ML20045D948

Reactor Containment Bldg Integrated Leakage Rate Test Rept.

ML20045D948
Person / Time
Site:	North Anna
Issue date:	03/31/1993
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
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ML20045D945	List: ML20045D941 ML20045D948
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NUDOCS 9306300247
Download: ML20045D948 (51)

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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT I REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TFST REPORT

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l March 1993 9306300247 930624 PDR ADDCK 05000338 DR

f C Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report TAHLE OF CONTENTS SECTION TITLE PAGE

1. Introduction 2

2. Summary 2

3. Methodology 3 3.1 Leakage Rate Calculations 3 3.2 Test Measurements 5

4. Test Conduct 6 4.1 Plant Status 6 4.2 Prerequisite Activities 7 4.3 Pressurization 7 4.4 Stabilization 8 4.5 Type A Test 8 4.6 Verification Test 10 4.7 Depressurization and Restoration 10

5. Results 10 5.1 Type A Test 10 5.2 As-Found Leakage Rate 13 5.3 Verification Test 13 5.4 Total Time Results 14 5.5 Summary Data and Individual Measurements 14

6. References 15

7. Tables and Figures 15 Appendix I Contaimnent Description Appendix 11 Computer Program Description Appendix III Type B & C Test Result Tabulation

l Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 2

1. Introduction The containment integrated leakage rate test (ILRT) is performed as required by 10CFR50, Appendix J, (Reference 6.1) to demonstrate that leakage across the containment boundary at design basis accident pressure does not exceed the Technical Specification (Reference 6.2) limit. Test methods and procedures are specified in ANSI N45.4-1972 .

(Reference 6.3) and in ANSI /ANS 56.8-1987 (Reference 6.4), both of which are cited by Appendix J, and in BN-TOP-1 (Reference 6.5) which defines an alternative methodology acceptable to the Nuclear Regulatory Commission.

The conduct of the ILRT follows a plant surveillance procedure (Reference 6.6) which, together with referenced subordinate procedures, contains detailed instructions for all test '

phases. References 6.1 and 6.5 provide two options for the calculation of leakage rate. If the I

test has a duration of at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, Reference 6.1 allows leakage rate calculations to be performed using the mass point method defined in Reference 6.4. If test duration is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, leakage rate calculations must be performed using the total time method described in Reference 6.5. The 95% upper confidence limit (UCL) expression derived in Reference 6.5 provides a very conservative upper bound on calculated leakage rate. Since the test reported herein had a duration of over 24 hc,urs, mass point calculations were used to determine leakage rate and UCL.

l The integrated leakage rate test is described in detail in the following sections of this report. Section 2, Summary, gives a synopsis of test activities and results. Section 3, Methodology, discusses leakage rate calculations and test measurements. Section 4, Test Conduct, describes ILRT preparations and implementation. Section 5, Results, presents the parameters calculated during the ILRT and the associated acceptance criteria. Section 6 lists references and Section 7 contains all tables and figures cited in the text. The Appendices contain a description of the containment, a discussion of the computer program used to calculate leakage rate and a tabulation of all Type B & C (local leakage rate) test results documented since the last ILRT. Containment atmospheric condition data recorded during the test is archived with the official test copy of Reference 6.6.

Numerous tables in this report are generated by the program used to calculate leakage rate. In these tables, leakage rate is listed to four decimal places. In the text of the report, l

these values are rounded off to three decimal places. This is done to limit the implied accuracy of reported leakage rate to a more reasonable level.

2. Summary l The North Anna Unit 1 ILRT was conducted between March 29 and April 1,1993.

l Pressurization commenced at 10:58 AM (all times in EDT) on March 29, following the completion of all prerequisite activities and the containment was isolated at 10:45 PM when l

Virginia Electric and Power Company North Anna Power Station l Unit 1 Reactor Containment Buildmg j Integrated Leakage Rate Test Report Page 3 l

pressure had reached 44.77 psig. Numerical temperature stabilization criteria were met in l four hours, at 2:45 AM on March 30. However, the start of the Type A test was delayed until 4:15 AM to ensure that the air mass vs. time plot was following a stable trend. The Type A test was conducted for 33 hou s and 45 minutes, ending at 2:00 PM on March 31. ]'

This extended duration was necessary because the leakage rate, initially large, l decreased fairly rapid as the test continued. Under these conditions, it may not be possible to pass the verification test if the Type A test is terminated too early. Extending the test

! duration reduces calculated leakage rate and provides assurance that the calculated rate can be verified.

The verification test induced leak was adjusted to its final value at 2:15 PM and a successful four hour verification test was conducted between 2:30 and 6:30 PM.

Depressurization of the containment commenced at 6:39 PM and was complete at 10:04 AM  !

on the following day, April 1.

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Test results are listed below.

0.031 %/ day I 95% UCL on mass point leakage rate Acceptance limit (0.75 La) 0.075 %/ day Verificatica test mass point calculated leakage rate 0.115 %/ day Upper acceptance limit 0.154 %/ day Lower acceptance limit 0.104 %! day The final as-left leakage rate (UCL) is 0.032 %/ day. This is the sum of the above mass point UCL and a penalty of 0.001 %/ day for minimum pathway leakage through penetrations not vented and drained during the test. There was no penalty for containment water inventory change.

The calculated as-found leakage rate (UCL) is 0.034 %/ day. This is the sum of the final as-left leakage rate and 0.002 %/ day minimum pathway leakage improvements made during the Type B & C testing program.

3. Methodology ]

3.1 Leakage Rate Calculations l

Integrated leakage rate is determined by pressurizing the containment to design basis accident pressure and calculating the average rate ofloss of dry air from the structure over an extended time period (6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more depending on the method of calculation and other factors). The quantity of dry air in the containment is computed using the ideal gas law and measurements of drybulb temperature, dewpoint temperature and absolute pressure.

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 4 A single average drybulb temperature, T, is calculated as the sum of the products of 18 measured temperatures and their associated weighting factors (discussed below). Each of the 5 individual measured dewpoint temperatures is converted to vapor pressure using the saturation line algorithm from the ASME Steam Tables. A single average vapor pressure is determined by the procedure applied to obtain average temperature. Dry air partial pressure, P, is the measured total pressure less the average vapor pressure.

The quantity of dry air in the containment is, from the ideal gas law:

M = PV/RT M is air quantity in pounds mass. V is containment free air volume, 1825000 cubic feet from Reference 6.6. R is the gas constant for air and is, in English units,53.35 pounds force-feet / pound mass-degree Rankine. P and T are defined above. The partial pressure of dry air is used in the computation so that pressure changes resulting from evaporation of liquid water and condensation of vapor do not affect calculated leakage rate.

There are two accepted methods to calculate leakage rate. If test duration is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the total time method derived in Reference 6.5 must be used. If test duration is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 'or more, Reference 6.1 allows the use of either the total time method or the mass point method described in Reference 6.4. The test reported herein had a duration of over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and the mass point method was used to calculate leakage rate since this method is more easily applied and yields more consistent results than the total time method. The basic characteristics of the mass point method are discussed below.

Ifleakage rate is constant, it is best defined as the slope of a straight line fitted by the method ofleast squares to a series of air mass / time data sets. Leakage rate expressed in fractional, or percentage, terms is the slope of this line divided by the initial air mass. Since there is always some scatter of individual data points about a fitted line, there is always some uncertainty as to the true slope of the line.

As a result, the calculated leakage rate is only a best estimate of the true value. A statistical upper bound on true leakage rate is defined, subject to certain restrictions on the nature of the data scatter, by an upper confidence limit (UCL). The UCL exceeds the calculated leakage rate by ar. amount which increases as data scatter increases. Reference 6.4 requires reporting leakage rate at the 95% UCL value. Statistically, this means that there is a 95% probability that true leakage rate is less than the reported 95% UCL number. The derivation of the least squares fit and confidence limit expressions can be found in statistics texts such as Reference 6.7. These calculations, which are standardized in research and engineering applications, are referred to as the mass point method in Reference 6.4.

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The UCL rate calculated during this Type A test (as opposed to the verification test l described below) phase of the ILRT is subject to additions to account for containment water l inventory increase and minimum pathway leakage through penetrations not aligned in post-accident configuration. The sum of the 95% UCL rate and applicable additions must not l exceed 0.75 La. La is the maximum allowable leakage rate as defined in Reference 6.2. .

Following the conclusion of the Type A test, the leakage rate calculation is verified by i inducing an additional leak on the containment 7d computing a new rate. The induced leak is between 0.75 La and 1.25 L;. The leakage rate calculated during this verification test phase must equal the rate (not UCL) calculated for the Type A test plus the induced rate, plus or minus a tolerance of La/4 as specified in Reference 6.1. ,

Leakage rate calculations were performed using the compiled BASIC program described in Appendix II. The program was validated prior to the ILRT as documented in the official test copy of Reference 6.6.

3.2 Test Measurements Leakage rate calculations are based on data taken from 18 drybulb temperature sensors and 5 dewpoint temperature sensors permanently installed in the containment at the positions listed in Table 1, and an absolute pressure transducer connected to the containment atmosphere through a piping penetration. The weighting factors associated with the drybulb and dewpoint temperature sensors are also listed in the table. Each weighting factor is determined as the fraction of total contaimnent volume represented by the volume zone assigned to a sensor. Each sensor is located so that it senses a temperature (drybulb or dewpoint) which is representative of temperatures throughout its zone.

Drybulb temperature sensors are 100 Ohm platinum resistance temperature detectors .

(RTD's). The dewpoint temperature sensors are lithium chloride cells. The lithium chloride cell consists of a nonconductive cylinder with a spiral wrap of two non-contacting gold wires, a coating oflithium chloride salt and an internal RTD. The gold wires are connected to a 24 VAC power supply. Lithium chloride is hygroscopic and absorbs moisture from its surroundings. The quantity of moisture absorbed is determined by the partial pressure of the surrounding water vapor and the temperature of the salt. As the salt coating on the cylinder absorbs moisture it becomes more conductive and allows a flow of current between the ,

parallel gold wires. This current heats the salt, causing evaporation of the absorbed water.

At some temperature, the rate of evaporation equals the rate of absorption. When this point is reached, moisture content, current and temperature are in a stable equilibrium. The temperature measured by the RTD at this equilibrium condition is a unique ftmetion of vapor pressure. The relationship between cell temperature and dew point temperature (which is, in turn, uniquely determined by vapor pre::sure) is provided by the cell manufacturer.

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i Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 6 The RTD's and dew cells are permanently wired to terminals located in the Unit I computer room.

Absolute pressure was measured by a vibrating cylinder manometer. This device uses an electronic circuit to detect a modal frequency of a low hysteresis alloy cylinder subjected to a vacuum on one side and test pressure on the opposite side. The detected frequency varies approximately linearly with pressure. An internal microprocessor is programmed during initial calibration to convert frequency to true absolute pressure in engineering units. The manometer has a resolution of 0.0001 psi and a stability on the order of 0.001 psi. ,

A computer based digital data acquisition system was used to acquire and store test data and to transmit data to the computers used to calculate leakage rate. The RTD's, dew cells and manometers (one primary and one backup) were wired to this system which was set up in the Unit I computer room. Signals from the RTD's and 4 dew cells (one was wired to a permanent plant device) were conditioned by analog modules incorporated into the system and then multiplexed and digitized for serial input to the computer. The analog modules were adjusted to generate output voltages proportional to temperature in degrees Fahrenheit. Dew cell input to the computer was cell temperature. The computer program used the relationship i provided by the manufacturer to convert measured cell temperature to dewpoint temperature.

The manometers were connected directly to the computer by serial links.

A complete data set was acquired by the computer every minute and written to disk.

Data sets acquired at quarter hour intervals were transmitted to the ILRT computers (IBM l compatible laptops located in the Technical Support Center) over a serial link.

A mass flow meter was used to measure the verification test induced leak. Other instrumentation used during the test included a barometer (used with the manometer described above to track containment gage pressure) and permanent plant level instruments to establish containment water inventory.

4. Test Conduct 4.1 Plant Status Plant systems were aligned for the ILRT as specified in Reference 6.6 and its

! subordinate procedures. These alignments reflect both UFSAR (Reference 6.8) and l operational requirements. Isolation valves were set in post-accident positions except where the opposite positions were required to maintain the reactor in a safe shutdown condition.

Piping, with certain exceptions, was vented and drained to expose valve seats to containment and outside atmospheres per UFSAR requirements. All compressed gas sources were either vented or removed from the containment. Containment sumps were flooded to simulate post-accident conditions. All containment fans and lighting were shut off.

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North Anna Power Station Unit I Reactor Contaimnent Building Integrated Leakage Rate Test Report Page 7 The official test copy of Reference 6.6 documents plant status including all exceptions to specified conditions.

4.2 Prerequisite Activities All Type B & C local leakage rate testing was completed prior to the start of the ILRT. System lineups, alignment or removal of in-containment components not designed for test pressure, test instrumentation calibration and containment cleanup were performed during -

a several day period prior to the start of pressurization.

The response of each RTD and dew cell was checked by measuring conditions ,

adjacent to the sensor with a psychrometer. Agreement to within 1 deg F was verified for each RTD. The dewpoint indicated by each lithium chloride cell was verified to be within 5 deg F of that derived from the psychrometer wet bulb and drybulb readings. A containment temperature survey was conducted to verify that the permanently located test instruments were indicating values representative of the temperatures in their respective zones.

The containment examination specified in Reference 6.1 was performed. No adverse indications were found.

All prerequisite activities are documented in the official test copy of Reference 6.6.

4.3 Pressurization '

l i The containment was pressurized through the containment purge supply piping penetration using diesel driven, oil free compressors having an aggregate capacity of about l 10000 SCFM. The compressors discharged through an aftercooler and refrigerated air dryer j which were cooled by plant chilled water supplied through temporary connections.

Pressurization commenced at 10:58 AM on March 29 and the containment was isolated at 10:45 PM on the same day when pressure had reached 44.77 psig. The pressurization rate was essentially constant at just under 4 psi per hour except during the final 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of the period. To maintain control of pressure as the maximum value was approached, the rate was reduced by isolating compressors. Figure 1 is a graph of containment pressure vs. time. ,

1 During pressurization, containment penetrations were examined for evidence of leakage. Nothing significant was found. When pressurization was complete, compressor discharge piping was vented to expose the outboard isolation valve to atmospheric pressure. I i

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Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 8 j J

4.4 Stabilization The stabilization period specified in Reference 6.6 commenced following containment isolation at 10:45 PM on March 29. The specified numerical criteria on rates of temperature change were satisfied in four hours (at 2:45 AM on March 30) which is the minimum required stabilization time. This is documented in the stabilization report presented in Table

2. However, since the slope of the air mass vs. time plot was quite steep at the end of the four hour minimum period, stabilization was extended to determine whether or not this mass trend would continue. The trend remained essentially unchanged over the following one and one half hours. Stabilization was terminated and the Type A test started at 4:15 AM on March 30. Total stabilization time was 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and 30 minutes.

Figures 2 and 3 are plots of mean temperature vs. time and mass vs. time, respectively, during the stabilization period. Temperature varies smoothly and almost exponentially, which is typical. Air mass appears to follow a reasonably linear trend starting about two hours into the stabilization period. However, since data scatter tends to mask small changes in the average trend, it is not possible to state with certainty that the trend is actually stable. The large negative spike appearing on the air mass plot at 11:45 PM results from a spurious dewpoint temperature indication and the corresponding error in calculated mean vapor pressure. Vapor pressure (calculated) during the stabilization period is plotted on Figure 4.

Containment drybulb temperatures, dewpoint temperatures and absolute pressure were ,

recorded at 15-minute intervals during stabilization and through the completion of the verification test. The water levels in containment vessels, tanks and sumps were recorded hourly over the same period. Water level data were used to establish containment water inventory. Any significant increase in water inventory requires a correction to calculated leakage rate (See Section 5).

4.5 Type A Test The Type A test commenced at 4:15 AM on March 30 and was successfully terminated at 2:00 PM on the following day. Total duration was 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> and 45 minutes.

This extended duration was necessitated by the combination of a high initial leakage rate and a rapid drop in rate with time.  :

As a result of the high initial rate, it was not possible to meet the acceptance criteria for a BN-TOP-1 (Reference 6.5) short duration test until over 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> had elapsed. It is not practical to conduct a BN-TOP-1 test if duration exceeds 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br />. Therefore, the type A test was continued. At the end of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the terminal leakage rate (as determined for the final 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of data) was considerably less than the rate calculated for the full test duration. As a  ;

result, it was concluded that a verification test would probably fail. The Type A_ test was l

Virginia Electric and Power Company North Anna Power Station Unit I . Reactor Containment Building Integrated Leakage Rate Test Report Page 9 continued until the difference between the full duration leakage rate and the terminal leakage rate had reached an acceptably small value. The significance of the difference in leakage ,

rates is discussed in the following paragraphs.  ;

Figure 5 is a graph of air mass vs. time over the Type A test period. The slope of the graph changes considerably over the early part of the test. This results from a combination of effects, one of which is migration of air into the spaces between isolation valves, concrete pores and other volumes with minute openings. The rate of migration goes down as pressures equalize and the slope asymptotically approaches its final value, which is the true leakage rate. Calculated leakage rate is determined using all data collected since the declared start of the Type A test. This results in a rate which is somewhere between the initial and final slopes of the air mass plot. For the air mass trend illustrated in Figure 5, the calculated rate will drop as test duration increases.

The calculated leakage rate at the end of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is 0.038 %/ day as listed in the mass point leakage rate report reproduced in Table 3. The rate calculated for the final 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of this period is 0.012 %/ day. (This latter calculation was one of many diagnostic calculations performed during the course of the ILRT. These are not documented in this report but can be recreated using the summary data presented in Table 7.) The acceptance band for the l verification test is (per Reference 6.1) +/- 0.25 La = 0.025 %/ day. Had the verification test l been started at the end of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the lower limit on the calculated composite leakage rate l would have been:

Lower limit = Lo (induced leakage rate) + 0.038 - 0.025 = Lo + 0.013 %/ day Since the slope of the air mass plot is still dropping at the end of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the expected calculated composite leakage is less than Lo + 0.012. Since the expected value is below the lower acceptance limit, it is unlikely that a verification test commenced at this time would have been successful.

l The Type A test was continued until 2:00 PM on March 31, at which time the calculated full duration leakage rate was 0.029 %/ day and the rate calculated for the final four l

hours of the period was also 0.029 %/ day. The resulting lower limit, upper limit and expected verification test leakage rates are:

Lower limit: Lo + 0.029 - 0.025 =

Lo + 0.004 Expected: Lo + 0.029 Upper Limit: Lo + 0.029 + 0.025 = Lo + 0.054 -

The expected verification test leakage rate is midway between limits. Since this equated to a high probability that the verification test would be successful, the Type A test was concluded at 2:00 PM.

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Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 10 4.6 Verification Test The leakage rate (Lam) calculated for the Type A test is verified by venting air from the containment at a measured rate, Lo, approximately equal to La. The calculated composite leakage rate must equal the sum of Lo and Lam plus or minus a tolerance of 0.25 La. The induced leak, Lo, was measured by venting air through a mass flowmeter located in a piping penetration room. An induced leak of 5 SCFM, equivalent to a leakage rate of 0.099 %/ day (0.99 La) was initiated at 2:15 PM on March 31 and the verification test was commenced at 2:30 PM. The test was successfully completed without incident at the end of four hours, which is the specified minimum duration.

4.7 Depressurization and Restoration Containment depressurization commenced at 6:39 PM on March 31 and was complete at 10:04 AM on the following day. The systems and components modified for the' conduct of the ILRT were restored to normal operational configurations following the completion of r depressurization.

5. Results >

5.1 Type A Test The acceptance criterion specified in Reference 6.6 was met early in the 33 hour3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> and 45 minute test period. The test was continued beyond 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for the reason discussed in Subsection 4.5. The end of test calculated leakage rate and UCL, and the acceptance limit on the latter, are listed below.

i Calculated mass point leakage rate 0.029 %/ day Acceptance limit N/A 95 % UCL on mass point leakage rate 0.031 %/ day Acceptance limit 0.075 %/ day The acceptance limit is based on the maximum allowable leakage rate, La, of 0.1

%/ day set forth in Reference 6.2. For return to power, Reference 6.1 stipulates that the leakage rate must not exceed 0.75 La. The margin of 0.25 La is an allowance for deterioration of the leakage boundary during the subsequent operating cycle. The 0.75 La criterion is applied by Reference 6.4 to the UCL on leakage rate. UCL additions required for penetrations which are not in the post-accident lineup and for containment water inventory increase are covered in an ensuing paragraph.

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Mass point leakage rates computed for successive hours of test duration are listed in Table 3 and the variation is illustrated graphically in Figure 6. The UCL converges to the calculated rate as test duration increases. This is as expected for well ordered data. It should be noted that figure 6, as well as other plots in this report, is a representation of discrete,15 l minute interval data sets. The straight lines connecting the discrete points are generated by l the plotting software and do not represent actual variations in the plotted parameters. l The final as-left leakage rate is the sum of the above UCL, the additions for minimum l pathway leakage through penetrations not in post-accident alignment and the correction for containment water inventory increase. There was no measurable change in containment water  ;

inventory during the test and, therefore, no correction. The additions for penetrations not in l post-accident alignment are tabulated below. ,

Penetration Service Minimum Pathway Leakage 9 CCW to containment air recire fan C 0.8 SCFil 10 CCW to containment air recire fan B 1.0 12 CCW from containment air recirc fan B 0.33 24 RHR line to RWST 0.5 25 CCW from RCP A 0.35 l 26 CCW from RCP C 0.45 39 Steam generator A blowdown 0.15 l

40 Steam generator C blowdown 0.20 103 Refueling purification inlet 0.38 i

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Total 4.16 SCFil At the end of the Type A test, pressure was 58.8 psia and temperature was 72.5 deg F l or 532.2 deg R (as listed in Table 7). At these conditions, the leakage rute equivalent to 4.16 l SCFil is (for a containment free air volume of 1825000 cubic feet):

l l Lequiv = 4.16 x 2400 x {l4.7 (Pstd) x 532.2} / {l825000 x 58.8 x 529.7 (Tstd)}

j = 0.001 %/ day The fmal as-left leakage rate is the sum of the mass point UCL,0.031 %/ day, and the above addition of 0.001 %/ day.

Final as-left leakage rate 0.032 %/ day I

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Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 12 Containment conditions during the Type A test were reasonably typical, except that dewpoint temperatures (and the corresponding vapor pressure) oscillated somewhat erratically about a reasonably constant mean value. Containment air mass, mean temperature, total pressure and mean vapor pressure are plotted on Figures 5,7, 8 and 9, respectively.

The slope of the air mass plot decreased in an approximately exponential manner with time. This is expected since, as discussed in Subsection 4.5, the rate of air migration into .  :

volumes with minute openings decreases as pressures in these volumes equalize with containment pressure. The difference between the initial and final slopes of the air mass  ;

i graph depends on test duration and varies from containment to containment and from test to test. A portion of the difference may be due to a varying deviation between calculated and true mean temperatures.  ;

Mean temperature (Figure 7) decreased in an essentially exponential manner during the first half of the test period and was almost constant over the second half. This can be >

( explained by offsetting heat transfers. Adiabatic heating during pressurization increases temperature by several degrees. When pressurization is complete, this heat is lost to the mass

- of concrete in and around the containment free air volume, and temperature falls accordingly.

As the temperature of the air approaches that of the concrete, the rate of heat transfer and temperature loss decreases. At the same time, the reactor coolant system (RCS) is giving up

heat to the containment atmosphere at an relatively constant low rate. When the rate of heat i transfer from air to concrete is equal to the rate of heat input from the RCS, the temperature I graph will be effectively flat.

Pressure (Figure 9) tracks temperature as expected. The small net downward slope of the pressure graph during the second half of the test represents continuing migration of air into concrete and other internal volumes, as well as containment outleakage. Based on this graph, it may be concluded that actual containment outleakage is very small and probably well under the reported value of 0.029 %/ day. -

l Figure 9 is a plot of mean vapor pressure vs. time. There is no real trend to the graph, which is consistent with expectations. Since the air in the containment is quite still and at a temperature reasonably close to that ofits surroundings, there should be no significant evaporation from the surface of the sump. With no evaporation (condensation is not expected since drybulb temperatures are uniformly above dew point temperatures) vapor pressure should vary at the same rate as total pressure. Total pressure fell by about 0.17 %

during the Type A test. This is too small a change to be noticeable on the vapor pressure graph. The vapor pressure fluctuations plotted in Figure 9 are too large to be real. These l result from a significant scatter in the underlying dew point temperature measurements.

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Integrated Leakage Rate Test Report Page 13

5.2 As-Found Leakage Rate j The leakage rate (UCL) which would have been calculated had the test been conducted at the start of the outage and prior to making minimum pathway leakage improvements, can be estimated as the sum of the as-left rate (UCL) and the total improvement. Minimum pathway improvements made during the local leakage rate (Type B and C) testing program j are listed below.

Penetration Service Minimum Pathway Improvement -

N/A Air lock 1.2 SCFH 25 CCW return from RCP A 0.35 43 Containment air sample monitor 0.10 44 Containment air sample monitor 0.05 53 Nitrogen supply to PRT 0.10 71 Recirc spray pump A discharge 0.80 104 Refueling puri6 cation 0.13 111D Post-accident sampling 0.70 N/A Type B test improvements 1.51 Total 4.94 SCFH At the end of the Type A test, pressure was 58.8 psia and temperaturc was 72.5 deg F or 532.2 deg R (as listed in Table 7). At these conditions, the leakage rate equivalent to 4.94 SCFH is (for a containment free air volume of 1825000 cubic feet):

Lequiv = 4.94 x 2400 x (14.7 (Pstd) x 532.2} / {1825000 x 58.8 x 529.7 (Tstd)}

= 0.002 %/ day The Unal as-found leakage rate is the sum of the as-left leakage rate,0.032

%/ day, and the above minimum pathway addition of 0.002 %/ day.

Final as-found leakage rate 0.034 %/ day 5.3 Verincation Test The verification test induced leak was imposed after the completion of the Type A test and adjusted to a flowmeter indication of 5.00 SCFM. At the temperature and pressure conditions listed in Subsection 5.1 for the end of the Type A test, this is equivalent to a leakage rate of 0.099 %/ day. The Type A test calculated leakage rate is 0.029 %/ day and the corresponding limits on the calculated composite leakage are 0.099 + 0.029 + 0.025 = 0.153

l.

i Virginia Electric and Power Company

( North Anna Power Station l Unit I Reactor Containment Building i

! Integrated Leakage Rate Test Report Page 14 i

l 1

%/ day and 0.099 + 0.029 - 0.025 = 0.103. Test duration'was four hours, which is the minimum specified in Reference 6.6. Results are detailed in Table 4 and summarized below.

Upper limit on mass point composite leakage rate 0.153 %/ day Mass point composite leakage rate 0.115 %/ day Lower limit on mass point composite leakage rate 0.103 %/ day ,

The calculated composite leakage rate is in the acceptance band. Figure 10 illustrates verification test results graphically.

5.4 Total Time Results The total time method defined in Reference 6.5 was used, in addition to the mass point method, to celculate leakage rate during the Type A test. Since test duration was over 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the total time results have no bearing on acceptance. These are, however, listed for information in Table 5 and 6. The variation in total time leakage rate with increasing test duration is shown graphically in Figure 11.

The marked drop in total time UCL at a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> duration is the result of a change in ,

the calculation procedure. The UCL calculation defined in Reference 6.5 contains a very conservative error. Since this document was accepted for use (by the then AEC) as submitted, the conservative calculation must be performed if test duration is less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If test duration is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more, the true 95 % upper confidence limit on calculated rate is determined. This is considerably less than the confidence limit calculated using the expression presented in Reference 6.5.

5.5 Summary Data and Individual Measurements l Table 7 lists mean temperature, total pressure, mean vapor pressure and air mass for each 15 minute interval data set recorded during the stabilization, Type A and verification

phases of the ILRT. These parameters are plotted in Figures 12-15. Individual drybulb and j dewpoint temperatures are plotted in Figures 16-38. The drybulb temperatures, with the l exception of T-11, varied smoothly as expected. Temperature sensor T-11 exhibited a period j ofinstability between about 3 and 9 PM on March 31. The indicated temperature fluctuations during this time period were small and do not impact measurably on test results.

l The dew point temperatures indicated by sensors M-1 and M-2 fluctuated erratically over a range of several degrees F, possibly as a result of electromagnetic '

l interference. Dew point sensors M-3, M-4 and M-5 exhibited considerably less scatter and I

showed dew point temperature trends to be essentially flat, as expected. The scatter exhibited l by M-1 and M-2 is reflected on the vapor pressure and air mass plots and has a measurable effect on calculated UCL.

L

Virginia Electric and Power Company North Anna Power Station Unit i Reactor Containment Building l Integrated Leakage Rate Test Report Page 15 i

l 6. References

! 6.1 Code of Federal Regulations, Title 10, Part 50, Appendix J, Reactor Containment Leakage Testing For Water Cooled Power Reactors.

6.2 North Anna Power Station, Unit 1 Technical Specification, Paragraph 3/4.6.1,

Containment Integrity.

6.3 ANSI N45.4-1972 Leakage Testing of Containment Structures For Nuclear j Reactors.

l 6.4 ANSl/ANS 56.8-1987, Containment System Leakage Testing Requirements.

6.5 Bechtel Topical Report BN-TOP-1, Testing Criteria For Integrated Leakage Rate Testing Of Primary Containment Structures For Nuclear Power Plants, Revision 1,1972.

s 6.6 NorQ Anna Power Station, Unit 1 Surveillance Test Procedure 1-PT-61.1, j Reactor Containment Integrated Leak Rate Test, Revision 10.

6.7 Miller, Irwin and John E. Freund, Probability and Statistics for Engineers. '

Englewood Cliffs, N. J.: Prentice-Ilall,1965.

6.8 North Anna Power Station, Updated Final Safety Analysis Report, Paragraph 6.2.1.4, (Containment) Testing and Inspection.

j 7. Tables and Figures Tables and figures referenced in the text follow.

Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 16 TABLE 1 DRYBULB AND DEWPOINT TEMPERATURE SENSOR LOCATIONS AND WEIGIITING Sensor Station ID Elevation Radius Bearing Weighting Drybulb T-01 1-LM-TE-100-3 268 ft. 48 ft. 315 deg. 0.06785 T-02 1-LM-TE-100-4 268 48 347 0.07513 T-03 1-LM-TE-100-5 329 49 053 0.04846 T-04 1-LM-TE-100-6 329 48 135 0.04846 T-05 1 -LM-TE-100-7 329 48 135 0.04846 T-06 1-LM-TE-100-8 329 47 311 0.04846 l T-07 1-LM-TE-100-9 390 33 324 0.09604 T-08 1-LM-TE-100-10 390 33 205 0.09604 T-09 1-LM-TE-100-11 390 33 083 0.09604 T-10 1-LM-TE-100-12 329 59 187 0.02256 T-ll 1-LM-TE-100-13 329 60 270 0.02256 T-12 1-LM-TE-100-14 329 59 090 0.02256 T-13 1-LM-TE-100-15 329 61 027 0.02256 T-14 1-LM-TE-100-16 238 56 300 0.04972 T-15 1-LM-TE-100-17 238 52 180 0.04972 T-16 1-LM-TE-100-18 237 53 058 0.04972 T-17 1-LM-TE-100-19 270 45 191 0.06785 T-18 1-LM-TE-100-20 268 48 072 0.06785 Dewpoint M-1 1-LM-MT-100-1 395 35 014 0.12569 M-2 1-LM-MT-100-2 395 35 211 0.12569 M-3 1-LM-MT-100-4 221 51 168 0.24954 M-4 1-LM-MT-100-5 221 51 291 0.24954 M-5 1-LM-MT-100-6 222 51 073 0.24954 l Sensor locations as noted and scaled on Dwgs. I1715-FE-57A-22, B-13, C-25, D-13, G-15 l AND 11-14.

i Reference dimensions and elevations: Inside radius to concrete -- 63 ft.

l Top of inside mat elevation -- 217 ft.

Refueling floor elevation -- 292 ft.

Dome spring line elevation -- 342 ft.

l i

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 17 TABLE 2 TEMPERATURE STABILIZATION REPORT Start Time at 10:45 PM, March 29

• indicates stabilization criterion satisfied

- ANSI - --- BN-TOP- 1 ---

data elapsed temperature dTl dT4 dT1-dT4 dT or d(dT) set time, hr T, deg F avg dT avg dT avg avg (1 hr) (4 hr) (2 hr) (2 hr) 1 0.00 75.713 2 0.25 75.256 3 0.50 74.893 4 0.75 74.616 5 1.00 74.422 -1.291 6 1.25 74.265 -0.991 7 1.50 74.135 -0.758 8 1.75 74.017 -0.599 9 2.00 73.923 -0.499 -0.895* 0.727 l 10 2.25 73.847 -0.418 -0.705* 0.573 11 2.50 73.776 -0.359 -0.559* 0.413*

12 2.75 73.709 -0.308 -0.453' O.252*

13 3.00 73.656 -0.267 -0.383* 0.211*

14 3.25 73.604 -0.242 -0.330* 0.155*

15 3.50 73.552 -0.224 -0.292* 0.132*

16 3.75 73.507 -0.201 -0.255* 0.098*

17 4.00 73.470 -0.187 -0.561 0.374* -0.227* 0.077*

18 4.25 73.426 -0.179 -0.458 0.279* -0.211* 0.053*

19 4.50 73.384 -0.168 -0.377 0.209* -0.196* 0.051*

20 4.75 73.351 -0.156 -0.316 0.160* -0.179* 0.040' l 21 5.00 73.316 -0.154 -0.277 0.123* -0.170* 0.033*

22 5.25 73.292 -0.134 -0.243 0.109* -0.156* 0.056*

23 5.50 73.264 -0.120 -0.218 0.098* -0.144* 0.034*

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1 Virginia Electric and Power Company l North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 18 l

TABLE 3 1 TYPE A TEST -- MASS POINT LEAKAGE RATE REPORT l date time date elapsed dry air leakage uci set time mass rate rate- rate ,

(hrs) (Ibm) (%/ day) (%/ day) 4 0500 330 0.75 542369.94 0.0401 0.0998 8 0600 330 1.75 542345.36 0.0705 0.1161 12 0700 330 2.75 542326.00 0.0778 0.0985 16 0800 330 3.75 542310.84 0.0790 0.0907 20 0900 330 4.75 542299.00 0.0788 0.0870 24 0000 330 5.75 542288.31 0.0796 0.0866 28 1100 330 6.75 542275.62 0.0709 0.0775 32 1200 330 7.75 542259.06 0.0696 0.0748 36 1300 330 8.75 542257.01 0.0687 0.0733 40 1400 330 9.75 542243.41 0.0664 0.0704 44 1500 330 10.75 542234.10 0.0637 0.0673 48 1600 330 11.75 542223.89 0.0609 0.0643 52 1700 330 12.75 542219.95 0.0604 0.0636 56 1800 330 13.75 542183.17 0.0587 0.0617 I- 60 1900 330 14.75 542182.34 0.0564 0.0592 64 2000 330 15.75 542167.15 0.0545 0.0572 68 2100 330 16.75 542198.58 0.0510 0.0539 72 2200 330 17.75 542192.81 0.0481 0.0510 76 2300 330 18.75 542176.93 0.0459 0.0487 i 80 0000 331 19.75 542189.79 0.0435 0.0463 )

84 0100 331 20.75 542149.25 0.0425 0.0451 88 0200 331 21.75 542153.34 0.0411 0.0436 92 0300 331 22.75 542163.27 0.0398 0.0421 96 0400 331 23.75 542154.06 0.0385 0.0408 100 0500 331 24.75 542158.80 0.0374 0.0395 104 0600 331 25.75 542145.23 0.0360 0.0381 108 0700 331 26.75 542182.15 0.0346 0.0367 112 0800 331 27.75 542142.14 0.0336 0.0355 l 116 0900 331 28.75 542155.73 0.0323 0.0343 120 1000 331 29.75 542140.60 0.0314 0.0332 l

124 1100 331 30.75 542142.57 0.0308 0.0325 128 1200 331 31.75 542147.42 0.0299 0.0316  !

l32 1300 331 32.75 542113.70 0.0295 0.0311 l 136 1400 331 33.75 542125.91 0.0291 0.0306 j l Allowable leakage rate, La = 0.1000 %/ day l 75% La =

0.0750 %/ day Mass point leakage rate =

0.0291 %/ day i

, Mass point UCL =

0.0306 %/ day i .

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment 13uilding Integrated Leakage Rate Test Report Page 19 TAllLE 4 VERIFICATION TEST -- MASS POINT LEAKAGE RATE REPORT data time date elapsed dry air leakage set time mass rate (hrs) (Ibm) (%/ day) 1 1430 331 0.00 542107.94 N/A 2 1445 331 0.25 542101.89 0.1071 3 1500 331 0.50 542093.71 0.1260 4 1515 331 0.75 542089.04 0.1149 5 1530 331 1.00 542080.32 0.1206 6 1545 331 1.25 542079.32 0.1075 7 1600 331 1.50 542035.82 0.1739 8 1615 331 1.75 542062.64 0.1474 9 1630 331 2.00 542026.74 0.1677 10 1645 331 2.25 542057.43 0.1392 11 1700 331 2.50 542034.00 0.1362 12 1715 331 2.75 542036.62 0.1274 13 1730 331 3.00 542026.36 0.1239 14 1745 331 3.25 542032.87 0.1149 -

15 1800 331 3.50 542030.17 0.1073 16 1815 331 3.75 542001.09 0.1113 17 1830 331 4.00 541993.11 0.1146 Upper limit on leakage rate =

0.1535 %/ day Mass point leakage rate = 0.1146 %/ day Lower limit on leakage rate = 0.1035 %/ day i

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I Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building l Page 20 1 Integrated Leakage Rate Test Report TABLE 5  ;

TYPE A TEST -- TOTAL TIME LEAKAGE RATE REPORT data time date elapsed dry air measured leakage ucl set time mass rate rate rate (hrs) (Ibm) (%/ day) (%/ day)  %/ day 4 0500 330 0.75 542369.94 0.0356 0.0431 0.2230 8 0600 330 1.75 542345.36 0.0774 0.0576 0.1840 12 0700 330 2.75 542326.00 0.0804 0.0716 0.1530 16 0800 330 3.75 542310.84 0.0769 0.0772 0.1406 20 0900 330 4.75 542299.00 0.0717 0.0799 0.1342 24 1000 330 5.75 542288.31 0.0675 0.0819 0.1306 28 1100 330 6.75 542275.62 0.0658 0.0761 0.1223 32 1200 330 7.75 542259.06 0.0668 0.0745 0.1175 36 1300 330 8.75 542257.01 0.0602 0.0735 0.1138 40 1400 330 9.75 542243.41 0.0602 0.0714 0.1097 44 1500 330 10.75 542234.10 0.0584 0.0689 0.1055 48 1600 330 11.75 542223.89 0.0573 0.0662 0.1014 52 1700 330 12.75 542219.95 0.0541 0.0650 0.0990 56 1800 330 13.75 542183.17 0.0620 0.0631 0.0959 60 1900 330 14.75 542182.34 0.0581 0.0609 0.0926 64 2000 330 15.75 542167.15 0.0587 0.0589 0.0896 68 2100 330 16.75 542198.58 0.0469 0.0557 0.0859 72 2200 330 17.75 542192.81 0.0457 0.0530 0.0825 76 2300 330 18.75 542176.93 0.0470 0.0506 0.0794 80 0000 331 19.75 542189.79 0.0417 0.0481 0.0763 84 0100 331 20.75 542149.25 0.0483 0.0466 0.0741 88 0200 331 21.75 542153.34 0.0453 0.0449 0.0717 92 0300 331 22.75 542163.27 0.0414 0.0433 0.0695 96 0400 331 23.75 542154.06 0.0413 0.0418 0.0673 100 0500 331 24.75 542158.80 0.0388 0.0403 0.0444

( 104 0600 331 25.75 542145.23 0.0397 0.0387 0.0427 108 0700 331 26.75 542182.15 0.0321 0.0372 0.0410 112 0800 331 27.75 542142.14 0.0373 0.0359 0.0395 ;

l 116 0900 331 28.75 542155.73 0.0339 0.0345 0.0380 120 1000 331 29.75 542140.60 0.0350 0.0333 0.0367 124 1100 331 30.75 542142.57 0.0336 0.0323 0.0356 128 1200 331 31.75 542147.42 0.0319 0.0312 0.0344 132 1300 331 32.75 542113.70 0.0354 0.0304 0.0336 136 1400 331 33.75 542125.91 0.0328 0.0297 0.0327 l

Allowable leakage rate, La = 0.1000 %/ day l 75% La = 0.0750 %/ day i Total time leakage rate = 0.0297 %/ day I Total time UCL = 0.0327 %/ day i

Virginia Electric and Power Company l North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 21 TAllLE 6 VERIFICATION TEST -- TOTAL TIME LEAKAGE RATE REPORT i

i data time date elapsed dry air measured leakage l set time mass rate rate l l

(hrs) (Ibm) (%/ day) (%/ day) '

l 1 1430 331 0.00 542107.94 N/A N/A 2 1445 331 0.25 542101.89 0.1071 N/A 3 1500 331 0.50 542093.71 0.1260 0.1260 l 4 1515 331 0.75 542089.04 0.1115 0.1171 l

5 1530 331 1.00 542080.32 0.1223 0.1214 l 6 1545 331 1.25 542079.32 0.1014 0.1106 i 7 1600 331 1.50 542035.82 0.2128 0.1635 8 1615 331 1.75 542062.64 0.1146 0.1479 l 9 1630 331 2.00 542026.74 0.1798 0.1650 10 1645 331 2.25 542057.43 0.0994 0.1457 11 1700 331 2.50 542034.00 0.1309 0.1431 12 1715 331 2.75 542036.62 0.1148 0.1360 13 1730 331 3.00 542026.36 0.1204 0.1323 14 1745 331 3.25 542032.87- 0.1023 0.1246 15 1800 331 3.50 542030.17 0.0984 0.1176 16 1815 331 3.75 542001.09 0.1262 0.1189 17 1830 331 4.00 541993.11 0.1271 0.1201 Upper limit on leakage rate = 0.1541 %/ day Total time leakage rate =

0.1201 %/ day Lower limit on leakage rate =

0.1041 %/ day l

l l

1 1

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 22 TABLE 7 (Sh.1/5)

DATA

SUMMARY

REPORT time date temperature pressure vapor dry air deg F psia pressure mass psia lbm Stabilization 2245 329 75.713: 59.2110 0.2693 542311.65 2300 329 75.2561 59.1555 0.2668 542286.93 2315 329 74.8931 59.1223 0.2665 542351.86 2330 329 74.6158 59.0979 0.2670 542403.80 2345 329 74.4224 59.0787 0.2781 542320.88 l 0000 330 74.2646 59.0628 0.2652 542453.93 l 0015 330 74.1350 59.0492 0.2670 542443.33 l 0030 330 74.0168 59.0376 0.2669 542457.38 l

0045 330 73.9231 59.0273 0.2673 542453.18

0100 330 73.8468 59.0182 0.2660 542458.96 l 0115 330 73.7761 59.0098 0.2670 542444.43 0130 330 73.7088 59.0022 0.2666 542445.83 0145 330 73.6564 58.9951 0.2659 542440.39

! 0200 330 73.6044 58.9886 0.2663 542429.44 l 0215 330 73.5520 58.9824 0.2672 542417.37 0230 330 73.5074 58.9767 0.2672 542409.61 0245 330 73.4696 58.9714 0.2653 542416.78 0300 330 73.4255 58.9663 0.2664 542404.06 0315 330 73.3837 58.9616 0.2660 542407.46

0330 330 73.3513 58.9570 0.2642 542414.04 0345 330 73.3158 58.9527 0.2665 542389.80 0400 330 73.2915 58.9487 0.2657 542385.04

! 0415 330 73.2638 58.9447 0.2657 542375.970 Type A Test 0415 330 73.2638 58.9447 0.2657 542375.97 0430 330 73.2267 58.9410 0.2665 542372.05 0445 330 73.2065 58.9375 0.2657 542367.48 0500 330 73.1732 58.9340 0.2656 542369.94 0515 330 73.1502 58.9308 0.2637 542381.96 0530 330 73.1273 58.9277 0.2657 542357.73 0545 330 73.1088 58.9247 0.2654 542351.46 l

0600 330 73.0885 58.9218 0.2654 542345.36 0615 330 73.0602 58.9190 0.2646 542355.29 0630 330 73.0413 58.9163 0.2658 542338.47 0645 330 73.0243 58.9136 0.2652 542337.02

Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 23 i

TABLE 7 (Sh. 2/5)

DATA

SUMMARY

REPORT time date temperature pressure vapor dry air deg F psia pressure mass Type A Test (cont.)

0700 330 73.0010 58.9111 0.2664 542326.00 0715 330 72.9830 58.9088 0.2651 542335.22 0730 330 72.9773 58.9065 0.2650 542320.60 0745 330 72.9506 58.9039 0.2657 542317.73 0800 330 72.9392 58.9016 0.2654 542310.84 0815 330 72.9215 58.8994 0.2665 542297.90 0830 330 72.9026 58.8972 0.2649 542312.15 0845 330 72.8915 58.8950 0.2650 542301.90 0900 330 72.8777 58.8928 0.2646 542299.00 0915 330 72.8627 58.8907 0.2660 542281.77 0930 330 72.8424 58.8887 0.2647 542296.11 0945 330 72.8302 58.8868 0.2672 542268.16 1000 330 72.8175 58.8849 0.2645 542288.31 1015 330 72.8051 58.8830 0.2642 542285.91 1030 330 72.7848 58.8810 0.2648 542283.23 1045 330 72.7700 58.8794 0.2635 542294.78 1100 330 72.7629 58.8776 0.2646 542275.62 1115 330 72.7513 58.8759 0.2638 542279.11 1130 330 72.7442 58.8742 0.2649 542260.61 1145 330 72.7322 58.8728 0.2656 542253.35 1200 330 72.7279 58.8713 0.2639 542259.06 1215 330 72.7133 58.8698 0.2660 542240.53 1230 330 72.7023 58.8684 0.2640 542257.93 1245 330 72.6894 58.8670 0.2666 542233.83 1300 330 72.6776 58.8656 0.2640 542257.01 1315 330 72.6750 58.8644 0.2653 542235.99 )

1330 330 72.6624 58.8632 0.2649 542242.21 l 1345 330 72.6504 58.8618 0.2654 l 542236.43 1400 330 72.6456 58.8606 0.2640 542243.41 1415 330 72.6365 58.8594 0.2643 542238.40 1430 330 72.6329 58.8583 0.2656 542219.88 1445 330 72.6298 58.8572 0.2632 542234.96 1500 330 72.6191 58.8561 0.2634 542234.10 1515 330 72.6088 58.8549 0.2634 542233.51 1530 330 72.6085 58.8538 0.2647 542211.39 1545 330 72.5888 58.8530 0.2640 542230.92 I 1600 330 72.5852 58.8522 0.2643 542223.89

Virginia Electric and Power Company North Anna Power Station j Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 24 l

TABLE 7 (Sh. 3/5)

DATA

SUMMARY

REPORT time date temperature pressure vapor dry air deg F psia pressure mass Type A Test (cont.)

1615 330 72.5859 58.8514 0.2637 542221.49 -

1630 330 72.5862 58.8504 0.2647 542202.40 1645 330 72.5753 58.8494 0.2685 542169.97 1700 330 72.5695 58.8488 0.2631 542219.95 1715 330 72.5610 58.8478 0.2636 542214.26 ,

1730 330 72.5561 58.8470 0.2654 542195.90 l

1745 330 72.5577 58.8464 0.2632 542209.05 ,

1800 330 72.5488 58.8455 0.2661 542183.17 1815 330 72.5396 58.8450 0.2647 542200.78 1830 330 72.5397 58.8441 0.2632 542205.92 l 1845 330 72.5286 58.8436 0.2643 542202.25 1900 330 72.5342 58.8430 0.2652 542182.34 1915 330 72.5304 58.8425 0.2641 542192.51 1930 330 72.5157 58.8419 0.2648 542195.19 1945 330 72.5141 58.8413 0.2637 542201.47 2000 330 72.5259 58.8408 0.2656 542167.15 2015 330 72.5012 58.8406 0.2635 542209.83 2030 330 72.5034 58.8404 0.2648 542193.84 2045 330 72.5019 58.8400 0.2630 542208.19 2100 330 72.4965 58.8396 0.2642 42198.58 2115 330 72.4972 58.8393 0.2631 542205.96

, 2130 330 72.4913 58.8391 0.2642 542199.94 2145 330 72.4971 58.8389 0.2652 542182.37 2200 330 72.4965 58.8388 0.2641 542192.81 2215 330 72.4968 58.8387 0.2656 542176.89 2230 330 72.4958 58.8385 0.2619 542211.22 l

2245 330 72.4919 58.8384 0.2648 542186.80 2300 330 72.5009 58.8383 0.2648 542176 93 2315 330 72.4944 58.8378 0.2638 542188 a 2330 330 72.4965 58.8376 0.2641 542181.70 2345 330 72.4969 58.8372 0.2619 542197.39 l 0000 331 72.4841 58.8370 0.2640 542189.79 0015 331 72.4874 58.8370 0.2647 542179.31 0030 331 72.4876 58.8369 0.2659 542167.36 0045 331 72.4895 58.8369 0.2656 542168.07 0100 331 72.4942 58.8368 0.2670 542149.25 0115 331 72.4940 58.8366 0.2647 542169.23 l

l

)

Virginia Electric and Power Company ,

North Anna Power Station  !

Unit 1 Reactor Containment Building j

Integrated Leakage Rate Test Report Page 25 '

TABLE 7 (Sh. 4/5)

DATA

SUMMARY

REPORT time date temperature pressure vapor dry air

. deg F psia pressure mass Type A Test (cont.)

0130 331 72.4865 58.8367 0.2642 182.08 0145 331 72.4936 58.8367 0.2648 5 59.33 0200 331 72.4910 58.8367 0.2668 542153.34 0215 331 72.4954 58.8366 0.2642 542172.28 0230 331 72.5002 58.8366 0.2657 542153.86 0245 331 72.4974 58.8366 0.2641 542171.52 0300 331 72.5000 58.8368 0.2649 542163.27 0315 331 72.4989 58.8367 0.2651 542161.40 0330 331 72.5018 58.8367 0.2654 542155.49 0345 331 72.4969 58.8367 0.2643 542170.51 0400 331 72.5005 58.8367 0.2657 542154.06 0415 331 72.4976 58.8368 0.2655 542159.56 0430 331 72.5055 58.8369 0.2648 542159.06 0445 331 72.4952 58.8370 0.2668 542151.84 0500 331 72.5044 58.8367 0.2648 542158.80 0515 331 72.4875 58.8366 0.2651 542172.35 0530 331 72.4918 58.8366 0.2659 542160.06 0545 331 72.4977 58.8367 0.2648 542164.84 0600 331 72.4968 58.8367 0.2671 542145.23 0615 331 72.4921 58.8366 0.2664 542155.47 0630 331 72.4971 58.8366 0.2646 542166.78 0645 331 72.4995 58.8365 0.2673 542138.61 .

0700 331 72.4964 58.8364 0.2628 542182.15 l 0715 331 72.4892 58.8362 0.2658 542160.19 '

l 0730 331 72.4952 58.8362 0.2665 542147 16 0745 331 72.4939 58.8361 0.2656 542156.70 0800 331 72.4968 58.8360 0.2667 542142.14 0815 331 72.4969 58.8358 0.2660 542146.60 0830 331 72.4920 58.8355- 0.2652 542155.90 0845 331 72.4896 58.8354 0.2645 542164.48 0900 331 72.4887 58.8352 0.2653 542155.73 0915 331 72.4950 58.8349 0.2659 542141.29 0930 331 72.4874 58.8348 0.2641 542164.89 0945 331 72.4867 58.8344 0.2663 542141.05 1000 331 72.4867 58.8340 0.2660 542140.60 I

1015 331 72.4854 58.833'i 0.2666 542133.46 1030 331 72.4879 58.8335 0.2665 542129.64 4

e

Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 26 TAllLE 7 (Sh. 5/5)

DATA

SUMMARY

REPORT time date temperature pressure vapor dry air deg F psia pressure mass Type A Test (cont.)

1045 331 72.4869 58.8332 0.2659 542134.13 1100 331 72.4883 58.8329 0.2645 542142.57 1115 331 72.4911 58.8328 0.2642 542141.10 1130 331 72.4801 58.8326 0.2658 542135.79 1145 331 72.4806 58.8323 0.2652 542137.99 l 1200 331 72.4825 58.8322 0.2639 542147.42 1215 331 72.4883 58.8319 0.2647 542131.57 1230 331 72.4801 58.8315 0.2651 542132.46 1245 331 72.4859 58.8314 0.2672 542105.98 1300 331 72.4802 58.8313 0.2669 542113.70 1315 331 72.4855 58.8312 0.2649 542125.71 1330 331 72.4814 58.8309 0.2663 542114.75 1345 331 72.4859 58.8309 0.2665 542108.08 1400 331 72.4837 58.8309 0.2648 542125.91 (Induced leak initiated at 1415 -- the 1415 data are not applicable to either the Type A test or the verification test and are not included in this 1. sting)

Verification Test 1430 331 72.4851 58.8298 0.2655 542107.94 1445 331 72.4740 58.8289 0.2665 542101.89 1500 331 72.4770 58.8280 0.2661 542093.71 1515 331 72.4778 58.8270 0.2655 542089.04 1530 331 72.4794 58.8263 0.2656 542080.32 1545 331 72.4789 58.8255 0.2650 542079.32 1600 331 72.4836 58.8248 0.2684 542035.82 1615 331 72.4802 58.8240 0.2651 542062.64 1630 331 72.4747 58.8234 0.2690 542026.74 1645 331 72.4779 58.8225 0.2644 542057.43 1700 331 72.4741 58.8218 0.2667 542034.00 1715 331 72.4751 58.8211 0.2656 542036.62 1730 331 72.4649 58.8204 0.2671 542026.36 1745 331 72.4639 58.8198 0.2659 542032.87 1800 331 72.4715 58.8190 0.2646 542030.17 1815 331 72.4690 58.8184 0.2674 542001.09 1830 331 72.4687 58.8176 0.2675 541993.11

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Virginia Electric and Power Company North Anna Power Station Unit i Reactor Containment Building Integrated Leakage Rate Test Report Page 38 Appendix I Contaimnent Description The North Anna Power Station containments are conventionally reinforced concrete structures with flat base mats and cylindrical walls topped with hemispherical domes. The inside concrete surfaces are covered with steel liner plates for leak tightness. Principal dimensions are listed below.

Cylinder inside diameter: 126 ft. (face to face of concrete)

Cylinder height: 127 ft. 7 in. (from top of structural concrete mat) l Cylinder wall thickness: 4 ft. 6 in.

Hemispherical dome thickness: 2 ft. 6 in.

Dome liner thickness: 1/2in.

l Wall liner thickness: 3/8 in.

Base mat liner thickness: 1/4in.

The base mat liner is topped with a 2 ft. 6 in working slab. There are three interior floors in the containment. These consist of concrete slab sections and grating. An interior cylindrical wall extending essentially to the level of the top of the containment cylindrical wall supports a polar crane. There are numerous concrete walls inside the containment. These serve as structural walls for the refuelling cavity, structural supports and shield walls.

Placement of the major equipment in the containment is typical for a Westinghouse 3 loop pressurized water reactor system. Residual heat removal exchangers and pumps, as well as recirculation spray exchangers and pumps, are located inside the containment.

Containment design pressure is 45 psig. The containment is designed for operation at l sub-atmospheric pressure and is maintained at about 10 psia when the plant is in service. Free air l volume is, per Reference 6.6, 1825000 cubic feet.

l t

l Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building l Integrated Leakage Rate Test Report Page 39 Appendix II Computer Program Description Leakage rate is calculated using the BCP BASIC program developed by Robert E. Blum. The program runs on an IBM PC or compatible computer which interfaces to the Data Acquisition System (DAS) via an RS 232C serial interface, or IEEE-488 Data Bus. BCP provides two computers with the second serving as a backup unit.

Both mass point (ANSI 56.8) and total time (BN-TOP-1) leakage rates are calculated. The more conservative BN-TOP-1 procedure is generally required by the NRC if test duration is less than the twenty-four hour minimum established in ANSI 45.4.

Raw data from the DAS is automatically recorded on disk storage. The ILRT program converts raw data to engineering units, calculates the volume weighted mean drybulb temperature, vapor pressures from individual dewpoint temperatures and volume weighted mean vapor pressure. It then computes containment air mass using these weighted mean atmospheric conditions. Air mass and time data are used as input to the routines which calculate mass point and total time leakage rates. Manual data entry and correction options are included in the program so that failure of the DAS serial output will not delay the test. Job specific predata loaded into the program include pressure transducer calibration constants, sensor volume fractions and containment free air volume. The volume fraction and free air volume data can be ch: .ged during the course of the test to account for sensor failure and changes in containment water inventory.

Program output includes printed reports and plots. Printed reports listing raw data, engineering unit conversions, weighted mean conditions and air mass are generated for each data set immediately following data input. Various diagnostic reports and plots are generated on command during the test.

These include listings of leakage rates and UCL's calculated for each incremental data set, plots of the same information, plots of weighted mean atmospheric conditions and air mass, and plots of individual sensor data. These same lists and plots, when generated following completion of the test, provide final documentation ofleakage rate. The program is validated prior to each use by loading a standard test data set and verifying that the calculation results agree with those obtained by a manual calculation.

l I

Virginia Electric and Power Company

, North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 40 Appendix Ill Type H & C Test Result Tabulation The Local Leakage Rate Tests (Type B & C)'of containment isolation valves and primary containment penetrations were conducted since the last ILRT (July 1989) in accordance with Appendix J,10CFR50, Para. V.B. The results of these tests are summarized in this appendix.

Containment Elcetrical Penetrations Type B Testing Summary Outace Total Leakace (SCFH)

Spring 1989 2.92 2.65 Spring 1991 2.98 1.69 Spring 1992 5.14 3.75  !

Spring 1993 6.07 4.55 l Containment Fuel Transfer Tube Type H Testing Summary i

Outace Total Leakace (SCFH) l Spring 1989 Spring 1991 Spring 1993 _ . . .

i Virginia Electric and Power Company North Anna Power Station Unit i Reactor Containment Building Integrated Leakage Rate Test Report Page 41 Appendix 111 l Type B & C Test Result Tabulation i

Containment Air Locks Type B Testing Summary Personnel Emergency Escape Test Date Air Lock (SCFH) Air Lock (SCFII)

June 1989 --- July 1989 6.30 ---

December 1989 ---

2.80 l

January 1990 8.00 ---

May 1990 5.40 3.20 l

November 1990 6.70 3.50 l

March 1991 2.90 2.00 August 1991 9.00 4.80 March 1992 10.00 2.06 August 1992 5.00 l March 1993 2.60 3.20 April 1993 ---

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 42 Appendix III Type 11 & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFII) l l

l l Penetration Spring 1989 Spring 1991 Spring 1992 spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage 1 0 0 (#) 0 2 0 0 (#) 0 4 0 0 (#) 0 l

5 0 0 (#) 0 1

! 7 0 4.80 0 0.30 l 0 l

l 8 0 0 (#) 0 l 1.10

(

9 >254 >257 0 0.8 0 0 10 >254 0 0 1.0 0

11 0 0 0 0 12 0 0 0 0.65 l

l 13 0 0 0 0 14 0 0 0 0 15 0 0 0 0 16 0 0 (#) 1.80 1

1. For outages the second figure is "As Left" when different than "As Found".

2. Leakages not quantified are indicated by (*).

3. Penetrations not tested are indicated by (#).

4. The Spring 1989 outage data is included for refererce.

i

Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 43 Appendix Ill Type 11 & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFil)

Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage 17 0 1.50 (#) 9.50 0

18 0.35 2.20 (#) 5.00 0

19 0 0 0 0 0.35 20 0 0 0 0 22 0 0 0 0.7 0

24 0.30 0 (#) 1.0 3.80 25 0.10 0 (#) >257 0.7 26 1.75 0 (#) 0.9 0

27 2.00 0 (#) 0 28 0 0 (#) 0.7 31 6.70 18.00 0 0.4 1.20 0 32 0 0 (#) 0 33 3.50 4.00 0 0  !

0 0 l l

34 0 1.00 0 1.00 i

. . - - . - = .. - -_ -__- _ _

i Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment 13uilding Integrated Leakage Rate Test Report Page 44 Appendix 111 Type 11 & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFil)

Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage l 38 0 >257 1.00 27.00 0.55 0 0 39 0 1.50 (#) 0.5 0

40 10.00 0.30 (#) 0.5 O

j l

l 41 0 1.50 (#) 3.00 1 0 2.00 I

l 42 0 0 0 10.00 0.35 43 0 0 10.00 0.2 i

44 0 0 0 0.1 j 0

l 45 0 0 0 0.65 46 (*) >257 0 0.35 0 0 47 0 0 (#) 0.35 48 0 10.00 (#) 4.00 0 0.70 l 50 0 0 0 0 53 0 0 0.50 0.25 54 0 0 0 0 1

i i

i l

Virginia Electrie and Power Company North Anna Power Station Unit I Reactor Containment Building Integrated Leakage Rate Test Report Page 45 Appendix III Type B & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFil)

Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage 550 0 0 0 0 56A 48.70 0 0 0 0.02 56B 1.40 0 1.50 0 0 0 56C 0.35 0 0 (5/91) (#) 0

560 0 0 0 0 l

! 57A 0 0 0 0 I

( 578 0 0 0 0 57C 0 0 0 0 60 1.30 0.10 0 3.00 0 1.00 1.60 61 0 0.10 0 0 0 1.24 62 0 15.90 0 23.00 0.90 0 63 0 0 6.00 1.00 0

64 0 0 0 0.80 l 66 8.80 0.6 0 0 0 3.00 67 5.20 0 1.00 0.65 1.80 0 1

Virginia Electric and Power Company North Anna Power Station Unit I Reactor Containment 13uilding Integrated Leakage Rate Test Report Page 46 Appendix III Type 11 & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFil) l l

Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage 70 8.00 0 2.30 3.20 0 0 71 1.00 0 1.30 3.00 0 0 j 79 180.00 0.5 0 0 4.60 0 80 28.00 0 0 0 7.00 81 3.30 0 1.90 0 0 0 82 185.00 2.5 0 0 0.07 0 83 14.00 0 0 0 0

84 250.00 >257 0 0 0 0 85 15.00 12.00 0 0 0 0 86 17.00 0 0 0 0

89 4.60 1.40 3.50 1.40 0 0.80 0.80

)

a Virginia Electric and Power Company North Anna Power Station l

Unit i Reactor Containment Building Integrated Leakage Rate Test Report Page 47 Appendix 111 Type H & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - L cakages (SCFil)

Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 Number Outage INTERIM Outage INTERIM Outage Outage 90 1.00 2.7 (12/89) >182 0 (7/91) (#) >257 0.80 2.1 (12/89) 0 2.5 (7/91) 4.10 91 1.00 2.3 (12/91) 0 (#) >257 1.10 3.1 (12/91) 0 92 0.80 0 0 0 l

l

! 93 1.50 0 0 0 1.00 94 6.60 2.1 (12/89) 30.00 0 (3/91) 1.10 10.00 1.80 0 0 (5/91) 0 l 0 (7/91) 97A 0 0 0 0 97B 0 0 0 0 97C 0 0 0 0 98A 1.40 0 0 0 0

988 0 0 0 0 l

100 0 0 (#) 0 103 0 0.3 0 0.75 i

104 0 0 0 0.25 0

f l

l l

a n .

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 48 Appendix III Type B & C Test Result Tabulation Containment Piping Penetrations Type C Testing Summary - Leakages (SCFil) l l

l Penetration Spring 1989 Spring 1991 Spring 1992 Spring 1993 l Number Outage INTERIM Outage INTERIM Outage Outage l ........... .......... .......... .......... .......... .......... ..........

105A 0 0 0 0 l

105B 0 0 0 0 105C 0 0.29 0.30 0.30 0.02 0 0 1050 0 0 (#) 0 106 0 0 (#) 0 l

108 0 0 (#) 0.90 109 0 0 0 0 111D 0 0 1.00 0.70 0 0 113 (*) 0 4.00 0.3 7.00 0 0.8 114 (*) 0.8 0 0 1 0 0 0.6 I 1

Recorded Work

Virginia Electric and Power Company North Anna Power Station Unit 1 Reactor Containment Building Integrated Leakage Rate Test Report Page 49 Appendix III Type 11 & C Test Result Tabulation Containment Piping Penetrations Type C Failure Summary The following is a summary of Type C test leakages which exceeded 0.6 La.

Recorded Work Pen Valve Test Leakage Order No Number Date (SCFH) Number Description of Repair 9 1-CC-572 1/23/91 >257 121844 Replaced valve 25 1 CC-TV 102F 2/07/93 >257 158315 Replaced SOV - leaking by preventing valve from closing fully 38 1-DA-TV-1000 1/21/91 >257 121863 Replaced broken actuator spring l 46 1-CH FCV-1160 1/15/91 >257 096144 Removed lip from seating area of plug l

84 1-SW MOV-104C 1/15/91 >257 121669 Reset stops in actuator 90 1-HV-MOV-100C 2/25/91 >182 122656 Adjusted seat 1-HV MOV-1000 3/10/93 >257 159543 No problem found -

Passed subsequent testing 91 1-HV MOV-100A 3/04/93 >257 159417 Replaced seat l

l l

l l

l l

l 1

l 1

l

_ _ _ _ _ _ . _ . _ _ . _ _ _ _