ML19305E095
| ML19305E095 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/16/1979 |
| From: | Clark K, White T TENNESSEE VALLEY AUTHORITY |
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| Shared Package | |
| ML19305E087 | List: |
| References | |
| NUDOCS 8004220358 | |
| Download: ML19305E095 (46) | |
Text
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NUCLEAR CONTAINMENT TESTING FOR TVA NUCIZAR POWER FIANTS e
Kenneth H. Clark Mechanical Engineer Tennessee Valley Authority Chattanooga, Tennessee Timothy J. White Mechanical Engineer Tennessee Valley Authority Chattanooga, Tennessee Presented to the American Nuclear Society Winter Mseting November.11-16, 1979 A004220
A TABIE OF CORISETS as.
Introduction 1
Test Objectives 3
Test Criteria 5
Techniques of Analysis 7
i Data Acquisition and Reduction Systems 10 Instrumentation Techniques 13 I
System Software 17 Discussion of Test Results I
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Conclusions 22 b
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INTRODUCTION A significant part of the surveillance requirements tor a nuclear power plant involves the assurance of isolation of raaioactive contaminants from the environment in the event of a radiological accident. The primary containment serves as the final barrier of isolation in an accident. General Design Criteria 54 and 56 of Title 10 Code of Federal Regulations, Part 50 (10 CFR 50),
spe n.fy design provirions for the reactor building primary containment.
Appendix J to 10 CFR 50 defines the basis for a surveillance program to ensure that the primary containment will perform as designed for the life of the plant.
The most significant test prescribed by Appendix J, the reactor building containment integrated leak rate test, involves simulating as close as is practical the predicted conditions within the primary containment after the most severe postulated accident. The leakage of air from the primary containment to the environment is measured to demonstrate that offsite exposure to postulated radioactive contaminants will not exceed 10 CFR 50 guidelines, as implemented by the plant technical specifications.
Since the publication of Appendix J to 10 CFR 50, it has been customary to conduct reactor building containment leak rate tests (CILRT's) for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This practice originated from experience gained in the ORNI,-AEC containment proof program. The current national standard for the conduct of the CILRT, ANSI 45.4-1972, recommends tests be conducted for "...not less than twenty four hours of retained pressure..." This arbitrary test duration was set as a means to ensure the primary containment leakage.would be accurately measured, with the instrumentation typically in use when the standard was prepared.
Experience gained by the Tennessee Valley Authority in the conduct of CILRT's has demonstrated that the prirary containment leak rate may be accurately mea 0ured for tests conducted for considerably less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The purpose of this presentation is to discuss the techniques, equipment, and method of analysis TVA proposes to use to conduct future CILRT's of shorter duration than current practice. Data collected from two CILRT's conducted for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> with the techniques and equipment described by this paper are discussed.
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3-TEST OBJECTIVES A.
General The reactor building primary containment is designed to prevent the release of radioactive contaminants to the environment either in nonnal operation of a nuclear power plant or as the consequence of an accident.
Plant site meteorolo61 cal conditions determine from the guidelines presented in 10 CFR 100 a maximum amount of radioactive contaminants that may be released to the environment.
Various plant design and reactor specific features detennine a predicted maximum pressure expected to exist within the primary containment under accident conditions and a maximum rate of release of radioactive contaminants to the environment. Appendix J requires that the plant operator periodically demonstrate the ability of the primary containment to limit the release of contaminants below the calculated maximum.
The CILRT measures the rate cf release, or the leak rate, of the primary containment atmosphere to the environment at a test pressure of either one-half or equal to the calculated peak pressure expected for the most severe accident. Lines that penetrate the primary containment are aligned with the configuration assumed automatically after an accident. Lines postulated to rupti re incide the primary containment are drained to the extent practical of fluid and vented to the containment atmosphere for
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the duration of the test. Lines postulated to.1pture outside the primary containment are drained to the extent practical of fluid and vented to the environment.
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-4 Before a nuclear power plant may return to operation, the CILRT must demonstrate that this measured rate of leakage is less than 75 percent of the design =vimm.
The 25-percent margin provides assurance that, with unforeseen degradation of performance, the maximum leakage will not be exceeded.
B.
Specific Objectives The specific objectives of the CILRT are:
1.
Accurately measure the actual rate of primary containment atmosphere leakage under conditions close to those predicted for the most severe postulated accident.
2.
Demonstrate that the primary containment leak rate has been accurately measured by the CILRT by a subsequent verification test.
3.
Demonstrate that the measured rate of leakage is less than 75 percent of the design maximum before the nuclear plant may return to power operation.
4.
IMmonstrate that no potential means for the release of primary cortainment atmosphere has arisen since the previous CILRT.
5.
Provide a statistical statement of the validity of the measured leak rate of the primary containment by calculating the confidence interval of the results.
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9 TEST CRITERIA A.
Primary Containment Atmosphere Stabilization During the pressurization of the primary containment, the containment atmosphere temperature will significantly increase. This heating, due to the work required to pressurize the air, can introduce instabilities of the containment atmosphere that may preclude the accurate measurement of leak rate. In a similar manner, the operation of large equipment within the containment can cause the apparent leak rate to change during the CILRT.
Appendix J requires that the primary containment atmosphere be allowed to stabilize at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the end of pressurization. This arbitrary requirement can prove of insufficient duration particularly when applied to high-pressure, small-volume containments. From the experience gained in the conduct of six CILRT's, the following guidelines were prepared to supplement the Appendix J requirement:
1.
The average pri2 nary containment atmosphere temperature change should be less than 10F per hour before starting the CILRT.
2.
A time versus temperature plot for the stabilization period should be approximately linear by the start of the CILRT.
3 Heat-producing equipment located within the primary containment should only be operated to maintain the safety of the reactor.
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4.
Any air circulation equipment operated durin; the CILRT should be operated continuously since intermittent operation could disturb the.
containment air temperature distribution.
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5 Water. Levels within the reactor and any other vessel within the primary containment should be held as constant as is possible. Any a
required level changes should be made slowly.
B.
Accuracy of the Measured Leak Rate Since any measurement has some degree of uncertainty associat_ vith random and systematic errors, the reported measured leak rate of the primary containment atmosphere is only an approximation to the "true" value. A statement of the goodness or degree of confidence of the CILRT results is necessary to provide assurance that the primary containment functions as designed. Following general testing practice, TVA reports a 95-percent upper confidence level for the reported leak rate.
A CILRT is ' considered satisfactory if the measured leak rate is less than 75 percent of the design maxinaam. To ensure adequate confidence in this leak rate, TVA further requires that the 95-percent upper confidence level be less than 75 percent of the design maximum leak rate.
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7 TECHNIQUES OF ANALYSIS i
A.
Containment Modelin6 l
The accurate measurement of primary containment leak rate pivots on the precise measurement of temperature, pressure, and vapor pressure. The primary containment is not constructed as a single homogenous pressure vessel but as a series of interconnected compartments. Althou6h all ccs::partments forming the primary containment are vented to each other for the CILRT, the flow of containment atmosphere may be restricted.
Pressure suppression containment designs incorporate special compartments that may have significantly different temperature and vapor pressure conditions from the rest of the primary containment. A boiling water reactor pressure suppression chamber is characterized by humidity approaching the saturation point. The ice condenser for a pressurized vnter reactor employs two large compartments far below the freezing point-of water. Since a substantial portion of the primary containment free air volume is contained within these pressurization suppression compartments for both reactor designs, significant errors may result in the calculation of the leak rate if the containment atmosphere conditions are not. correctly considezvi by the analys.is.
To compensate for the compartmental construction of the primary con +minnant, the leak rate is calculated from a model in which the containment is a multiple element system. Temperature, pressure, and vapor pressure are measured for each compartment. The mass of the air in each compartment is calculated from these measurements. The primary containment leak rate is calculated from the sum of the compartment air masses. Temperature, vapor l
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8-pressure, and pressure measurements are individually assigned volumetric weighting or influence factors determined by the relative volume each sensor represents within the compartment.
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A primary containment model is developed from information provided in t
i section 6.2 of the Final Safety Analysis Report. Any compartment that l
represents more than 10 percent of the containment free air volume is considered a compartment for the CILRT.
i B.
Method of Leak Rate Calculation Several techniques have been used previously to calculate the primary containment leak rate. ANS 45 2-1972 recognizes the absolute and the reference vessel methods. The proposed standard for containment testing, ANSI 56.8, reco6nizes the same techniques. We have found the absolute, or mass loss, method yields the most accurate measurement of the primary containment leak rate.
The primary containment leak rate is calculated by the application of the ideal gas law. During the CILRT, the mass of the air in the containment is calculated periodically. The leak rate is tomputed from the slope of the least squares fit line to these data. The uncertainty of the measured leak rate is estimated by calculating the dcviation of the individual mass points from the l~ sst squares fit line, with adjustments for the sample size.
C.
Instrumentation Selection Guide The accurate determination of leak rate by the absolute method requires the precise measurement of primary containment atmospheric temperature, vapor pressure, and total pressure. Since any measurement will include some error, the accuracy of.these measurements determine the accuracy of the measured primary containment leak' rate. Prior to the performance of.
the CILRT, the number of temperature, vapor pressure, and total pressure sensors required to accurately determine the leak rate m st be estimated, i
Based on the expected leak rate and the anticipated conditions encountered in the test, this instrumentation selection guide detemines the minimum instrumentation necessary to conduc+ the CILRT.
The basic criteria TVA uses for the selection of minimum CILRT instrumen-tation is that the primary containment ~ leak rate should be accurately measured within the first 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of data collection with an assumed leak rate equal to 25 percent of the maximum allowed under technical specifica-tions. In addition, no temperature measurement may represent more than 10 percent of the containment free air volume. Appendix A presents an example of the estimation of sensors required for a typical boiling water reactor CILRT.
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. IATA ACQUISITION AND REIAJCTION SYSTEMS The precise measurement of many test variables is required to accurately calculate the primary containment leak rate. CILRT test data salet, therefore, be acquired and analyzed rapidly. TVA has developed a leak rate measurement system that acquires and reduces test data automatically. The principal advantages afforded by this automatic system are highly accurate, reliable results and data collection speed. The purpose of this section is to describe the principal functions and features of the automatic data acquisition and reduction systems.
A.
Data Acquisition System The principal function of the data acquisition system is to periodically l
measure the test variables. A microprocessor controls the timing of periodic acquisition, the conversion from analog to digital values, and the transmission of data to the data reduction system. The microprocessor will periodically collect data at a set interval or, at the discretion of the test director, can be demanded to acquire data within the selected interval. A log of all collected data is printed for permanent records.
P Table 1 lists typical data collected for a boiling water reactor and a pressurized water containment. The data acquisition system is designed to allow for any combination of temperature, pressure, and vapor pressure measurements. Figure 1 depicts the components that fona the data acquisition i
system.
l The principal feature of the data acquisition system is the accurate, I
rapid measurement of test variables. In CILRT's previously conducted by
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TVA without the automatic data acquisition system, data could not be l
l collected more frequently than once per hour. Even at this slow rate of i
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collection, mis' takes by test personnel in the measurement of test variables degraded the results. For a typical ice condenser pressurized water reactor, the data acquisition can collect up to 20 samples of the test variables per hour. The significant increase in the volume of collected data improves the confidence of test results.
B.
lata Reduction System The primary purpose of the data reduction system is to accurately perform the necessary calculations to compute the primary containment leak rate.
The central element of the data reduction system is a minicomputer system directly connected to the data acquisition rystem. All raw data collected by the data acquisition system is transmitted to the minicomputer and stored on flexible disks. These data are subsequently corrected accord 3.6 to each sensor's calibration data. The leak rate is automatically calculated and results are printed on a local printer. The system is designed to be tolerant of power failure. Figure 2 depicts the data reduction system.
Several features are included in the design of the data reduction system.
The most significent is that the reliability of field test results is significantly enhanced because no manual data entry or calculations'are required. The speed of data reduction is significantly increased. For a typical ice condenser, pressurized water reactor data can be collected by the acquisition system, stored, reduced, and the leak rate calculated in less than 2 minutes.
In addition to speed, the minicomputer offers several features to enhance test performance. Test variables or results may be automatically plotted by the minicomputer any time during the CIIRT. The test engineer may also choose to redefine the tima of the test start to any previously collected
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sample while the test is conducted. This " base reset" feature allows-the field evaluation of the effect of prolonging test duration.
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INSTRUMENTATION TECHNIQUES A.
Temperature Measurement Four-wire resistance temperature detectors (RTD's) are used by the leak rate measurement system to monitor primary containment atmosphere temperature. Before and after the performance of each CILRT, each RTD is individually compared with a standard certified by the National Bureau of Standards over a temperature range of 0-150 F.
The uncertainty of the 0
te.Terature standard is better than 0.005 F.
A unique temperature as a 0
function of resistance calibration curve is calculated for each RTD from this comparison.
When installed in the primary containment, each RTD is connccte.d to a separate excitation bridge (wheatstone) by quick disconnect extension cables. Systematic errors due to lead length resistance, excitation bridge nonlinearity, and analog to digital conversion repeatable offset error are measured by substituting precision resistors in place of the RTD at the end of the extension cable. ~A unique resistance as a function of measured bridge output calibration curve is calculated for each measurement channel. The minicomputer automatically calcu.lates and stores each calibration curve. For each temperature measurement, measured bridge voltage is first converted to resistance. The minicomputer then uses the 4
individual RTD calibration curve to calculate.the equivalent temperature from this resistance.-
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Tests have been conducted to determine the accuracy of temperature.
. measurements by the integrated leak rate measurement system.~ Seven RTD's
. were ecsqmrod with a standard certified by the National Bureau of Standards at five temperatures. 'This standard is certified with a measuremsat
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uncertainty of better than 0.005 F.
Figure 3 depicts the difference i',
between that temperature measured by the standard and the leak rate measurement system over the range of comparison. Analysis of the data i
indicates that the system uncertainty of temperature by the leak rate measurement system is better than 0.0202 F.
i B.
Vapor Pressure Measurement Lithium chloride dewcels are used by the leak rate measurement system to t
monitor primary containment atmosphere mointure content. The principle of operatirm of a deweel is that certain hygroscopic salt solutions will l
t change the amount of water in the solution in relation to the moisture
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content of the air. The dewcel consists of a thin coating of lithium chloridc between two gold wires. As the moisture content of the air changes, the. salt solution will either absorb or liberate water. This I
change in moisture content of the salt. solution changes the solution resistance proportionally. Passing a constant voltage through the two wires and the solution causes resistance heating'. An RTD embedded in
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the support bobbin measures the induced heating. 'Since the temperature I
of the solution is directly related to the solution resistance, and hence i
the moisture content of the salt solution and the. air, it is necessary i
only to measure this temperature to measure atmosphere moisture content.
Three-wire IEl,'s moniter the salt solution temperature. Before and after i
- each CIIRT, each dewcel RTD is indivi<inally cospared with' a standard f
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certified to the National Bureau of Standards over a temperature range i
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I RTD from this comparison..
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. Each deweel is connected to a separate excitation bridge (wheatstone) and constant voltage power supply by quick disconnect extension cables.
t As in the discussion of the air temperature measurement, a calibration i
curve of resistance as a function of measured bridge output is calculated i
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by the substitution of precision resistors for the dewcel. Each dewpoint is first converted to e,quivalent resistance. The minicomputer then i
calculates the salt solution temperature from the dewcel's unique element temperature as a function of resistance curve. Equivalent dowpoint is i
calculated from data tabulated by the National Bureau of Standards.
d C.
Pressure Measurement Precision quartz bourdon tube manometers were selected for contaimeent total pressure measurement. Prior to the CILRT, a pressure cell is i
selected so that the rated pressure is just above the expected test pressure. Each manometer and cell is compared with a standard certified 1
by the hational Bureau of Standards before and after each CILRT over the
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range of the pressure cell. Proper selection of the pressure cell ensures the highest possible sensitivity to small changes of the primary con + min = ant pressure. The pressure measured by the quartz manometer is converted l
internally to digital values by a special encoder. The rated cell pressure corresponds to c digital output of four hundred thousand counts, with a resolution of one count.
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To convert the digital signal acquired from the quartz mancaster to i
pressure, the minicomputer linearly interpolates the true pressure from the pressure cell calibration data. This technique yields a certified system accuracy of better than 0.015 percent of reading.
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D.
Calibration of Test Instruments All instruments included in the leak rate measurement system are compared with standards traceable to the National Bureau of Standards prior to and after each CILRT. Any instrument found to be out of tolerance in the range of measurement for the CILRT is rejected from consideration by eliminating all data collected from the sensor. Influence or volume weight factors are aujusted for the remaining sensors to compensate for 8
the failure.
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. SYSTEM SOFIWARE 8
As a minicomputer performs all calculations required to determine the primary containment leak rate, the computer software system represents a complex element of the leak rate measurement system. This section describes the purpose and features of the software required to conduct the ClLRT. Three basic tasks are performed by the software programs of the leak rate measure-l ment system. First, before the CILRT, model definition, calibration data, and channel repeatable error correction data must be stored in the minicomputer.
Secondly, sof tware programs acquire the test data and perform the leak rate calculations during the CILRT. Finally, raw and corrected data must be summarized after the test for plant records.
A.
Prior to the CILRT Several programs are used to define the model of the primary containment I
before the CILRT is conducted. Based upon the number of temperature, vapor pressure, and pressure sensors, the minicomputer allocates storage space for the test data. In addition, the calibration data for each sensor must be stored prior to the test. Several programs are available to check various parts of the data entry process. The most significant is CIIECK, which allows the computer to instantaneously compare the temperature of an installed RTD with a precision temperature standard.
Table II lists and sumnarizes all software required in the preparation for the CILRT.
B.
During the CILRT As the ClLRT is conducted, the raw data must be stored, corrected according'to the calibration factors, and the results calculated. The
primary program, JVRE, receives data from the acquisition system, corrects according to the sensor calibration factors, c,wputes,. stores, and displays the primary containment leak rate. Several other programs (BASE, TALLY, and LIST) provide the ability to change the sasyle considered the start of the test, provide statistical confidence intervals, and 3
tabula'te the test results.
Several unique features are included to prevent the loss of data and enhance the information provided to the test engineer. The moat significant i
feature ensures that any time the data acquisition is prepared to tranmait I
1 data, the minicomputer stops all activities so that the main data collection
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program, FORE, may execute. When these data have bea:1 received and results printed, the minicomputer completes the.mak interrupted by the acquisition l
of data. All programs are designed to be tolerant of power failure. No l
i previous data is lost when power is restored. Table III lists and summarises all software pro 6 rams required during the CILRT.
C.
After the CILRT i
After the CILRT is completed, test-data can be corrected for any instrument l
failure and arranged for inclusion in the pemanent test record. Several i
1 software programs provide the ability to list all raw and corrected hts, i
final test results, and calibration constants. Table IV lists and summarizes the software programs used after the CILRT is complete.
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_. DISCUSSION OF TEST RESULTS Two CILRT's have been conducted with the equipment and techniques described in this paper. Each type represents an extreme of conditions typically expected during the CILRT--small volume with moderately high pressure and low pressure with moderate volume. Both tests were conducted for at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, with data collected at least every 15 minutes. This section presents a suonary of the CILRT results. Complete reports have been filed with the NRC's Division of Operating Reactors.
A.
Browns Ferry Nuclear Plant Unit 2, Conducted June 1978 Browns Ferry unit 2 is a boiling water reactor employing a steel pressure suppression Mark I containment. The maximum leak rate at a reduced pressure of 25 psig is limited by technical specification 4.7.a.2 to less than 0.04437 percentage per hour of containment air mass. The containment was modeled as two compartments--the pressure suppression chamber and the drywell. Twenty-nine temperature sensors, six humidity sensors, and two pressure gauges were used to measure the primary containment leak rate.
The free air primary containment volume is approximately 300,000 cubic-feet..
A 24-hour CILRT and a 12-hour verification test were conducted June 13-16, 1978. The final measured leak rate was 0.00949 percentage of containment air mass per hour. The observed 95-percent upper confidence limit for this measured leak rate was O.00994 percentage of containment air mass.
The mass leak ra'te calculated-during this test is depicted in figure 4.
Table 5.ccmpares test dura. tion with leak rate and upper confidence limit.
Clearly, the primary containment leak rate was accurately detennined within the first 4_ hours of the test. Figure 4 indicates that data collected beyond the. fourth hour of the test served. only to improve the
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upper confidence limit of the leak rate. Figure 5 depicts the upper b
confidence interval as a function of the time of data collection. The rapid approach to the asymptotic limit demonstrates the value of proper l
t instrument selection. Complete summaries of the calculated test results I
are included in appendix B.
t B.
Sequoyah Nuclear Plant Unit 1, Conducted March 1979 Sequoyah unit 1 is a pressurized water reactor employing an ice condenser pressure suppression primary containment. The masinann leakage of air at
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a test pressure of 12 psig is limited by technical specification 4.6.1.2 to less than 0.0078 percentage per hour of containment air mass. The pri=ary containment contains four compartments--the lower ice condenser compartment which houses the energy sbsorbing ice beds, the upper ice f
condenser compartment which encloses support equipment for t:.e ice condencer system, the lower compartment which encloses the reactor and cT.in piping systems, and the upper compartment which encloses the refueling i
vork area. The free air mass was calculated separately for each compartment, f
i with the calculated leak rate derived from the sum of the compartment air j
masses. Based upon the instrument selection guide, 46 RfD's were used for containment atmosphere temperature measurement, 10 humidity sensors were i
used to monitor the containment atmosphere moisture content, and four quart: mancmeters monitored the total pressure. Total free air volume for
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the primary containment is approximately 1.19 million cubic feet.
1 A 24-hour CILRT and a 4-hour verification test were conducted March 13-16, 1979 The final measured leak rate was 0.00011 percentage of containment air mass. The observed 95-percent upper confidence limit was o.00024 percentage of the containment air mass. The mass leak rate calculated is l.
, depicted in figure 6.
Table 5 compares test results with the duration of data collection. Clearly, the primary containment leak rate was accurately determined within the l'irst 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of data collection.
Figure 7 depicta the upper confidence interval as a ataction of the time of data collection. Complete summaries of the calculated test results are included in appendix C.
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p CONCLUSIONS CILRT's conducted by TVA on a high-pressure boiling water reactor containment and a low-pressure ice condenser pressurized water reactor containment verify that the leak rate measurement system used with the techniques outlined in this paper measured the primary containment leak rate in far less than the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the tests were conducted. An analysis of the 95-percent upper confidence limit of the measured leak rate indicates that the primary containment leak rate was accurately detemined with a high level of confidence within the first 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of data collection.
To consistently achieve this accuracy for future CILRT's, this paper has outlined several key techniques. The model used to calculate the primary containment leak rate must compensate for areas of varying temperature, pressure, and moisture content. The test instrumentation must be capable of extremely accurate and repeatable measurement of the containment atmosphere conditions.
Collected test data must be acquired quickly with reliable equipment. The i
test director must be provided with accurate results during the test.
TVA will conduct future CILRT's in accordance with the techniques described i
in this paper. Each CILRT will be conducted for at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and extend until adequate confidence in the accuracy of the measured leak rate is achieved.
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6 TABLES
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TABLE I DATA COLLECTED BY AUTOMATIC ACQUISITION SYSTEM i
i 1.
Boilin6 Water Reactor, Pressure Suppression Containment t
Quantity Function i
29 Resistance temperature detectors (RTD's) for ct.itainment f
atmospheric temperature measurement 6
Lithium chloride dewcels for containment atuospheric vapor pressure measurement 2
Precision quartz manometers for containment atmospheric total f
pressure measurement r
4 RTD's for containment vessel metal temperature and test station temperature t
1 Mass flowmeter for measurement of induced leak required for the verification test 1
Precision quartz manometer for atmospheric pressure l
1 Suppression chamber water level 1
2.
Pressurized Water Reactor, Ice Condenser Suppression Containment f
Quantity Funetion I
t 46 RTD's for containment atmospheric temperature measurement t
i 10 Lithium chloride dewcels for containment atmospheric vapor pressure measurement 4
Precision quartz manometers for containment atmospheric total 1
pressure measurement 4
RTD's for containment vessel metal temperature and test station temperature measurement l
1 Mass flowmeter for measurement of induced leak required for the verification test 1
Precision quartz manometer for atmospheric pressure I
, TABLE II SYSTEM SOFTWARE REQUIRED PRIOR TO THE CILRT Program Name(s)
Description S1 Define the integrated leak rate system parameters: number of RTD's, dewcels, pressure gauges, analog inputs, and local RTD's.
Create the required system files required to store the test data.
CREAM Lefine the sensor calibration data and volume weights. Requires EllTAM ENTVW calibration reports on all dewcels and RTD's that may be used for the CILRT.
AM Measure the integrated leak rate system analog to digital repeatable offset. Requires all temporary cables to be installed and integrated leak rate system to be operational.
STARTN Define the calibration data for the quartz manometer pressure gauges and any plant process instrumentation, e.g., suppression chamber and reactor level transmitters.
CIECK Verify in-place system temperature or dewpoint measurements.
A standard for comparison is required for this program.
CIECK8 Print all stored calibration constants required to conduct the C1LRT.
r r
a TABLE III SYSTEM SOFTWARE REQUIRED DURING THE CILRT Program Name(s)
Description l
FORE Acquire containment data from the data acquisition system, store, correct raw data, and calculate leak rate.
t l
LIST Print a summary of measured leak rate. Drive an online
[
digital plotter to produce graphs of principal test results.
i TALLY Calculate confidence limits of the calculated leak rate.
I BASE Redefine the sample considered the start of the CILRT.
I l
a b
f f
r l
4 i
e l
I
TABLE IV
~
SYSTEM SOFTWARE REQUIRED APfER THE CILRT 1
Program Name(s)
Description AM Measure the integrated leak rate system analog to digital i
repeatable offset after test is completed.
DUMDEV Print all raw and corrected test data.
A1101 ASS Print a compartment summary of the measured temperature, vapor pressure, pressure, and air mass. Correct the test results for any sensor found out of calibration.
i L
i I
t
[
l L
- _, TABLE V CILRT RESULTS AS A FUNCTION OF TEST DURAT1oN Browns Ferry Nuclear Plant Unit 2 PTP Leak
- UCL PIP
- Mass Leak UCL Nass CILRT Duration Humber of Rate Leak Rate Rete Leak Rate (Hours)
Mass Samples
% Per Hour
% Per Hour
% Per Hour
% Per Hour 8
33 0.00527 0.01693 0.00855 0.01036 12 49 0.00798 0.02318 0.00785 0.00893 24 97 0.00506 0.01921 0.00949 0.00994 Sequoyah Nuclear Plant Unit 1 PTP Leak
- UCL PTP*
Mass Leak UCL NP.ss CILRT Duration Number of Hate Leak Rate Rate Leak Rate (flours)
Masn Samples
% Per H'our
% Per Hour
% Per Hour
% Per Hour 6
25 0.00456 0.00470 0.00193 0.00238 8
34 0.00323 0.00336 0.00159 0.00188 10 42 0.00254 0.00265 0.00190 0.00211 12 51 0.002 %
0.00307 0.00178 0.00193 24 100 0.00248 0.00258 0.00162 0.00168
- As defined in ANS-274 (draft)
L.
INSTR? MENT SELECTION GUIDE The containment air mass is calculated by th.4 application of the ideal gas law:
g, 144 x V x (P - Pv)
(1)
RT By the mass point method the primary containment leak rate is the normalized slope of the mass loss curve:
W = At + B, LR=
x x 100 (2)
The total differential of the calculated is mass is:
V dP dPy dT (3) dW = 144 4
R T
T TI Therr' ore, LR =
NE dPy y[r (P - Pv).
x 100
'(4) dt dt dt T
The error in measurement of the independent variables, pressure, vapor pressure, and temperature determine the error in the Icak rate.
In general, an upper bound on the error in measurement of an independent variable X is:
(e ) + Ev)
E=
(5) v n*
An upper bound on the error in a dependent variable Y, as determined by the measurement of a set of independent variables X, X,
X is:
1 2
a - -
. + (Ex ) 2 ' 1/2
. N Ey1 (EX) + (EX) +.
(6) 1 2
Therefore, the upper bound of error of the measured leak rate can be expressed as:
ELR 1 (E )2 + (Epy)2 + (E )
(7)'
p T
L i
L.
The minimum change that may be reliably detected in the measurement of an independent variable is determined by the error of measurement.
In general, 2-1/2 dx <
- ?)
+ I6 1 (8) 1 X
~.
UX i
Substituting for each independent variable differential in equat. ion (7) yields:
LR =
b
+
- E_py, 4
E_7 x (P - Pv) x 100 (9) dt dt dt T
In the paper, " Describing The Uncertainties In Single Sample Experi-ments," by McClintock et. al., it was shown the contribution of the measurement of each independent variable should be equal for an optimal instrumentation system. Therefore, equation (9) may be rewritten:
I'R =
2+
- V) x 100 (10)
[
T If a bound on the error in leak rate is assumed, the error in the meanurement of an independent variable can be bounded.
l E=
(11) 100 2T + (P - Py)
TVA selects test instrumentation so that 25 percent of the maximum l
allowable leak rate can be measured within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
It is assumed that data is collected every 30 minutes. Therefore, equation (11) is rewritten:
E = (. 5 ) (. 25 x L., x. 7 5)
T (12) 100 2T + (P - Py),
Substituting into equation (8) and solving for the number of instruments yicids:
1ey)2+(gy)2'1/2 (13)
UX1 E2
~
Definition at Symbols e
Absolut e error of the ceasute of a variable 5
Absolute error of the indication of the measure of a variable E
Retnrive error of a varinble g
I.
Abnolute error of leak rate, percent of containment air mass per hour Niunber of replientions of a measurement N
Nur,her of independent measurements l'
Absolute pre.icure, i..
R Universnl gas constant S
D.:vintion from the mean of a population t
Time of nample t9 c, Student't; t dintribution for N-1 degrees T
Te:npera t ure, degrees Rankino DV T
W' V
Containment air volume, scf ci 6@
J J.
a b
t!
Absolute mass of containment air, Ibm Subscripts A
~
Estimate corrected for replication' and sample size 1.
Lower bound
'Ifpper bound-11 -
-Yoper previsus " -
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l f
1
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G f
APPENDIX B t
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f SHEET 110.
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Ill*E57L VALLE) Au!NORiii CONTAIMENT LEMCE MEASUREMENT 1EtT S R P Mil I!0URS A'/[9 ACE C0%ECTED TOTAL PASS SINCE 19PERAltFF PRESSWE P-i P OF AIR 101AL TIME 51ARI DEC f.
PSIA LEAKRATE LEAXRATE LEAX liATE RAS $
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PSIA LBM 1 PER 1409R I PER HOUR 1 PER H3UR
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c
I i
e APPENDIX C I:
u t
I s
IENNESSEE VAllET AUTHORlli i
(EQUOTAH NUCllAR PIA 41 -- UNii !
CONIAINMENT LEAVACE MEASUREMENT IEST 'iut!.1RT ML CCf'PMllMENTS 12 PSIC CILRT H9URS AIR 11AS3 AIR M.%S AIR MASS AIR PASS P-i-P 10iAl ilNE MASS SINCE ICWrR COMP.
UPPER CONF.
VIFER ICE LOWER ICE LEAK RATE LEAK RATE LEAX RATE JART ILM lFM LEM LBM 1 FER HOUR 1 PER HOUR 1 FER HOUR f.fM E.t. )
it]A$,"
Jjf),)
[6949,$
p,M$$$
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- 1. 2'i9 53738.9 91137.6 7183.f 16962.1
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MUJuh
ilNNESSEE VAllti AUTHORIII 5.1000fAH NULLEAR N ANT -- UKli i r0H1AlNMTNT IfArACE NEASUREMENT TEST S'NRART
)_
ALL COMI M IMENTS 12 PSIC CILRT HOURS AIR MASS AIR MASS AIR MASS AIR MASS P-i P TOIAL TIME MASS j
SINCF
[0k'ER COMP.
11NTR CORP.
UFPER ICE LOWER IEE LEAX RATE LEAKRATE LEAKRATE STAR 1 LBM LPM LBM
...........................................................LOM
! PER NOUR I FER HOUR I PER HOUR 8.564 51934.5 91156.0 7698.9 16928.5 f.ff839 f.ff!49 f.ffl71 8.814 53936.0 91155.5 7991.1 16927.1 f.fff26 f.If243 f.ffl77 9.864 53936.3 91155.7 7991.5 16926.2 f.fff22 f.08236 f.ffl88 9.314 53937.2 91156.1 7992.4 16925.5
-0.ff384 f.ff223 f.ff!82 9.564 53938.1 91156.9 7696.3 16924.8 f.ff311 f.00222 f.0f!84 9.814 53938.4 91159.3 7985.3 16924.1 f.ff673 f.90234 f.98186 ff.f54 53938.5 91169.4 7083.7 16922.8 f.00425 f.ff238 f.ffl98 16.314 53939.1 91151.2 1911.7 16921.8
-0.91527 f.18196 f.ff!87 16.564 53939.7 91162.3 7693.2 16921.2
- f. fill 6 f.ffl65 f.ffl81 10.014 53941.2 91161.6 7986.6 16929.5 f.fif68 f.ffl85 f.ffl78 18.724 5394f.8 91161.5 7684.0 16920.2 0.98278 f.ffl81 f.ffl75 11.f64 5394?.i 91110.4 7%f.7 16928.2 f.ff389 f.ff!83 f.ffl72 11.314
'3741.2 91166.2 1870.3 16918.6 f.91737 f.ff218 f.ff!74 11.944 53939.7
?ll6?.i 7Efil.C 16916.5 f.ffl13 f 06223 f.88177
!!.814
% 939.6 91161.9 79C5.0 16915.2
-f.00396 f.ff21f f.ffl7u ll. fat 53.'.19. 6 1116.'.5 7987.1 16914,'3 F.00122 f.ff2f3 f.f8178 It.314 SP4f.3 91148.5 7005.5 16913.5 f.fJ166 f.ff2f2 f.ffl78 li. 5.',4 SND.7 ol l6.'i 7M6.f 16912.6 0.0fl33 f.ffif t f.6fl79
- 11. 814 4%'.4 91164..'
7600.9 16911.0 f.f8896 f.ff2f5 f.ffl??
L 13 (A4 51911.5 0l!63.2 7650.1 1A910.1 f.00155 f.ff2f 4 0.00179 13.314 5.937.2 91141.1 1998.8 11.999.1 f.*fff7 f.ff2ff f.fft?9 13.5'4 53931.6 91163.8 1989.9 16?I"1.3 0.06436 f.ff285 f.98180 13.P.14.
53937.6 9116t.?
7f90.5 16987.5
-8.ff835 f.f"!86 f.ff!79 14.i44 53133.8 91169.4 799f.6 16106.9 0.ff758 f.ffl69 f.ffl75 14.314 51939.7 91176.3 7210.1 16986.2
-f.ffl52 f.ffl63 f.ffl72 ft.564 53139.8 911%.5 7888.7 16905.3 f.ff949 f.ffl17 f.ffl10 14.814 53041.4 91172.6 if35.6 16904.4
-f.ff448 f.ffl67 f.ffl68 15.054 53941.9 91173.7 1979.9 16983.4 f.fl231 f.ffl84 f.ffl67 i
15.314 53148.1 91172.5 7679.6 16982.1 f.91161 f.ffl99 f.00168 15.564 53939.9 91171.9 1979.6 169ff.6 f.90573 f.ff205 f.ffl69 15.814 5?937.2 91172.3 7f88.0 16899.6 f.ffl74 f.88205 f.M178 16.844 53949.1 91174.6 7878.4 16899.2
-f.ff314 f.ffl97 f.ffl71 14.314 Sh41.4 91175.7 1979.8 16098.4
-0.ff665 f.ffl83 0.00178 16.544 53941.1 11178.3 7879.8 16897.3
-0.ff788 f.ffl76 f.ffl69 16.Rl4 51142.4 91176.6 7974.3 16896.3 f.fl640 f.ffl98 f.89178
" D) T Y M D * ]De w Ju e AL d d li h i
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ifFISSEE iAllEl A01HORiff SFQUOTAll NUllE6R P'. ANT -- UNIT 1 CONTAINMENT LIAKACL MEASUREMfNT TEST SUMART 6tl COMPMilHENTS 12 PSl(, CILRI t"UR1 AIR MA 5 AIR MASS AIR MASS AIR MASS P-i-P 10iAL ilME MASS
$!hCE LOWER C0!iP.
UTFER COMP.
UFPER ICE LOWER ICE LEAK RATE LEAK RATE LEAK RATE S1AR1 LBM LBM LBM LBM I FER 110'JR I PER HOUR I PER HOUR 17.664 53941.1 11178.1 7972.9 16895.1 f.88551 f.f9283 f.ff!71 17.314 53948.8 91174.6 7974.6 16893.8 f.ff987 f.ff215 f.ff!73 17.564 53948.4 91175.7 707i.8 16892.7
-0.01868 f.ffl96 f.fflT3 17.814 53948.6 91177.3 7773.2 16891.8 f.01182 f.ff209 f.88175 19.f64 53948.6 91177.6 7873.3 16898.7 f.98174 f.ff289 f.89176 18.314 51986.4 91176.5 7079.8 16889.4
-0.ff916 f.ffl93 f.ffl76
!?.564 53948.2 91174.1 7f81.2 16889.2 f.ff399 f.ffl96 f.ffl16 19.014 53!4f.3 91!76.9 7902.2 16887.4
-0.88549 f.98186 f.89176 10.9.'6 53941.3 71178.2 7P81.4 16087.4
-0.ffi62 f.ff!78 f.f9175 19.186 5MO.5 91t'9.1 790f.3 16886.7
-f.ff255 f.ffl73 f.00173 19.06 53947.9 11188.1 1979.1 16885.5 f.ff718 f.ffl88 f.96173 17.!86 53948.9 91177.3 7879.1 16884.2 f.fil35 f.00192 f.fsl73 19.9 4 53942.4 91178.4 7976.0 16 % 3.3
-9.fff41 f.ff189 f.ffl73 27.186 53947.4 91177.6 7078.5 16867.4 f.ff311 f.ffl98 f.ffl13 20.U6 SH4I 5 11179.2 1978.6 16881.7
-f.ff279 f.ffl85 f.ffl73 Tf.686 51942.1 71179.1 7918 6 1688f.7 9.98383 f.90186 f.ff!73 If.935 53143.5 91179.6 7378.7 16068.2
-0.ffl99 f.ffl88 f.ffl72 21.11;.-
53943.5 91189.5 7917.7 16879.3 f.ff251 f.ff!81 f.ffl72 Z!.436 539 0.6 91191.2 7977.9 16370.4
-f.fff33 f.05179 f.ffl71 21.686 53943.4 91100.3 7678.7 16877.3 8.99299 f.ff!88 8.ffl7f 2!.936 53944.7 91181.9 7879.8 16876.7
-0.f8708 f.ffl69 f.ffl69 22.145 53945.4 91184.1 7G78.8 16876.5
-f.cf399 f.ff!63 f.8f168 22.436 53947.3 91187.3 7978.6 16876.0 0.81829 f.ffl58 f.ffl66 22.6 %
53948.8 91183.9 7678.5 16875.6
-f.ff603 f.ff141 f.ffl63 22.916 53949.8 91191.7 7968.8 16875.1 f.fl5ff f.ffl56 f.ff!62 23.196 53949.6 91191.5 7962.2 16873.5 f.92826 f.ffl76 f.ffl62 23.436 53947.3 91189.3 7f67.1 16871.9 f.88281 f.ff!77 f.ffl62 23.696 53945.6 91107.3 707f.8 1687f.3 f.ff356 f.H179 f.00162 23.936 53946.8 11183.1 7874.8 16869.3 f.00181 f.ffl79 f.ffl&2 24.196 53946.8 91185.4 7f74.0 16868.3
-0.00981 f.f0177 f.ffl62 24.436 53946.6 91187.3 7973.8 16867.5 f.88392 f.ffl71 0.00162 24.686 53946.0 911P1.9 7874.8 10866.6 f.ff822 f.ffl69 f.ffl61 i
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