello T-Quencher Thermal Mixing Test was to evaluate
the thermal mixing characteristics of a modified T-quencher device and a modi
fied RHR discharge line by providing pool thermal mixing data of pool tem
perature under extended discharge of the T-quencher.
1-2
10-inch SCHEDULE 80 PIPE - SRV DISCHARGE LINE
NUMBER OF HOLES
ARM 1 ARM 2
90 90
QUENCHER ARM 2 (SEE FIGURE 1-3)
12-inch SCH 80 /
B 112 112
C 176 176 0
D 416 376 . -- ---- -- -10 X 12 SCH 80 L
E 0 40 REDUCER
1588 TOTAL NUMBER OF HOLES/QUENCHER
QUENCHER ARM 1 HOLE PATTERN ON BOTH (SEE FIGURE 1-2) N: 'SIDES OF QUENCHER ARM
ZONE A
EZONE B
ZONE C
HOLES SYMMETRICAL ABOUT HORIZONTAL C ZONE D
Figure 1-1. Monticello T-Quencher
ZONE
A
ZONE E
-Ic
tVj
U1
Figure 1-3. T-Quencher Hole Pattern (Arm 2)
*Proprietary information deleted
NEDO-24542
MID-ARM SUPPORT
10-in. DISCHARGE PIPE
RAMSHEAD SUPPORT
12-in.QUENCHER
TORUS SHELL MITERED JOINT RING GIRDER
Figure 1-4. Quencher Installation
1-6
SRV DISCHARGE LINE
C TORUS
ELEVATION 912 ft - 7-1/2 in.
Figure 1-5. Monticello Plant Configuration
t')
NEDO-24542
DISCHARGE FOR LOOP
CONTAINING PUMPS 12, 14
0
10 in. RHR DISCHARGE
STRAINER
20 in. SUCTION LINE
Figure 1-6. Locations of RHR Suction and Discharge Piping in Monticello Torus
1-8
VIEW A- A
NEDO-24542
2. SUMMARY OF PRINCIPAL OBSERVATIONS
Two extended SRV discharge tests were run - one to evaluate the thermal mixing characteristics of a T-quencher with holes drilled in one endcap and the other to evaluate this same T-quencher with RHR operating in the recirculation mode. Both upstream and downstream sides of the test bay were analyzed. The following phenomena were observed.
a. Holes drilled into one endcap of a T-quencher did induce some pool circulation to enhance thermal mixing.
b. RHR operation showed a marked improvement in thermal mixing.
2-1/2-2
NEDO-24542
3. TEST PROCEDURE
The overall procedure for the two extended actuations of a single SRV was to
first cool the pool to -500F with both RHR systems operating in the pool
cooling mode. The RHR system was then shut off for more than eight hours to
allow the pool to stop circulating before the SRV was opened. The SRV was
opened for 11 minutes, 7 seconds and discharged steam into an initially still
pool. Temperature data were recorded for one hour after the SRV was opened.
Both RHR systems were again operated in the pool cooling mode to bring the
pool temperature down to .50aF. One and a half hours before the second test,
the RHR system operation was switched to one RHR system discharging 1800
around the torus from the test bay and operating in the recirculation mode.
The SRV was opened for 12 minutes, 15 seconds and discharged steam into the
pool, which was already circulating at steady state conditions with the one
RHR system continuing to operate. Temperature data were recorded for
45 minutes after the SRV was opened.
The more specific procedure to collect temperature data was as follows:
After verifying that all initial conditions requirements were satisfied
(Table 3-1) and proper communication existed between the control room and the
recording station in the reactor building, steady state data were collected.
The actual test started with a 15-second countdown. All recording equipment
was started before the count of ten and the SRV was actuated at time zero.
The SRV was closed at the time the bulk pool temperature was calculated to
reach 950 F based on SRV flowrate. Temperature data were recorded for at
least 30 minutes after the valve closed.
Operational limits were included in the test to ensure that safe operation of
the plant was not impaired. These limits are provided in Table 3-2. The time
to heat the pool to a bulk pool temperature of 950F was determined to be the
most limiting test condition.
3-1
NEDO-24542
During the test the following additional information was recorded:
a. Feedwater flow rate
b. Reactor vessel water level
c. Reactor vessel pressure
d. Turbine steam flow rate
e. Average Power Range Monitor (APRM) readings
f. Times the SRV was opened and closed
g. Torus pool water temperatures.
3-2
NEDO-24542
Table 3-1
TEST INITIAL CONDITIONS
Allowable
Initial reactor power level
Initial core flow
Initial reactor water level
Initial reactor pressure
Torus water volume
Torus water temperature
Drywell-wetwell AP
65% to 85%
90% to 100%
29 ±1 in.
985 ±5 psig
68,000 to 70,000 ft3
50 to 550F
0 psid
Actual Test 1 Test 2 (No RHR) (With RHR)
82.6 83.1
100% 100%
29.0 29.0
981.5 982.5
69000 69000
52.1 53.2
0 0
Table 3-2
TEST LIMITING CONDITIONS
Drywell pressure, maximum
Margins from scram:
Neutron flux, minimum
Reactor vessel water level, minimum
Reactor vessel pressure, minimum
Pool water volume, maximum
Average bay D temperature, maximum (T16, T17, T18, T19)
Bulk pool temperature, maximum
Allowable
16 psia
11%
6 in.
15 psi
76,000 ft3
140OF
950F
Actual
Test 1 Test 2 (No RHR) (With RHR)
15.5 15.2
20%
12.5-14.5
64
71,000
121
89
21%
13-14
63
72,000
97
93
3-3/3-4
NEDO-24542
4. INSTRUMENTATION
Twenty-three resistance temperature detectors (RTDs) were installed in the suppression pool. The sensors were Rosemount Series 78 Platinum RTDs with a
measurable temperature range of 50aF to 200aF and an accuracy of ±20F.
Detailed RTD specifications are given in Table 4-1. Locations of these
sensors around the torus are shown in Figures 4-1 through 4-8.
Temperatures were recorded by a Validyne DS-83 digital recorder. Detailed
DS-83 specifications are given in Table 4-2. A block diagram of the DS-83
scanner system is shown in Figure 4-10. The DS-83 temperature signals were
calibrated by a decade resistor.
Temperature data were printed on paper tape in real time, with an interval of
one minute beween successive readings of the same channel. There are 40 chan
nels available on the DS-83; channels 1 to 23 were connected to sensors Tl
T23 and channels 24 to 40 were connected to sensors Tl-T17. Temperature
data on these 17 sensors were actually recorded twice a minute, 23 seconds
apart. (Tl recorded at 1 and 24 seconds, T2 recorded at 2 and 25 seconds;
etc.)
The two plant pool temperature monitoring sensors were recorded by the plant
temperature recorder. Locations of these sensors are shown in Figure 4-9.
Other plant data were monitored on the plant process computer or other plant
recorders.
4-1
NEDO-24542
Table 4-1
SENSOR SPECIFICATIONS
Type of sensor: resistance temperature detector
Location: wetwell - pool
Sensor designation(s): Ti through T23
Variable to be measured: temperature (of pool)
Range of variables Maximum Value Minimum Value
Typical 150 500F
Maximum 212 500 F
Highest frequency component (Hz): 1
Lowest frequency component (Hz): 0
Maximum environment (including before, during, after tests)
Fluid: Water, steam
Temperature (oF): 200
Pressure (psia): 30
Other: water maximum flow rate at 75 ft/sec over sensor. Steam impingement
on sensor.
Sensor manufacturer, model: Rosemont 78 series (Platinum) RTDs
Range/accuracy: 50OF to +200aF/±2 0F steady-state.
4-2
NEDO-24542
Table 4-2
RECORDING SYSTEM SPECIFICATIONS
Digital recorder:
Input:
Scan rate:
Signal conditioning:
Output:
Format:
Linearity:
Validyne DS-83 (for pool temperature)
±10 volts for 10,000 counts
Intervals of 1, 2, 4, 10, or 20 minutes (or 1, 2, 4, 10 or 24 hrs). Automatic 40-channel mechanical scanner
PT-174
Newport Laboratories, Model 2000 DPM and 200B DPM
21 columns for 11 headings
Less than ±0.1% using standard RTD curves
4-3
NEDO-24542
SOUTH
0
90
A PLANT POOL TEMPERATURE THERMOCOUPLES (EXISTING)
Figure 4-1. Pool Water Temperature Sensor Locations in Torus
4-4
270'
NEDO-24542
T1, T2, T3
BAY C/D
SECTION A-A
VENT HEADER vSUPPORT
TORUS SHELL
A -+ A
1616 in.
() T1
T2 131.4 in.
Iin.
80.0 in.
38.0 in. T
Figure 4-2. Pool Water Temperature Sensor Location - Bay C
4-5
NEDO-24542
T4, T5, T6
Figure 4-3. Pool Water Temperature Sensor Location - Bay B
4-6
NEDO-24542
in.
Figure 4-4. Pool Water Temperature Sensor Location - Bay H
4-7
T7, T8, T9
-TORUS SHELL
A
NEDO-24542
T10, T11, T12
TORUS SHELL
Figure 4-5. Pool Water Temperature Sensor Location - Bay E/F
4-8
NEDO-24542
T13, T14, T15
BAY E
SECTION A-A
VENT HEADER SUPPORT
TORUS SHELL
A -- A
166 in.
O1 T13
131.4 in.
80.0 in. I1 T15
38.0 in.
Figure 4-6. Pool Water Temperature Sensor Location - Bay D/E
4-9
NEDO-24542
- T-QUENCHER ARM SUPPORT
- BAY D - ( DISCHARGE
VENT HEADER
- RING GIRDER
- DOWNCOMER
DOWNCOMER BRACE
T-QUENCHERPIPING
Figure 4-7. Pool Water Temperature Sensor Location - Bay D
4-10
q_
U'
Figure 4-8. Pool Water Temperature Sensor Location - Bay D
NEDO-24542
VIEW E-E
G 2250 AZIMUTH
E
Figure 4-9. Pool Water Plant-Temperature-Sensor Location-Bay G/H
4-12
SW PLANT SENSOR
SW PLAN
E
O ti2
0
'-
Figure 4-10. Block Diagram of DS-83 Scanner System
NEDO-24542
5. DISCUSSION OF RESULTS
5.1 DESCRIPTION OF PHENOMENA
When the SRV is opened, steam flows through the T-quencher into the suppres
sion pool. The heat and momentum imparted to the pool water from the inflow
ing steam result in circulation of the pool water and create thermal currents.
If there is no bulk circulation of the pool water around the torus, water
circulation and the creation of thermal currents will be essentially contained
within the discharge bay. If there is bulk circumferential circulation of
the pool water at a low velocity, the circulation and thermal current
patterns are skewed in the direction of flow. If there is bulk circumferen
tial circulation of the pool water at a high velocity, the turbulent mixing
will break up circulation and thermal current patterns.
5.2 INSTRUMENTATION AND TEST DATA SUMMARY
Twenty-three temperature sensors (Tl through T23) were installed at selected
locations in the pool to measure the pool heatup transient. The location of
these sensors is presented in Section 4. In addition, data from the two plant
pool temperature monitoring sensors were recorded by the plant process
computer. The temperature data for sensors Tl-T23 were recorded at one-minute
intervals by a data acquisition system whose output was in a paper tape format.
All of the sensors were operational for the two tests. Time plots of tempera
tures for each sensor are provided in Appendix A.
Sensors Tl through T23 were distributed within bay D and throughout the pool
to measure: (1) temperature of the water supply feeding the T-quencher,
(2) average bay D temperature, (3) bulk pool temperature, and (4) temperatures
in locations comparable to those of the previous tests.
5-1
NEDO-24542
The sensors were located around the torus in approximately every other bay, and were located within a bay at approximately the volumetric center of
equal volume regions.
5.3 RESULTS
5.3.1 Bulk Pool Temperature
The bulk pool temperature was measured by 15 sensors (Tl through T15) distributed
throughout the pool. These sensors were located to give an accurate measure
ment of the bulk pool temperature; i.e., within 30F of the calculated values.
The measured bulk pool temperature (average of the 15 sensors) is compared
to the calculated bulk pool temperature as a function of time in Figures 5-1
and 5-2. The long-term bulk pool temperature (average of the 15 sensors) was
used as one of the ways to determine the SRV steam flow rate (Appendix C).
Since the SRV steam flow rate was calculated to be essentially the same with
two other methods, there is good confidence in the measurement of the bulk
pool temperature.
5.3.2 Test Bay Temperature
Two temperatures are of interest within bay D itself: the temperature of
the water feeding the T-quencher and the average bay temperature. The
upstream and downstream sides of the bay are analyzed separately. The tem
perature of the water feeding the T-quencher is the temperature measured
above and below the T-quencher arm; i.e., T18, T19 and T20, T21.
Figures 5-3 and 5-4 present the maximum temperatures of the water feeding
the T-quencher with the calculated bulk pool temperature for both tests.
In general, while the SRV is open, the maximum temperature occurs below the
arm. After the SRV is closed, the maximum temperature is above the arm.
The average upstream and downstream bay D temperatures are the average of
the four sensors on each side of the bay. The two sides of the bay are pre
sented separately. Figures 5-5 and 5-6 present the average bay D tempera
tures and the calculated bulk pool temperature for both tests.
5-2
NEDO-24542.
5.3.3 Torus Temperature Distribution
The average temperatures for bays other than bay D are shown in Figures 5-7
and 5-8. The total torus temperature distribution is given in Figures 5-9
and 5-10 for specific times. In the first test (no RHR), the bays on either
side of the T-quencher (bays C, D/E) heated up at approximately the same rate
for the first few minutes. Then the pool circulation induced by the holes in
the endcap slowed the rate of temperature rise upstream of the T-quencher. If
there were no pool circulation, the bays farther away on either side of the
T-quencher (bays B and E/F) should show approximately the same temperature
due to convective currents. In these more distant bays, the pool circulation
was sufficient to override the convection and to heat up bay B and bay H
faster than bay E/F. This indicates that steam discharging from the endcap
holes did induce some circulation.
In the second test (with RHR) , the pool water was moving at sufficient velocity
such that the temperature spread in both directions was not so apparent,
although there appeared to be some spreading, since the top sensor in bay D/E
upstream of the T-quencher heated up in the first two minutes. The tempera
tures of bays B and C downstream.of the T-quencher were much the same
bay C reaching a given temperature approximately one minute earlier than bay B.
The temperatures of bays D/E and E/F upstream of the T-quencher were also much
the same, although oscillating around each other. The temperature of bay H
at the opposite side of the torus was somewhere between the temperatures
of other bays. All bays heated up at approximately the same rate. After the
SRV was closed, all the temperatures blended to within a total range of five
degrees in six minutes. This shows the RHR modifications did induce consider
able pool mixing. Temperature oscillations appeared in the temperature
transients of the second test (with RHR) (e.g., Figure A-9) and also to a
small degree in some of the centrally elevated sensors of the first test
(no RHR) (e.g., Figure A-2). These waves show the effects of an uneven tem
perature distribution around the torus, as shown in Figures 5-9 and 5-10.
5-3
NEDO-24542
5.3.4 RHR Pool Cooling
Following the first test, both RHR systems were operated in the pool cooling
mode to bring the pool temperature down to %500F. Temperatures were recorded
during this time to see how quickly RHR system operation could reduce the
stratification of an initially still pool. Time plots of temperatures for
each sensor are provided in Appendix B.
5-4
1 1 1 1 11111f l i i 1 1 1 1 11 'I I
I iii 111 I 1 1i
] & AVERAGE OF T1-T15
40 2 4 6 8 1 1 1 1 1 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure 5-1. Measured Versus Calculated Bulk Pool Temperature - Test Without RHR
120
110
100
90U
1
w
CL
U-' -M
0
.I Ila
vzn . . , . i i . .. . I I . . I 1 1 . 1 . 1- 1 1 1 1 . 1 - 1 - 1 .
1 1 1 1 1 1 1 1 1
DU
t
I
I I l l I I I I
& AVERAGE OF T1-T15 11
1111111 111111111 I
' I 'I I I I II i i Ii ' " I 'I I
40 2 4 6 L LL1L1. 1 1 2 1 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure 5-2. Measured Versus Calculated Bulk Pool Temperature - Test With RHR
120
110
100
U 0r D
iwU a.
w Ui
I l I lII1
90
80
70
II
-S
tri
t-n
7
rn
I I - 7 7 - -
I Afli i
I Xr!
I i V I
A DOWNSTREAM ARM (MAXIMUM OF T20-T21)
* UPSTREAM ARM (MAXIMUM OF T18-T19)
T19 T20
140
130
120
110
100
90
45
.K POOL
NI) 4-1
i i i i i i i I 1 11
SRV CLOSES
ERhI
0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure 5-3. Maximum Temperature of Water Feeding the T-Quencher - Test Without RHR
L
Iwn CL
T18 tl 1 1 1
80
70
60
50
40
aT21 I
I .i i . I
-
I i
r - i ! i f i1 4 4 4 I. I I I I I I . . I . .
y
I Iii I BULK POOL TI I I I I I
DOWNSTREAM ARM , (MAX IMUM OF T20-T21)
* UPSTREAM ARM (MAXIMUM OF T18-T19)
T19 T20
T18 T21I I II IPERAT
II !I I II II I I II I I IF I I
1i I lil SRV CLOSES
I I I I I I I I I I I I I 1I I
6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure 5-4. Maximum Temperature of Water Feeding the T-Quencher - Test With RHR
130
120
I I I I
4 -- ~--
-H
7'KTh'~
I I I I I I I±Hzb--V&~iF4110
100
90
80
2(
4-4
Z0
w a.
w I-
70
60
50
40E 0 2 4
0
f"3
I I ' 11
,
,
: I . II I I
-
I1I1 I 1 1 1 1 1 1 1 1 11L L
! I I II
- 4 I I
0 0
L/1 .p 11.
TIME (min)
Average Bay D Temperatures, Test Without RHR
140
130
120
110
U.
9L 100 w
90 w
w
Figure 5-5.
140
-4 130
120
t 4 4-
110
In
CL
80 I F 10 .4
I-
SRV C LOSES 90 4
50
40 I 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28
TIME (min)
Figure 5-6. Average Bay D Temperatures, Test With RHR
734 36I I 3 4
30 -3 IC 34 36 358 40w
* BAY C (AVERAGE OF T1-T3)
O BAY B (AVERAGE OF T4-T6)
O BAY H (AVERAGE OF T7-T9)
A BAY E/F (AVERAGE OF T10-T12)
X BAY D/E (AVERAGE OF T13-T15)
. I . .I I -I - 1 . 1
SRV CLOSED
18 20
TIME (min)
22 24 26 28 30 32 34 36 38
Figure 5-7. Bay Average Temperature, Test Without RHR
130
120
110
LL 0
F
I.-
100
90
80
70
60
50
40
t~j 0
Ln
0 I I . ..1 . 6 L 1 1..2. 1 4 16J 0 2 4 6 8 10 12 14 16 40
... ... I... - I4.T
130
120
110
100
90
80
70
60 LSRV CLOSED 600
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure 5-8. Bay Average Temperature, Test With RHR
U
0U
wj
z txj
0
G/H GI I I
F/G_ F E/F E-- P . 14 wI ON P 1
I I I
b-V
El PLANT SENSOR (11 MIN)
A AVERAGE OF SENSORS IN BAY
11111
BAY DESIGNATIONS D/E D C/D C B/C B A/B A
D.Im ' 1 4T I IIII
H
I
140
130
120
110
100
90
L7 min
C
Lni
. . . . .,,. n I ,
3 mi
111111
5 sec1
.L140 120 100 80 60 40 20 0 20 40 60 80 100 120 140 160
DISTANCE FROM BAY D CENTERLINE (ft)
Bay Average Temperature, Test Without RHR
1
11 0 w
I-
80
70
60
50
40160
' I
i i H+i i UPSTREAM t+ -
149.2 1 1 1 " -aTTI zj:l
I I IH/A
I-T-T--H :F ---. 4
Figure 5-9.
BAY DESIGNATIONS
H
-
160 140 120 100 80 60 40 20 0 20 40 60 80 100 120 140 160
DISTANCE FROM BAY D CENTERLINE (ft)
Figure 5-10. Bay Average Temperature, Test With RHR
120
110
t-n U
I-
NEDO-24542
6. REFERENCES
1. "Mark I Containment Program Final Report:
Task Number 5.1.2," NEDO-21864, June 1979.
Monticello T-Quencher Test.
6-1/6-2
NEDO-24542
APPENDIX A
POOL TEMPERATURE TRANSIENTS
130
120
110
2 100
I- 90
LU l Uln
m 80
70
60
50
0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-1. Bay C Temperatures, Test Without RHR
*Proorietary information deleted
*
130
120
110
C 100
90
7 0 loo3 UU'
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
.TIME (min)
Figure A-2. Bay B Temperatures, Test Without RHIR
*Proprietary information deleted
130
120
110
U. 100
w
o4 90 cc
80
70
60
50
400 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-3. Bay H Temperatures, Test Without RHR
*Proprietary information deleted
*
z
0-nl
130
120
110
E 100
LU oo
I- 90
tL
m 80
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-4. Bay E/F Temperatures, Test Without RHR
*Proprietary information deleted
*
z~
C,
130
120
110
2100 o
70
60
50
400 2 4 6 8 10 12 14 16 18 20 22 24 26
TIME (min)
Figure A-5. Bay D/E Temperatures, Test Without RHR
*Proprietary information deleted
28 30 32 34 36 38 40
*
zT
t'3
130 1
120
110
2 100
oo
09
1-80
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26
TIME (min)
28 30 32 34 36 38 40
Figure A-6. Bay D Temperatures, Test Without RHR
*Proprietary information deleted
*
0
140
130
120
110
Uo 100 L
w s80
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22
TIME (min)
24 26 28 30 32 34 36 38 40
Figure A-7. Bay D Temperatures, Test Without RHR
*Proprietary information deleted
I*d
130
120
110
100 0
90
w CL
w I- 80
70
60
50
40
0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-8. Plant Sensor Temperatures, Test Without RHR
*Proprietary information deleted
*
0
Li' -
0 2 4 6 8 10 12 14 16 18 20
TIME (min)
22 24 26 28 30 32 34 36 38 40
Figure A-9. Bay C Temperatures, Test With RHR
*Proprietary information deleted
130
120
110
oo a 100
70
60
50
40
*
U.
130
120
110
100
LL 0
.1L 70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-10. Bay B Temperatures, Test With RHR
*Proprietary information deleted
*
z
4-1
130
120
110
100
U0
80
LU C2 80 LU
70
60
50
4030 32 34 36 38 40
Figure A-11. Bay H Temperatures, Test With RHR
*Proprietary information deleted
0 2 4 6 8 10 12 14 16 18 20 22 24 26 28
TIME (min)
*
'-
4 6 8 10 12 14 16 18 20 22 24 26 28 30
TIME (min)
32 34 36 38 40
Figure A-12. Bay E/F Temperatures, Test With RHR
*Proprietary information deleted
130
120
110
100
LU
90
90 I-.
w 02 80; LU
70
60
50
40
tz
IL3
0
130
120
110
- 100 L
w
90
w
mi 80 IL
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38 40
TIME (min)
Figure A-13. Bay D/E Temperatures, Test With RHR
*Proprietary information deleted
*
0 2 4 6 8 10 12 14 16 18 20 22
TIME (min)
24 26 28 30 32 34 36 38 40
Figure A-14. Bay D Temperatures, Test With RHR
*Proprietary information deleted
130
120
110
LL
. 100 Lii
(C 90 Lii
2 .
80
70
60
50
40
*
z
0 C-l
-
130
120
110
IL 100
80
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22
TIME (min)
24 26 28 30 32 34 36 38 40
Figure A-15. Bay D Temperatures, Test With RHR
*Proprietary information deleted
*
zi
M' 03
120
110
100
IL.
cc90 U
80
70
60
50
40 0 2 4 6 8 10 12 14 16 18 20 22 24 26 28 30 32 34 36 38
TIME (min)
Figure A-16. Plant Sensor Temperatures, Test With RHR
*Proprietary information deleted
z
9I 0~'
4{
A
NEDO-24542
APPENDIX B
POOL TEMPERATURE TRANSIENTS WITH RHR POOL COOLING
160
150
140
130
120
110
LL 0
100
2 90 w
80
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-1. Bay C Temperatures, RHR Cooling
*Proprietary information deleted
160
150
140
130
120
- 110 LL 0
80 100 < 50 wU 90 J I-n
80
70
60
50
40 60u 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-2. Bay B Temperatures, RHR Cooling
*Proprietary information deleted
140
130
120
110
100 LL .
LU
0 80
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-4. Bay E/F Temperatures, RHR Cooling
*Proprietary information deleted
140
130
120
110
100
U
0 90
a
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-3. Bay H Temperatures, RHR Cooling
*Proprietary information deleted
*
140
130
120
110
100
U0
D 90 t
Lii CL Ln
80
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-5. Bay D/E Temperatures, RHR Cooling
*Proprietary information deleted
140
130
120
110
100
D 90
w CL)
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-6. Bay D Temperatures, RHR Cooling
*Proprietary information deleted
140
130
120
110
100
U
0 90 <
80
70
60
50
40 60 70 80 90 100 110 120 130 140
TIME SINCE SRV OPENED (min)
Figure B-7. Bay D Temperatures, RHR Cooling
*Proprietary information deleted
NEDO-24542
APPENDIX C
SRV STEAM FLOW RATE
NEDO-24542
APPENDIX C
SRV STEAM FLOW RATE
Calculation of expected SRV steam flow rate gave a bounding value of
849,000 lbm/hr. Evaluation of the data taken in the first test determined
that the SRV steam flow rate was actually lower. This allowed the SRV to be
open for an additional minute before reaching bulk pool temperature limits in
the second test. The three techniques used to determine this steam flow rate
are presented here. The results of the three techniques are within 5%. A
presentation of each calculational method follows.
C.1 SUPPRESSION POOL HEATUP METHOD
Based on the anticipated SRV steam flow rate of 849,000 lbm/hr, the valve was
opened long enough to heat the pool to a calculated bulk temperature of 950F.
Looking at the results of the first test, the bulk temperature was 4890 F at
the end of the test (Figure 5-2). Since the relationship between steam flow
rate and time to heat the pool to 950 F is linear, the ratio of expected to
actual test results will give the actual steam flow rate.
expected pool heatup rate expected steam flow rate. (C-1) actual pool heatup rate actual steam flow rate
actual steam flow rate = expected steam flow rate (C-2)
(actualN exact )pool heatup
m = 849,000 lbm/hr * (89 - 52.5)oF (C-3) actual 8(95 - 52.5)oF
m actual= 729,000 lbm/hr = 202.5 lbm/sec (C-4)
C.2 REACTOR PRESSURE VESSEL MASS BALANCE METHOD
During the extended discharge test, the plant process computer recorded turbine
steam flow and feedwater flow. A mass balance can be made for the reactor
pressure vessel to determine the SRV flow.
C-1
NEDO-24542
TSF TSF
RPV RPV FWF FWF
SRVF
BEFORE AFTER
Output from RPV - nput to RPV + Storage of RPV = 0 (C-5)
(TSF + SRVF) - FWF + STG = 0 (C-6)
where
TSF = turbine steam flow
SRVF = SRV flow
FWF = feedwater flow
STG = storage of RPV
Since measurements were taken when water level change and transients in TSF
and FWF had stabilized the storage term is removed.
TSF + SRVF - FWF = 0 (C-7)
Likewise,
ATSF + ASRVF - AFWF = 0 (C-8)
where
A = (flow before SRV is opened) - (flow after SRV is opened)
ATSF = 0.85 x 106 lbm/hr
ASRVF = 0 - SRVF
6 AFWF = 0.10 x 10 lbm/hr
SRVF = AFWF - ATSF (c-9)
SRVF = -0.10 x 106 + 0.85 x 106 (C-1)
SRV flow = 750,000 lbm/hr = 208.33 lbm/sec (C-11)
C-2
NEDO-24542
C.3 CONDENSATE STORAGE TANK LEVEL CHANGE METHOD
During SRV discharge, some of the water stored in the condensate storage tank
is drawn by the feedwater system to supplement the reduced flow of condensate
from the turbine-condenser. If a mass balance is made for the entire system,
the steam flow through the SRV can be determined.
SRVF
CF
CSTF
Output from RPV - input to RPV + storage of RPV = 0 (C-12)
Measurements were taken when water level change and transients had stabilized
so there is no storage term.
SRVF + TSF = FWF = CF + CSTF
where
SRVF = SRV flow
TSF = turbine steam flow
FWF = feedwater flow
CF = condenser flow
CSTF = condensate storage tank flow
(C-13)
C-3
NEDO-24542
Assuming no losses in the turbine-generator and condenser
TSF = CF
Then,
SRVF = CSTF
Likewise,
ASRVF = ACSTF
The condensate storage tank drawdown volume was accurately established at
18,400 gal/ft elevation. There is more confidence in this value than in the
flow rates read from strip charts of the second method. The difference in
water levels of the condensate storage tank before and after test no. 1 was
0.90 ft.
SRVF = 0.90 ft * 18,400 gal/ft *
* 60 min/hr
= 752,000 lbm/hr =
8.33 lbm/gal * 1/11 min
208.88 lbm/sec
C-4
(C-14)
(C-15)
(C-16)
SRV flow
(C-17)
(C-18)
NUCLEAR ENERGY DIVISIONS * GENERAL ELECTRIC COMPANY SAN JOSE, CALIFORNIA 95125
GENERAL ELECTRIC
TECHNICAL INFORMATION TITLE PAGE
EXCHANGE
By cutting out this rectangle and folding in half, the above information can be fitted into a standard card file.
DOCUMENT NUMBER NEDO-24542
INFORMATION PREPARED FOR
SECTION
Nuclear Power Systems Division
Containment Improvement Programs
BUILDING AND ROOM NUMBER PYD 409
AUTHOR SUBJECT TIE NUMBER 79NED101
B. J. Patterson 730 DATE August 1979
TITLE Mark I Containment Program GE CLASS Monticello T-Quencher Thermal I Mixing Test Final Report GOVERNMENT CLASS Task Number 7.5.2
REPRODUCIBLE COPY FILED AT TECHNICAL NUMBER OF PAGES SUPPORT SERVICES, R&UO. SAN JOSE, 79 CALIFORNIA 95125 (Mail Code 211) SUMMARY
This document presents the results of the Monticello T-Quencher Thermal Mixing Test that was performed in November 1978. The objective of the test was to evaluate the effectiveness of a modified T-quencher design (holes in one endcap) and a modified residual heat removal (RHR) return system (90-degree elbow and 10inch by 8-inch reducing nozzle at the end of discharge line) on thermal mixing of the water in the pressure suppression pool during safety/relief valve (SRV) discharge. Results of the test show that the modified RHR discharge system yields a marked improvement in thermal mixing over the modified T-quencher design.
MAIL CODE 90 5
GENERAL* ELECTRIC