ML20081C034
| ML20081C034 | |
| Person / Time | |
|---|---|
| Site: | Cook, 05000000 |
| Issue date: | 02/26/1975 |
| From: | INDIANA MICHIGAN POWER CO. |
| To: | |
| Shared Package | |
| ML20081B916 | List: |
| References | |
| FOIA-83-296 NUDOCS 8310310077 | |
| Download: ML20081C034 (67) | |
Text
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.,,, .e DONALD C. COOK NUCLEAR PLANT l l
UNIT 1 l INDIANA & MICHIGAN POWER COMPANY l l
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ING THE ATTACHED FILES ARE OFFICI AL [ RECORDS OF THE OFFICE OF REGULATION. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME '
PERIOD ANS MUST BE RETURNED TO THE CENTRAL RECORDS STATION 008. ANY PAGE(S)
REMOVED FOR REPRODUCTION MUST BE RETUR TO ITS/THEIR ORIGINAL ORDER.
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E DEADLINE RETURN DATE o
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MARY JINKS, CHIEF CENTRAL RECORDS STATION
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REACTOR CCHTAINMDTT BUILDING INTEGRATED LEAK RATE TEST D. C. C00K NUCLEAR PLANT - UNIT #1 TABLE OF CONTENTS PAGE
. . 1.0 Introduction 1 2.0 Test Criteria and Results A. Test Criteria 3 B. Test Results 4 30 conduct of Test A. Organization of Test 6 B. Log of Times and Events 8 4.0 Measurements and Calculations -
A. Test Equipment 10 B. Sensor Locations 13 C. Pressurization Apparatus 16 D. RTD Weighting Factors 19 E. Computer 24 50 Analysis and interpretation A. Discussion of Graphical Data 34 B. Cocparison of One Volume with Three Volume Method 37 C. Erro. Analysis 39 D. Discussion of Air Particulate Detector Leakt.ge 43
. 6.0 Tabulated Results 49 70 Local Leak Test Program 56 8.0 References 64 k
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1-INTRODUCTION The Pre-Operational Integrated Leakage Rate Test (ILRT) for the Donald C. Cook Nuclear Plant - Unit 1 Reactor Containment was sucessfully completed on November 24, 1974 by members of the Indiana and Michigan Power Company and the American Electric Power Service Corporation.
As per FSAR and Technical Specifications the containment allowable leakage rate La is limited to 0.25 percent by weight of the containment air per twenty-four hours at a pressure P, of 12.0 PSIG. In conformance with the criteria specified in Appendix J of 10CFR 50 this allowable leakage is reduced to 0 75 L, which is equivalent to 0.1875 percent by weight per day. The measured leakage rate for the Donald C. Cook Nuclear Plant - Unit 1 Reactor Containment was found to be O.16044 percent by weight per day.
This ILRT is unique in the fact that it is the first such test to be performed on an Ice Condenser equipped reactor containment.
The reactor containment is designed to insure that acceptable limits for leakage to the environment of radioactive materials are not exceeded under conditions resulting from the Design Basis Accident for doses dictated by the 10CFR 100 criteria. The steel-lined, re-inforced concrete containment structure, including foundations, accesshatches, and penetrations is designed and constructed to maintain I
full containment integrity when subjected to accident forces.
The Reactor Containment is divided into three volumes; a lower volume which houses the reactor and Reactor Coolant System, an intermediate volume housing the energy absorbing ice bed and an upper volume which accommodates the air displaced from the other two volumes during the unlikely event of a loss-of-coolant accident.
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2-INTRODUCTION (CONTD.)
The containment design pressure is twelve (12) PSIG.
The ILRT was performed as specified in the I&M approved Pre-operational Test Procedure Po-033-334 written by AEPSC. The
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American National Standard - ANSI N45.4-1972-leakage - Rate Testing of Containment Structures for Nuclear Reactors and 10CFR50; Appendix J were used as a guideline for the procedure. The absolute test method was used to calculate the leakage rate using data taken every thirty
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. minutes for twenty-four hours. The normalized weight of original air r~ remaining in the containment determined from these calculations was plotted against time and a statistically averaged leakage rate in per cent by weight per day was obtained by a linear least-squares fit to .
the resulting graph. Following the twenty-four hour test, a supplemental test was performed by imposing a known leak on the containment to verify the validity of the measurements made during the twenty-four hour test.
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3-2.0 TEST CRITERIA & RESULTS f'
. A. TEST CRITERIA
[i As specified in the Acceptance Criteria of the test procedure the test was considered acceptable when the following I' had been verified:
- 1. The measured leakage rate (LAM)3 as determined by a linear least-squares fit to a graph of calculated points, 5~ proves to be less than 0 75LA as specified in the D. C.
Cook Nuclear Plant Technical Specifications.
- 2. The accuracy of this test has been verified by per-formance of the supplemental test. The measured leakage rate (LAM) is validated when the difference between the leakage rate L'AM, determined from the supplemental test,
,. and the leakage rate LAM, determined from the linear least
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i squares fit to the graph of calculated points, is within 0.25 LA*
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_y-B. TE3T RESULTS
- During the twenty-four hours of the ILRT, computer l calculations were performed to determine the leakage rate at thirty minute intervals. These calculations were made using the absolute test method based on weighted individual compartment calculations I
i and volumetric weighting of RTDs for average compartment temperatures, f At the end of the twenty-four hours (which corresponds to computer run number 49) the measured leakage rate was 0.16191% by weight per day. A 95% confidence level was imposed on the calculations to yield a " leakage band" between 0.18564 and 0.13817 per cent per day. Note the higher limit of leakage is still below the allowable limit. With these results the twenty-four hour ILRT was considered acceptable on November 24, 1974 and the go ahead for the Supplemental Test was given. As the Supplemental Test continued the confidence limits for the leakage rate were observed as a basi's for termination.
A minimum test duration of six hours following the stabilization period is required as per the test procedure. After nine hours
' elapsed the Supplemental Test was terminated with a measured leakage of 0 33642 per cent per day and confidence limits of 0 37939 to 0.29356 per cent per day.
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< The known leak imposed on the containment was set to r 2 70 SCFM, (flowmeter correctedh which is equivalent to 0.17544 per cent by weight per day. The Supplemental Test was performed in r accordance with ANSI 45 4 and 10 CFR 50 Appendix J which state the containment leakage rate is determined by deducting the known leakage rate from the composite leakage rate. The results from the Sup-
, plemental Test are acceptable provided the difference between the Supplemental Test Data and the Type "A" test data is within 0.25La.
5-When the forementioned deduction is made, the difference between the Supplemental Test data and the twenty-four hour ILRT is 0.00093%
.- per day which is well within the 0.25 La margin (0.0625% per day).
With the above results obtained from the twenty-four hour ILRT and the Supplemental Test, all Acceptance Criteria was met and the Pre-Operational Test considered acceptable.
To verify the results obtained during the actual performance of the ILRT were indeed the true leakage rate, all input data was rechecked to locate any errors. A review of the data input did reveal errors caused by handling of the input parameters. These errors were corrected and a new leakage rate of 0.16044 per cent by weight per day was computed .s the official leakage rate. It should be noted that by .
correcting the bad data points the confidence limits were improved to a 0.17097 to 0.14991 per cent by weight per day leakage band. The Supplemental Test Data was also reviewed, corrected and rerun on the computer which calculated the official composite leakage to be 0 31501 per cent by weight per day with the confidence limits at 0 35525 to 0.27477 per cent by weight per day. When the known leak was substracted l
from the composite leakage rate, the leakage difference is 0.02087 per cent per day, which is well below the 0.25La acceptance.
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6-30 CONDUCT OF TEST A. ORGANIZATION OF TEST v
I&M Power Company Performance Engineers were responsible for the Integrated Leak Rate Test. The testing activities were supervised by the test supervisor (1 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) with support given by
{. various sections as described in Figure 3 1.
t Test responsibilities:
(1) Shift Operating Engineer
,. (a) En.sure that the plant is maintained in a safe condition i (2) Test Supervisor (1 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift)
- (a) General conduct of test (3) AEPSd Support Group (4)
(a) Technical Support to the test supervisor (b) Test results review responsibility (4) Timekeeper / Data Analyst (1 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift)
(a) Responsible for coordinating data collection and trans-forming data to computer input format.
(b) Responsible for preliminary review of data for correctness.
(5) Computer Operator (1 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) r t (a) Responsible to transfer data from computer input sheets to data cards and receiving results printout from the computer.
(6) Data Takers (4 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift)
(a) Responsible to readout and record specific instriunents assigned to and apply correction factor to reading, if
- m. required.
(7) Startup/ Maintenance (On Call)
(a) Responsible to assist and coordinate any repair work that 7
may be required during the test.
I (8) Instrument Technician (1 per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> shift) 1 (a) Responsible for maintaining all test instrumentation in
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working condition.
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START-UP COMPUTER TIME AND OPERATOR KEEPER AEPSC MAINTENANCE DATA -SUPPORT DEPARTMEtiT ANALYST GROUP
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- TAKERS TECHNICIArt s.
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- 3. LOG OF TIMES AND EVENTS Prior to containment pressurization an inspection of all e
, accessible interior and exterior surfaces of the Containment
- Structure was performed to uncover any evidence of structural deterioration. The visual inspection consisted of verifying in
" the log the condition of containment surfaces elevation by elevation and verifying by check list the integrity of the containment penetrations. The inspection did not uncover any adverse conditions which may have affected the leak-tightness of
' the containment,therefore, the pressurization of the containment was initiated.
Pressurization of the Containment Vessel for the Integrated Leakage test began at 23:22 hours on 11/20/74 and continued through 23:04 hours on 11/21/74. Data collection for this period consisted
[ of an hourly log of the average temperatures, pressures, and vapor
,- pressures for the 3 containment compartments. Upon attainment of test pressure, 23: 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> on 11/21/74, pressurization was discontinued I by closing the air supply valve and data collection at 1/2 hour s
intervals began in a preliminary attempt to determine the leakage rate and to determine if stabilization criteria could be met. After concluding that the preliminary data showed that leakage should be acceptable, the containment pressure was increased to 12 5 psig to ensure sufficient capacity for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and supplemental tests.
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The containment pressurization was isolated by removing the spool piece and installing a blank flange which was leak tested. Formal
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data collection to verify stabilization criteria began at 12:47 hours j I
L on 11/22/74. Data collection for this period consisted of 1/2 hourly readings of forty-six containment temperatures, two ambient temperatures ;
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six containment pressures, one ambient pressure, and four dew point temperature readings. After revieu of the data, it was determined that temperature stabilization criteria for the Ice Condenser could not be achieved due to the cyclic operation of the air handling units causing larger than anticipated temperature deviations in this compartment . The criteria was waived for the Ice Condenser compartment
, and at 20:17 hours on 11/22/74 the formal 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test data collection commenced. Data collection for this period was the same as for the stabilization period. Raw data was punched on cards and input to the computer for averaging and regression analysis. Final reading for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test was recorded at 20:17 on 11/23/74 with the leakage rate equal to .16191% per day. After review of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test data and determination of its acceptability, a known leak was introduced to the containment volume through the supplemental test flow meter and the supplemental test stabilization period began.
This occured at 21:00 hours on 11/23/74. After sufficient stabilization time the Supplemental Test began at 2:00 hours on
, 11/24/74 and was terminated at 10:00 on 11/24/74. Data collection
, for the Supplemental Test was identical to that during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test. Review of the data verified the sum of the introduced leak and the containment leakage equal to .33642% which agreed with the measured value within 25%. Therefore, all acceptance critiera were met and the Integrated Leak Rate Test was terminated.
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4.0 MEASUREMENTS AND CAlfULATIONS A. TEST EQUIPMENT The best state of the art pressure, temperature, and vapor ,
pressure instrumentation was employed during the ILRT test. The
- Ice Condenser reactor containment is unique in the fact that con-tainment design pressure is limited to 12 PSIG. This low pressure l/ requires more accurate instrumentation to detect leakage to the i
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, same degree as for conventional containments with design pressures of 50-60 PSIG.
Six prescision Mensor quartz manometers were used to measure containment absolute pressure. Two sensed lower volume pressure,
- two upper volume, and two ice condenser pressure. A seventh manometer measured ambient pressure during the test. Each instrument was supplied f
with an NBS certified calibration correction curve. These correction
, factors were applied to readings during the test. The direct reading accuracy of the manometers is .020% full scale with no corrections applied and .010% of reading + .002%F.S. when readings are corrected.
The manometers have a resolution capacity of .0001 PSIA. The large I
t resolution capability of this instrument and the fact that six sensors
, were used resulted in a ~very precise pressure determination during i
l the ILRT.
Forty six precision RTD sensors were located in the containment for temperature determination. Seven sensors were in the Ice Condenser, twenty four in the lower volume and fifteen in the upper volume. Two
, sensors were also located external to the containment for an ambient
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L temperature indication. 2,330ficopper RTD's were used for this ap-plication. Copper was selected because its resistance temperature L
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relationship is the quite linear in this temperature range. The high resistance sensor was specified to obtain a large change in resistance for a small change in temperature (Ell /o p). This resulted in a high resolution capatility. The resistance of each sensor is readout with a Rosemount bridge whose 0-50 mv. output is fed into a Doric Scientific Corporation digital printout device. The Doric printer is programed to accept a linear 0-50 mv. input for an output range of 0-100 F. Each temperature sensor, each bridge, and the Doric printer were supplied with calibrations certified to NBS. Temperature correction factors were applied. The overall temperature sensing accuracy was .1 F. Volume fractions were also calculated for each sensor, and these weighting factors were applied to each temperature reading in the computer program.
Four Cambridge Dew Point Hydrometers were used to sense containment humidity during the test. Two units sensed lower volume dew point, one Ice Condenser and one in the upper volume. Each unit is complete with its own sample pump which draws the sample through the mirror surface sensor. The sensor is cooled until vapor is formed on the mirror surface and electronic circuitry is used to maintain an equilibrium condition on the sensor. The sensor temperature
, is measured by the use of a platinum RTD. Each RTD had certification
! to NBS. The overall dew point temperature sensing accuracy is 5 F.
t- A Fisher & Porter flowmeter was used to introduce a known leak during the supplemental verification test. The flowmeter was a s
rotometer with certification to NBS at 12.0 PSIG and 70 F by the manufacturer. The specified accuracy of the meter is 2%
i The chart shown in Table 4.1 lists identification numbers and specifications of test instrumentation used during the test in tabular form.
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If4STRUMErlT SPECIFICATIONS i
l' Item Manufacturer Type Model Serial # Range Accuracy 1-Pressure Mensor Duartz 632, 633, 427, 0-30 PSIA .0001 PSIG Resolution l Manometer 428, 425, 426, 631 1.010% of Heading +
- .002% F.S.
Temperature Hinco 2330.n. Copper S3334 1 thru 101 0-1000F t.010 F Srnsors RTD.
! Temperature Doric Digitrend Linear Readout 210 6789 0-100 F .040F R2adout Printer 0-50 MV j
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Temperature Doric, Bridge & . 0-1000F .10F y (Ov;rall System) Sensors ,
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,. Dew Point Cambridge Mirror Surface 992-C1 409, 428, 418, 420 -100 - .5 F
- ! Temperature +2000
.l i Supplemental Fisher & Porter Rotometer 10A1735S 7112AA280A1 0-17CFM 2% f.s. !
I 1 Lcak Pressure Gage Heise_ Bordon Tube CCM 7870 0-30 PSIG .1% f.s.
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B. SENSOR LOCATIONS The Test Instrumentation, which included forty-six RTDs, six absolute pressure reading quartz manometers, and six vapor pressure sensing points, was located throughout the containment to give an accurate accounting of the containment environmental conditions
$ during the test. The actual location of each sensor can be seen on the elevation and plan views of the containment found on Figure 4.1 of this report. l In genera.1., the breakdown of sensor locations as per con-tainment volume are as follows:
I. UPPER VOLUME 1 a) Fifteen Resistance Temperature detectors 1.
ETR-101 9 ETR-109
- 2. ETR-102 10. ETR-110
- 11. ETR-111 3 ETR-103
- 4. ETR-104 12. ETR-112 5 ETR-105 13. ETR-ll4
- 6. ETR-106 14. ETR-128 7 ETR-107 15. ETR-133 9
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b) Two absolute pressure reading Quartz manometers.
c) One vapor pressure sensing point (one Hygrometer).
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- i. II. LOWER VOLUME a) Twenty-four resistance temperature detectors
- s. 1. ETR-113 13. ETR-135
- 2. ETR-122 14. ETR-136
[. 3 ETR-123 15. ETR-137
- 4. ETR-124 16. ETR-138 5 ETR-125 17. ETR-139
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- 6. ETR-126 18. ETR-140
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7 ETR-127 19 ETR-141
- 8. ETR-129 20. ETR-142 9 ETR-130 21. ETR-143
- 10. ETR-131 22. ETR-144
- r. 11. ETR-132 23 ETR-145
- 12. ETR-134 24. ETR-146 b) Two absolute pressure reading Quartz Manometers c) Four vapor pressure sensing points (two Hygrometers).
III ICE CONDENSER VOLUME a) Seven resistance temperature detectors
- 1. ETR-ll5 5 ETR-119 t 2. ETR-116 6. ETR-120 3 ETR-ll? 7. ETR-121
- 4. ETR-ll8
( b) Two absolute pressure reading Quartz Manometers c) One vapor pressure sensing point (One Hygrometer).
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C. PRESSURIZATION APPARATUS The Plant air system was used to pressurize the ontainment for the Integrated Leakage Rate Test. A three stage centrifugal air compressor located in the turbine room supplies compressed air f to the plant air system. The compressor is designed to provide 1500 cfm of oil free compressed air at a discharge pressure of t 100 psig continuously. Air discharged from the plant air compressor
- retains the third stage heat of compression. An aftercooler installed in the discharge line, is designed to cool the air to within 10 F of,its inlet cooling water temperature. The condensed moisture resulting from the cooling is removed by a cyclone-type separator installed immediately downstream of the aftercooler. The air discharged from the moisture seperator is fed through the plant air system to the I Containment test pressurization filters and dryers. In order to avoid condensing water vapor during the test the plant air supplied is dried to a dew point that is below the coldest temperature anticipated in the Ice Condenser. Two parallel, 100 percent capacity strings of prefilters prevent contamination of the drying dessicants from i moisture carryover or scale. Two afterfilters in parallel protect the containment from desicant dusting.
L The dried and filtered air is fed through a three inch test I
- line, spool piece, and valve to penetration #CPN-57 This valve was used to throttle the air flow during pressurization and de-pressurization. The spool piece was used to isolate the containment i volume from the pressurization system after stabilization was met t
during the test.
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PRESSURIZATION APPARATUS (CONTD.)
l' The spool piece was removed after pressurization was complete.
A blank flange was installed and leak tested to prevent out leakage from the penetration. See Figure 1+.2 for sketch of pressurization apparatus.
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FIGURE 1+.2 UNIT # 1 -REnoVABLE CONTAINnENT stoot mece H '
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- -II PLANT AlR, AFTER COOLER
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CoHTAINMENT TEST PRE-FILTERS PRESSuge24Tios air DR'fER lNLET FILTER PLAN 7 AIR COMPRESSOR
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, D.RTD WEIGHTING FACTORS Calculations for containment leakage were made using in-I dividual weightingfactors for each temperature sensing RTD. The
- RTD weighting factors were computed in two ways; volumetric weighting and mass weighting,with a leakage rate calculation made for both.
I. Volumetric Weightinc of RTDs p In computing the weighting factor for RTDs by the vol-i umetric method,each containment volume was sectioned off by elevation C and/or structural barriers to form representitive RTD volumes. These I
volumes were calculated using approved Indiana and Michigan Layout drawings for the D.C. Cook Nuclear Plant. The individua1 weighting factor for each RTD was computed using the formula:
n Representitive RTD Volume y y Weighting Factor =
, Total Compartment Volume numDer MIus in Representitive Vol.
The total of all RTD weighting factors for each containment compartment
, is equal to one. A listing of all RTD weighting factors determined by the volumetric method can be found on Table 4.2 of this report.
, II Mass Weighting of RTDs In computing the weighting factors for RTDs using the mass
- t. weighting method the ideal gas law is applied. In addition, it is j
concluded, quite naturally, that the total mass of air in each com-l b partment is equal to the sum of the masses in each of the representitive
- i volumes. The representitive RTD volumes are the same as determined for i the volumetric weighting method.
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II Mass Weighting of RTDs (Contd.) ,
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From the ideal gas law; solving for the total mass W on a compartmental basis we get:
W= PW = PVip P% $ .. .. ,
R T,3 8T i RT2 l'
l Where:
P= Pressure in containment compartment t Yy= Total compartment volume r
M= Representative volume for RTD #1
{= Representative volume for RTD #2 R= cas costant for air Ta3= Average compartment temperature I = RTD #1 Temperature reading Yg= RTD #2 temperature reading i
It can be seen from the above equation that each RTD reading is instrumental in calculating the mass in its representative volume.
Rearranging and cancelling like terms we get:
l _
l
[I \+ 1[f + ...
[ Tw3 v.r i T / V7( T/ 2 g
This equation is used to compute the weighted average L temperature for each particular containment compartment.
I L .
b
+
1
(
l t
. ,l l
4 TABLE 4.2 )
VOLUMETRIC WEIGHTING OF RTDs
. I UPPER VOLUME RTD NO. WEIGHTING FACTOR ETR-101 0.0651
. ETR-102 0.1203 f ETR-103 0.0861 .
ETR-104 0.0861
- i. ir
- ETR-105 0.0995
[ ETR-106 0.0995 ETR-107 0.0995 ETR-108 0.0995 ETR-109 0.0306 ETR-110 0.0306
( ETR-111 0.0306 ETR-ll2 0.0306
, l ETR-114 0.0938 ETR-128 0.0109 ETR-133 0.0173 i
L- TOTAL 1.0000
(
i t
s t-i e
(
I- L L. ., a y.---. - ,
TABLE 4.2 VOLUMETRIC WEIGHTING OF RTDs II LOWER VOLUME RTD NO. WEIGHTING FACTOR ETR-113 0.0597 ETR-122 0.0388 r ETR-123 0.0388 i
ETR-124 0.0388 I
ETR-125 0.0388 ETR-126 0.0130 r .
, ETR-127 0.0266 ETR-129 0.0547 ETR-130 0.0080 ETR-131 0.0248 ETR-132 0.0547 l ETR-134 0.0976 ETR-135 0.0976
{
- ETR-136 0.0976 ETR-137 0.0976 l
ETR-138 0.0467 I ETR-139 0.0086 L.
ETR-140 0.0228
[. ETR-141 0.0135 ETR-142 0.0159 L ETR-143 0.0232
{ ETR-144 0.0204 ETR-145 0.0224
! ETR-146 0.0394 h.
L TOTAL 1.0000
(
b- -
22 -
s.
- =,% r- ...s%.-e.w=4 ..~. + -w -#.
a
.-.-..7 -
F ,
TABLE 1+.2 VOLUMETRIC WEIGHTING OF RTDs III ICE CONDENSER COMPARTMENT I
RTD NO. WEIGHTING FACTOR ETR-115 0. lW2 ETR-116 0. lW2 I
I ETR-117 0.1490
[ ETR-118 0.1490 ETR-119 0.1300 ETR-120 0.1619
[
ETR-121 0.1217 TOTAL 1.0000 r
$ f k
t I
L I
i L
I L.
t
( )
i 1
l.
1 L. .
s
(
L -
= " * ~ = ^ 6 -. ~, ,
E. COMPUTER PROGRAM The program calculates the amount of air in each compartment as based on the fractional amount of air originally in each com-partment at the start of the test (Computer Run #1). The fractional amounts of air in each compartment are then combined to yield the fractional amount of air for the entire reactor containment. The program computes the leak rate at a given time from input values of I
t pressure, temperature and vapor pressure. The leak rate, as a function of time, is determined by the least-squares method.
The program is designed to allow evaluation of test results every half-hour after the first 3 sets of data. The print out consists of a summary of all sets of data up to and including the data just submitted. Included are fractional air reports for each compartment, for the containment as a whole, as well as the 24-hr i
leak rate at the time each set of data was taken. In addition, the
- upper and lower leakage bounds associated with the 95% confidence limits are printed out.
EXPLANATION OF PROGRAM f
Part One (actually a separate program).
Raw data corrected for instrument calibration, for the
[ pressures, temperatures and vapor pressures of each compartment is inputed along with the run number and the elapsed time from the t- start of the test.
t The computer then prints out the corrected data and the volume weighted average temperatures. The output is then examined for correctness of data input. If any incorrect data is detected, f
new input cards are prepared and the entire data deck for that i particular run number re-submitted.
f .
L
( During our subsequent analysis, the entire data deck was re-r run with a different program that yielded mass-weighted temperature averages. The difference in results is discussed in the Analysis I and Interpretation section of this report.
t Part Two (Leak rate on daily basis)
{ l. The leak rate is given by the Equati N:
F W= T, ( P t Pyz )
(
Tt ( P, - Pe i )
r Where W = Fractional amount of air in compartment T1 = Average temperature of start of test - R T2 = Average temperature at time of run R P1 = Average pressure at start of test - PSIA
( P2 = Average pressure at time of run - PSIA Pvl = Average vapor pressure at start of test - PSIA Pv2 = Average vapor pressure at time of run - PSIA This is calculated three times, once for each compartment.
- 2. The fractional amounts for the three compartments were combined by
7 l.
+ 2.2.g3g P- P P- Pv'i
! 4,2,cgyg +
L w= T U T L T /7.
t 4.7.959 ( T P- PyU0+ 2.2635 P- Pv. P. p, L T to 7 y,,o f
Where U Stands for upper containment L Stands for lower containment l
- I Stands for Ice Condenser I L 0 Stands for reading at the start of the test.
! l t.
F 3 statistical Treatment ,
p I
- A least squares analysis of a plot of the values of W versus time yields a straight line. The slope of this line is the fractional l leakage per hour. This is converted to % per day leakage by
~
multiplying by 21+00.
The slope of the least squares fit line is I
i b _- ( 2.t + 1) 8 W e - EWEt
, ( 2.6 +1 ) E 62
([tf Where i is time in hours.
In order to check the confidence limits, the following calculations were made:
The vertical intercept g - Eb 2 E W ~ E t E \^1t t
The
( 2.t + i) 2 t 2 - (Ic 32 variance of W
[ s#= E( W'"- 6t f
( 2 + - n '>
The variance of the slope t
3t .
Su' h
p [g,7 p Where { = average value of f.
The confidence limits were expressed as b K55 , where K is taken from a table showing the
{ variation of K with the number of runs completed.
t r
t i
4.
s; m--"t""
s . .
- l l
27 -
l l
< Tabin 309 :
I TABLE A-8 Disratsurion or E
=t o I
- Probabday a
, a 0.10 0.05 0.01 0.001 f I k314 12.706 63.657 436.619 i 2 2.920 4.303 9.925 31.598 3 2.353 3.t82 5.841 12.94l' 4 2.132 2.776 4.604 8.610 j 5 2.015 2.571 4.032 6.859
' 6 1.943 2.447 3.707 5.959 7 1.895 2.365 3.499 5.405 8 1.860 2.306 3.355 5.041 9 1.833 2.262 3.250 4.781 j 10 1.812 2.228 3.169 4 587 11 1.796 2.201 3.106 4.437 12 1.782 2.179 3.055 4.318 13 1.771 2.160 3.012 4.221 14 1.761 2.145 2.977 4.140 15 1.753 2.131 2.947 4.073 16 1.746 2.120 2.921 4.015 17 1.740 2.110 2.898 J.ve5 18 1.734 2.101 2.878 3.922 19 1.729 2.093 2.861 3.883 20 1.725 2.086 2.845 3.850
, 21 1.721 2.080 2.831 3.819 22 1.717 2.074 2.819 3.792 23 1.714 2.069 2.807 3.767 24 1.711 2.064 2.797 3.745 25 1.708 2.060 2.787 3.725 26 1.706 2.056 2.779 3.707
{
27 1.703 2.052 2.771 3.690
[
23 1.701 2 048 2.763 3.674 29 1.699 2.045 2.756 3.659
, 30 1.697 2.042 2.750 3.646 40 1.684 2.021 2.704 3.551 60 1.671 2.000 2.660 3.460 120 1.658 1.980 2.617 3.373 m 1.645 1.960 2.576 3.291
'Tha table gives the values of a curresponding to vanous values of the prob.bday a (level of signincance) of a random vanable falhng inside the shaded areas in the 6gure for a gtwen number of degrees of free.
dom e avadable for the estimanon of error. For a one-sided sens the conhdence linuis are obtained for a/2.
This tableis taken from Tab 6e III of Fisher & Yates: Sssamust Tams jee As lerwat. Arinstanut, sw j MM Aussed pubhshed by Obver & Boyd Ltd., Edanburgh, by pernussion of the authors and pubhshers.
l The above table used to determine the variation of K has been extracted from Basic Statistical Methods For Engineers and Scientists.
l
, $ ~o l L I . _ . . - -
- r. ~ ,-- . , - - -. < - - , - - - , -, --, , .'
AMERICAN [LECTRIC PDWER SERVICE C0RPOR ATION COMPUTER APPLICATIONS DIVISION .
-. SDURCE LIBR ARY PROGRAM PAGE 0002 OUTPUT LISTING 000100 C **********************************************
003200 C *
- 000300 C *
. 70 s LONT AINMENT VESSEL DAT A PROGR AM
- 000400 C *
- 000500 C
- THIS FROGR AM E NTITLE0 CCVDREP
- _. . _ 000600 C *
- 000T00 C
- 1.REA05 RAW INPUT DATA FOR THE LINEAR
- 00Je00 C
- REGRESSION ANALYSIS PROGR AMtCCVREPT
- 000900 C
- 2.W91TES THIS DAT A A5 A MEAN5 0F
- 001000 C
- ERROR CHECKING
- 001100 C
- 3. CALCULATES THE AVERAGE TEMPERATURE
- __ . 001200 C
- 001300 C
- 001400 C
- AS A CUMMULATIVE
SUMMARY
001500 C
- 4. CALCULATES A W FOR EACH CHAMBER A5
- 001600 C
- WELL A 5 A TOT AL W.THESE CALCUL ATIONS
- 001700 C
- ARE SAVED IN A DISK OATA SET TO BE
- 00lP00 C
- I 001900 C
- ANALYSIS PROGRAM
- 002000 C
- 5.THE OUTPUT OF THIS PROGRAM SERVE 5 *
- h$
002100 C AS THE FINAL FORMAT FOR PRESENTATION
- 002200 C
- TO THE A.E.C.
- I 002300 C *
- 002400 C **********************************************
002500 OIME NSION T E M PUC( Ibl ,PR E SUC l21.T L MPL C(24), PRE SLC( 2 3 002600 DIME NSION VPR ELC(2),Tt MPICt fl, PRE 5f C(2) 002700 INTEGER *2 NR,NRR,N2R 002000 RE AL*8 WUCOEM,WLCDEM WICOEM,WDEM,WUC t 991,WI Cl998,WICl99),Wl99) 002900 R E AL*8 T IMi l 9H), A TUC , ATLC. ATIC, AFUC , APLC , APIC i
003000 REAL*8 AVPUC,AVPLC,AVPIC,05,02 003300 RE A L
- 8 WU CNUM ,W LC NUM ,W I C NUM WNUM 003200 DEFINE FILE 4199,146,L.IDI 003300 13 RE ADt5,100,END=12)NR,TIMEf NR )
003400 100 FORMATf!2,1X,F5.21 003500 W R I T E ( 6,200 l N R, II ME I NR I 003600 200 FORMAT (IH1,44X,'*** THIS IS A CHECK OF THE INPUT DATA ****///1H , '
003T00 *RUN P',5X,' TIME',21X,' TEMPERATURE READING 5',11X,' PRE 55URE READINGS 003000 *',ltX,' VAPOR PRESSURE READING 5'/IH ,1X,12,6X,F6.2.26X,80F UPPER *,2 003900 *2 X , 'DF UP PER ' ,2 4X ,'UF UP P ER '/1H ,30X,'CONTAINMFMT',19X,8CONTAINMEN 004000 *T e ,p g x,,CCNT AINMENT ' /l 004100 RE A015,10Il f f f MPUCt II,1=1,15 3,(PRESUCll),Isl,2),VPRE UC
~ ' '
009200 101 FORM AT ilo t F5.2 lX I/5 f F5.2.1XI e 2 t FT.4,1XI,F6.4 3 j 004300 WRIT ( (6,201)T f MPUCll t PRE SUCi t i VPRE UC 004400 201 FORMAT 11H 40X,F6.2,24X,F8.4,22X,F7.43 004500 WRITE f 6,202)T EMPUCl2 ),PRESUCl2 3 004600 202 Ft*RMAT11H 4 0 X, F 6. 2. 24 X, F 8.4 )
004T00 WR IT E t 6,2031 t TE MPUC f I I ,I =3,151 004000 203 FORMAT IIH e40X,F6.25 004900 WRITE 16,204) 005000 204 FORM Af t 1HO,35X,' TEMPER AT URE RE ADING5',11X,' PRE 55URE RE ADING5 8,11X, 005800 *
- VAPOR PRESSURE READING 5 '/1H ,40X ,'0F LOWE R ',22X,'UF LOW E R * ,24X,'O 005200 *F LOWER'/1H . 38 X, ' CONT AINMEN T',19X,'LONT A INMEN T ',21X ,'LUNT AINM ENT
- _ _ _ _ _ _ ___m____ ___.._________.____m
r._ - . , , _ ~
p -~.- r -- -- p---- - -- -- -- -- -
q - - - - -
~
a SOURCE LIBRARY PROGQAM PAGE 0003 {
005300 */l 005400 RE A0 t 5,10 2 )( T E MPLC I I I ,I = 1,24 3 , lP RE 5L C I I I ,I m1,2 8, ( VPR E LC I I I,1=1,2 5
, . 005500 102 FORMATI-12tFS.2,1X1/12tF5.2.1XI/2(F7.4,1XI 21F6.4,1XII ~
005600 WHI1F (6,2013 t TE MPLCl l),PRESLC III,VPRELCI II,1=1,21 005700 WRIT E (6,203 8 t TEMPLCI II,I =3,24 3 005P00 WRITE (6,2061 00$ 000 206 FDRM AT11HI,35X,'TE MPE R ATURE R E ADINOS ',11X,' PRE 55URE RE ADINGS',11X, 006000 * *V APOR PRES 5URE RE ADINGS '/lH ,40X,'0F ICE',24X,'0F ICE',28X,'0F IC 006100 *E'/1H . 3 8 X , ' C ONOCNS E R ' ,21X , ' C ONDE NG E R ' ,2 5 X , ' COND E N$ t R '/ 3 006200 R E A0( 5,103 3 8 T EMPIC E I I ,1=1,71, ( PH E SIC t II ,1=1,2) ,VPRE IC 006300 103 FORM A1(7( F5.2,1XI 2 t F 7.4.1X I,F6.4 3 000400 WRITE 16,201)TEMPIC(1),PRESICit),VPaEIC 006500 WR I T E (6,2021 T EMPICl 2 ),PRESIC l 2) 006600 wRITEl6,203lETEMPICIII,I=3,7)
.. 006700 REAL*8 WTUPf151/.0651 1203,2*.0861,48.0995,4*.0306,.0938,.0109. 0 0 06 P 00 *173/
006900 REAL*8 WILOWl243/.0597,4*.0388,.0130,.0266,.0547,.0080 0248,.0547 007000 e ,4* .09 76, .0467, .008 6, .0228, .0135. 0159. 023 2, .0204. 0224, .0 394 /
007100 RFAL*8 WTICE(71/.1442,2*.1490,.1300,.1619. 1217,.1442/
00 F200 REAL*8 TMSMUC PR$MUC,IMSMLC,PR5MLC,VPSMLC,TMSMIC PRSHIC 007300 TMSMUC=0.
007400 DO I J=1,15 .
007500 1 TMSMUC=TM5MUC*(T.EMPUClJl*459.71*WTUPlJ) 007600 ATUC=TMSMUC 007700 P R SM I PC = 0.
I 037800 DO 2 K=1,2 h) 007900 2 PR 5MUC=PR 59UC + PRE SUC t K ) yo 00B000 APUC=PR$MDC/2.
8 00H100 AVPUC =VPR E UC 00h200 WRITEt6,2073ATUC,APUC,AVPUC 008300 207 FORMAT (IH ,36X,' AVG TEMP UPPER CONT ,,gx, eAVG PRES $URF UPPE R CONT ',
008400 *eX,' AVG V PRES $URE UPPER CONT'//1H ,39X,F9.4.18X,F9.4.24h,F9.4/l 008500 TMSNLC=0.
008600 DO 3 L=1,24 009100 3 TM5MLC=T MSMLC*(T EMPLCILl +459.71*WTLOWIL) 008800 ATLC=TM5MLC 008900 PRSMLf=0.
> 009000 DO 4 M=1,2
"~
009300 4 PR $hlC=PR SMLC + PRE SLC t HI O D9200 APLC=PR5MLC/2.
009300 VP$MLC=0.
009*00 DO 5 IN=1,2 009500 5 VPSMLC=VP5MLC*VPRELCIIN) 009600 AVPLC=VPSMLC/2.
~ ~
009700 WRITEt6,2093AILC APLC,4VPLC 009P00 208 FORM A1 (IH ,36X,' AVG T EMP LOWER CENT ',8X ,' AVG PRE S$URE LOWER CONT ',
009900 *8X,' AVG V PHESSURE LOWER CONT'//1H .3 94, F 9.4,18X , F 9.4,24 X ,F 9.4 / l 010000 TMSMIC=0.
010100 00 6 IT=1,7
- 010200 6 TMSMIC=TMSMIC*(TEMPIC(ITl*459.71*WTICE(IT) 010300 ATIC=TMSMIC 010400 PR5MIC=0.
010500 DO 7 JJ=1,2
"~ ~~ ~
010600 7 PRSMIC=PR5MIC*PRESIC(JJ)
. 010700 APIC=FRSMIC/2.
010800 AVPIC=VPREIC 010900 WRITLl6,209]ATIC,APIC,AVPIC 011000 209 FORMAT (IH ,36X,* AVG TEMP ICC CON 004 ',8X, ' AVG PRESSURE ICE CONDENe, i
7
_) _ ,
q _ _. . . .
4
. SOURCE LIBR ARY PROGRAM PACE 0C04 011100 *8N,' AVG V PRESSURE ICE CONDEN'//1H .39x,F9.4,18X,F9.4.24x,F9.43 011200 D5s4.2959 011300 D 2= 2. 28 35 011400 IFINR-IIS,8,9 -
011500 8 WUCDEN=lAPUC-AVPUCl/ATUC 011600 WLCOLM=l APLC- AVPLCl/AILC 0117hD WICDEMalAPIC-AVPICl/ATIC 011000 WDEM=WICDEM.D5*WUCDEM+D2*WLCDEM 011900 N2R=NR 012000 WR I Tt l 4 ' l lN2 R ,T IMF IN2R ) ,W'JCOE M ,W LCDE M .WI CDEM.WDE M 012100 NRR=NR 012200 WRI11(4'99)NRR 012300 9 RE AD6 4'llN2R,TIMEIN2RI,WUCDEM,WLCDEM.WICDEM,WDEM 012%00 WUCNUMalAPUC-AVPUC3/ATUC 012500 WUC INN I= WUCNUM/WUCDE M 012600 WLCNUM=lAPLC-AVPLCl/ATLC '
012700 WLC INR l = WLCMUM/WL CDE M 012800 WICNUMal APIC- AVPICl/ATIC 012900 WIC IN R l = WICNUM/WI CDE M 013000 WNUM=WICNUM*DS*WUCNUM*D2*WLCNUM 013100 WINRl=WNUM/WDEM 01320E IFINR-Il10,10,11 013300 10 N2R=NR a 013400 013500 WRITEl4'1 h2R,TIMEIN2RI,WUCDEM WLCDEM,WICDEM,WDEM,ATUC.APUC,AVPUC, LA8 013600
- A TLC , APLC , AVPLC , ATIC, APIC, AVPIC,WUC IN2R ),WLC IN2R ),WIC IN2R ), WIN 2R ) 0 GD 70 13 013700
. 013800 11 WRITE 14'NHINR,TIMEINR),ATUC,APUC,AVPUC,ATLC,APLC,AVPLC,ATIC,APIC,A
- VPIC,WUCINRI,WICINRI,WICINR),WINRI 013900 REA014899)NRR 014000 I F INR-NR R l 13,13,14 014100 14 NRR=NR 014200 WRITEl4899)NRR
. _ _ _ 014300 GO TO 13 014400 12 STOP 014500 ENO
__ , . . ,_ _ . , y .- , . ._. . . , . _ , _ . -.
AMERIC AN ELECTRIC POWER SERVICE CORPORATION ,
COMPUTER APPLIC ATIONS DIVISION
. . 500RCc LIGRARY PROGRAM PAGE 0002 OUTPUf LISTING
- , 000100 C ************************************************
000200 C * *
. 00U300 C
- COOK CONT AINMENT VE SSEL REGRE SSION PROGR AM
- 000400 C *
- 000500 C
- THIS PROGR AM ENTITLED CCVREPT
- _ . . _ _ _ _ _ _ . .. . _ . . _ _ 000600 C *
- 000T00 C
- 1. READS THE DISK DATA SET THAT
- 000000 C
- WAS CREATED BY THE CCVDREP PROGRAM
- 000900 C
- 2. PERFORMS A LINE AR Rf GRE SSION
- 00I000 C
- ANALYSIS TEST ON THE5E DAT A PolNTS
- 001100 C
- 3.THE ANALYSIS IS PERFORMED ON THE *
, . . _ _ . _ . . _. _ _ _ . _. 001200 C
- CURRENT MAXIMUM NUMBER OF DATA POINTS.
- 001300 C
- 4.1HE W F R PE RIMFN TAL ,THE W R E GR E 5510N,
- 001400 C
- THE LEARAGE RATE. CONFIDENCE LIMITS
- 00I500 C
- FOR THF RATL,AS WEEL A5 THE INTERCEPT ,*
001600 C
- ARE ALL QUTPUTED.
- 001700 C
- 5.THE OUTPUT OF THIS PROGRAM $FRVES AS *
. 001800 C
- THE FINAL FORMAT TO ME PRESENTED 10
- 001900 C
- THE A.E.C.
- 3 002000 C * *
~ ' ~' ' 002100 C ************************************************ 00 002200 RE AL* 8 AT UC , A PUC , AVPUC , A T LC , A PLC , AVPLC, AT IC , APIC, AVPIC h" 002300 REAL*8 dOCl991,WLCl991,WICt993,Wl999,11ME(981
... _. . _ _ _ . . 002400 REAL*8 WR(99),WLR(993,WURt99),ATAnl998 002500 INTEGFR*2 NR,NRR,N2R J02600 DIMENSION TARLEl965 002 T00 REAL*8 A,B,BL,8H ,
002P00 REAL*8 WUCDEM WLCDEM WICDEM,WDEM 002900 DEFINE FILE 4899,146,L,IDI 003000 RE AL *$ T55,TS.WS,TS2W ANUM, ADEM,BNUM,EK,W50M SICMAB,RNRR,$1GMA 003100 NE AL*8 A T, AITN ERR, TOT,F2,F1 F ,FF 003200 READl4'99lNRR 003300 IF(NRR-311,2,2 003400 1 WRITE (6,2001 003500 - 200 FORMAf f1H1,10X,* INSUFFICIENT NUMBER OF DATA POINTS FOR A MEANINGFU 003600 **. ANALYSIS TO BE RUN.MORE DAT A POINT S ARE NEEDE08 3 003700 ;0103 003800 2etRR1=2 0039JO 847 NRRl=NRR1+1 004000 155=0.0 004100 75=0.0 004200 DO 4 Is2,NRR1 004300 RF ADI4'IINR,TIMFIII, ATUC, APUC, AVPUC, ATLC, APLC AVPLC, ATIC, APIC, AVPI 004400
- C ,WUC t I I ,WLC I I I,WIC I I I ,W I I I 004500 T SS= T S$ *T IME ( II **2 004600 4 T5=T5+1IME(Il 004700 RE AD(4'llN2R, TIME IN2RI,WUCDEM,WLCDEM WICDEM,WDEM. ATUC, APUC, AVPUC A 004800
- iLC, APLC AVPLC, ATIC, APIC , AVPI C,WUC(N2R I,WLCIN2RieWICIN2R),WINfa l 004900 WS= WIN 2R) 005000 00 S J=2,NRR1 005100 RE ADf 4'J INR,T IME( J), AT UC, APUC, AVPUC, ATLC, APLC, AVPLC, ATIC, APIC, AVPI 005200 *C,WUC(J),WLCtJ),WICtJ),WlJ)
- ~ -
& -- - - - - ----- ~ - ' -r - '-~' ~* - - - - -
r- p -' 1 SOURCE LIBRARY PROGRAM PAGE 0003 1*
005300 5 WS=WS,WlJ) 005400 T52W=0.0
--- ~ -_ _ 005500 DO 6 K=2,NRR1 005600 RE ADt 4'K INR.T IME IK), ATUC, APUC,AVPUC, ATLC. APLC, AVPLC, ATIC, APIC, AVPI 005700 *C.WUCtKI,WLCini,WICtKI,WIKI 005P00 6 152W=152 W + T IM E E K l *W I K )
005900 ANUM =TS5*W5-TS*T52W 006000 XNRR=NRR1 006100 ADEM=XNRR*TS5-75**2 006200 A= ANUM /ADEM 006300 8NUM = X NR R
- T S 2 2-T S *W S
. . . - 006400 8=BNUM/ADEM OD6500 DATA TABLE /12.706,4.303,3.182,2.770,2.571,2.447,2.365,2.306.2.262,
. 006600 *2.228,2.201,2.179,2.160.2.145,2.131,2.120,2.110.2.101,2.093,2.086,
._ _ 006700
- 2.O r o ,2. 074. 2 .0 69,2. 06 4,2. 0 60,2. 0 56,2.0 5 2,2. 04 8,2.04 5,2.0 4 2,2. 0 40, 006800 *2.038,2.036,2.034,2 032,2.030,2.02T,2.025,2.023,2.021,2.020,2.019, 006900 *2.018,2.017,2.016,2.015,2.014,2.013,2.012.2.011,2.009.2.00s,2 007,
. . . . .. . . . 00f000 *2.006,2.005.2.004,2.003,2.002,2.001,2*2.000,3*1.999,3*1.998,3*1.99 007100 *7,381.996,3*l.995,381.994,3*1.993,381.992,381.991,3*1.990,3*1,989, 007200 82*l.980/
00T300 WRtll=A 00T400 AE A0( 4'2 )NR, TIME t 21, ATUC, APUC ,AVPUC, ATLC, APLC, AVPLC, ATIC, APIC, AVPI C07500 *C WUC l2),WLCl 2),WICl 21,W l 2 3 4
,_, _ 007600 WRt2)=A,8*TIMEt2l 007700 DO 7 II=3,NRR1 Ud 00T800 RE ADt 4'IllNM, TIME t III . ATUC, APUC, AVPUC, ATLC, APLC, AVPLC, AT IC, APIC , AV
. . . , . . _ . 007900 *P I C , WUC l l I I , W LC I I I I , WIC l ! I ) , W I I I I I 009000 WRtlll=A*B*TIMEtIII 008100 EK=TABLEtII-2) 008200 RE AD t 4'l l N2R ,TI ME t N2 R ),WUCDEf;,WLCDEM ,WICDEd,WDEM , ATUC , APUC e AVPUC , A 008300
- TLC,APLC,AVPLC,ATIC,APIC,AVPIC,WUCll),WLCll),WIClll,Will 008400 WSUM =lW t i l-A l **2
- - _ _- 008500 DO 8 L=2,NRR1 008600 RE ADt 4'L INR.TIMEIL), AT UC, APUC, AVPUC ATLC, APLC, AVPLC, ATIC, APIC, AVPI 008700 *C,EUCIL),WLCILI,WICilleWIL) 008800 8 W5Uff =WSUM
- t WI L)-A-8
- IIME t L i l**2 008900 SIGMA =D50Rit(I./XNRRl*WSUM) 009000 AT=TS/XNRR
, _ , _ _ 009100 RE ADt 4'IllNR, TIME t II I, ATUC, APUC, AVPUC, ATLC, APLC, AVPLC ATIC, APIC, AV 009200 *PIC,WUCtIII,WLCIIII,WICIIII,WIIII 009300 ATTN =tTIMEtIII-AT!**2
- 009400 TOT =AT**2 009500 DO 9 M=2,NRRI 009600 RE Ant 4'M INR, TIME IM), ATUC, APUC, AVPUC, ATLC, APLC, AVPLC. ATIC , APIC, AVPI 009700 *C,WUCIMI,WLrtMI,WICtMI,WiMI 009e00 9 TOT = TOT
- t IIMEIM I-At l **2 009900 F2= ATTN / TOT
_ . , 010000 F 1s t XNRR + 1. 3 /XMRR 010100 F=Fl*F2 010200 F F =F
- t X4RR/ t X NRR-2. l l 010300 AT Au t 1Il =DSQR TI F F l* SIGMA 010400 WLR E Il l =WR II I I-EK* A T A8 t III 010500 WURIIID=WRt1II*ER*ATABtIII
_ 010600 7 CONTINUE
, 010700 8=882400 010800 SI GMAB=D50RT t WS UM/t t XNRR-2. l* TOT i l
, 010900 EKK=TABLEENRR1-23 011000 BL =8- t EKR* SIGMA 81 *24 00
... . . .- , . - . - .. ,__, ~. .- .. , - - -, ~ .
SOURCE LIERARY PRDGRAM PAGE 0004 -
'~
011100 SH*S* f EKK*$1GMA 8l *2400.
011200 RE ADl4'NRRilNR,TIMEINRI,4TUC, APUC, AVPUC, ATLC, APLC, AVPLC, ATIC, APIC,
- _ _ - _ _ . .. - _.. 011300
- AVP IC ,WUC INR ) ,WLC (NR I, WI C (NR I ,W I NR )
011400 WR ITE l4'NRk1) NR , TIME lNR ) , ATUC , APUC, AV PUC , ATLC, APLC, AVPLC, AT IC, APIC 011500 *, AVPIC ,WUCINR ),WLC(NR I,WIC(MR ),W INRI,8L,8,8H, A
_ _ _ _ . . . . 031600 WRITEl6,20ll 011100 201 FORMAft1H1,48X,'$UMMARY CF AVERAGE 5'///lH . 2 X , ' R UN f',2Xe' ELAPSED 011000 * * ,2X,3(3 4 HAVG T EMP AVG PRESS AVG V PRE S$ 1/IH ,10X,, TIME',6X,'U
. __ =-- . . . 011900
- PPER ' ,5 X , 'UP P ER ', TX , 8 UPP ER * ,7 X , ' LOW ER ' ,5 X , ' LOW ER ' ,6X , 'LOWE R ' ,8 X , 'I 012000
, *CE',1X,' ICE',9X,' ICE 8/l 012100 RE ADl4'llN2R , IIMEINZR I,WUCDEM WLCDEM,WICDEM.WDEM, ATUC, APUC, AVPUC A
. . . _ 012200
- TLC. APLC, AVPLC. ATIC, APIC, AVPIC , _ _
012300 ATUC=ATUC-459.7 0124C0 ATLC=ATLC-459.7
_.. . . 012500 AT IC = A T IC-459.7 _ _ _ _ , ,
012600 WRITE l6,202)N2R, TIME (N2R), ATUC APUC, AVPUC, ATLC, APLC, AVPLC, ATIC, API 012700 *C,AVPIC
.... ._ _ _ __ _ _ _ _, . 012800 202 FORMATf1H .2X,13,4X,F6.2,2X,3fF9.4.2X,F9.4,3X,F9.4,2Xil 012900 00 8 46 JG=2,NRR1 013000 RE ADl4'JGlNR, TIME (NR I,4TUC, APUC, AVPUC, ATLC, APLC. AVPLC, ATIC, APIC, AV 013100 *PIC 013200 ATUC=ATUC-459.7 e 013300 ATLC=ATLC-459.7 013400 gg
... . . , ATIC=ATIC-459.7 to 013500 846 WRITE (6,2023NR,TIMEINRI,ATUC,APUC,AVPUC,AitC APLC,AVPLC,ATIC,APIC, 013600 *AVPIC 8
, _ _ . .__ 013700 WR I T i t 6,205 )
013800 205 FORFATilHI,34N,'RESULTS CF THE LINE AR REGRESSION ANALYSTS TEST'///
013900 *1H 014000 ,2 X , ' RUPP UN E8 R8,8
' X ,7, 'W X ,' , I,Wl X,'LE AK AGE R AT E ' e 9X , 'LE A k AGE * ,9X ,'L F AK AGE
___ . . _.___ _ _. __ _. _ _ _ . *kATE',8X,'W LOWE R ',9 X , ' W ICE'/1H ,10X,' EXPERIMENTAL',
014100 *6X,' LOWER L IM IT 8,11X , 'R A T E ',11X, 'UPP ER LIMI T ',5X, ' CONT AINME NT ',3X, 014200 ** CONTAINMENT',5X,'CONDEN$ER'/3
._, .._ , _ 014300 00 845 JG2=3,NRR1 014400 RF AD( 4'JG23 NR ,TIMElJG2 3. ATUC, APUC, AVPUC, ATLC, APLC, AVPLC, A TIC, APIC, 034500 *AVPIC,WUC(JG21,WLC(JG23,WICfJG2),WlJG2),RL,5,8H,A
_ _ . _ ._ __ ,_ _ . . 014600 845 WRITEt6,206thR,WlJG23,BL,8,8H,WUClJG2),WLClJG2),WIClJG21 014700 206 FORMAT (1H ,3 X ,13,4X , F o .5,9X , F 9.5,9X , F 9.5 ,10 X , F 9. 5,8 X , F9.5,5 N , F V.5, 014800 *6X,F9.59
.. .. __.. _ . _ _ _ _ . - _ _ 014900 READf4'99)NRR 015000 IF INRR I-NRR l 8 47,9 44,844 ~
015100 844 RE ADf 4*NRR11NR,TIMEINR I, ATUC. APUC,AVPUC, ATLC, APLC, AVPLC, ATIC, APIC,
_ .. ____ 015200
- AVP IC ,WUC INR ) ,W LC INR S ,WIC IN R S ,W INR) ,8L,8,8H, A 015300 WRITL16,203)B.A 015400 203 FORM AT ilHO,21 X,' FINAL LE AK AGE RATE I X PER DAY S =',F9.5,5X ,'INTERCE
..__ 015500 *PT=',F9.51 015600 WRI T E 8 6,204 l B L,8H _
015700 204 FORMAT (1HO,21X,' FINAL CONFIDENCE LIMITS FDR THE RATE ARE ',F9.5,'
,__ . . . 015R00 *TO ', F 9.51 .
015900 3 STOP 016000 END e . *e e rap ge e - see- ei .
e.
5.0 ANALYSIS AND INTERPRETATION The previous sections of this report described the method of measuring and computing the containment leakage rate. This section will present the observations, discuss the problems encountered and
, the conclusions drawn from the performance and analysis of this ILRT.
I i
A. DISCUSSION OF GRAPHICAL DATA r Figures 5 1 and 5 2 are the graphical representations of the calculated leakage rates as determined from the twenty-four hour ILRT and the Supplemental Test respectively. The axis of these graphs are the normalized weight of original air remaining in the containment versus time (or run). The slope of the least squares line is the leakage rate.
In reviewing these graphs it is observed that the normalized value of the weight of original air remaining in the containment tends to cyclic. The cycling of normalized weight is experienced throughout f the entire twenty-four hour ILRT and is also present in the Sup-plementary Test. This behavior is directly influenced by the cycling value of the normalized weight of air remaining in the Ice Condenser I Compartment. This is in turn related to the cycling temperature
[
experienced in this compartment (see Figure 5 5) caused by the f
{ periodic defrosting of the Ice Condenser air handler cooling coils.
The average vapor pressure plot for each compartment, found
'. in Figure 5 4, indicates a steady increase for both U'pper and Lower Compartments while the Ice Condenser Compartment tends to cycle slightly while increasing. Again the Ice Condenser's abnormal Lehavior was influenced by the periodic operation of the air handler's
, defrost mode which in turn caused the Ice Condenser temperature to cycle. It is important to note at this time that, due to what i
t
~
- was thought to be a malfunction in the Ice Condenser's dew point sensing hygrometer, it was decided that the Ice Condenser vapor pressure would be determined using the average compartment temperature and hygrometric tables prepared by the Smithsonian Institution for the saturation vapor pressure over ice. Sub-( sequent inspection of the sampling line, from the Ice Condenser p
Compartment to the hygrometer, revealed that the line was open at approximately El. 670 ft. and was actually sampling Upper Compartment atmosphere. -
Figure 5 3 shows a plot of the absolute pressure in cach I compartment during the twenty-four hours of the ILRT. The graph indicates a steady decay of pressure in the containment with slight
)\ . fluctuations, the largest of which is approximately 0.002 psi. The extreme accuracy in which the Quarz Manometers can measure the change in pressure can be seen in the tabulation of data found in Section 6.0.
When the initial and final absolute pressure readings of the Upper, Lower and Ice Condenser compartments are compared, the measured change I in pressure is 0.0509, 0.0505 and 0.0500 psi respectively. It was
,- therefore concluded that the Quartz manometers gave an accurate i'
indication of containment pressure.
A review of the average temperature plot, found in Figure 5 5, indicates a relatively stable trend for both upper and lower com-
! partments. The Upper Compartment experienced 'a defective RTD (ETR-lo3) just prior to the start of the test. Therefore, for the purpose
, of calculating temperature in the Upper Compartment, the reading l
of an RTD (ETR-102) in same general vicinity with the same weighting factor was substituted for the defective one. The problem RTD was i demonstrated as being defective, after the completion of the test, by measuring its resistance which proved to be far above the
. .. 1
_ _m_ - _ _ - - _ _ . .
. . . . o .
9 manufactured specification. The temperature plot also indicates j that the Ice Condenser's average temperature tends to cycle. This l cycling of temperature was brought on by the periodic defrosting of the Ice Condenser air handler cooling coils. For this reason, t
it was impossible for the Ice Condenser Compartment to meet the temperature stablization criteria set forth in the test procedure.
I t .,
a .
5 }
i i !
i
, [
i 1.
t t'
e
\
i i I
I t e
l
!L l
B. COMPARISON OF ONE VOLUME WITH THREE VOLUME METHOD The method employed in this report was based on calculating the weight of air in each of the three compartments, combining them into the weight of air in one compartment, and then normalizing the result. The purpose of this section of the report is to explore the possibility of considering the entire containment as one compartment.
The pressures at all points in the containment should be the same. An average of all six pressure readings would give an adequate figure for substitution into a one volume formula.
However, since there is no reason for the temperatures to be the same, we must be careful about the method for calculating the average temperature to be used for substitution in a one volume formula.
! Since the whole equals the sum of its parts:
b/ = W, + We + W3 + -
PV P, V, RT R T , g PsRTg , ,,,
i
.; R Ta 3 We can eliminate R and all the values of P from this equation since P = P, =P2=P" 3 V: V, % V3
+ ***
Y t I
T Ti T 3 1
4 - W + +t%+T W)
If we substitute " upper ' for "1", " lower" for "2",
+" ice" for "3", and use "0" to designate original values we can solve:
W (Normalized) = _.
P /vS p
w : S =
S _( T j v+ ( T
/vh+/v3
/L ( T )g 1
P V. ry3 ry p,
R To i ' +7 y R 2 T ho+-( T o (T o_
l' ,
But this is a variation of the formula that we used to combine the three volumes into one in the 3 volume method.
In conclusion, the act of determining a weighted average for the temperature forces us to go through the same steps, and leads to the same result, as calculating masses in the three
, l, separate compartments and then combining the masses into one.
r, i
I 4 6 ij i
l j
1 k
o
't l
1
C. ERR 0_R ANALYSIS s
The following Error Analysis is based on the parameters I
measured during the actual ILRT.
Leakage during the test resulted in a drop in pressure of about 0.05 psi. Temperature and vapor pressure were measured i
s but were not directly related to leakage. ,
Since the total pressure should be essentially the same f
throughout the containment, all six pressure gages should show
- 'l the same change in pressure throughout the test. The actual
. measurements show:
i Mean Change: 0.050l+ psi
( Std. Deviation:
- 0.00053 psi Probable Error: 0.00036 psi I'
At time zero (beginning of test) the probable error of the
- mean temperature was
O.19 */~ Upper Containment i
- 0.27 *sf Lower Containment 0.80 */I Ice Compartment and after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was:
t 0.207f Upper Containment j
0.27 */r Lower Containment
{ t 1.07 7f Ice Compartment The measurement of vapor pressure employed a cooled mirror,
, the temperature of which was accurate to tO.5F. Multiplying this
- by hP. yields the probable error for measurements made in each com-l partment.
i l l l \
i!
- _ i
. l c .-. . . . _ .
)
Upper compartment-for a temperature of 62F the probable l crror is:
0 5F (0.01 psi /F) = 0.005 psi Lower compartment-for a temperature of 73F the probable
- error is
0 5F O.01373 psi /F S= 0.005 psi
' 4L )
Ice condenser-as was previously mentioned the dew point hygrometer was not sensing Ice Condenser atmosphere. Since the i
water vapor should be at saturation pressure using the mean temperature of the 'seven RTD's in the ice condenser yields 1.07F (0.0017 psi /F) = 0.0018 psi i
It is interesting to note that the large probable error
- AlO in the temperature is more than offset by the low }~I , giving a smaller probable error for this vapor pressure than for either of the other two vapor pressure measurements.
f Probable error for combined quantities.
i P-P W = 4.2959(T P-U Pv + 2.2835 ( P- T Py /L '+ T I
, p-P,
- 4. 2959 {P- Py , Z tg3g ( +
Where P = Total pressure - PSIA Py = Vapor pressure - PSIA l T = Temperature - R U = Upper Containment l L = Lower Containment I = Ice Containment
' An 0 added to a subscript refers to measurements made 0
at time zero (the start of the test).
l W = Fractional weight of air remaining
!}
1 l
In order to evaluate the probable error of the above I
equation, it is best to use a step-by-step approach. If E l represents the probable error, we calculate:
2
- 1. E for P-Pe
- 2. E2 for P-Pa-
! T l 3 El for the numerator of the fraction
- 4. E l for W, and finally E for W The two types of formulas used are:
- 1. If A = B - C El = Ek + E[
- 2. If A = B/C Ea t
_ (f El Ee' \ og g t, (El Ee'Qt A2 Bt ct j ( g2 ct /
[
SolutionsforEf,p 1.a. Upper Containment
~8 E' E/ + Epk = (o. oco302 + (o. cos)*e 3.47 x #o
- b. Lower Containment
' E' Ef+E*pv =
(o.ooon)*+ (o.cos)* = 3 A Jx io
, c. Ice Containment i E *= Ef+ Ey , = t o.00036)*+ (c. col 8)* = 0 47 x 'o' *
- 2. Solution for P-Py t
I 2.a. Upper Containment f tog id
~
1 E.. -
3Ai x lib f 24.9 h\ = 4.82 x to ;o (2G W ( S 2 2 )'- r 52 2 )
2.b. Lower Co tainment -
t ,
3Ahc so~8 I 23 x to' 26.9 S2, 7,g fg /o -
(26.9)1 ((532)/ _
\ 531 /
i
- - 42 -
2.c Ice containment
( ti f = jg,g no-10
~
8 7,1 0 41 s 10
( 71Y-y (/(1.ob Y 478 / I 478 j 3 Solution for the numerator
. E ' = ( A .ms9)*(1.s 2.xoc"*)+ (2.183SY(2 4s tro*) + Ko 5 **""
i
' ~
ft: 2 87. S 3 x /o #O f
- 4. Solution for W 2.87,53xio"#
l E =
. xi p
(c. 394 GP (o.394Q1
, E* - 3693 63x10
l-
-5 E = 60 77x10 = 0.061 o L
This is the probable error of one point on a graph of weight
~
of air in the containment (normalized) plotted against time. The straight
{ line representing the least-squares fit of all 49 points had a slope
,. of 0.16044% 0.01053% with a confidence limit of 95%.
b Conclusion r It has been shown that any one reading has a probable error I
of 0.061[. When all the points are used to determine a least-squares-line, we have a 955 confidence limt of
- 0.010535 It can be shown that, for a normal distribution, a 50% confidence f
s limit is the same as the probable error.
(0.16044
- 0.01053)% 95% confidence ,
l
$ (0.16044 0.00363)% 50% confidence l l
I L
P ' N"* OM@@@**o* w & e- e-w & .- g e
" 43 -
D. DISCUSSION OF AIR PARTICULATE DETECTOR LEAKAGE During the course of the ILRT it was found that the air particulate detector sample line used to measure the air borne contamination of the lower Volume was experiencing out-leakage through a flow control mixing valve. The extent of the leakage I was measured to belO.2 SCFH.
This flow control mixing valve is used during normal 7
operation to manually throttle the correct sample flow-rate to the detector. When the sample pump is not in operation, I s as was the case during the ILRT, the flow control mixing valve acts as a vent from which the containment air escaped.
i Provisions will be taken to eliminate this source of
{'
leakage by modifying the present air particulate sampling system.
It is important to note that the acceptable leakage rate reported f
in this text includes the leakage through the flow control mixing
} valve.
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. 6.0 TABULATED RESULTS The following pages are a tabulation of measured parameters and calculated values of the Integrated Leakage Rate Test and Supplemental Test.
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SUMMARY
OF AVERAGES ( . (VOLUMETRIC WEIGHTING) ! RUN 8 elm SED AVG TEMP AVG PRESS AVG V PRESS AVG TEMP AVG PRESS AVG V PRESS AVG TEMP AVG PRESS AVG V PRE SS
. TIME UPPER UPPER UPPER LOWER LOWER LOWER ICE ICE ICE _. _
l
~
l 1 0.0 62.6819 27.0030 0.1012 72.9587 27.0045 0.0858 18.5255 27.0101 0.0468
- __ 2 0.50 62.6535 27.0005 0.1014 72.9488 27.0024 0.0864 18.7261 27.0077 0.0472 .
3 1 00 62.6333 26.9978 0.1015 72.9502 26.9999 0.08 72 18.6939 27.0053 0.0471 4 1.50 62.6259 26 9968 0.1017 72.9021 26.9987 0.0876 18.5955 27.0041 0.0469
. 5 2.00 62.6011 26.9944 0.1019 72.8753 26.9968 0.0880 18.5690 27.0021 0.0469 6 2.50 62.6080 26.9923 0.1020 12.8627 26.9897 0.0852 18.4555 27.0001 0.0466 7 3.00 62.5858 26.9920 0.1024 72.8602 26.9941 0.0882 18.4712 26.9995 0.0467
. 8.__ 3.50 62.5423 26.9909 0.1027 72.8192 26.9927 0.0868 18.5456 26.9955 0.0468 i 9 4.00 62 5531 26.9902 0.1030 77 8133 26.9920 0.08 91 19.0716 26.9977 0.0400 10 4.50 62.5597 26.9888 0.1034 72.8217 26.9902 0.0893 19.2578 26.9960 0.0484
_. 11 . 5.00 62.5513 26.9P96 0.1039 12.9041 26.9933 0.0897 19.0203 26.9969 0.0479 . _ _ _ , 12 5.50 62.50nl 26.9913 0.1039 72.7962 26.9930 0.09 02 18.9498 26.9985 0.0477 ' 13 6.00 62.4360 26.9909 0.1042 72.7753 26.9927 0.0859 19.1504 26.9982 0.0482 - 14 6.50 62.5022 26.9F60 0.1045 72.7495 26.9929 0.0904 19.1168 26.9935 0.0481 . { 15 7.00 62.4524 ,26.9882 0.1049 72.7381 26.9850 0.0914 18.8678 26.9903 0.0475 16 7.50 62.4600 26.9026 0.1052 72.7247 26.9844 0.0914 18.9170 26.9899 0.0477 _ 17 8.00 62.4755 26.9 PUG 0.1054 72.7105 26.9818 0.0906 18.8621 26.9873 0.0475 i 1H 8.50 62.4652 26.9778 0.1066 72.7159 26.9846 0.0919 19.2600 26.9848 0.0484 19 9.00 62.4374 26.9761 0.1060 72.6834 26.9781 0.0920 19.1958 26.9836 0.0483 20 9.50 62.4362 26.9752 0.1066 72.6477 26.9777 0.0932 18.8097 26.9832 0.0474 8 21 10.00 62.3935 26.9746 0.1066 72.6391 26.9770 0.0923 18.6155 26.9827 0.0470 22 10.50 62.3796 26.9776 0.1071 72.649n 26.9785 0.0918 18.7244 26.9853 0.0472 gn _ 23 11.00 e2.3609 26.9761 0.1072 72 6291 26.9780 _ 0.0919 19.1280 26.9840 0.0481 Fa
- 24 11.50 62.3499 26.9768 0.1076 72.5951 26.9786 0.0929 19.0745 26.9845 0.0480 8
25 12.00 62.3155 26.9736 0.1078 72.5905 26.9753 0.0930 19.2481 26.9814 0.0484 26 12.50 62.2088 26.9705 0.1079 72.5651 26.9725 0.0931 19.4101 26.9185 0.0488 27 13.00 62.23J4 26.9697 0.1083 72.5519 26.9721 0.n931 19.2984 26.9782 0.0485 ' l 28 13.50 62.2813 26.96D4 0.1088 72.5403 26.9703 0.0928 19.2246 26.9764 0.0484 t , _ 29 14.00 62.2760 26.9657 0.1090 72.52F0 20.9677 0.0941 18.9334 26.9738 0.0477 , , 30 14.50 62.2583 26.9664 0.1093 72.5095 26.9683 0.0941 18.76R8 26.9745 0.0473 ; 31 15.00 62.2299 26.9672 0.1095 12.5202 26.9692 0.0949 18.7681 26.9753 0.0473 ; _ 32 15.50 62.2357 26.9673 0.1099 72.4900 26.9691 0.0951 18.9634 26.9753 0.0478 , 33 16.00 62.1966 26.9658 0.1100 72.4919 26.9678 0.0954 19.3770 26.9739 0.0487 ! 34 16.50 62.2236 26.9665 0.1104 72.531% 26.9003 0.0957 19.7.467 26.9746 0.0496 35 17.00 62.1996 26.9665 0.1107 72.4511 26.9604 0.0961 20.4266 26.9744 0.0512 . 36 17.50 62.1988 26.9658 0.1109 72.4667 26.9677 0.0959 20.3783 26.9739 0.0511 37 18.00 62.1656 26.9635 0.1120 72.4482 26.9655 0.0966 19.7779 26.9716 0.0497 ' 38 18.50 62.1424 26.9610 0.1116 72.4401 26.9629 0.0969 19.5064 26.9693 0.0490 39 , 19.00 62.1223 26.9606 0.1118 72.4388 26.9626 0.0975 19.3Pio 26.9689 0.0487 40 19.50 62.1208 26.9583 0.1122 72.4185 26.9653 0.0973 19.3560 26.9664 0.0467 41 20.00 62.1138 26.9568 0 1125 72.4190 26.9588 0.0974 14.4361 26.9648 0.0488 42 20.50 62.1032 26.9550 0.1129 72.4196 26.9571 0.0977 19.2987- 26.9630 0.0485 !
.43 21.00 62.0438 26.9523 0.1143 72.3800 26.9543 0.0993 19.7997 26.9603 0.0497 44 21.50 62.0182 26.9504 0.1132 72.3798 26.9524 0.0973 19.7022 26.9584 0.0495 ,,
45 22.00 62.0481 26.9491 0.1151 72.3574 26.9510 0.0995 19.3130 26.9571 0.0486 46 22 50 62.0418 26.9489 0.1151 72.3707 26.9508 0.09 90 19.1616 26.9568 0.0482
+ 47 23 00 62.0267 26.9528 0.1154 72.3237 26.9549 0.0997 19.2963 26.9610 0.0485 48 23.50 62.0277 26.9549 0.1156 72.3039 26.9570 0.0999 19.9639 26.9631 0.0501 49 24.00 62.0037 26.9521 0.1160 72.3118 26.9540 0.1002 20.2865 26.9601 0.0509
_ _ __ _ _ - - -_ . _ . _ . _ . _ _ _ = . _ - p -- r - -
--y p. .q 7.
i
SUMMARY
OF AVERAGES _ (VOLUMETRIC WEIGHTING) RUN 8 ELA SED AVG TEMP AVG PRESS AVG V PRESS AVG TEMP AVG PRESS AVG V PRESS AVG TEMP AVG PRESS AVG V PRESS
. TIME UPPER UPPER UPPER LOWER LOWIR LOWtR ICE ICf ICL 1 0.0 62.6819 27.0030 0.1012 72.9587 27.'0045 0.0858 In.5255 27.0101 0.0468
_ _ 2 0.50 62.6e35 27.0005 0.1014 72.9488 27.0024 0.0864 18.7261 27.0077 0.0472 3 1.00 62.6333 26.9978 0.1015 72.9502 26.9999 0.08 72 10.6939 27.0053 0.0471 4 1.50 62.6259 26.9968 0.1017 72.9021 26.9987 C.0876 18.5955 27.0041 0.0469
. 5 2.00 62.6011 26.9944 0.1019 72.e753 26.9968 0.0800 18.5690 27.0021 0.0469 6 2.50 62.6080 26.9923 0.1020 12.8627 26.9897 0.0882 18.4555 27.0001 0.0466 7 3.00 62.5858 26.9920 0.1024 72.8602 26.9941 0.0882 18.4712 26.9995 0.0467 8 62.5423 26.9909 0.1027 72.8192 26.9927 0.0868 18.5456 26.9985 0.0468 9 .. 3.50 i 4.00 62.5531 26.9902 0.1030 12.8133 26.9920 0.0891 19.0716 26.9977 0.0480 10 4.50 62.5597 26.9888 0.1034 72.8217 26.9902 0.0893 19.2578 26.9960 0.0484
_. 5.00 b2.5515 26.9P96 0.1039 72.9041 26.9933 0.0897 19.0203 26.9969 0.0479 _ _ 11 12 . . 5.50 62.5081 26.9913 0.1039 72.7962 26.9930 0.0902 18.9490 26.9985 0.0477 13 6.00 62.4360 26.9909 0.1042 72.7753 26.9927 0.0889 19.1504 26.9982 0.0482 14 6.50 62.5022 26.9F60 0.1043 72.7495 26.9929 0.0904 19.1168 26.9935 0.0481 15 7.00 62.4524 ,26.9882 0.1049 72.7381 26.9850 0.0914 18.8678 26.9903 0.0475 1 16 7.50 62.4600 26.9876 0.1052 72.7247 26.9844 0.0914 18.9170 26.9899 0.0477 , _. 17 8.00 62.4755 26.9 PUG 0.1054 72.7105 26.9818 0.0906 18.8621 26.9673 0.0475 1H 8.50 62.4652 26.9778 0.1u66 72.7159 26.9846 0.0919 19.2600 26.984A 0.0484 19 9.00 62.4376 26.9761 0.1060 12.6834 26.9701 0.0920 19.1958 26.9836 0.0483
, 20 9.50 62.4362 26.9752 0.1066 72.6477 26.9777 0.0912 18.8097 26.9832 0.0474 8
21 10.00 62.3935 26.9746 0.1066 72 6391 26.9770 0.0923 18.6155 26.9827 0.0470 22 10.50 62.3796 26.9776 0 1071 72.6490 26.9785 0.0918 18.7244 26.9853 0.0472 sn _ 23 11.00 62.3609 26.9761 , 0.1072 72.6291 26.9780 _ 0.0919 19.1280 26.9840 0.0481 Fa
. 24 11 50 62.3499 26.9768 0.1076 72.5951 26.9786 0.0929 19.0745 26.9845 0.0480 s
25 12.00 62.3155 26.9736 0.1078 72.5905 26.9753 0.0930 19.2481 26.9814 0.0454 a 26 12.50 62.2988 26.9705 0.1079 72.5651 26.9725 0.0931 19.4101 26.9785 0.0488 27 13.00 62.23J4 26.9697 0.1083 72.5519 26.9721 0.0931 19.2984 26.9782 0.0485 28 13.50 62.2813 26.9604 0.1088 72.5403 26.9703 0.0928 19.2246 26.9764 0.0484
;; . 29 _ 14.00 62.2760 26.9657 0.1090 72.52PO 26.9677 0.0941 18.9334 26.9738 0.0477 , ,
,; 30 14.50 62.2583 26.9664 0.3093 72.5095 26.9683 0.0941 18.7688 26.9745 0.0473 31 15.00 62.2299 26.9672 0.1095 72.5202 26.9692 0.0949 18.7681 26.9753 0.0473
. _ 32 15.50 62.2357 26.9673 0.1099 72.4900 26.9691 0.0951 18.9634 26.9753 0.0418
- ! 33 16.00 62.1966 26.9658 0.1100 72.4919 26.9678 0.0954 19.3770 26.9739 0.048i 34 16.50 62.2236 26.9665 0.1104 72.5315 26.9683 0.0957 19.7.467 26.9746 0.0496 35 17.00 62.1996 26.9665 0.1107 72.4511 26.9604 _
0.0961 20.4266 26.9744 0.0512 . 36 17.50 62.1988 26.9658 0.1109 72.4667 26.96F7 0.0959 20.3783 26.9739 0.0511 37 18.00 62.1656 26.9635 0.1120 72.4482 26.9655 0.0966 19.7779 26.9716 0.0497 j _. 38 _. 18.50 62.1424 26.9610 0.1116 72.4401 26.9629 0.0969 19.5064 26.9693 0.0490 39 19.00 62.1223 26.9606 0.1118 72.4388 26.9626 0.0975 19.3P10 26.9689 0.0487 40 19.50 62.1208 26.9583 0.1122 72.4185 26.9653 0.0973 19.3560 26.9664 0.0487 41 20.00 62.1138 26.9568 0.1125 72.4190 26.9588 0.09 74 19.4361 26.9648 0.0488 42 20.50 62.1032 26.9550 0.1129 72.4196 26.9571 0.0977 19.2987 26.9630 0.0485
.43 21.00 62.0438 26.9523 0.1143 72.3800 26.9543 0.0993 19.7997 26.9603 0.0497 44 21.50 62.0182 26.9504 0.1132 72.3798 26.9524 0.0973 19.7022 26.9584 0.0495 __
45 22.00 62.0441 26.9491 0.1151 72.3574 26.9510 0.0995 19.3130 26.9571 0.0486 46 22 50 62.0418 26.9489 0.1151 72.3707 26.9508 0.09 90 19.1616 26.9568 0.0482
. 47 23 00 62.0267 26.9528 0.1154 72.3237 26.9549 0.0997 19.2963 26.9610 0.0485 48 23.50 62.0277 26.9549 0.1156 72.3039 26.9570 0.0999 19.9639 26.9631 0.0501
. 49 24.00 62.0037 26.9521 0.1160 72.3118 26.9540 0.1002 20.2865 26.9601 0.0509
.l
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, ,. , p_ . , ~s ,
_q -- g -- s - RFSULTS OF THE LINF AR REGRESSION ANALYSIS TEST (VOLUMETRIC WEIGHTING) W LEAMAGE RATE LEAKAGE LfaKAGE RATE W OPPER W LOWER W ICE
~ 'RUN N ~ EXPERIPENTAL ^ ~~ LOWts, L IMIT ~-
RAIE ~~ ~ UPPLR LIMIT' CONTAINMENT CONTAINMENT '-~ CONDENSER
~
~
3 0.99995 . -3.14352 -0.12105 2.90142 0.99990 0.99990 1.00026
~4
~
1.00c01 ' -0.54017 -0.04407 0.45203 0.99995 0.99992 1.00039 5 0.99977 -0.67146 -0 24534 0. I n0 78 0.99990 0.99933 1.00017
~ ' ~ 6 U.90972 ~
-0.56F96 -0.30655 '-~
-0.04415 0.9a976 0.99988 0.99919 7 0.99955 -u.58502 -0.30084 -0.17666 0.99974 0.99985 0.99818 8 0.99952 -0.53572 -0.3902o -0.24481 0.99959 0.99974 0.99882 9 0.99956 -0.47480 -0.35662 -0.21943 0.99944 0.99966 0.99984 10 ~ ~
0.99954 -0.42627 -0.32535 -C . 2 2' 44 0.09935 0.99958 1.00022 11 0.99951 -0.38721 -0.29974 -0.2122? 0.99925 0.99456 1.00045
~
12 ' 0.99950 -0.35381 -0. 2 Fi i7 -0.19F74 0.'89932 U.99958 1.00006 13 O.99935 -0.34176 -0.27660 -0.21163 0.99925 0.90963 0.99915 14 0.99917 -0.35332 -0.29393 -0.23454 0.99927 0.99966 0.99772 15 0.99902 -0.37273 -0.31424 -0.*5774 . 0.99921 0.99962 0.99705 16 0.99902 -0.37390 -0. 3 2 3 M -0.27219 0.99912 0.99935 0.99793
! 17 0.99902 -0.36622 -0.32163 -0.27704 0.99989 0.99940 0.99876 10 , , 0.99902 -0.35525 -0.31501 -0.27477 0.99891 0.99925 0.99898
', FINAL LEAKAGE RATE (3 PER OAV) = -0.31501 INTERCEPT = 1.00007
~~ '
FINAL CONFIDENCE LIMITS FOR THE RATE ARE -0.3552 5 TO -0.27477
.-.7- ..
s
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$UMMARY OF AVIRA6IS
~
(VOLUMETRIC WEIGHTING) RUN 8 ELAP5t.; AVG T f MP Avt, P RI S$ AVG V PFf55 AVG TEMP AVG FRi$$ AVG V PRESS AVG TEMP AVG PPE55 AVG V FRE 55 TIME UFPER Lif P E R Lf PPE R LIMf 8L LOVf P LOWER ICE ICE ICf 1 0.0 61.9519 26.9204 0.1085 72.1661 26.9301 0.1000 19.8240 26.9366 0.0498 2 0.50 61.9297 26.9266 C'.1086 72.1550 26.9292 0.1003 19.4163 26.9346 0.0490 3 , 1.00 (1.9480 26.9156 U.1096 72.157P 26.9272 0.1003 19.6546 26.9336 0.0494 4 1.50 61.91F9 2t 9256 0.808R 72.1442 26.9272 0.1002 19.5939 26.9336 0.0492 - - 5 2.00 61.91ve 26.9239 0.1028 72.4336 26.9256 0.1000 19.6656 26.9319 0.0494 6 2.50 61.9630 26.9231 0.1090 72.1194 26.9249 0.1004 20.1016 26.9310 0.0504
~ ' 7 ~ 3.00 63.9514 ~6.9222 0.1092 12.1206 26.92'2 0.1005 20.5515 26.9299 0.0515 8 3.50 61.9620 26.91p6 0.1092 12.1075 2e.9207 0.1006 20.1457 26.926% 0.0506 9 4.00 61.95?3 26.5144 0.1092 72.0907 26.9166 0.0995 19.6545 26.9224 0.0494 10 4.50 61.9624 26.4123 0 1093 72.0798 26.9145 0.1001 19.4490 26.9205 0.0489 ~~~ ~~
11 5.00 61.9715 26.1i le4 0.1093 72.0643 26.9126 U.0995 19.3063 26.9183 0.0486 12 5.50 61.9571 26.9114 0.1051 72.0653 26.9136 0.10 tn0 19.5060 26.9194 0.0490 13 6.00 62.0116 26.9123 0.1093 72.0475 26.9146 0.I003 19.9378 26.9202 0.0500 - - ~ ~ 14 6.50 62.0032 26.9127 0.1097 72.0322 26.9150 0.1007 20.5957 26.9203 0.0516 f 15 7.00 62.0029 26.9110 0.1097 72.0254 26.9134 0.1007 20.8810 26.9188 0.0523
"~ 16 7.50 62.0013 26.9084 0.1097 72.0067 26.9058 0.1012 20.4297 26.9162 0.0512 26.9118
' - ~
j 17 8.00 62.0294 26.9039 0.10** 71.9878 26.9061 0.1011 19.9720 0.0501 18 8.50 61.9414 26.9001 0.1099 71.9879 26.9022 0.1013 19.0037 26.9079 0.0497 V1 w i i 6 M. e.'ad . m . i u s
, c - . . ,
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i l
$ Rf $ULTS OF THE LINE AR REGRE5510N AN ALYSIS 7EST (NUUSS WEIGHTIhMI) l l
D RUM 8 W LF AKaG5 R AT E LEAMACf LEAKAGE RAir W UnprR w tcwrA w ICE l
- EXPERIMFMTAL L DWEP LIMIT R 4T F UPPEp LIMIT CONT AINME NT CON 7AINwENT CON 0fN$fR D 3 0.999a0 -2.45759 -0.47451 1.50856 0.99999 0.oe979 0.99949
_. 4 . 0.99982 -
-0.84459 -0.28396 0.27666 0.999P6 0.999P2 0.99964 5 0.99978 -0.49958 -0.22829 0.03200 0.*90KI 0.**97* 0.***62 9 6 0.9096R -0.40110 -0.24R84 -0.09654 0.99972 0.9*954 0.99979
. 7 0.99973 -0.323P3 -0.20367 -0.08391 0.99973 0.90971 0.99973 8 0.99974 -0.26991 -0.16352 -0.06111 0.99976 0.99979 0.99914 I 9 0.90051 -0.30!PI -0.20642 -0.11003 0.00971 0.99969 0.96P36
- _. 10 0.99937 -0.35219 -0.25400 -0.15599 0.99962 0.***60 C.99790 11 0.99969 -0.32370 -0.24409 -0.36439 0.aco65 0.99966 0.99945 D 12 0.99961 -0.29737 -0.20500 -0.12263 0.999P0 0.99971 0.aaD66 13 0.99963 -0.29217 -0.170R7 -0.08957 0.99991 0.99979 0.99P22
__ __ 14 0.99944 -0.24040 -0.17144 -0.10251 0.999'.9 0.99079 0.acP12 D 15 0.99950 -0.22104 -0.16023 -C.09941 0.9997% 0.99948 0.*9R'4 _. 16 0.00934 -0.2tR66 -0.16546 -0.112?5 0.99952 0.*"949 0.*9P37 17 0.999?7 -0.22059 -0.17105 -0.12950 0.a9030 0.*9949 0.99f44
; D 18 0.99999 -0.23822 -0.14087 -0.14352 0.9097P 0.99949 0.9a749
___. 19 0.49905 -0.24903 _ -0.20326 -0.19F49 0.99929 0.99931 0.99758 20 0.99916 -0.24185 -0.20169 -0.16154 0.95924 0.99939 0.*9839 i D 21 0.99024 -0.23076 -0.19313 -0.19949 0.98930 0.***34 0.*oP79 22 0.90a30 -0.2tR03 -0.100u3 -0.14367 0.99942 0.99939 0.99a66 23 0.99916 -0.21097 -0.17619 -0.14261 0.*9039 0.99941 0.99775 D 24 0.99921 -0.20lt9 -0 16943 -0.1369R 0.90942 0.99946 0.9c78R
. 25 0.99907 -0 19816 -0 16n35 -0.13R44 0.99916 0.99036 0.99739 ,
26 0.99894 -0.19917 -0.17148 -0.14379 0.***2R 0.99928 0.99692 D 27 0.99906 -0.19406 -0.16R16 -0.14227 0.99942 0.99929 0.*9715 g
.28 0.99993* -0.19764 -0.16963 -0.14463 0.99920 0.99925 0.*9724 +
29 0.99R92 -0.19060 -0.16930 -0.145*9 0.**910 0.9%911 0.90778 , I 30 0.99902 -0.17527 -0.16389 -0.142&O 0.99915 0.00919 0.99m16 31 0.09904 -0.17914 -0.15794 -0 13574 0.99923 0.99917 0.99P19 l '. 32, 0.999a0 -0.17424 -0.15392 -0.13139 0.e**21 0.***22 0.9a777 I 33 0.99896 -0.17253 -0.15314 -0.13418 0.99422 0.59915 0.99663 _ _ _ _ 34 0.99871 -0.17407 -0.15511 -0.13755 0.99918 0.99909 0.99608 35 0.99 P 56 -
-0.17867 -0.16r)9 8 -0.14249 0.99922 0.99923 0.99459 I 36 0.99654 -0.18194 -0 16412 -0.14669 0.9991P 0.99918 0.99467
! 37 0.99m65 -0.19105 -0.16440 -0 14774 0.9e912 0.00911 0.995Pe 1 3R 0.99 hon -0.17912 -0.16331 -0.14750 0.99908 0.00002 0.a9639 5 39 0.99471 -0.17628 -0.16107 -0 145,6 0.,e9 0 0.99 9R 0.*9664 40 0.99470 -0.17393 -0.158h8 -0.14422 0.""900 0.99913 0.946A0 41 0.99P56 -0.17271 -0.15878 -0.14485 0.99994 0.99888 0.99637 8 42 0.998*4 '0.17172
-0.I'447 -0.14521 0.99R89 0.99681 0.**6e0 l 43 0.99832 . -0.17397 -0.16100 -0.14902 0.99995 0.9ep72 0.99=41 l . ._ _ 44 0.99E?5 -0.17414 -0.16227 -0.149P0 0.44 m m 7 0.99872 0.99955 6
li 45 0.99634 -0.17503 -0.163n9 -0.15114 0.99869 0.99P63 0.996?4
.L _ 46 0.99839 -0.17418 -0.16275 -0.19133 0.90P 7 0 0.*9862 0.996f6 l
47 0.99852 -0 17160 -0.16031 -0.14901 0.99986 0.9.9803 0.9e653 48 0 99839 -0.17015 -0.15925 -0.14836 0.99893 0.99994 0.99517
, ___ _ 49 0.99820 -0.17075 -0.16024 -0.14974 0.**Pp6 0.*9880 0.90437 l FINAL LEAKAGE R4TE IT PER D4Y) = -0.16024 INTERCEPT = 0.99988
. FINAL CONFIDENCE LIMITS FOR THE RATE ARE -0.17075 70 -0.14974 I
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$UMHapf nF AvrtarJS !
(MASS WEIGHTING) RUN 8 EL46 SED 4VG TFMa AVG r1E%S 4VG V PPf55 AVC TEMP AVG PRESS AVG V PEFS$ AVG TfMP AVG PRF55 AVG V PRF55 TIME UDPER USPE" UPPER LOWER LOWFR LOWER ICF ICE ICF
-t i 1 0.0 62.6901 27.0030 0.1012 72.9516 27.0045 0.0958 18.5049 27.0101 0.0468
! .__ 2 , _. _ 0.50 62.6815 27.0005 0.1014 72.9419 21.0024 0.0864 18.6978 27.0077 0.0472
! 3 1.03 62 6316 26.9978 0.1015 72.9435 26.9999 0.0872 le.6A'7 27.0053 0.0471
'I 4 1.50 62.6240 26.9969 0.1017 72.8951 26.9987 0.0876 19.5690 27.0041 0.0469 l
_ . . 5 2 .00 62.4991 26.9944 0.1019 72.8679 26.9969 c.0880 tr.5440 27.0021 0.0469 6 2.50 62.6062 26.9923 Q.1020 72.e553 26.9997 0.0982 te.A313 27.0001 0.0466 i l 7 3 00 62.5941 26.9920 0 1024 7?.8531 26.9941 0.0PP2 18.4471 26.9995 0.0467
.. 8 3.50 62.5406 26.9909 0.1027 72.R118 26.9927 0.0868 18.5224 26.99R5 0.c469 9 4.00 62.5511 26.9902 0.1030 72.P061 26.9720 0.0891 19.0468 26.9977 0.04e0 i i 10 4.50 62.5577 26.9888 0 1034 72.8146 26.9902 0.uR93 19.2?o9 26.9960 0.04e4 I
. 11 5.00 62.5499 26.9R96 0.1039 72.7971 26.9933 0.0897 18.9939 26.9969 0.0479 12 5.50 62.5062 26.9933 0.1039 72.7891 26.9930 0.0902 In.9?2? 26.9995 0.0477 13 6.00 62.4337 26.9909 0.1042 72.7694 26.9927 0.0an9 19.l?23 26.99R2 0.0482 14 6.50 62.5003 26.9P60 0.104S 72.7426 26.9929 0.0904 19.0895 26.9935 0.0491 15 7.00 62.4506 26.9R82 0 1049 72.7311 26.9P50 0.0914 19.9412 26.9903 0.0475 16 7.50 62.4582 26.9826 0.1052 72.7177 26.9044 0.0914 18.909% 26.9A99 0.0477
'? . ___. 17 8.00 62.4735 26.9000 0.1054 72.7034 26.9818 0.0966 19.9360 26.99'5 7 0.0475 18 8.50 62.4632 26.9779 0.1066 72.7092 26.9046 0.0919 19.2*?3 26.9P49 G.05P4
<.'I 19 9.00 62.4356 26.9761 0.1060 72.6763 26.97At 0.0920 19.1706 26.9936 0.04?3 8 20 9.50 62.4342 26.9752 0.1066 72.6405 26.9777 0.0al2 1P. 1C74 26.9832 0.0474 21 10.00 62.3915 25.9746 0.1066 72.6321 26.9770 0.09?3 18.5935 26.9027 0.0470 ($ 22 10.50 62.3775 26.9776 0.1071 72.6424 24.9785 0.0918 la.7006 26.9m*3 0.0472
- ' _. 23 11 .00 62.3590 26.9761 0.1072 72.6224 26.9780 0.0919 19.0*64 26.9840 0.0481 '
+
24 11.50 62.34P1 24.9768 0.1076 72.5e81 26.97R6 0.0929 19.0446 26.*845 0.0490 2 25 12.00 62.3135 26.9736 0.107R 72.5836 26.9753 0.0930 19.2187 26.9P14 0.04a4
' 26 12.90 62.2948 26.9705 0.1079 72.5581 26.9725 0.0931 19.382A 26.97P5 0.0499 27 13.00 62.1992 26.96*7 0.1083 72.5449 26.9721 0.0931 19.2727 26.9 7e2 0.0495
! 28 13.50 62.2795 24.96r4 0.1088 72.5333 26.9703 0.0928 19.1997 26.9764 0.04R4 li 29 14.00 62.2742 '26.9657 0.1090 72.5209 26.9677 0.0941 19.9094 26.9738 0.0477
- I 30 14.50 62.2567 26.9664 0.1093 72.5024 26.9683 0.0441 18.7451 26.9745 0.0473
- ! 31- 15.00 62.2282 26.9672 0.1095 72.5134 26.9692 0.0949 19.7437 24.9753 0.0473 ij .... 32 15.50 62.2337- 26.9673 0.1099 72.4930 25.9691 0.0951 18.925R 26.9753 0.0478
- j 33 .16.00 62.1950 26.9659 0.1100 72.4852 ?6.9676 0.0954 19.3'80 26.9739 0.04m7 il 34 16.50 62.2216' 26.9665 0.1104 72 5246 26.96P3 0.09%7 19.7068 26.9766 0.0496
?
_, 35 17.00 62.1974 26.9665 0.1107 72.4439 26.9684 0.0961 20.?912 26.9744 0.0?l2 36 17.50 6?.1969 26.1655 0.1109 72.4600 26.o677' O.0959 20.3432 26.9739 0.0511 37 10.00 62.1636 26.9635 0.1120 72.4411 26.9655 0.0966 19.1474 26.9216 0.0497 33 1R.50 62.1404 26.9610 0 1116 72.4330 2$.4629 0.0969 19.4775 26.9693 0.0490 39 19.00 62.1203 26.9606 0.1119 72.4319 26.9626 0.0975 19.3526 26.9689 0.0487 40 19.50 62.1188 26.9583 0 1122 72.4115 26.9653 0.0973 19.3254 26.9664 0.0487
. 41 20.00 62.1167 26.9564 0.1325 72.4121 26.9588 0.0974 19.4096 26.964P C.0'eR
;i 42 '20.50 62.1012 26.9550 0.1129 72.4128 26.9571 0.0977 19.2700 26.8630 0.04P5 i 43 21.93 62.0417 26.9523 0.1143 72.3728 26.9543 0.0993 19.7693 26.9603 0.0497 44 21.50 62.0162 26.9504 0 1132 77.3730 26.9524 0.0*73 19.6745 26.9584 0.0495 l{-
45 22.00 62.0461 26.9491 0.1158 72.3503 16.9510 0.0955 19.2875 26.9571 0.04e4 , 46 22.50 62.0397 26.9489 0.1151 72 3639 26.9500 0.0990 19 1348 26.9564 0.0482
' , . , _ . 47 23.00 62.0245 26.9528 0.1154 72.3167 26.9549 0.0997 19.2eP2 26.5510 0.04e5 48 .. 23.50 62.0258 26.9549 0.1156 72.2967 26.9570 0.0999 19.9200 26.9631 0.0501 .
49 24.00 62.0016
- 26.9521 0 1160 72.3049 26.9540 0.1002 20.2497 26.9601 0.0509
56 - 7 0 LOCAL LEAK TEST PROGRAM r A local leak test program was conducted in acecrdance with guidelines specified in 10CFR50 Appendix J, FSAR, and Technical Specifications, under AEPSC vritten and I&M approved' procedures, P0-033-330 " Containment Penetration and Personnel Lock Leakage [ Test", P0-033-331 " Sensitive Leakage Rate Test", arid PO-033-332 r- " Containment Isolation System Pneumatic Leak Test". These tests were conducted as a prerequisite to the Integrated Leak Rate test to systematically verify acceptable leakage across each containment I penetration and pressure containing boundry. The program consisted I of type B tests, designed to determine leakage through the containment j j , penetrations, air lock door seals, lock cover flange seal, ring body l flange seal, overall air lock leakage, and weld channel leakage (in-r ternal to the containment), and type C tests designed to determine l 1 leakage across isolation valves. Two test methods were employed in the conduct of these tests. Where test volumes were small enough to pressurized with our leak [ detection instrument, it was used to determine the leakage rate. p This instrument (Volumetrics Leak Rate Monitor) is a self contained k mass flow leak test system capable of measuring small gaseous leak { rates. The monitor pressurized the test volume to a predetermined setpoint ( 12.0 PSIG). After test pressure is attained precise e pressure regulators, internal to the instrument, maintain the pressure setpoint by adding air through a thermal flow sensor. Since i-the test volume pressure remains constant during the test the amount j of air leakage is equal to the amount of air added. This leak rate is electronically converted and displayed on a digital rate meter. i i L ,
. g -, , . . .. .g...op. . , - . .- ,
i l 1 57 - 70 LOCAL LEAK TEST PROGRAM (CONTD. )
, Two ::uch instruments were employed in our local leak test program l
each having calibration certification to NBS. The following pressure boundaries were tested in this manner I with results and acceptance criteria as listed. Measured Leakage Acceptance Criteria !r 612' Personnel Access Hatch .000294La .00lLa i Door seals inner .000037La .0005La outer .000248La .0005La 650' Personnel Access Hatch .0000092La .001La 7 l Door seals inner .0000184La .0005La outer .0000737La .0005La 650' Lock Cover Flange 34SCCM N/A )a t 650' Ring body flange 16SCCM N/A Isolation Valves (total Leakage) 16,835SCCM 54,516SCCM For an individual accounting of containment isolation valve [ 1eakage rate, Table 7 1 is included. In this table each valve is ( identified by tag number, valve diameter, allowable leakage and actual ( [. leakage as measured during the pre-operation leak-test. The individual i allowable leakage values were determined by allocating a portion of the L total allowable leakage based on valve size (diameter). The allowable leakage values were dstermined as a guideline to enable the test
~
engineer to decide which valves should be repaired, if necersary, to meet the total allowable leakage value of 54,516SCCM. Refering to Table 7 1, it can be seen that the actual leakage measured for isolation valves VCR-105 and VCR-205 exceeded their allowable leakage
, 4 limit. The pre-operation test, however, was accepted because, as t
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per 10 CFR 50; Appendix J, the combined leakage for all valves subject to Type 'C' tests must be less than the allowable limit. When the total actual leakage is compared to the total allowable leakage a value of 30.88 per cent of the allowable limit was attained. I
; The second test method used to measure leakage was the , reference volume method. This method employs a reference volume, I
of known internal volume, fitted with precise pressure and temperature measuring equipment. A non-bleed type pressure regulator is attached to the discharge line of the volume. The discharge side of this regulator is attached to the test volume and the regulator is set to maintain test pressure (12.0 PSIG) on the test volume. By timing the pressure decay in the reference volume, the leakage rate of the test volume can be calculated. The following pressure boundaries were tested in this manner with results and acceptance criteria as listed. [ Measured Leakage Acceptance Criteria 7 Containment penetrations 3 735%La 15 7%La i Containment liner weld channels 8.105%La 10%La e ( L+ f t f 'i. I 1 I
. ..- 3l
- _ _ , _ _ j
7 0 LOCAL LEAK TEST PROGRAM TABLE 7 1 VALVE ALLOWABLE ACTUAL DIAMETER LEAKAGE LEAKAGE VALVE I.D. (INCHES) (SCCM) (SCCM) ( l CCR-455 & CCR-456 2.0 360 61 r l 4 CCR-457 & CCW-135 2.0 360 45
, CCR-462 & CCR-460 30 540 269 I
PW-275 30 270 23 r DCR-201 & DCR-203 0 75 135 14 - DCR-202 & DCR-204 0 75 135 20 DCR-207 1.0 90 12
, DCR-600 & DCR-601 30 540 8 i DCR-610 & DCR 611 25 450 137 r
DCR-620 & DCR-621 1.0 180 76 ECR-10 & ECR-20 05 90 32 ECR-11 05 45 28 ECR-21 05 45 (~ 31 L ECR-12 05 45 2 ECR-22 05 45 0 ECR-13 05 45 17 { L ECR-23 05 45 4 ECR-14 05 45 i 3 L ECR-24 05 45 7 f ECR-15 05 45 0 ECR-25 05 45 10 f ECR-16 L 05 45 1 ECR-26 05 45 1
. .. *9
-~ -
; --_-_;~_--- _ ~3 - ~ ' - ~ ~ ~ - ~ ~ ~ ~ _ _ - ~___~_ - :-- - ;-- ---
7 0 LOCAL LEAK TEST PROGRAM t TABLE 7 1 i VALVE ALLOWABLE ACTUAL I DIAMETER LEAKAGE LEAKAGE VALVE I.D. (INCHES) (SCCM) (SCCl,O _ r ECR-17 05 45 10 ( ECR-27 05 45 15
,I ECR-18 05 45 0 ECR-28 05 45 6 ECR-19 05 45 0 r ECR-29 0.5 45 2 GCR-301 0 75 67 5 ig GCR-314 1.0 90 38 f
ICR-5 & ICR-6 05 90 2 i NCR-105 & NCR-106 05 90 6 NCR-107 & NCR-108 05 90 9 NCR-109 & NCR-110 0.5 90 2 { NCR-252 30 270 11 QCM-250 & QCM-350 4.0 720 118 ( [. QCR-300 2.0 180 29
, RCR-100 & RCR-101 0 375 67 5 1 VCR-10 & VCR-11 30 540 498
{ VCR-20 & VCR-21 30 540 9
~
XCR-100 & XCR-101 0 75 135 66 XCR-102 & XCR-103 0 75 135 63
,. CCM-458,-454 3 0,4.0 1350 o ;
and - e52 8.0 [ CCM-459,-453 3 0,4.0 1350
! and - 451 8.0 0 1.0 180 8 ECR-31 & ECR-32 l L . .
a o .o , ,
. _ _ . _ . . . . . . _ _ _ _ . . ~~~~~.~. '~~,~h
. - . _ _ - . _ _ __ . =- _ - _
, 7 0 LOCAL LEAK TEST PROGRAM i TABLE 7 1
[ l VALVE ALLOWABLE ACTUAL j DIAMETER LEAKAGE LEAKAGE j VALVE I.D. (INCHES) (SCCM) (SCCM) r WCR-951 & WCR-955 30 540 88 [ WCR-952 & WCR-956 30 540 59 r WCR-953 & WCR-957 30 540 31 l WCR-954 & WCR-958 30 540 299
~
{ WCR-961 iCR-963 2.0 360 103 WCR-965 & WCR-967 2.0 360 9 WCR-901 & WCR-903 6.0 1080 61 6.0 1080 WCR-905 & WCR-907 6 WCR-909 & WCR-911 6.0 1080 155 { WCR-913 & WCR-915 6.0 1080 568 o WCR-925 & WCR-927 30 540 167 WCR-933 & WCR-935 30 540 121 I WCR-921 30 270 48 WCR-929 30 270 27 [ WCR-923 30 270 go WCR-931 30 270 28
.. VCR-101 & VCR-201 14.0 2520 884 VCR-102 & VCR-202 14.0 2520 645 VCR-103 & VCR-203 30.0 4320 644 I VCR-104 & VCR-204 30.0 5400 1211 VCR-105 & VCR-205 30.0 5400 8023 , < VCR-106 & VCR-206 24.0 4320 168 j VCR-107 & VCR-207 14.0 2520 76 L
SI 189 4.0 360 303 f L , ,
s 7 0 LOCAL LEAK TEST PROGRAM
' TABLE 7 1 I
VALVE ' ALLOWABLE ACTUAL i ; DI/JiETE.R . LEAKAGE LEAKAGE VALVE I.D. (INCHEfQ, (SCCM) (SCCM) r CS 321 30 270 3 '{ SI-171 & SI-172 0 75 13.5 15 N-102 1.C 90 26 DCR-206 & DCR-206 4.0 720 110
- i. SF-159 & SF-160 30 540 4 r DW-209 & DW-210 2.0 360 16 .
C S-W2-1 2.0 180 116 CS W2-2 2.0 180 9 CS h42-3 - 2.0 180 111 ' I I i CS W2-4 2.0 180 3 91
, CA 181 N 05 45 - 23 s CA 181 S 0.'5 ' 45 12 i('
[ DA 145& Blind Flange 2.0 360 9g f CPN-80 . 6.0 1080 t (2) Blind Flange 51 i l. CPN-57 (2) Blind Flange 4.0 \ 720 ig ( SF-151 15 135 52 i SF-153 15 135 0 I ICM-250 4.0 . 360 18 r , ICM-251 4.0- 360 38 1 t. ICM-260 4.0 360 184 ICM-265 4.0 360 198
- f ICM-305 18.0 168 46 ICM-306 ' 100 168 , 961
\ 1 . 'L, lL ^
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. m _ _
l l 63 - 7 0 LOCAL LEAK TEST PROGRAM TABLE 7 1 ALLOWABLE ACTUAL DIAMETER LEAKAGE LEAKAGE Ii! STP. . I. D. (IITCHES) (SCCM) (SCCM) [ PPA-310 & PPA-311 0.5 90 22 PPA-312 & PPA-333 05 90 0 PPP-300 05 ' 45 5 PPP-301 05 45 o PPP-302 05 45 2 [ PPP-303 05 45 6 f s l f k - ' 1 s , 9
8.0 REFERENCES 8.1 D. C. Cook Nnclear Plant P Final Safety Analysis Report
, 8.1.1 Initial Leakage Rate Testing of Containment (Page 5 2-7).
t 8.1.2 Initial Containment (Pre-Operational) Leakage Rate Test I (Page 5 7-4) f 8.1 3 Containment Leakage Test Program FSAR Question 5 93 8.2 D. C. Cook Nuclear Plant - Unit 1 Technical Specifications 8.2.1 Containment Systems - Containment Leakage I. (Page 3/4 6-2) i jj 83 American National Standard - ANSI, N45.4-1972 Leakage-Rate Testing of Containment Structures for Nuclear Reactors. 8.4 10 CFR 50, Appendix J Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors. l[ 8 5 Basic Statistical Methods for Engineers and Scientists - A. M. Neville J. B. Kennedy I
- E i 8.6 Hygrometric and Psychrometric Tables Smithsonian Institution
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F 8.7 D. C. Cook Nuclear Plant
! Pre-Operational Test Procedure 871 Containment Penetration and Personnel Lock Leakage i
Test - Po-033-330 872 Sensitive Leakage Rate Test Po-033-331 8.7 3 Containment Isolation System Pneumatic Leak Test Po-033-332. 1 8.7.4 Cold Containment Integrated Leakage Rate Test - Po-033-334. I' I o,s f 1-as i l l' r
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