ML20153G042

Reactor Containment Bldg Integrated Leak Rate Test

ML20153G042
Person / Time
Site:	Quad Cities
Issue date:	06/13/1988
From:	Bax R COMMONWEALTH EDISON CO.
To:	Murley T Office of Nuclear Reactor Regulation
References
RLB-88-267, NUDOCS 8809080021
Download: ML20153G042 (82)

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i REACTOR CONTAINMENT BUILDING i INTEGRATE 0 LEAK RATE TEST

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QUAD-CITIES NUCLEAR PCHER STATION [

UNIT TWO JUNE 12 13, 1988 ,

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TABLE OF CONVENTS 4

PAGE TABLE AND FIGURES INDEX. ...................... 3 i

INTRODUCTION . . .......................... 4 A. TEST PREPA3ATIONS s

A.1 Type A Test Procedures . . . . . . . . . . . . . . . . . . 4  :

i A.2 Type A Test Instrumentation. . . . . ........... 4 A.2.a. Temperature . . . . . . . . . . . . . . . . . . . . 8 A.2.b. Pressure. . . . . . . . . . . . . . . . . . . . . . 8 1 A.2.c. Vapor Pressure. . , . . . . . . . . . . . . . . . .

8 A.2.d. Flow. ....................... 9 A.3 Type A Test Measurements . . . . . . . . . . . . . . . . . . 9 l

A.4 Type A Test Pressurization . . . . . . . . . . . . . . . . 10  ;

I B. TEST METH00  :

8.1 Basic Technique. . . . . . . . . . . . . . . . . . . . . . 12 I

< t 8.2 Supplemental Verification Test . . . . . . . . . . . . . . 13  !

4 8.3 Ins trument Error Analysi s. . . . . . . . . . . . . . . . . 13  !

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, C. SEQUENCE OF EVENTS ,

C.1 Test Preparation Chronology . . . . . . . . . . . . . , , 14 i C.2 Test Preparation and Stabilization Chronology. . . . . . . 15 C.3 Measured Leak Rate Phase Chrenology. . . . . . . . . . . 16 l l C.4 Induced leakage Phase Chronology . . . . . . . . . . . . . 16 C.5 Depressurization Phase Chronology. . . . . . . . . . . . . 16 1

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l TABLE OF CONTENTS (CONTINUED)

PAGE

0. 7YPE A TEST DATA 0.1 Heasured Leak Rate Phase Data . . . . . . . . . . . . . . 17 I 0.2 Induced Leakage Phase Data . . . . . . . . . . . . . . . 17 E. TEST CALCULATIONS . . . . . . . . . . . . . . . . . . . . . . 32 F. TYPE A TEST RESULTS F.1 Measured Leak Rate Test Results . . . . . . . . . . . . 33 l

F.2 Induced Leakage Test Results'. . . . . . . . . . . . . . . 34 F.3 Pre-Operational Results vs. Test Results. . . . . . . . . 35 ,

F.4 Type A Test Penalties . . . . . . . . . . . . . . . . . . 35 F.5 Evaluation of Instrument Failures . . . . . . . . . . . . 36  !

i F.6 As-Found Type A Test Resul ts. . . . . . . . . . . . . . . 37

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APPEN0!x A TYPE B AND C TESTS . . . . . . , . . . . . . . . 38 i

l APPEN0!X B TEST CORRECTION FOR SUMP LEVEL CHANGES . . . . 47 APPENDIX C COMPUTATIONAL PROCEDURES . . . . . . . . . . . . 53 APPENDIX 0 INSTRLMENT ERRCR ANALYSIS ...........65 l

APPENDIX E BN-TOP-1. REV. 1 ERRATA . . . . . . . . . . . . 71 APPENDIX F TYPE A TEST RESULTS USING MASS-PLOT. . . . . , , 76 METH00 (ANS/ ANSI 56.8) i i

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TABLES AND FIGURES INDEX i

PAGE TABLE 1 Instrument 3pecifications. . . . . . . . . . . . . . . . 5 TABLE 2 Sensor Physical Locations. . . . . . . . . . . . . . . . 6 TABLE 3 Measured Leak Rate Phase Test Results. . . . . . . . . 18 TABLE 4 Induced Leakage Phase Test Results . . . . . . . . . . 19  ;

FIGURE 1 Idealtred View of Drywell and Torus. . . . . . . . . . . 7 Used to Calculate Free Air Volumes l

FIGURE 2 Measurement System Schematic Arrangement . . . . . . . 11 FIGURE 3 Measured Leak Rate Phase - Graph of Calculated . . . . 20 Leak Rate and Upper Confidence Limit j FIGURE 4 Measured Leak Rate Phase - Graph of Total. . . . . . . 21  !

Time Measure Leak Rate and Regression Line j FIGURE 5 Measured Leak Rate Phase - Graph of ....... . . 22 ,

Dry Air Pressure FIGURE 6 Heasured Leak Rate Phase - Graph of Volume . . . . . . 23 i Heighted Average Centainrent Vapor Pressure  :

FIGURE 7 Measured Leak Pate Phase - Graph of Volume . . . . . . 24 i Heighted Average Containment Temperature i

FIGURE 8 Induced Leakage Phase - Graph of Calculated. . . . . . . 25  ;

Leak Rate FIGURE 9 Induced Leakage Phase - Graph of Total Time. . . . . . 26 I Measured Leak Rate and Regression Line i

FIGURE 10 Induced Leakage Phase - Graph of Volume. . . . , , . 27  !

Weighted Average Containment Temperature (

FIGURE 11 Induced Leakage Phase - Graph of Volyme. . . . . . . . 28 i Heighted Average Containrent Vapor Pressure

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l FIGURE 12 Induced Leakage Phase - Graph of . . . . . . . . . . . 29 j Dry Air Pressure 1 FIGURE 13 Graph of Reactor Water Level . . . . . . . . . . . . . 30 Through Testing Period FIGURE 14 Graph of Torus Water Level . . , . . . . . . . . . . . 31 Through Testing Period ,

r FIGURE F-1 Statistically Average Leak Rate and' Upper. . . . . . . 79 ,

Confidence Limit (AN5/ ANSI 56.8 Method)

FIGURE F-2 Statistically Averaged Leak-rate and Target. . . . . . 80 Leak-rate (ANS/ ANSI 56.8 Method) 1490H/ i 1

INTRCDUCTION This report presents the test method and results of the Integrated Primary Containment Leak Rate Test (IPCLRT) successfully performed on June 12-13, 1988 at Quad-Cities Nuclear Poder Station, Unt; One. The test was performed in accordance with 10 CFR 50, Appendix J and the Quad-Cities Unit One Technical Scecifications.

For the fourth time at Quad-Cities a short duration test (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) was conducted using the general test method outlined in BN-70P-1, Revision 1 (Bechtel Corporation Topical Report) dated November 1, 1972. Th3 first short duration test was conducted on Unit One in December,1982.

Using the above test methed, the total primary containment integrated leak rate was calculated to be 0.4155 wt %/ day at a test pressure greater than 48 PSIG. The calculated leak rate was within the 0.750 wt %/ day acceptance criteria (75% of LA ). The associated upper 95% confidence limit was 0.4621 wt %iday.

The supplemental induced leakage test result was calculated to be 1.3542 wt l t/ day. This value should compare with the sum of the measured leak rate phase I result (0.4155 wt 1/ day) and th9 inducted leak of 8.82 SCFM (1.0814 wt %/ day). The l calrulated leak rate of 1.3542 wt %/ day lies within the allowable tolerance band of l 1.4969 wt %/ day . 0.250 wt %/ day.

SECTICN A - TEST PREPARATIONS A.1 Type A Test P_rocedure The IPCLRT was performed in accordance with Quad-Cities Procedure QTS 150-1, Rev. 15, including checklist QTS 150-52, 53, 55, 56, 57, 58, 510. 511. S12, S13, 517 SIS, 519, and subsections T2, T6, T8, T10. Til, T12, T13, T14, il5. Approved l Temporary Procedures 5537, 5540, 5541, 5542, 5543, and 5547 were written in conjunction with the test, Procedure 5537 was written to cover the various manual isolation valves not included in the IPCLRT valve checklist QTS 150-57. Procedure 5540 was written to alle= resetting of the scram after original jurper installation. Procedure 5541 was written to cover exceptions to the manual isolation valve checklist. Procedure 5542, 5543, and 5547 were written to cover j exceptions to the valve checklist of QTS 150-57.

These prccedures mere written to comply with 10 CFR 50 Appendix J. ANS/ ANSI N45.4-1972, and Quad-Cities Unit One Technical Specifications, and to reflect the Commission's approval of a short duration test using the BN-TCP-1, Rev. 1 Topical Report as a general test method.

A.2 _ Type A Test instrumentation Table One shows the specifications for the instrumentation utilized in the I IPCLRT. Table Two lists the physical locations of the temperature and humidity sensors within the primary containment, Figure 1 i. an ideali:ed view of the l drywell and suppression enamber used to calculate s., primary containment free air '

subvolumes. Plant personnel performed all test instrumentation calibrations using NBS traceable standards. Quad Cities procedure QTS 150-9 was used to perform the calibration, j

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TABLE ONE INSTRUMENT SPECIFICATIONS REPEATABILITY MANUFACTURER MODEL NO. SERIAL NO. RM ACCURACY INSTRUMENT Precision 1 001 PSI Pressure 846,847 0-100 PSIA 1 015 PSI Gages (2) Volumetrics 44210 - 44222 44224 - 44232 i.1-F Burns 44234 - 44238 50-150*F 1 5*F Engineering SP1A1-5 d2-3A .

RTD's (30) inclusive 191501, 191509, 191522 5535-1,5835-2 5835-3, 6084 4 6084-9, 5835-6 ,

Lithium 6084-7. 5835-9 i.5*F Vo!=: ei r ics 5835-10, 6084-8 104*F 31 0*F (Foxboro) Chloride De= cells (10)

Pall Trinity 0-600*F 12 0*F 1 1*F Micro 14-T-2H _-

Thermocouple Fischer 8405A0348A1 0.927-11.23scfm 11 0% of

& Porter 10A3555S man iIon flowmetc.r Level Model 180 indicator Type VSt tl 263-101 0-400" H 2O CE Model 50-553122CAAU2 LT 263-61 10.85"H 20=10mA 106958 15.84"H 20 30mA Torus 11510P3812ns Rosemount 20.84"H 0150mA 2

Level Indicator 075GV0306Z

TABLE TWO SENSOR PHYSICAL LOCATIONS RfD NUMBER SERIAL NUMBER SUBVOLUME ELEVATION AZIPUTH' l 1 191522 1 670'0" 180' l 670'0" 2 44210 1 O' 3 44211 2 657'0" 20' 4 44212 2 657'0" 197*

5 44213 3 639'0" 70'  :

6 44214 3 639'0" 255"  !

l 7 44215 4(Annular Rin9) 643'0" 55'  :

8 44216 4 615'0" 225' s 9 44217 5 620'0" 5' 10 44218 5 620'0" 100' i

11 44219 3 620'0" 220' 12 44220 6 608'0" 40*

13 44221 6 608'0" 130' 14 44222 6 608'0" 220' 15 191509 6 608'0" 310' [

16 44224 7 598'0" 70' l 17 44225 7 598'0" 160* l 18 44226 7 598'0" 250' .

19 44227 7 598'0" 340' l 20 44228 8 587'0" 10'  ;

21 44230 8 587'0" 100' 22 44232 8 587'0" 190' L 23 191501 3 587'0" 280' i 24 44234 9(CR0 Space) 595'0" 170'  !

25 44235 9(CR0 Space)) 580'0" 170' 26 44236 10(Torus) 578'0" 70'  !

27 44237 10(Torus) 578'0" 140' 28 44238 10(Torus) 578'0" 210' i 29 44229 10(Torus) 578'0" 280'  ;

30 44231 10(Torus) 578'0" 350' Thernoccuple (Inlet to 11(Ri Vessel) -

clean-up HX) i DEWCELL NO. SERIAL NUMBER SUCVOLUME ELEVATION A21HUTH 1 5835-1 1 670'0" 180' 2 5835-2 2.3.4 653'0" 90' >

3 5835-3 2.3.4 653'0" 270' 1 4 6084-4 5 620'0" 0* i 5 6084-9 6 605'0" 45' 6 5835 6 7 600'0" 220'  ;

7 6084-7 8.9 591'0" O' l 8 6084-8 8.9 591'0" 202' 1 9 5835-9 10 578'0" 90' l 10 5835-10 10 578'0" 270' i Thermocouple l (Saturated) 11 --- ---

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A.2.a. Temperature The location of the 30 plati_num RTD's 'was chosen to avoid conflict with local temperature variations and thermal influence from metal structures. A temperature survey of the cont 31nment was previously performed to verify that the sensor locations were representative of average subvolume' conditions.

The RTO's were manufactured by Burns Engineering Inc. and are Model SP 1Al-5 1/2-3A. Each RTO and its associated bridge network was calibrated to yield an output of approximately 0-100 mV over a temperature range of 50-120*F. Each RTD was calibrated by comparing the bridge output to the true

, temperature as indicated by the temperature standard. Four temperat'Jres were' '

used for the calibration. Two calibration constants (a slope and intercept of the regression line) were computed for each RTD by performing a least squares .;

fit of the RTO bridge output to the reference standard's indicated true ,

temperature.

The tempert.ture standard used for all calibrations was a Volumetrics RTO Model VMC 701-B used with a Deweell/RTD Calibrator Model 07782. The standard was calibrated by Volumetrics on January 20. 1988 to standards traceable to the NBS.

The plant process computer scannDd the output of each RTO-bridge netword dnd f.onverted the output to engineering units using the cdibration constants.

A.2.b. Pressure Two precision quartz bourdon tube. absolute pressure gauges were utillud to measure total containment pressure. Each gauge had a local digital readout and a Binary Coded Decimal (BCO) output to tne process computer. Primary containment pressure was sensed by the pressure gauges in parallel through a 3/8" tygon tube connection to a special one inch pipe penetration to the containment.

Each prectsion pressure gauge was calibrated from 62.8-65.8 PSIA in approximately 0.5 PSI increments using a third precision pressure gauge (Volumetrics Model 07726) that had been sent to Volumetrics for calibration.

The pressure standard was calibrated on February 19, 1988 using NBS traceable reference standards.

The digital readout of the instruments were in "counts" or arbitrary I units. Calibration constants (a slope and intercept of a regression line) l were entered into the computer program to convert "counts" into true ,

atmospheric pressure as read by the third, reference gauge. No mechanical calibration of the gauges was performed to bring their digital displays into agreement with true pressure.

A.2.c. Vagor Pressure Ten lithtui chloride dewcells were used to determine the partial pressure '

due to water vapor in the containment. The dewcells were calibrated using the Volumetrics calibrator described in section A.2.a. above and a chilled mirror

dewcell standard (Volumetrics S/N 1263) calibrated on January 20, 1988 by 1490H/ - 8-1 4

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Volumetrics. The calibration constants ior e nh dewcell (the slope and intercept of a regression line) were computu relating the 0-100 mV output of the signal conditioning cdeds to the actual uewootnt indicated by the reference standard. ,

A.2.0. Flow A rotameter flowmeter, Fischer-Porter serial c.uc.ber 8405A0348A1, was used for the flow measurement during the Induced leakage phase of the IPCLRT. The flowmeter was calibrated by Fischer-Porter on February 19, 1988, to withia 317 of full scale (0.927-11.23 SCFM) using NSS traceable standards.

Plant personnel continuously monitored the flow juring the induced leakage phase and co,rected any minor deviations from the induced flow rate of 8.82 SCFM by adjusting a 3/8" needle valve on the flowmeter inlet. The flow meter outlet was unrestricted and vented to the atmosphere. The flowmeter was calibrated to standard atmospheric conditions.

A.3 Type A Test Measurement The IPCLRT was performed utilizing a direct interface with the station process computer. This system consists of a hard-wired installation of temperature, dewpoint, and pressure inputs for the IPCLRT to the process computer. The interface allows the process computer to scan the inputs and send the data, still as a millivolt signal or BCD (binary coded decimal) in the case of pressure, to the PRIME computer with minimal manual inputs and without the disadvantages of multiplexers or positioning sensitive electronic hardware inside the containment durIng the test.

The PRIME computer was usea to compute and print the leak rate data using either the ANSI /ANS mass plot method (ANSI /ANS 56.8), a total time method based on ANSI /ANS N45.4, or the BN-TOP-1 method. Key parameters, such as total time measured leak rata, volume weighted dry air pressure and temperature, and absolute pressure were monitored using a Tektronix 4208 terminal and a Tektronix plotter. Plant personnel also plotted a large number of other parameters, including reactor water level and temperature, torus water level, dry air mass, volume weighted partial pressures and temperature, total time leak rate, statistically averaged leak rate and UCL, and all sensor outputs in engineering units. In all cases, data was plotted hourly and computer summaries we e obtained at 10 minute time intervals. The plotting of data and the computer printed summaries of data allowed rapid identification of any problems as they might develop, Figure 2 shows a schematic of the data acquisition system.

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A.4 Type A Test Pressurization A 3000 SCFM, 600 hp, 4kV tiectric oil-free air compressor was used to pressurize the primary containment. An identical compressor was available in standby during the IPCCRT. The compressors were physically located on a single enclosed truck trailer located outside the Reactor Building. The compressed air was piped using flexible metal hose to the Reactor Building, i through an existing four inch fire header penetration, and piped to a temporary spool piece that, when installed, allowed the pressurization of the drywell through the "A" containment spray header. The inboard, containment '

spray isolation valve, H0-1-1001-26A was open during pressurization. Once the containment was pressurized, the H0-1-1001-26A valve was closed and the spool piece was removed and replaced with a blind flange. The outboard containment spray value H0-1001-23A was closed and out-of-service for the test.

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SECTION 8 - TEST METHOD B.1 , Basic Technique The absolute method of leak rate determination was used. The absolute method uses the ideal gas laws to calculate the measured leak rate, as defined in ANSI N45.4-1972. The inputs to the measured leak rate calculation include subvolume weighted containment temperature, subvolume weighted vapor pressure, and total absolute air pressure.

As required by the Commission ;n order to perform a short duration test (measured leak rate phase of lee,s then 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), the measured leak rate was statistically analyzed using the principles outilned in 8N-TOP-1, Rev. 1. A least squares regression lin't for the measured total time leak rate versus time since the start of the test is calculated after each new data set is scanned. The calculat.1 'eak rate at a point in time, t i , is the leak rate on the regression line t the time tj.

The use of a regression line in the BN-TOP-1, Rev. I report is different from the way it is used in the ANSI /ANS 56.8 standard. The latter standard uses the slope of the regression line for dry air mass as a function of time to derive a statistically averaged leak rate. In contrast, BN-TOP-t, Rev. I calculates a regression line for the' measured leak late, which is a function of the change in dry air mass. For the ANSI /.;NS calculations one would expect to always see a negative slope for the regression line, because the dry air mass is decreasing over time due to leakage from the containment. For the regression line computed in the BN-TOP-1, Rev.1 method the ideal slope is zero, since you presume that the leakage from the containment is cor stant over time. Since it is imoossible to instantaneously and perfectly measure the containment leakage, the slope of the regression line will be positive or negative depending on the scatter in the measured leak rate values obtained early in the test. $1nce the measured leak rate is a total time calculation, the values computed early in the test will scatter much more than the values computed after a few hours of testing.

The computer printouts titled "Leak Rate Based on Total Time Calculations" attached to the BN-TOP-1, Rev. I topical report are misleading in that the column titied "Calculated Leak Rate" actually has printed out the regression line values (based on all the measured leak rate data computed frcm the data sets received up until the last time listed on the printout). The calculated leak rate as a function of time (t )t can only be calculated from data available up until that point in time, t t. This is significant 'n that the calculated leak rate may be decreasing over time, despite a substantial positive slope in the last computed regression line. Extrapolation of the  ;

regr.;sion line is not required by the BN-TOP-1, Rev. I criteria to terminate a short duration test. What is required is that the calculated leak rate be decreasing over time or that an increasing calculated leak rate be extripolated to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The distinction between the regression line values and the calculated leal, rate as a function of time is made in Section 6.4 of BN.10P-1, Rev. 1. Calculated leak rates, as a function of time, are correctly printed out in the "Trends Based oa Total Time Calculations" computer printouts in Appendix B of BN-TOP-1, Rev.1.

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. Associated tfith each calculated leak rate is a statistically derived upper confidence limit. Just as the calculated leak-rate in SN-TOP-1, Rev, I and the statistically averaged leak rate in the ANSI /ANS standards are not the same (and do not necessarily yield nearly equal values), the upper confidence limit calculations are ~ greatly different. In the BN-TOP-1, Rev. I topical report the upper confidence limit is defined as the calculated leak rate plus the product of the two sided 97.5% T-distribution value (as opposed to the one-sided 95% T-distribution used in the ANS/ ANSI standard) and the standard.

deviation of the measured leak rate data about the computed ,egression line (wht;h has no relationship to the value computed in the ANSI /ANS standards).

There are two important conclusions that can be derived from data analyzed using the BN-TOP-1, Rev. I method: 1) the upper confidence limit for the same measured leak rate data can be substantially greater than the value calculated using the ANSI /ANS method, and 2) the upper confidence limit does not converge to the calculated leak rate nearly as quickly as usually observed in the latter method as the number of data sets becomes large. With this in mind, the upper confidence limit can become the critical parameter for concluding a short duration test, even when the measured leak rate seems to be well under the maximum allowable leak rate. A graphical comparison of the two methods can be made by referring to Figure 3 for the BN-TOP-1, Rev. I calculated leak rate and upper confidence limit and to Figure F-1 in Appendix F for the statistically averaged leak rate and upper ccqfidence limit based on ANSI /ANS 56.8-1981. This data supports the contention of many that BN-TOP-1, while it may not give the best estimate of containment leakage, is a conservative method of testing. The ANSI /ANS 56.8 data contained in Appendix F is provided for information only. The reported test results are based on BN-TOP-1, only.

B.2 Supplemental Verification Test The supplemental verification test superimposes a known leak of approximately the same magnitude as LA (8.16 SCFM or '.0 wt %/ day as defined in Technical Specifications). The degree of detectability of the combined leak rate (containment calculated leak rate plus the superimposed, induced leak rate) provides a basis for resolving any uncertainty associated with measured leak rate phase of the test. The allowed error band is 1 25% of LA .

There are no references to the use of upper confidence limits to evaluate the acceptability of the induced leakage phase of the IPCLRT in the ANS/ ANSI standards or in BN-TOP-1, Rev. 1.

B.3 Instrument Error Analysis An instrument error analysis was performed prior to the test in accordance with BN-TOP-1, Rev. 1 Section 4.5. The instrumert system error was calculated in two parts. The first was to determine the system accuracy uncertainty The second and more important calculation (since the leak ate is impacted most by changes in the containment parameter $> was performed to determine the system repeatability uncertainty. The results were 0.1801 wt 1/ day and

.0265 wt %/ day for a 6-hour test, respectively. These values are inversely proportional to the test duration. .

The Instrumentation uncertainty is used only to illustrate the system's ability to measure the required parameters to calculate the primary containment leak rate. The mathematical derivation of the above values can be found in Appendix 0. The method of calculating the equipment uncertalqty is in conformance with the method outlined in BW-TOP-1.

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E It is extremely important during a short duration test to quickly identify a failed sensor and in real time back the spurious data out of the calculated volume weighted containment temperature and vapor pressure. Failure to do so can cause the upper confidence limit value to place a short duration test in jeopardy. It has been'the stations experience that sensor failures should be removed from all data collected, not just subsequent to the apparent failure, in order to minimize the discontinuity in computed values that are related to the sensor failure (not any real change in containment conditions). For this test, however, no l'istrument failures af ter the start of the test were enuuniered. However, a single RTO failed in the drywell, RTD 8 in tubvoluma 4, prior to the start of the test for spiking high and then reading high. The effect of this failure is analyzed in section F.5 of this report. The instrument error analysis in Appendix 0 reflects the instrument failure and unused instrument.

SECTION C - SEQUENCE OF EVENTS C.1 Test Preparation Chronology The pretest preparation phase and containment intpection was completed on Junc 12, 1988 with no apparent structural deterioration being observed.

Major preliminary steps included:

1) Blocking open three pairs of drywell to suppretston chamber vacuum breakers.

2) Installation of all IFCLRT test equioment in the suppression chamber.

3) Completion of all repait s and installations in the drynll affecting primary containment.

4) Venting of the reactor vessel to the drywell by onening the manual head vent line to the drywell equipment drain somp.

5) Installation of the IPCLRT data acquisition system including computer programs, inctrument console, locating instruments in the drywell, and associated wiring.

6) Completion of the pre-test valve line-up.

This tes; was conducted at the end of the refuel outage to test the co'itainment in an "As lef t" condition with repairs and adjustments. The Station has an exemption to 10CFR50, Appendix J requirements to allow performing the test at the end of the refuel outage.

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p. y C.2 Test Pressurization and Stabilization Chronology i DATE ' TIME EVENT 06-12-88 0300 Began pressurizing containment.

0550 Drywell Head, X-1, and X-4 snooped. No leaks observed.'

Snooped all accessible penetrations in reactor -

building. No leaks observed.

0613 2-1402-4B leaks excessively through packing.

0807 Stopped pressurizatio,; due to reactor water and torus '

water level decreasing at an unacceptable rate.

Increased reactor water level to approximately 87". ,

0820 Closed the 2-1001-26A and 2-4799-127 valves. Unioaded the compressor and stopped pressurization. . Raised 1 reactor water level to approximately 100".

0900 Tightened packing on the 2-1402-48,.2 ',01-28A, 34A valves. Closed the 2-2301-6 valve to fully seat.

1052 Containment is pressurized to 65 PSIA. Beginning containment stabilization phase.  ;

1200 Attempts are being made to determine a leak of

approximately 500 SCFH. All systems are being snooped.

2050 Closed the 2-1001-25A talve on the outboard side of the 2-1001-26A valve. No effect on the leakage rate. i 2355 Leakrate has stabilized at 1.3LA still searching 'or the leakage.  ;

I 6-13-88 0225 Locked out RTO #8 in subvolume #42-2499-20A was found blowing air.inside the hydrogen monitoring panel.

Heater sample box w?.s disconnected and removed. ,

l

, 0230 2-2499-20A valve was closed. The leakage path 5:as found.

i 0405 All stabilization criteria have been satisfled.

l i

i 1490H/ , i r_______.__.________m__._

C.3 Measured Leak Rate Phase Chronology.

DATE -TIME EVENT 06-13-88 0405 Containment temperat'ure stable below 0.lF/ hour.

Reactor vessel level drop:of approximately 0.5 inches / hour. Reactor water temperature stable below 1*F/ hour.

0405 Started meausred leak rate phase. Base data set #181.

1006 Terminated measured leak rate phase at 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> point, base data set #218. Calculated leak rate was 0.4155 wt 4

%/ day and decreasing over time. The average measured leak rate over the last five hours was 0.4194 wt %/ day.

The upper confidence limit was 0.4621 wt%/ day. All other BN-TOP-l~,.Rev. I criteria for terminating the test were satisfied.

Cs4 Induced Leakage Phase Chronology

)

4 DATE TIME EVENT 06-13-88 1040 Valved in the flowmeter at 8.82 SCFM (80% scale reading). Radiation Protection is collecting a sample-of containment air.

1106 Stabilization began for l'nduced' phase. Data set #224 1206 Began induced phase of the test. Base Data set #230.

The one hour stabilization required by 8d-TOP-1 was comp 1ted.

i 1517 Terminated induced phase. Last data set was #249.

Calculated leak rate was 1.3542 wt%/ day. With an upper confidence limit of 1.4626. Data indicates a successful test.

j C.5 Depressurization Phase Chronology

$ DATE f!ME EVENT 06-13-88 1650 Began containment depressurization using procedure for venting through the Standby Gas Treatment System-j (SBGT). flowmeter isolated.

3 1810 Depressurlted down to 52.24 PSIA to perform special test 2-81.

1490H/  ;

r ,

F-DATE T!ME EVENT 06-13-88 2010 Completed special test 2-81 preparing to depressurization again.

2210 Depressurized to 27 PSIA. Opened 2-1601-63 wide open for final depressurization.

06-14-88 0315 Technical Staff personnel entered drywell. No apparent structural damage. Verified all instruments remained in place. Removed all instrumentation in the drywell.

0604 Made initial entry to suppression chamber. Verified all instrument remained in place and removed all remaining instruments. Sump levels in drywell cbocked and recorded.

SECTION O - TYPE A TEST DATA 0.1 Measured Leak Rate Phase Data A summary of the computed data using the BN-TOP-1, Rev. I test method for a short duration test can be found in Table 3. Graphic results of the test are found in Figures 3-7. For comparison purposes only, the statistically averaged leak rate and upper confidence limit using the ANS/ ANSI 56.8-1981 standard are graphed in Figure F-1. A summary of the computed data using the ANS/ ANSI standard is found in Appendl* F.

0.2 Induced Leakage Phase Data A summary of the computed data for the Induced Leakage Phase of the IPCLRT is found in Table 4. The calculated leak rate and upper confidence limit using the BN-TOP-1, Rev. I method are shown in Figure 8. The measured leak rate and last computed regression line are shown in Figure 9.

Containment conditions during the Induced Leakage Phase are presented graphically in Figures 10-12.

l 1490H/ -17 l

Measured Leak Rate Test Results TABLE 3 DRY AIR REACTOR MEAS. CALC. UPPER DATA TEST - AVE. PRESSURE LEVEL LEAK LEAK CONF.

SET # TIME DURATION TEMP. (PSIA) (INCHES) RATE RATE LIMIT 181 04:05:31 0.000 93.1 63.6012 91.9940 182 04: 15:33 0.167 93.1 63.5971 91.8900 0.4937 183 04:25_33 0.334 93.1 63.5935 91.7510 0.4135 184 04: 35:35 0.501 93.1 63.5907 91.7510 0.3569 0.3529 0.4471 185 04:45:35 0.668 93.1 63.5850 91.6120 0.4342 0.3893 0.6826 186 04: 55:36 0.835 93.1 63.5825 91.5080 0.3940 0.3828 0.5716 187 05:05:39 1.002 93.1 63.5781 91.5080 0.4414 0.4050 0.5728 188 05:15:39 1.169 93.0 63.5752 91.3690 0.3843 0.3916 0.5297 189 05:16:01 1.175 93.0 63.5752 91.3690 0.3823 0.3885 0.5031 190 05:25:04 1.343 93.0 63.5714 91.3690 0.4185 0.3923 0.5006 191 05:36:05 1.509 93.0 63.5675 91.3690 0.4552 0.4087 0.5208 192 05:46:06 1.677 93.0 63.5636 91.2650 0.4381 0.4164 0.5223 193 05:56:09 1.844 93.0 63.5608 91.1260 0.4244 0.4184 0.5169 194 06:06:09 2.011 93.0 63.5576 91.1260 0.4328 0.4223 0.5150 195 06:16:10 2.178 93.0 63.5547 90.8830 0.4024 0.4171 0.5053 196 06:26:10 2.344 93.0 43.5505 90.8830 0.4323 0.4207 0.5047 197 06:36:14 2.512 93.0 63.5473 90.7440 0.4247 0.4217 0.5017 198 06:46:15 2.679 93.0 63.5434 90.7440 0.4387 0.4257 0.5026 199 06:56:15 2.846 93.0 63.5419 90.6400 0.4205 0.4250 0.4988 200 07:06:15 3.012 93.0 63.5389 90.5010 0.4115 0.4226 0.4938 201 07:16:16 3.180 92.9 63.5352 90.3620 0.4219 0.4226 0.4913 202 07:26:20 3.347 92.9 63.5324 90.3620 0.4302 0.4241 0.4906 203 07:36:21 3.514 92.9 63.5300 90.2580 0.4246 0.4244 0.4887 204 07:46:25 3.682 92.9 63.5282 90.2580 0.4147 0.4230 0.4855 205 07:56:25 3.849 92.9 63.5249 90.2580 0.4190 0.4225 0.4833 206 08:06:26 4.015 92.9 63.5206 90.0840 0.4151 0.4214 0.4806 207 08 16:28 4.183 92.9 63.5198 90.0840 0.4129 0.4202 0.4780 208 08:26:30 4.350 92.9 63.5168 89.9450 0.4224 0.4205 0.4768 209 08:36:33 4.517 92.9 63.5147 89.8070 0.4176 0.4200 0.4751 210 08: 46:33 4.684 92.9 63.5131 89.8070 0.4176 0.4197 0.4735 211 08 56: 35 4.851 92.9 63.5091 89.7020 0.4249 0.4203 0.4730 212 09:06:35 4.018 92.9 63.5034 89.7020 0.4162 0.4197 0.4714 213 09:16 36 5.185 92.9 63.5070 89.5630 0.4082 0.4183 0.4691 214 09:26:36 5.352 92.9 63.5033 89.5630 0.4212 0.4185 0.4684 215 09:36:37 5.519 92.9 63.5020 89.5280 0.4158 0.4181 0.4670 216 09: 46:39 5.666 92.9 63.5003 89.3900 0.4086 0.4169 0.4651 217 09:56:41 5.853 92.9 63.4975 89.2510 0.4151 0.4166 0.4639 I 218 10:06: 43 6.020 92.9 63.4971 89.2510 0.4072 0.4155 0.4621 l

l 1490H/ .

Induced Leakage Phase Test Results TABLE 4 ORY AIR REACT 0F. MEAS. CALC. UPPER DATA TEST AVE. PRESSURE LEVEL LEAK LEAK CONF.

SET # TIME DURATION TEMP. (PSIA) (INCH 25) RATE RATE LIMIT 230 12:06:56 0.000 93.0 63.4372 30.4520 231 12:16:57 0.167 93.0 63.4308 88.3130 1.3986 232 12:27:00 0.335 93.0 63.4242 88.3130 1.5294 233 12:37:04 0.502 93.0 63.4189 88.1750 1 4124 1.4537 2.4337 234 12:47:05 0.669 93.0 63.4132 88.1750 1.4618 1.4615 1.8206 235 12:57:05 0.836 93.0 63.4075 88.1750 1.4628 1.4652 1.6916 236 13:07:06 1.003 93.0 63.4023 88.0010 1.3386 1.4018 1.6317 237 13:17:06 1.170 93.0 63.3975 88.0010 1.3192 1.3566 1.5575 238 13:27:08 1.337 93.0 63.3905 87.8620 1.3553 1.3442 1.5174 239 13: 17:10 1.504 93.0 63.3857 87.8620 1.3568 1.3373 1.4926 240 13: 47:14 1.672 93.0 63.3806 87.7580 1.3598 1.3341 1.4774 241 13:57:15 1.839 93.1 63.3743 87.6190 1.3649 1.3340 1.4692 242 14:07:16 2.006 93.1 63.3695 87.6190 1.3661 1.3347 1.4635 243 14:17:16 2.173 93.1 '63.3651 87.6190 1.3635 1.3348 1.4578 244 14:27:20 2.340 93.1 63.3589 87.4450 1.3623 1.3349 1.4528 245 14: 37:25 2.508 93.1 63.3532 87.4450 1.3645 1.3356 1.4495 ,

246 14:47:28 2.676 93.1 63.3476 87.3070 1.3663 1.3369 1.4473 247 14: 57:29 2.843 93.1 63.3411 87.3070 1.3991 1.3451 1.4569 248 15:07:31 3.010 93.1 63.3369 87.2020 1.3821 1.3485 1.4579 249 15: 17:33 3.177 93.1 63.3307 87.2020 1.3962 1.3542 1.4626 l

l i

l l

l l

1490H/ -13 1

MEASURED LEAK RATE PHASE GRAPH OF CALCULATED LEAK RATE' AND UPPER CONFIDENCE LIMIT I

S N -TO P - 1 LEAKRATES VS TIM E 0.80  :  :  :  :  ;

- _ _ _ _ _ _ _ _ _ _ - - - - - - _o w eAlld Le _ _ _c_k_ R _ _a_ te . , _

0.70 --

b 0.60 -

--l ,

>- f 0.50 . UPPER CONFl0ENCE LIMIT w  % -

0.40 --

~  !

CALCULATED LEAK RATE 0.30 -

t 0.20 --  !

L C .10 .  ; i 0.33 1.23 2.13 3. o'3 3 93 4.83 5.7'3 6.63 HdURS (

I i

/!GJRE 3 l l

1490H/ 20 ,

)

MEASURE 0 LEAK RATE PHASE GRAPH OF TOTAL itME HEASURED LEAK RATE AND REGRESSION LINE TOTAL TIME LEAKRATES VS TIM E 0.80  : '

0.70 --

0.60 --

i"i 0.50 -

5 o w!A5UREO ',En uit

• AA =b ^

0.40 -

VU \ 's ~ ~~^ ~

~_ -

4E:RE55I:N .Ist 0.30 +

~

0.20 +

,i l

0.10 -

0.33 1.23 2.13 3 03 3 93 4.33 5. 7'3 6.53 HOURS FIGURE 4 i

1490H/ -21*

NEASURED LEAK RATE PHASE GRAPH OF ORY AIR PRESSURE  ;

'h L i

CONTAINM ENT ORY AIR PRESSURE VS TIME  !

i 63.65 ':  :  :  : -

i t

63.60 -

63.55 -

,. j 1 ,

< 63,50 - {.

g i

4

63.45 -

i i

63.40 -

l

~i -

i 1 i

a 63.35 --

I i

{

63.30 . -

I

0.00 0.90 1.80 2.70 3.60 4.50 5,40 6.20 l i HOURS l

(  :

.i j r! cure 5 I l i

< 1 l 1490H/ 1  !

s i

I '

MEASURED LEAK RATE PHASE GRAPH OF VOLUME WEIGHTED AVERAGE CONTAltdMENT VAPCR PRESSURE CONTAINMENT VAPOR PRESSURE VS TIM E 0.4920  : '

0.4900 -

+

0.4880 -

• 0.4860 - I 2 1 I

0.4840 - -

0.4820 -

l l

0.4800 1 I i 0.4780 ,

D.00 0.90 1 80 2.70 1 60 4.50 5.40 6.2 J HOURS FIGURE 6 i

1490H/ - _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

),

MEASURED LEAK RATE PHASE-

. GRAPH OF VOLUME WEIGHTED AVERAGE CONTAINMENT TEMPERATURE CONTAINMENT AIR TEMPERATURE VS . TIME 93.15  :  :  :  : -

93.10 --

93.05 --

u e 93.00 --

M .

92.95 -

f 92.90 -

92,85

• 92.80  : >

0.00 0.90 1.80 2.70 3.60 4.50 5.40 6.30 HOURS TABLE 7 1490HI 5

INDUCED LEAKAGE PHASE GRAPH OF CALCULATED LEAK RATE f

i t

BN-TOP-1 LEAKRATES V5 TIM E -

i 1.50 ' '

UPPER BOUNDS 1.70 -

, i 1.50 -

>- t 5 -------------------getLeckRete Tar  ! i

= 1.50 - - - - - . . -

1.40 "

CALCULATED LEAK RATE +

i 1.30 -

LOWER BOUNDS ,

1 1.20 -

1.10  :

O.33 0.83 t .33 1 S3 2.33 2.83 3.33 3.83 HOURS FIGURE 8 1490H/ I

INDUCE 0 LEAKAGE PHASE GRAPH OF TOTAL TIME HEASURED LEAK RATE AND REGRESSION LINE l

TOTAL TIME LEAKRATES VS TIM E -

. l i 1.80  :  :  :  :

1.80 -

UPPER BOUNOS 4

1 1 70 --

1.70 j l -

1.60 --

p 1.60 ,

t-6

= 1.50 -

1.50 E

I l u!.asuato 'rac an !  !

1.40 --

1.40 V

EcatsS:cs '.!NE 1 1.30 --

• 1.30 I LOWER BOUNDS  !

! 1.20 +

1.20

' 1

)

l 1.10 -

j 0.33 0.83 1.33 1.83 2.33 2.83 3.33 3.831 10 ,

l

] HOURS I c

1 l l

l FIGURE 9 i l

l a ,

, 1490H/  !

INDUCED LEAKAGE PHASE GRAPH OF VOLUME WEIGHTED AVERAGE CONTAINHENT TEMPERATURE CONTAINMENT AIR TEMPERATURE VS TIME 93.15  :  :  :  :

93.10 --

I 93.05 --

l l

u e 93.00 --

~

I Ed i,

92.95 -

t 1

92.90 -

I 92.85 +

92.80 0.00 0.50 1. 0'0 1 50 2 00 2. 5'O 3.[0; 3.0'O HOURS l I

l FIGURE 10 l

l 1490H/ 27 1

i INCUCEO LEAKoGE PHASE GRAPH OF VOLUME WEIGHTED AVERAGE CONTAINMENT VAPOR PRESSURE b

i CONTAINMENT VAPOR PRESSURE VS TIME j a 1

0.4845  :  :  :  :

a  : -

{

i .

1 1

0.4840 - -

I ,

q l 1

I 0.4835 - -

L i

a '

i t

< 0.4830 - -

Z ,

?

0.4825 - k i

1 I.

f 5

0.4820 -- 1 l

t 0.4815 - '

,  ! l 0.481g.00 0.50 1.00 1.50 2.00 2.50 3.00 3.50

) HOURS

i i

i i

l i

1 1490H/  :

1 1

e INDUCE 0 LEAKAGE PHASE GRAPH OF CRY AIR PRESSURE 3

CONTAINM ENT ORY AIR PRESSURE VS TIME t

i 63.44  :  :  :  :

• 63.42 -

1 63.40 --

I i

63.38 "

J I

63.36 -

63.34 -

4 l

i

63.32 - ,

j -

4 63,30 .

j  :

0.00 0.50 1.00 1.50 2.00 2.50 i

3.00 3.10 4

HOURS s

4 I

l 1

FIGURE 12 i

I

) 1490H/ 29-i

GRAPH OF REACTOR WATER LEVEL THROUGH TESTING PERIOD RX VESSEL LEVEL VS TIM E 92.00  :  :  :  :  :  : .

91.00 --

I 90.00 --

1' d

= 89.00 "

d _

88.00 -

4 1 6 87.00 --

l f

86.00 --

85.00 .

0.00 1.60 3.20 4.80 6.40 8.00 9.60 I 11.20 HOURS FIGURE 13 1490H/

GRAPH OF TORUS WATER LEVEL THROUGH TE5 TING PER100 4

TORUS LEVEL V5 TIME 0.10 ,

0.00 --

-0.10 --

d

= -0.20 --

h_!_!

-0.30 --

-0.40 -

\ --

x

\

\

-0.50 + '

x -

-0.60 -

0.00 1.60 3.20 4.80 6.40 8.00 9.60 11.20 HOURS FIGURE 14 1490H/

SECTION E - TEST CALCULATIONS

/

Calculations for the IPCLRT are based on the BN-TOP-1, Rev. I test method and are found in the functional requirements specification CECO Generic ILRT computer code document 10# SSS-88-002 Dated April 1, 1988. A reproduction of the BN-TOP-1, Rev. I test method can be found in Appendix C. In preparing for the first Quad Cities short duration test using BN-TOP-1, Rev. I a number of editorial errors and ambiguous statements in the topical report were identified. These errors are presented in Appendix E and are editorial in nature only. The Station has made no attempt to improve or deviate from the methodology outlined in the topical report.

Section 2.3 of BN-TOP-1, Rev. I gives the test duration criteria for a short duration test. By station procedure some of these duration criteria have been made more conservative and in some cases these chsnges may be required by regulations.

A. "Containment Atmosphere Stabilization" Once the containment is at test pressure the containment aimosphere shall be allowed to stabilize for about four hours ( 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> re.;uired by Quad Cities procedure and' actual stabilization: 17 hrs, 57 min)

The atmosphere is considered stabilized when:

1. The rate of change of average temperature is less than 1.0'F/ hour averaged over the last two hours.

DATA SET

• AVE. CONTAINMENT TEMP. AT 180 93.153 174 93.237 0.084 163 93.294 0.057 average: 0.0705'F/bour

• Approximate time interval between data sets is 10 minutes.

or

2. "The rate of change of temperature changes less than i 0.5'F/ hour / hour avsraged over the last two hours."

(Not required if A.1 satisfied)

8. Data Recording and Analysis

1. "The Trend Report based on Total Time calculations shall indicate i that the magnitude of the Calculated leak rate is tending to stabilize at a value less than the maximum allewable leak rate (L A )..."

By Quad Cities procedure the cair C. 1 leak rate must be less i than 0.75 LA . The actual value r 155 LA , stable, and i decreasing (no extrapolation requis I i'

and 1 ,

] 1490H/ 32 l 1

2. "The end of the test upper 95% confidence limit for the calculated leak rate based on total time calculations shall be less than the maximum allowable leak rate."

By Quad Cit"les procedure the upper confidence limit must be less than 0.75 LA . The actua?, value was 0.4621 L A-aC$

3. "The mean of the measured leak rates based on Total Time calculations over the last five hours of the test or last 20 data points, whichever provides the most data, shall be less than the maximum allowable leik rate."

By Quad Cities procedure this average must be less than 0.75 L.A The actual value was 0.4194 LA for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

1.ng 4 "Data shall be recorded at appro>imately equal intervals and in no cace at intervals greater than one hour."

At Qusd Cities data scan's are automatically performed on 10 minute intervals. No data sets were missed or lost during the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test period. No computer failures were encountered.

1"$

5. "At least twenty (20) data point shall be provided for proper statistical analysis."

There were 38 data sets taken for this test.

Afi$

6. "In no case shall the minime.m test duration be less than six (6) hours."

Quad Cities' procedure limits a short duration test to a minimum of six (6) hours. The data taken during this test would support the argument that a shorter duration test can be condt.cted. All of the above termination r.riteria were satisfied in six (6) hours.

SECTION F - TYPE A TEST RESULTS F.1 Heasured Leak Rate Test Results Based upon the data obtained during the short duration test, the following results were determined: (LA = 1.0 wt %/ day)

1) Calculated leak rate at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> equals 0.4155 wt %/ day and declining steadily over time (<0.7500 wt %/ day).

1490H/ -33

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

1 I

'2) Upper confidence limit equals 0.4621 wt %/ day and declining (<0.750 wt

.%/ day).

3) Mean of the measured leak rates for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (32 data sets) 1 equals 0.4194 4t %/ day (<0.750 wt %/ day).  ;

, 4) Data sets were accumulated at approximately 10 minute time intervals

a. and no intervals exceeded I hours.

5) There were 38 data sets accumulated in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> measured phase. .

i 6) The minimum test duration (by procedure) of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> was successfully accomplished (> 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />). ,

.c .

F.2 Induced Leakage Test Results j

1 A leak rate of 8.82 scfm (1.0814 wt %/ day) was induced on the primary containment for this phasa of the test. The leak rates during this phase of  !

j the test were as follows.

BN-TOP-1 Calculated Leak Rate 0.4155 0.4155 i (Measured Leak Rate Phase) 1 Induced Leak (8.79 scfn) 1.0814 1.0814 Allowed Error Band +0.2500 -3 2500 4 1.7469 1.2469 ,

BN-TOP.1 Calculated Leak Rate 1.4626 wt %/ day I (Induced Leak Rate Phase)

! l The induced chase of the test has a duration criteria given in Section  ;

, 2.3.C of BN-TOP-1. The test duration requirements are listed below and i were satisfied by the f.est procedure and the data ana'ysis:

i i 1. Containment atmosoneric conditions shall be allowed to stabilize for '

j about 9ne hour after superimposing the known leak. (ac?ual: I hour).

i  :

j 2. The verification test duration shall be approximately igual to hal'  !

i the integrated leak rate test duration. (actual: 3 hc Jrs for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> i j test) ,

j l 3. Results of this verification test shall be acceptable provided the  !

) correlation be': ween the vvrlfication test data and the integrated leak l 1

rate test data demonstrate an agreement within plus - mi~ s 25  !

percent. (actual: see results above) l I

! I i

1 l

1 i i  !

1490H/ 34.

1 I

' l

F-3 Pr^-Operational Results vs Test Results Past IPCLRT reports have compared the results'of each test with the i pre-operational IPCLRT, performed April 20-21, 1971. Over the'last 16 years, different tist equipment, sensor locations and number of sensors, test methods, and test duration have been used. This test yleided results that compare favorably with recent tests and demonstrate that there has been no substantial deterioration in containment integrity. l TEST DURATION CALCULATED LEAK RATE STATISTICALLY /VE. ,

TEST DATA (HOURS) (BN-TOP-1) LEAK RATE (Ar ./ANS) 4 August, 1971 24 Not Available 0.1112 i 1976 24 Not Available 0.327  :

1980 24 Not Available 0.449 ,

1983 74 Not Available 0.464 February, 1984 24 Not Available 0,385  :

May, 1985 24 .3670 0.4071 October, 1986 8 .3225 0.3294. L June, 1987 6 .4155 0.4141 -

i I

F.4 TYPE A TEST PENALTIES During the type A test, there were a number of systems that were not drained and vented outside the cov;ainment. The isolation valves for these systems or, penetrations were a.ot "challenged" by the type A test. Even though these systems would not be drained and vented during a DBA event, historically, penalties for the1e systems have been added to the type A test results.

W 4

1 1490H/ 15-L-

AS LEFT MINIMUM PATHWAY LEAKAGE SClH WT1/ DAY ,

Primary Sample Valves

• 0.00 0.00 ACAD 3.30 0.00674 RHR A 2.45 0.00500 '

RHR B 1.65 0.00337 feedwater- r 4-DNFOS 0.75- 0.00153 DWEOS 0.40 0.00082 t RCIC steam exhaust 3.88 0.00792 RCIC drain 1.65 0.00337 HPCI steam exhaust 3.22 0.00658 HPCI Drain 2.10 0.004t9 All electrical penetrations _0.20 0.00041 ,

Oxygen analyzer ' .'16.0 0.03268

, Tip purge check valves 3.0 -0.00613 CAM.. Isolation Valves & Panels 0.00 0.00 MSIV drain valves 0.00 0.00 .

SRM/1RM Purge 0,00 .

0.00 Total 38.60 St.Tii 0.0788.wt%/ day '

J F.5 EVALUATION OF INSTRUMENT FAILURES Prior to the start of the test, RTD No. 8 located behind the biological '

snield, failed. The instrument spiked high, then read high. The failure was noted and locked out approximately one hour forty minutes prior to the measure phase. t The effect of this instrument failure on the instrument error reported in  !

section B.3 of this report is minimal.  !

The system accuracy uncertainty becomes 0.1801 wt %/ day and the system repeatability uncertainty becomes 0.0265 wt %/ day for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test.  ;

f 1 =

l T 4

i i

)

i i

! 1490H/ l i  !

c F.6 AS FOUND TYPE A VEST RESULTS The fcilowing table summarizes the results of all' type B and C testing, as

• well as the IPCLRT results to arrive at an "As Found" type A test result, i Since the total is more than the 0.750 wt 7./ day, the present scheditie of  :

performing a type A test every refuel outage must be maintained.  !

l 4

SUMMARY

OF ALL CONTAINMENT-  !

j LEAK RATE TESTING DURING i UNIT TWO REFUEL OUTAGE l SPRING, 1988

],

i' AS FOUND (SCFH) AS LEFT (SCFH) [

MINIMUM PATHWAY MINIMUM PATHWAY l j LEAKAGE 4

LEAKAGE l

) (1) MSIV's @ 25 PSIG 17.28 17,28 l

(2) MSIV's converted 27.30 27,30 I to 48 PSIG' l I

(3) All Type C Tests '

1511.84 64.94 l (Except MSIV's)  ;

.: (4) All Type B Tests 12.5 12.2 f 1

! TOTAL (2 + 3 + 4) 1568.92 121.72 l l l

{ (1) Type A Test Integrated j

! Leak Rate Test) = 0.4155 wt %/ day (

l (2) Upper Confidence Limit i j of Type A Test Result 0.4621 wt %! day l (

1 (3) Correction for Unvented l j Volumes During Type A Test 0.0788 wt %/ day l

l (4) Correction for Repairs  !

{ Prior to Type A Test 2.956 wt %/ day (1568.92 121.72) l (As Found - As left) 489.59 l (5) Correction for Change 0.000 wt %/ day in  !

i Sump Level! I 3

l TOTAL (2 + 3 + 4 + 5) 3.497 wt %/ day (As Found ILRT Result)

)  ;

• Leak Rate at 25 PSIG converts to Leak Rate at 48 PSIG using conversion i ratto of 1.58. REFERENCE ORNL - NISC - 5. Oak Ridge National Laboratory, '

i Aug. 1965, page 10.55. l l 9 j 1490H/ .

i 4

l l

l APPENDIX A l TYoE 8 AND C TESTS l

Presented herin are the results of local leak rate tests conducted on all .

peretrations, double-gasketed seals, and isolation valvts sir.cc the previous IPCLRT in October 1986. Total leakage *or double gasketed seals and total leakage f or all penetrations and isolation valves following repairs satisfied the Technical ,

Specification limits.  !

l

\

I i

l l l l 1490H/ l I

b 1

i 015 100 51 REFUEL OJTAGE LOCAL Revision T LE AA RAf t it$1 SteeAARY un 1941 o UNIT /# ,f APPROVED <

tist 6TntCTV

,f ys itm stAn suPv. A /a -d./y /-,

OegaAri=o f ac. , s e SEP 091987 f 0 C,0 $ R.

AS FOUeJSCFHJ ASL1(f_(SCFH) __

l valvtfS1/ ulNi M WAAI M__ ulNI M uAAI M

__0E SCfti Pf lom i Pf 4E_TRAfl0N DAff TOTAL PATHeAr PATHeAv Catt TOTAL PAtNeAr 9ATHeAi,

'A' usly I A0 gg3-1A,2A h N!3 M 1/73 l3W lWe pl7 Yf I fpf l1# l i 'e' usly l A0 203-18.?8 fv /syi 'r t/ I ; J I  ! 9 // ly ,# 14. (/ 12.3# 1Y0 l l 'C' WSiv i 40 ?O3-1C.?C .199J.yl(1/ 13 W l (. 9 / Iw, p l (it IiW I r_10 l

0iusiv i A0 203-10,20 IV-rp y l.2.48 1 /./r 1 J_3 0 INg;-Je ! / /s- l ;', 3 e l total 17.27 TOTAL, / 7 .2 7 _

TOTAL CORRICTED

• E730 torAL CORRICTED

• y 30 1(<* Vf it.3-21 6 0 16o W5L DRAIN 1WJOA? 14-uMl (6 Vf1 J2/3 10.0 l PRiuaRf SAMPt( l A0 220 4A,45 ls 2 jtl 0 0 1 00 100 lc [th! 0.0 1 0-0 t. [

'A'_FitMAttR i CV !?On58Lj24 Ivar14 fff 21 h P. QfeM[-y MI 3; ( l / 9/" l ![.1

'B'F(EMATER I CV JfQ;$88 a6_E8 iM gl f *d. Il 970 / Lt9a / 1(f *1rf 2 s r 1.4 rP 8 12,eMli RH4 TO RADeASTE I u0 1001 20,21 f f,1fA 0 o 1 o .7 13_o lyggtLo o I o (1 13o l

'A' De SPAAf I W 1001-23AJ6A ledIfl 01/ 1 # /t' I dJr lyn eio n 1 0/9 10.J,7 [

I

'A' u Refuma 1 WO 1001-794 1v 4X1 vf I ) Jr i 45 im y195 1JM i4r l

.) 'A* . TCfttJS C00LihG SPRAv l @ 1001-34,36,374 !Y-f ? H /./2 1 0 v/ l/JR y-+ rid #a i c.so I/.a L j i 'B' De_LPe r i W1001-238,768 If 11Ef_'/J f Ij2 I ( ,'J f% 9 71 e r

• 1 7 ; ll. Iejv (

l ,'.B ' H Rt f um i u0_1001-?98 leJ7g Jd7 l / 3 */ I J ,9 7 g og; g I /a Y I J PLl

'B' 10RUS_C00 QNGL5 PRAY l _W 1001-34,36,378 1929.m{ # #1 1 O f/ 1 / PA l' A .yL/,_f J. I 6 fe I / f([

PAGE TOTAL l ha ljyag e7l g,qvt /t'rs.(17 l hA l (tACEPT WSIV'$) l 1 l 1 _1 l9 P 7Ill f I7 lN 77' i 10 /01(J s 1- .

I 4

l i

1 d

R(FUEL OUTAGE LCCAL QTS 100-51 LEAR RATE itST $1Ae44RT Revision 7 A $ F0uej SCF,HL.,_. __. .

AS Lf FTj$CFH1__ _l t VALVE ($)/ WINitRAI 4AA414Atl WINit4M I4Mit4As I

_0($CRIPTION P(N( TRA f _ ION CATE _ TOTAL PatHeAT PATHDAY DAff TOTAL PATHUAf PATHOAM j 1 WJP).1,4L50 ly n af 0 0 10,0 130  ;

$ Hut 00sN_C00QtoG .

- ff / tei l s 1 1/,7 f f 3fLl HFAD $ PRAY l W0,,1001 60_ 63 Mr4M 0.5710 JT I357 IM ap4 d.S 7 ! t'. 2f I d.f 7 i Clin UP $uCTION I WO 1201 7.5 Mjf t / 3 I I f. 95 ld3/ If ? fri_/,t f_.1 o W I / PP i RQlcSTE44fjyf(L, 1 @ 1301-16.17 1%7tl 0 0 7 f o_ d V l Qv7 C tr fA /.f Y l 6 7) f/f9 l RCic SifAad 1s.HAU1T 1 CV _130141 14 n ).% 7.?r i 3 ff I " N* INel 7 75" l 3 Jf' I7.75 l Rg1C_v&C PtasP_ f 4. I CV 1301 A0 11% #13 3 I/(S I 3. 3 INel 3.3 1 /. fr 13.3 l Qe/tqmu$ PURGE _$yPPLY l A0_,1_6.01 0 21.77.55.5614-n if1/ V VS 1 7. O I /9. &s IF-/s PJ/Y.tr l 'L;3 l/F 4_f l i ts/ TORUS Punct it l A0 1601-23,24.60 l l l l l l l l 1

! l 61.62.63 II 'O 0 # 1 OO f I #'# IT f'F l d 0 1 00 GOO g l

'A' TORUS ttNT l A0 1601-204, i l i j l l l l l l CV if41-314 I I l l

" l ## l 8# l

_l I 4 'B' TORUS vtNT l A0 1601-208 l \ l l l l j __ E vj 601-318 I E#Ulf lY l l ?'N l*## 9 U l IY l9 f _l I 1 7 j ts/t0RUS PURGE 1 A01601-57Ja_A9 i'/4 nl 0 4 d 1 0.30 1/(> IP a >A # (o I O So i v fo I

Ce_ft,00R_0RA,1,N $ w I A0,000 R 4 JJ IVit Is4 Yo 1 '/ o 1Yo lf-Y1(1/.fc.1 # 77 1 / f# l

] Ce (Q_cs yt __ i A0 N01 15, 16

_ 193#1 o f I o */ 1of IP # #l S P l d. F id ? l b 1*PCLSTLani.SUPP_LL_

- _LW 00'* 4 b n'*!! !ShI* 3 I ! !E. Lo? $

- I4'"I ht1 E 5 1 6 'E IAl 1 Hr;!_StiAW At_ . _ . LCv_2301 45 It'-/o m f y1 ! J J2 l f._aJ_Jt3; gin 3eL L Lt t i Q L i HPCI tstat4_PQt it i CVJM1J4 IV-tjPl K A I J./ lj_Utrfid Z_Gy / l Vl_ ]

De lesje aAAllC 1 A0 47?0. 4F21 M2 Dio,As i o /r I AJ_jJffgi o 24 l e e s- !4/L;

' Pact rotAt -=4 ## D M 7 # 00 s,- .1..)7l5? 15 f f.R.37 l ~

SEP V') 1987 OCO$R

• J w tav...c) 2 haL,A.

,, y ' g g a.p wisi)....< J.ustt mis o 10/Olf as  !

J 4

[

i l

l .

REFUEL OUTAGE LOCAL 8115 100 31

't AR AATE fist StasaA4f

. , w sion F ,

1 tsvi t / Uf' j AL F0 Lee ($CFMI AS tl Ff ($CFH) 1 VALVffSI/ ulNitem laulM_ ultletal _WAn llam I ._ M MA2119N P(ht f R A f_ ION DAff .f0fAL PADear PAfteAT Daft TOTAL. PATHg4T PATHg4f I

Q2 #"Al'II" I#S88086024 ls'. I M J .0 l o.3 12.0 i f 3 dri / .0 1 00 l_i2 o l j 9 2 ""'I' Jim IJ0Js018.86006 tr 1 fe l /. S' Iao I /.5 Ir O r t /.S" I oo 1 /.S l

] j 9, ANAL]Em 1 AQJ602QJ6,9?C h 3 fri /J d' l Jf I /v 0 IC v trl // # l // 0 1 /jA,,,)

Q2AhALT2fA I A0 46010. 84020 ist-J ftl To i '/' O lfa lO 2 m 1 9, o I */ # To l 9 7AN_ALJJtm i 40_t803. 8804 It-&N'l 0/ /2 l o f I A 10;/2 li-/t h4 /,( l e. a i // Wl p 11M1 73b /8 M.,.t 11 d # l0o I

flP BALL valvt Ido (.f fyl v. 3 1 4 3 l oj_ l q fir BAtt vatyt LT h 73?.re ILLW1 i d Ie0 10o ICAppl #_ J l00 1 d. 0 l t 1 IIP 88LLVALyf 1Thd "G7 /O If iJyl // / l /J. / I // / If is,(( l O.0 19) I# 0 ( ,

I /. o 1'2 '

j fJP_BALLVRif I thi 717- /t li il frl i 0 I/o IT-e 21 /. 2 LLL I i fIP BALL VA6 vt LJ)>$ 737~# _lig@l2 A i 1. 2 f .J 2. 16ffg[0_A IOa _ j^U

, flP PURCE E CA. l 700-743 WJ arl 3 o L1. 0 1 1_o Irgtpl 10 i La {74 l i

QAW l 59_Z499 14.7A Iv >v 91 04 1 00 I .* O IV 42 0 o 10J l31 l t

QAu I so 2499 18Je htfrL o.0 1 00 1 0o w,* JM d.o 10o 13a  !

(88 U4J_4999AJA Y stz1. 0.0 i se 13 0 + y.scl o o iOo I a.o  ;

]

i 98W- 159)dM-JI!d! tY/Yfft o # 130 I d.P kv N..Y10 0 I oo t o.o l ACAO ,LA0jty-; A,g)A ty ry gj_L; .y 10 o JJA g ,g,y aA y,yyy sp ,, , i S A Q y W;;

A;AD 1 A0jp918J)8 ly pyg J./ 10 J 23flf ? A 8 }q v gg};,f ly y J 3 8 g f,9 dd~g i A.QAD lAQJjpgJA,p44 lggggj f f gy g J A } ) 7 d egy.j y pg , (; y JA )37 Av4 j ' CAD LA0_U_99.3eJ48 _,_itgJtLt.J [g 2 Wi g.y_J S gg,3 g, Jggs ;

ACA0_ _LAQJ599 4AJA lf iftLO.? l #.7 JLA fd Ig.g.g 0,7 jp y vd I d.O Ti 1/ p w/ g /.O jyI,g j J Aj j TJ']g ACAD_ _ 1 A0 J)9 h48.84 le g g / o l . _ _ _

PA0f TOTAL l ha b bbk a na

[YE h7 _).__

j $[9 09 ($$/

j to / O SA

• OC0$R '3-a s

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UNII ,/_d i

al ~F0use (548wI as tl Ff 1Ecrh) vatytt$1/ a einiiium "~iiGT~~m- miniu m nann tum ,

JsCRiPfl0N Pf 4E fmail0N Daff!70 fat PaDe la Pa_fwear Deft 70 fat Pafveng, Pafwear i igt]yur_qt Hafoi i I.t #W/r W1 o o 1 00 l g.o g.t,.ac. I O n 10o_100 I i i ce p ts Haf04 1I4 Ite stijs a I po  ! o. d t,.is a l e o I c. 0 1 3,e l j C5c Haf 04 I I-6 l"-d ?M o o 1 /s. O Ieo Islefrl 0 o 1 0 i,f I# 0 l i tip PtntimAfl0N_ l I,jia te/i Ei 0. T I 0. f I## 15. = 1>l 0 f I O 4" l0f 8 ,

I flP PENETRail0N 1 I-)f! ,

S k /Y Fi d.O l 8,0 lo9 lCAwi 0 0 l#o 1o0 l flP PfmEfftafl0N I I 35C t etJf! v 0 1 0.0 100 1 wsloo 100 100 l i flP Pf4ETRail0N 1 I 350 fr w #1 o o I d.o I 0. # h-ev ar-l 0 3 12 0 I03 ) i flPP(WETRaftQN ,

1 I 35E k /f ifl # o 1 0# l C .? k .+)pi #14 10 o l #,,p l i flP PfNifeat10m {I-357 fr tv Jf1 0 0 10d I9o !Cr* hi o 0 Ioo I80 i i i flP PEN (frail 0N I I 35G ff./V fft 8 o l 80 ldO M 4 Jrl do 1oo  ! O (,_ l ,

i 70RiJ1HatCM i X-200a ly c.y1 0 o I oo ipo Ipi,#1 0 0 1 Oo _I O q,,,_I c

!0Aus haf 04 1_A-2006 IMtLO o 1Od I_ O ' jf,c,jj-1 Or> 1 OJ l O J_ l '

OR2sttt HL40 1 ---- In sfl O.J l O.3 In3 IO"-tri O o 1 o. 0 1 037_ l l l M an tui i.wsP MafCH I st-1 H a ni O.4 1 0.0 1. 3 o t.a n] 00 1 >c I J.o I I

) wr4 tuo insP wafgu I se.rt r , - nt o ,3 1 0.o 1 0 <> ls.c. n l 0 0 I Js i J.- l

) M an Luc insP >Afcx i st 3_ !w o c 1 po 1 eo isn ul Oc ! o., 1 .+s . 1 3 4 m uo i s, afC- i st.4 s ,mi , , i o ,, ioo it.o.w u i ., , I o3 _I i w aR tuQ 145P MafCH i st-$ IT-8 tyl O p l 2,0 1 0J lt.ql e o l Jy j o. 3 l

(

SHi[Rj h msP MafCH IS 6 It a fq a_0 t oe i e0 1atL) 3 l J.o 1 00 I

[

W aR tug INSP MafCH __ 1 h ' M S yl O 3 1 d. 3 10 1 1:1y1J3i a3 L o_.1_ t ,

I sof f R tuc insP HafCM Lskt IDW4514 0 10o_ i o o juhl 3 0 I J 0 1 0.0 i E f APFHuvLD l lp'^3 l f, y I f,z l l l ry, g l q ,7 1 ract t0f at i _.=a _1 l i l _ y_J i i _l g g g, l scio u,ns OC0s4 -4 r

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{ valvt(su uimi h iiiliiim Tisi71 ($e)mani44r

__QtsCRIPfiON i ,_P[httRail(m D4ff TOTAL PatHeat Patwear Dart total Patwear Patweg,,

i WCH. PtWIRATION I I TA ____ !ar /t PLO O I 00 l go i t- y tti 00 1. 0.0 l oo I l

W CH, PtNetu tion 1 78 kerv fri 00 I Od i Fo I V.i'vs1 0.0 1 00 1 00 l j Wf 1 E NETRAfl0N 1 1 7C }Ws ?rl 0 0 1 04 l_ 00 It iijf1 C o 1 00 1 00 l

W CH ._ Pt NE TMil0N i 70 Is.i+rl 0 0 1 c' O l oo ly/ wi 0 0 1 Oo 1 o a_l i

WCH Pt% furl 0N I I-8 , ly-v W1 0 0 1 00j 03 -

Iv.sv.s,4 0.0 1 0.4 1 0.o l l J w % MNatutiON i I 94 lY sv #1 0 0 l oO l 0.O fr-jy Ml O O l 0.0 100 l l WCH P(NGRAffM, I I-98 lY <rWI O @ l0.9 l 09' 19.// Ni ( 7 i o 7 10f l j WCH Pt%iRAttCw I t 10 It'-er f ri !.0 10o 100 lbkriOo10-0 I O C' l

, W oi PtN=TRatqpN I -11 t e i,-i+1 g 3 I O_ J l03 ly.ysgi 0 3 1 0 3 Ioy g I

WCH nwrRat:0N 1 -17 ly-,e-ei r e Iro Iea ly , M s o Iro Ife 1

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w CH M NffRAfiON l 1-13A ly- v fA J o I 0. O I J0 f t ev M O <> l 00 10O_ l .

W CH P(MTRail{4 1 I 138 IV ,t1Tl 0 'l I o. L l 0 'l 14j, h1 O .I. 102_ 1 0, ** l 1 W CH Pl%fRafiC4 1 1-14 l % rv {rt / V l /. Y l/Y Ivjv.sA / */ l p. 9 l/y l l W CH_PtW TRA U C* 1 8-73 IFnfri 0 o 1 0 0 1 01 liefi 0 0 1 0.o 100 I i

W CH Ptwinatica i -74 19-,,W 0 o 1 oo iJo I tw-nt e. o 1 0.a 100 1 [

l W CH Pi g tRatiCe 1-y 4,y hl 0 0 1 0o 1 00 IV-et &l 0,) 1 06 1 0, e l l l WCH _ M(TRAfigN I IJ6  !'r-4 gri C o LO o 10o pevdPio.O I 0.3 10 0 1

) w m>t w iu' LC*. . _ _ _ Li_36c Ivar*LO_3 1 01. I o 3._Jv-m o 3 1 4 3 i o. 3__ l J

W CM _N M T Ra f ica _ _ _L' 4 7 +2Jrl a 1 00 1 9 3 _ ly. r /r1 J o I 03 100_t ,

W M_P(MIRaIlON L' 17 IWv #1/ 4 i'Y I d '/ 1**/rf / v i e' L/+ i w CH fw rutica ___J .'s4 ity_wLtJ_ I 'J L 'l_.hgLd_1_LJ_1jl .. ;

I APhvuot0 I I sy,7 l fy 7 I I

/37 Ijg 7 I fg, 7 I g

Pact totat i _v_.1 ff7 f f Lqj i l ___l io cies, o s o 3 ,, s. I I

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A AS F.0Use 15QF,N) AU FT ($CFN) valvEts)/ uiNilaas inexltaal Yiilmas inAnime,_

0LSQLJPfl0N l M M TRA D ON___ DAff JQTAL PAIMWAf PAT 4Af DATI TOTAL PAINGAf_ PATHWaf IN]MI o Y l Q Y WcH,__PtWifRAft0N j I 198 _ ._l # 9' ly-Q j/l # 4/ I o. )' l O 9' l ufCTRICAL METRatION 1 2-100A la)/A 1 m /A 1 4 /d 1NA / IN - A l N A4 I w// I gt./L1

[

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. utCTRICAL PrW tRAtiON l X 19QE l#f */AM'l Ool C0 l00 ff-n nl M o l 0.o l_ O 8 l ;

J (gCtRiCAL _PtwrRAnce 1,.n.; 100s Ir., ret oa1 00 IoO tr-i.1 M a o 1 00-100 I j u f CtReqALEW rRAfiON 1 u 190c if s3 in o o l 04 I po fr st att o.o I a.0 10,4 i ,

(Lf CTRi(Al PtW TRafI.ON 1 IdQ14 IW//-fr! O.0 l # 0 J AC 19,# sfl oo I o.o lOo t QEQg&L PtWTRAlt04 1 1 1018 IV-/r-fri C.A l OO I C. O Aj/.pl 0 o 1 0. J l C. 0 l (LECTRICA(PtWtRail0N l_I.1010 If,3.g 0 0 _1 0.0 l 04 15.j M t o.0 1 Od 100 l ELECTRICAL Pt W IRAll0N l 4 102A l l l l l l l l l 4

jl.nli CHEAT I I I U/" f h/M i M I 7/d 1 DM i M/A I N!A I A#!I l  ;

ELECTRICAL PENETRAt60N l I 1000 l 6 l l l l l l l

j umit fe0 0 NIT) 1 I N# #' l i 'E 1 01 l i'4 1

1. ' I 0*E I 0'1 i j u fftRiqat Pt W 1RAfiON I I 103 IWityI o.0 100 100 1%iIrl d o 100 !00 l ,

EttCTRICAL METRAfl0N I t-1044 i 1 l l l l l l f

j juNit,t0_0en T ) I l*'#l ## 1 1 0d , 0 .4s ge/W, 0 0 , o.4 , at , t t g qtRiCat PfW tRaticw I 1qae lbs trl o o ! Ov Ioa 14 (11 0 o 1 0.o I c. 9 l L

ELECTRICAL PtWrRaf t(4 I t 10AC  % ,fri 0 0 1_o (8 iOo INi4M 0 0 !Oo 1 c 0_)

APPROVED Pact total I l

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W[liLif

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VALYE(!)/ OiNiiRAd '~iaEIidii OIiqiRAI

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tunit fe0_0NLT) i l l l (LECTRICAL et,NgfRAflgM i A 104P is81N o O L<LO Ioo k.tLM o o i Sa 100 i ELECTRICAL MNETRATION l 1 10$A l' ( l l l l l e

_LUNii ONE _0NLJ) l__ IN /4 i M/A 1 A//A I M/A 1 *J /A ! 4//A fl M M li l EttCTRICAL PENEtelATION l K 1054 l l l l l l .

(UnitQN(_0NLT) I l u/A l M/Al l 4/A l ajM lM/Ai g As/d 3 ^#/A ll h/A ,

(LEQTRICALMNEtRAfl0N _l t-10$C IV elf 1_d_p I oo I oJ 14-/egj,d,_o l dJ_l00 l ,

8 ELEJ1RICAL PENETRAfl0N l X 1050 l l l l l l l l DIt ONE_0NL])

l N/A l Al/A I P /A , b)/A l >>/4 2/4 l A)/4 l n/4 g i ELECTRICAL PEN!(TRAf tom l X 1064 l l l l l l l r funn tqomtvl 1 I '"Yl i C #

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othe test total es the sua of all page totals en the checklast (estleje II$1V's f rom all test totals). ',

i Rele.ence; Of 5154 8. "Determination el fotal Containment Leak Rate.'

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4 i APPEN0!X 8 l I

] TEST CORRECTI0t: FOR SUMP LEVEL CHANGES 4 .  :

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The total time treasured leak rate, given by the functional' requirements pacification CECO Generic ILRT Ccmputer Code Occument 10

• SSS-38-002 Dated April 1, '988 (see Appendix C1, assumes that the containment free air space is 280,327.5 ft3 at a water level in the reactor of 35", torus water level is

cro, aac that any charige in reactor water level is due to a water leakage

frrim the containment chJnging the free air volume. If the water leakage is

~

from the containment and due to the operation of the shutdown cooling mode of RHR to maintain reactor water temperature, this leakage would not be d

representative of accident concitions when shutdown cooling would be isolated.

During tne stabilization phase of the test considerable effort went into re I ftjucingtwrateofleveldeclinetoapproximately0.45

/hr 1r 1.40 GPM) that was experienced during the test. inchesSince

/ hour the(11.25 leakage a could not be reduced further and level indication for the suppression pool indicated that most of the water leasing the reactor was not entering the suppression pool, but leaving containment, the computer program option for including the vessel level in the leak rate calculation wab selected.

i The test verification during the induced phase of the test demonstrates j the accuracy of this model and the enange was completely explained to the NRC inspector witnessing the test.

A hand calculation, using a cord ete water balance, is included in this i Appendix to show that the leak rate reported is not $lgnificantly affected by i a Jere detailed analysis, including changing subvol ae free air space due to rater laaking from the reactor vessel to the drywell sumps and suppression pool.

To perform a leak rate calculation with a changing containment free air space, the diy air mass for each containment subvolume is calculated using the fol'owing equation. ,

t j Hi 2.6995 X Pi X Vj  ;

(Tj

• 459.69;  !

where Pj = dry air pressure in Ith subvolume,  ;

Vj free air space in the ith subvolume, and i j T . average temperature in the i th $Ubvolune.

The total containment dry air mass is given by the sum of the dry air l masses for all of the subvolumes.

11 l

Ht . I y, 11 4

, 1490H/ 43-J

The computed leak rate will be ene total time leak rate and is given by:

Lt = - 2400 X Hi - N'

~

H H'

where H' = dry air mass of the containment at the start of the test.

Ht = dry air mass of the containment at time t, H = duration of the test from start to time t in hcurs, and Lt = total time leak rate at time t.

i There are 3 subvolumes to consider in evaluating the effects of water leakage from the vessel: the vessel itself (subvolume 11), the suppression pool (subvolume 10), and the subvolume for the drywell equipment drain sump (OHE05) and the drywell floor drain sump (DWFOS) (subvolume 9). Any water leaking from the vessel in excess of that added to the sumos and suppression pool will be assumed to have leaked from the containment through the shutdown l cooling mode of RHR.

DATE TIME OWFOS* OWEOS*

06/21/88 0300 10 8.0 I 06/14/88 0315 24.0 6.2 Rate of level change 0.290 0.0373 >

(in/hr)

Rate of frte air vol -1.108 0.142 change (ftJ/hr);

'The sumps are assumed to have filled at a constant rate during the period i when the containment was fully pressurized. Each sump holds 1200 gallons and I is 42" deep, I The following table gives the entrapolated values of the subvolume free air spaces using the above data:

6 HOUR TEST INDUCED TEST SU8 VOLUME NO. (1) Vi t=0 vg t=6 vg t=0 vg t=3  !

I I 10.550 10.550 10,550 10,550 2 9,596 9,596 9.596 9.596 3 10,990 10,990 10,990 10,990 4 3,783 3,783 3,783 3,783 5 24,125 24.125 24.125 24.125 6 32.265 32,265 32,265 32,265 7 27,618 27,618 27,618 27.618 8 26.071 26.071 26,071 26.071 9' 8,808 8,802 8,800 8,797 '

10* 119,530 119,658 119,700 119,714 1 11' 5,146 5,215 5,235 5,266  !

l 1490H/

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V9 8,901 -1 DWF05 X 1200 X .13368 '-I OWEDS X 1200 X .13368 l l

l ( 42 ~ / ( 42 i I

i V;o - 119.268 - 863.75 (ft3 ) X Torus level (in) l Tn i

! Vil - 6571.0 - 25(Level -35) l L i Using the subvolume vapor pressure, subvolume temperature, and the i subvolume free air space, the dry air mass for each subvolume can now be  ;

j calculated. The fo11owin9 table gives the necessary data for the start of the f

test as 04:05:31 on 06/13/88(Data Set No. 181).  !

1 ORY AIR SUBVOLUME l i SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS

• i NO. (PSI) (PS!A) 'F (Ibs. mass) [

1 .473 63.620 104.456 3211.72

! 2 482 63.$11 110.334 2890.76 i j 3 .482 63.011 109.135 3317.68 1 4 .482 63.611 109.428 1141.43 f 1

5 .494 63.599 106.536 7314.94 i 6 .496

• 63.597 101.419 9871.98 i 7 .458 63.635 96.697 8526.97 l d

8 .443 63.630 86.329 8204.11  ;

l 9 .443 63.650 87.720 2764.68  :

j 10 .481 37,818.08 63.612 83.287  ;

I 11 2.264 61.829 130.436 1455.46 j t

4 1 11  !

' w' t wi 86,517.81  !

i:1  ;

I  !

l The fo11owin9 table gives the necessary data for the end of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> i j test at 10:06:43 on 06/13/88 (Data Set No. 218). '

l ORY AIR SUBVOLUME l SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY A!R MASS ,

, No. (PSI) (PSIA) 'F (1bs. mass) 4 l 3

1 .458 63.522 102.829 3216.05 I 2 467 63.513 109.441 2890.84 l

l 3 .467 63.513 109.030 3313.18 i

! 4 .467 63.513 109.397 1139.73 I

! 5 .481 63.499 106.680 7301.59 I I 6 .481 63.499 101.512 9855.14 I 7 .446 63.534 96.630 8514.46 l 8 .444 63.536 86.203 8191.31 .

i 9 .444 63.536 87.616 2758.38 i 10 475 63.536 83.043 37,796.08 j 11 2.218 61.762 129.686 1475.25 l w6 - 86,452.01

)

l

1490H/ l l

}. l

The leak rate for the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> %est 15:

L6th , . 2400 x 86.452.01 - 86.517.81 6.020 ,

86,517.81 L6hr . 3032 wt % / day (compared to .4072 computed ignoring sump level changes)

The following t:ble 91ves the necessary data for the start of the induced l phase of the test at 12:06:56 on 06/13/88 (Data Set No. 230).  !

ORY AIR SU8 VOLUME SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY A!R MASS l NO. _, (PSI) (PSIA) 'F (1bs. mass) i 1 .456 63.463 103.329 3210.21 2 .463 63.456 109.392 2888.49

. 3 .463 63.456 109.154 3309.48 l 4 .463 63.456 109.580 1138.34 5 .476 63.443 106.780 7293.86 i 6 .479 63.440 101.555 9845.23 7 .443 63.476 96.648 8506.41 8 .447 ' 63.472 86.206 8183.01 9 .447 63.472 87.621 2754.95 10 .475 63.444 83.051 37,772.47 11 2.234 61.685 129.949 1478.40

, start H = 86,380.85 induced f The following table gives the necessary data for the end of the induced phase of the test at 15:17:33 on 06/13/88 (Data Set No. 249).

ORY AIR SUBVOLUME ,

l SU8 VOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS l l

NO. (PSI) (PSIA) 'F (lbs. mass) 1 3

1 .456 63.359 104.369 3199.04 ,

j 2 .463 63.352 109.674 2882.33 -

3 .463 63.352 109.394 3302.67 l 4 .463 63.352 109.883 1135.87 5 .477 63.338 106.971 7279.33 -

I 6 .478 63.337 101.668 9827.26 l 7 .442 63.373 96.703 8491.77 '

8 .455 63.361 86.166 8169.30 i 9 .455 63.361 87.740 2748.60 l 10 .476 63.339 83.148 37,707.63 t 11 2.273 61.542 130.586 _1482.11 end l H - 86,225.9) i

! . i n(.uc e d i b

1 1490H/ L i

The leak rate for %he induced phase is L (induced) = - 2400 X (86.225.91 - 86.380.85) ~

3.177 86,380.85

= 1.3550 wt % / day (compared to 1.3962 computed ignoring sump level changes)

The above calculations show that the leakage from the reactor vessel did not significantly affect the reported leak rate and that the reported values are conservative values with respect to the actual leakage.

l 1

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APPENDIX C COMPUTATIONAL PROCEDURE l

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0. INPUT PROCESSING .

Calculations cerfomed by the software are outlined below:

0.1 Average temperature of subvolume #i (Tg)

= The average of all RTO temps in subvolume #1 1 N T i= r i t,)

N j=1 l where N = The number of RTDs in subvolume #1 0.2 Average dew temperature of subvolume #1 (Og)

= The average of all dew cell dew temps in subvolume #1 1 N Og= Dj,)

N j1 -

l where N = The number of RTOs in subvolume #1 l

0.3 Total corrected pressure #1, (P1 ) '

C) First correction f actor for raw pressure #1, (frcm pregram initialization data set).

Mt Second correcticn factor for raw cressure #1, (frcm pr gram initiali:atien data set).

Pr) Raw pressure #1, frcm BVFFILE.

P1 C1 + M1 Prg/IC00, for 5 digit pressure transmitters P1=Ci+M1 Pr1 /lC000, for 6 digit pressure transnitters D.4 Total corrected pressure #2, (P2 )

( C2 First correction factor for raw pressure 12, (frem pre; ram l initislization data set.

H2 Second correction factor for raw pressure #2, (from crc;ra?

initialization data set, t

} Pr2 Ra. pressure a2, frem EUFFILE.

l P2C292 Pr2/10CO, for 5 digit pressure transmitters P2=C2+H2 Pr2/1C000, fer 6 digit pressure transmitters l 54 i hP./COC. 7 L

0.5 Whole Containment Volume Weighted Average Temperature, (Tc )

Approximate N Method Ic = I fj Tj i.1 1

Exact N fj Method I i1 Tj where: fj. The volume fraction of the ith subvolume N - The total

• of subvolumes in containment 0.6 Average Vapor Pressure of Subvolume 1 (Curve fit of ASME steam tables.) (Pvi)

Pvi = 0.01529125 + 0.0016g3476 0 1 7 3 1 1

-- 2.28128 1.44734x X 10-910-0 (01 )(0 )4 + 7.081828

+ 3.03544 X 10- x (01011 1)

(0 )5 0.7 hhole Containment Average Vapor Pressure, (Pve )

Approximate N Hethod Pv c- I fj Pyg 1-1 Exact N ft Pyg Method PVc . T cI 11 Tj N - The total of subvolumes in containment f t. Volume fraction of the ith subvolume 0.8 Whole Containment Average Dew Temperature, (Oc)

Approximate N Hethod Oc .  : ft Oj i.1 Exact Method The whole containment average vapor pressure.

(Pve ) calculated with the exact method is used to fina Oc. An initial value of Oc is guessed and used =ith the ecuation in 0.6 to calculate Pye.

This value is then comoared to the known value frc-0.7. A new value of Oc is guessec and the pro:ess is repeatet' until a value of Oc is found that results.C001

=ithin in a calculated psia of the value value of fremPvc that is 0.7.

55 WD./DCC. 7

D.9 Average to'tal Containment pressure.(P)

P-( Pt+P2)/2 Average total containment dry air pressure, (Pd )

Pd = P - PVc D.10 Total Containment dry air mass (H) 4 Pd Vc Type 1: H=

R Tc where: R - Perfect gas constant, Vc Total containment free volume.

Type 2: Type 2 dry air mass accounts for changes in Reactor Vessel level. ,

for uncorrected dry air mass. (Type 1) the below definitions apply.

N Vc = I Vi and ft - V /Ve t

i=l where Vi is the user entered free volume in subvolume i.

For corrected dry air mass, (Type 2) the same definitions for Ve and fj apply, encept that one of the Vjs is corrected for changes in vessel level. If k is the subvolume number of the corrected subvolume then:

Vg = Vk o - a(C - b) a is the number of cubic feet of free volume per inch of vessel level.

b is the base level of the reactor vessel, in inches.

C is the actual water level in the reactor vessel, in incnes.

Vko is the volume of the subvolume k when C equals b.  :

The volume fracticns (fj) are then calculated with the corrected volume, and 111 other calculations are subsequently performed as previously specified for Type I dcy air mass.

l l

56 l o.ite.c. 7  !

0.11 1.eakrate C'alculations using Hass-Plot Method:

This method assumes that the leakage rate is constant during the testing period, a plot of the measured contained dry air mass versus time would ideally yield a straight line with a negative slope.

Based on the least squares fit to the data obtained, the calculated containment leakage rate is obtained frem the equation:

H = At + 8 Where H = containment dry air mass at time t (lbs.)

B = calculated dry air mass at time t=0

' (Ibs.)

A . calculated leakage rate (lbs/hr) t time in,terval since start of test (hours)

B 1

1 M

(lbs) t (hours) -

l l

l

' The values of the constants A and B such that the line is linear least squares best fitted to the leak rate data are:

NI(tj)(Hj) - (Iti) (I H i )  ;

A= '

NI(ti)2 . (:tg )2 j i

IH1 -

AIti i N

l 1

) $7 a./occ. 7

By definition, leakage out of the containment is considered positive leakage. Therefore, the statistically averaged least squares containment leakage rate in weight percent per day is given by:

l L - (-A) (2400)/B (weight %/ day)

In order to calculate the 95% confidence limit of the least squares averaged leak rate, the standard deviation of the least squares slope and the student's T-Distribution function are used as follows: .

1 Nt(Hj)2 - (IHj)2 --)2(2400) (weight %

e . -A2

__(N-2) Nt(tt)2 - (Itj)2 _, B

~

UCL = L + o (T) 1.6449(N-2) + 3.5283 + 0.85602/(N-2) where T-(N-2) + 1.2209 - 1.5162/(N-2)

N - Number of data sets l l

I tj -

test duration at the i th data set (hours) e = standard deviation of least squares slope (weight %/ day)

T - Value of the single-sided T-Oistribution function with 2 cegrees of freedom L =

calculated leak rate in weight %/ day UCL - 95% upper confidence limit (%/ day)

B - calculated containment dry air cass at time t=0 (Ibs.)

0.12 Point to Point Calculations ihls method calculates the rate of change with respect to time of dry air mass using the Point to Point Method.

1 I

t 58 WP./CCC. 7 l

For Every* data set, the r&te of, change of dry air mass between the most recent, (ti) and the previous time (tt.1) is calculated using the two point method shown belod;

. 2400 Hg . (1 - Hj/Mg.j)

)

Then the least square fit of the point to point leakrates is calculated as described for dry air masses in section 0.11 0.13 Total Time Calculations l

' This method calculates the rate of change with respect to time of dry air mass using the Total Time Method I Initially, a reference time (tr) is chosen. For every data set the rate of change of dry air mass between tr and the most recent time, tj is calculated using the two point method shown below.

. 2400 1

Mi- (1 - Hj/Mr )

l (tt-tr) i Then the least squares fit and 95% UCL of the Total Time l leakrates are calculated as shown belcw:

I Aj I(tt )2 - I tt I $j tj B=

I N I (tj)2 - (I tj)2 '

! (NItt Aj - I tj I Sj )

N I (tj)2 - (I tj)2 L= B + At 1.6449(N-2) . . 5283 + 0.85602/(N-2)

(N-2) + 1.22C9 - 1.5;62/(N-2)

Note: N is the number of data sets minus one.

l l 59 WD./ DOC. 7 l

I (tp - I (tj) / N)2 N I (t))2 - ( I tg )2 /3

/ /

/ F / ..

o-/ / I (Mg)2 - B I A - A I Aj tt

/ /

\/ N \/

UCL = L + To Note: This equation is calculated for information only frcm the start of the test up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then it becc?.es the official leakrates for future times.

0.14 BN-TOP-1 ,

l

) This method calculates the rate of change with respect to the i time of dry air mass using the Total Time Method.

I Initially, a reference time (tr) is chosen. For every data set the rate of change of the data item between tr and the most recent time. (ti) is calculated using the two point method shown belcw:

2400

' Hj = (1 - Hj/Mr)

(tt - tr) 1 Then the least squares fit of the Totil Time leakrates and the BN-TCP-1 957. UCLs are calculated as shown below.

B=

( I At I(ti)2 -

I tt IAt tt)

N I (t))2 - ( I tj )2 Note: N is the nu.?ber of data sets minus ene.

l .

1 1

60 s.icce. ,

^"

( N I tj At -

Iti !At)

N I (tj)2 - (I tj)2~ ~ ~

L= 8 + At 2.8225 T 1.95996 + 2.37226 -+-

(N - 2) (N - 2)2 F= 1+

1

+

(tp - I (ti) / N)2 N

I (t )2 - (I tt)2 /N t ,

/ /

/ F ,/

o ,/

\f N

\/j/ I (M t )2 - B : Aj - A I Aj tt UCL = L + io Note: This equation is calculated for information only frc1 the start of the test up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then it beccmes the of ficial lenkrates for future times.

D.15 Temperature stabilization checking per ANSI 56.8-1931  !

Ti Heighted average contain ent air te?perature at 50ur 1.

Tj,n Rate of change of '=tighted average centainment air te perature over an n hour period at hour 1. using a t o point back=ards ,

difference method, I l

Tj,n -

I' I'"

n I

61 HP+/ DOC. 7

Zj is the AtlSI 56.8-1981 Temperature stabilization criteria at hour 1, Zg . l T t,4 - Tj,1l 1 must be 1 4.

Per ANSI 56.8-1981s 2 must be less than or equal to 0.5 oF/hr NOTE: If the dcta sampling interval is less than one hour, then:

Ootion #1 Use data collected at hourly intervals Option #2 Use average of data collected in previous Acur for that hour's data.

D.16 Calculation of Instrument Selection Guide, (ISG)

ISG 2400 / 2 (ep/p)Z . 2 (e r /I)2 ' l. ('d 0)#

- /

t \/ N p Nr Nd I where: t is the test time', in hours p is test pressure, psia T is the volume weighed average containment temperature, OR N is the number of pressure transmitters N is the number of RTDs Nd is the number of dew cells en is the combined pressure transmittert' error, psia er is the CCEDined RTDs' error, CR ed is the ccebined de* cells' error, CR ep . /

l \/ (Sp)2 . (Rpp . Rsp)2 l

=here: So is the sensitivity of a pressure transmit <.

RP is the repeatability of a pressure transititter i FS;p is the resciutien of pressure transmitter '

er. /

\/ (Sr)2 * (RPr

• RSr)2

.nere: Se is the sensitivity of an RTD RPr is the repeatatility of an RTO R$p is the resolutien of an RTD 62 n ./0CC. 7

APy ed =

I ATd Td \/ (S )2 d + (RPd + RSd)2 where: Sd is the sensitivity of'a dew cell RPd is the repeatability of a dew cell R$d is the resolution of a dew cell aPv change in vapor pressure ATT Td change in saturatien temperature The above ratio is from ASME steam tables and evaluated at the  !

containment's saturation temperature at that time.

0.17 BN-TOP-1 Temperature Stabilization Criteria Calculation A. The rate of change of temperature is less than 1 'F/Hr averaged over the last two hours.

K1 = lTj - T t_1l K2= Tj _1 - Ti -2l '

K' and K2 must both be ess than 1 to meet the criteria l' steri in A.

B. Jherateofchangeoftemperaturechangeslessthan0.5 F/P ur/ hour averaged over the last two hours, j

' K1 = (Tj - Tj_t)/(tj - ti_1) 1 K

i 2 = (Tj_1l-Z= (K)T--2)/(ti_1 - ti-2)l K2 )/(tj - ti_1)

Z must be less than 0.5 to meet the criteria listed in B.

0.18 Reactor Vessel Free Volume Hass Calculation As shown in section 0.10, the free volume of the Reactor Vessel i

subvolume < is given by the below equation.

V, = Vgo - a (c-b) l The dry air mass in subvolume e can then be written as:

l Me = 144 (P-Pve) Vc/RTs

, Hhere: M.: is the dry air mass in subvolume x, (Ibm)

R is the gas constant of air l isg the average temperature of subvolume e, (OR)

Pyg is the average vapor pressure of subvolume e, (pisa)

~P is the average Containment pressure, (psla)

V, is the free air volume in subvolume e, (ft 3)

WP+/00C. 7 63 I

<e 0~.19 Torus Free Volume Calculation Free volume calculations of ?the Torus: rely upon narrow rang' e Torus '

watcr level inputs. These values-range between plus and minus five.-

inches. It is assumed that the-Torus subvolume free air-volume'is -

that subvolume's volume when the Torus level equals zero. The user may . enter three constants to model the variation of Torus air volume with water level.

The equations for~ Torus free volume ~in subvolume t are given:

V t " V to - (al + bl +-cL3 when L1 0 Vt - V ot + (-al + bl2 -cL ) when L1 0 ,

The dry air mass.in subvolume t can then be written as:

Mt = 144 (P-Pvt) Vt /Rit Where: Mt is the dry air mass in subvolume t, (lbm)

P is the-average containment pressure, (psia) 55t is 'the average vapor pressure of subvolume t (pisa)

Vt is the free volume in subvolume t, (ft3)

R is the gas constant of air Tt is the average temperature in subvolume t (CR)

L is the Torus level, (inches)  !

a,b,c are Torus level constants ,

Vt o is the free volume in subvolume'T when L equals zero, taken from standard free volume inputs, (ft3)  :

E. OUTPUTS E.1 OUTPUT DEVICE TYPES: The below output devices shall be supported.

There are no special constraints on output device locations. i' PRINTER $; PRIME High Speed Line Printer '

OKIDATA 2410 OKIDATA 93 i LAl20 1 PLOTTERS: Hewlet Packard 7475A 8.5" X 11" l Hewlet Packard 7585A 8.5" X 11" Hewlet Packard 7585A 11" X 17" CRTs: Hyse Hy75 l View Point 60 l Ampex Olalogue 80 & 81 i PRIME PT200 GRAPHICS TERMINALS: RamTech 6200 RamTech 6211 Tektronix 4107 Tektronix 4208 64 Tektronix 4014 WP+/00C. 7 1

APPENDIX 0 INSTRUMENT ERROR ANALYSIS 4

J 1490H/

IPCLRT SAMPLE ERROR ANALYSIS FOR SHORT DURATION TEST A. ACCURACY ERROR ANALYSIS Per Topical Report BN-TOP-1 the measured total time leak rate (M) in weight percent per day is computed using the Absolute Method by the formula:

[ T P H (% / DAY) 2400 * ( ) . I N

\

(j)

H N 1 -

where: P1 - total (volume weighted) containment dry air pressure (PSIA) a'. le start of the test; PN = total (volume weighted) containment dry air pressure ,

(PSIA) at data point N after the start of the test; H = test duration from the start of the test to data point N !

in hours; Ti - containment volume w0ighted temperature in 'R at the ,

start of the test; l

TN = containment volume weighted temperature in 'R at the  !

data point N.

The following assuaptions are made. 1 l

A A '

P) - PNP where P is the average dry air pressure of the 4 containment (PSIA) during the test; A A T1-TN=T where T is the average volume weighted primary containment air temperature (*R) during the test:

PtPN where P is the total containment atmospheric pressure (PSIA);

Pyj = PVN Where Py is the partial pressure of water vapor in j the primary containment.

I

l i

i 1490H/  ;

d a. }'p . /

Taking the' partial derivative in terms of pr:.ssure-and temperature of (1) equation and substituting in the above assurrptions yleids the following equation found in Sectlen 4.5 of BN-TOP-1 Rev. 1:

e 9 X i eM = 1 2400

• 2 - ( _p_) 2 +2( _t_,) 2 H A A P T where ep - the error in the total pressure measurement system.

ep = 1 [(epT)* + ('DV)* 3 1/2; ePT = (instrument' accuracy error) / / no. of inst. In measuring i total containment pressure; epy = (instrument accuracy error) / / no. of inst. in measuring i vapor partial preesure; ,

et = (Instrument accuracy error) / / no. of inst. In measuring l 2 containment temperature;  !

eg = the error in the measured 3eak rate; I i

! H = duration of the test. ,

,' l NOTE Subvolume #11, the free air space above the water in the reactor vessel, is

, treated separately from the rest of the

! containment volume. The reason for the l separate treatment is that neither the i

air temperature or the partial pressure of water vapor is measured directly.

The temperature of the air space is assumed to be the temperature of the reactor water, as measured in the shutdown cooling or clean-up j demineralizer piping before the heat 1

exchangers. The partial pressure of a

water vapor is computed assuming saturation conditions at the temperature of the water. Volume l weighting the errors for the two volumes (Subvolume #11 and Subvolumes #1-10) i s the method used.

j 1490H/ - 67-f L_-__________________ _ _ _ _ _ .

B. EQUIPMENT SPECIFICATIONS FLOHMETER THERMOCOUPLE INSTRUMENT RTD (*F) PPG (PSIA) DEWCELL (*F) (SCFM) (*F) __

Rtnge 50-150 0-100 20 - 104 0.927-11.23 0 - 600 Accuracy 1 50 3 015 11 1 111 102 Repeat-abi1ity 2 10 3 001 1 50 1 02 t.10 C. COMPUTATION OF INSTRUMENT ACCURACY UNCERTAINTY

1. Compu t 'i ng " e T "

Volume Fraction for Volume #11 .02344 Volume Fraction for Volumes #1-10 .97656 ei - t (.97656 .50 + .02344

• _2._, )

/29 /1 ei = 1 131S*R

2. Computing " ept "

ePT = + .015

/I ePT = 1 0106 PSIA

3. Computing " epy "

At a dewpoint of 65'F (assumed), an accuracy of g l'F corresponds i to + .011 PSIA. For subvolume #11 at an average temperature of 140*F, in accuracy of 2*F corresponds to 1 150 PSI. I epy 1 (.97656 * .011 + .02344 * .150 )

/10 /1  !

I epy t .0069 PSIA l

4. Computing " ep "

ep - 3 C (.0106)2 + (.0069): ;1/2 l ep - t .0126 PSIA 1490H/ ,

5. Computing total instrument accuracy uncertainty " eg "

eH =

1 2460

• 2*I.0126h2 + 2 *I 0.1376La H

i 63.5 j i 552.6 j A

assuming P = 63.5 PSIA A

T = 552.6*R Therefore, for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test (H),

A eH = 1 1801 wt % / DAY

0. COMPUTATION OF INSTRUMENT REPEATABILITY UNCERTAINTY

1. Computing " er "

er = 3 10

/30 eT = 1 0183*R

2. Computing " epi "

epT = 1 001 ]

/2

'pi = 2 0007 PSIA I l

3. Computing " epy "

'pv = (.97656 * ,006 + .02344 * .008 )

JTb li

'py = 1 0020 PSIA

4. Computing " ep "

ep = C (.0007)8 + (.0020): )1/2 l ep = 1 0021 PSIA I

1490H/ l l

R

5. Computing the total instrument repeatability uncertainty " eg" R X eg = 2400

• 2 f.0021'a + 2,' O.0183'8 ,

,552.6 4 H

i 63.5f Therefore,'for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test, R

eM.* 1 0265 wt % / DAY E. COMPUTING TOTAL INSTRUMENT UNCERTAINTY A R eg = g 2 * [ (eg): , (,M): 3 1/2 o eg =.3 2

• C.(.1801): + (.0265)2.1 1/2 [

eg = 1 3641 weight % / OAY for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test.

t J

i b

s ,

i N

l l

i 4

1

i

)

1 1' 1 l

i 1490H/ 70 l e

i.

l t

APPENDIX E BN-TOP-1, REV 1 ERRATA '

I 1

1490H/ <

APPEND 8X E BN-TOP-1, REV. 1 ERRATA the Station uses the general test method outlined providec in thThe topical report. ' The prtsary difference between that methe BN-TOP-1, Rev. 1 previously used is in the statistical analysts of the od seasured and the ones lean rat e data.

Without making any judgments concerning the validity of The intent hera is not to change the test clarify r sethod, re discovered.but rathe the method errors areto a sachematically listed below. precise manner that allows its '- 'esent atton. *he EQUATION 3A, SECTION 6.2 Reads:

. L.L s A

• 8 t.

t Should Read: L

=Ag*S g t

g Reason:

The calculated leak rate (L ) at ttee t using equations the regression 6 apd 7). line e natants A ,g ts 3 computed computed as tag a The sumsatton sthms kn(equation 6 are defined as I = tst1, ubere a is the number of data sets up ti unt time t,.

new dafa set The regressten line constants change eacn tt.ne a is received.

linear function of time. The calculated leak rate is not a PARAGRAPM TOIJ.CWING _EQ. 3A, SECT:0N 6.2 Reads:

The leas ratedeviation (L) of the seasured 'eak rate (M) and ts expressed as:is snown grapatcally :n itgure A.1fr:s in Appen: . x A tue cai:i. ate Cavtation s M. . L, t i Should Read:

The

'.une deviation (N ) of the measured '.eax rate (M, f)t:m tne regres s.:-

expresskd as:is snowo grapascal.'y :n Ttgure A. tn Appendix A i. : .5

eviatten a M k -N i

nere N ' =A +

3 ': k, 7 7 A

? , 3,' a Rer,ressten line constants c:mputed fr:m al.' :sta

'.sets a s availaole t data set at f rom timetnet start of ne test to ete p,

t, a cine from tne start of the test to tne ten data set 72

neason:

The calcula'ed Lead rate as a function of ttco d utrg tho ttst is based on a regresston Lane.

The regressir.n line constants. A and B , are changing as each additional datatset ts k:ccetved.

Equation 3A ist used later in the test to compute the upper confidence limit as a function of time.

For the purpose of thi? calculation, it ts tse donation from the last computeu regressten line at time t that is important.

7 EQUATION 4, SECTION 6.2 Reads: SSQ = I (M g - I, ) ?

Shc.uld Read: SSQ u I (M - N )2 ,

Reason: Same As'Above EQUATION 5, SECTION 6.2 Reads: SSQ = I ( M g -

(A + St )]2 Should Read: SSQ = 1 ( M g -

(A +3 *t )]2 p p Reason: 34ee As Above EQUATION ABOVE EQUATION 6, SECTION 6.2 Reads: 3 = (C i 5)(M *S i 1(t.

t t)3 ~

~

Should Read: 3.L = N ( * *.

I t-

<. t,t - -),-

c* -

Reason: Regressten li.ne constant 3 changes over time as a functLort of C is received. BSc) of 't"an,escaiddittanaldataset left out of den:mt.at::

Sumsation s t ans orat tted.

EQUATION i. SECTION 6.2 Rese

• 3=*At t H

i

(  %

t

'Z1' n It, d -

(I t,;-

? - -

Should Read: S = a ' ' t 'Mi (1 t!) C "* 'i .

n It 4 -

(I L J' L L Reason: Same AJ Above 73

CQUATICN ?, SECT!CN'6.2 Reads: Aa5-3g Should Read: A g*5-B C g

Reason: Same As Above EQUATION 10. SECTION 6J

' Reads: A=( '( t

) * (A C() (I tt 1()

nit 3 - (I t ja Should Read: Ag a . (I '1() (I E t

~

n I t.3

• ) " (I t() (I t( .1( )

L - (I ,L)3 Reason: Same As Above CQUATION 13 SECTION 6.3 Reads: e3 = s2 [t ,*1 , (t,

• t)2 Rt g

- tja)

Should Read: 03=s2 (t

• 1 + (t o

• C)

I (e t - T) where c  :

E time free the start of the test of the last data set leakforcatas whten Us,)the standara deviation of :ne .9easure:

betag computed; from the regression line (.9 ) ts t 5 g

tima from the start of the test of tne t *3 set; 24:4 a a number of data sets to time P; n

I = I  ; and tal I = 1 I: t .

n Reason:

Appears to be error in editing af the report.

Report does a poor job of defining vartaoles.

74

i I

EQUATION 16, SECTION 6.3

{

1 Reads: a= s ( 1 + n1 . (t,

• C )*

i l (t g -

t)3 l

1 Sheuid Read; a= s(1 1 + ( t, .

e )2 I (t.

L

-IJ2)

Reason: Same As Above EQUATION 15, SECTION 6.3 Reade: Confidence LLatt "L: T Should Read: Confidence Limits a L: Txa where L

• calculated Isak rate at time t ,

Tu T distribution value based on n, the museer af daua sets received up untti stae t p; ea standard deviation of seasured leak ette values (Mt ) about the regressten line based on data frem the start o f tile tes t antti tsaa sp.

Reason: Same As Above EQUATION 16, SECTION 6.3 Reads: UCL = L

• T Should Read: UCL = L + !

• J Reason: Same As Above EQUATICN 17 SECTION 6.3 Reads: LCL = L - T Should Read: L C L = L - T  : '

Reason: $ame As Above i

75 ,

l j

O APPENDIX F TYPE A TEST RESULTS USING MASS - PLOT HETH00 MEASURE 0 LEAK RATE PHASE i

i 1490H/ 4

TYPE A TEST RESULTS USING MASS - PLOT METHOD MEASURED LEAK RATE PHASE DATA DATA SET TIME ' TEST ORY AIR LEAK 1 ATE, 95% UP CONF SET # OAY HH MM SS TIME, (HR) MASS, (LBM) (%/D) LIMIT, (%/0) 181 165 04:05:31 0.000 0.86622156E+05 182 165 04:15:33 0.167 0.86619172E+03 183 165 04:25:33 0.334 0.86617172E+05 0.4136E+00 0.8110E+00 184 165 04: 35:35 0.501 0.86615703E+05 0.3545E+00 0.4720E+00 185 165 04:45:35 0.668 0.86611687E+05 0.4051E+00 0.4926E+00 186 165 04: 55:36 0.835 0.86610281E+05 0.3950E+00 0.4483E+00 187 165 05:05:39 1.002 0.86606187E+05 0.4217E+00 0.4690E+00 188 165 05: 15:39 1.169 0.86605937E+05 0.4012E+00 0.4422E+00 189 165 05:16:01 1.175 0.86605937E+05 0.3918E+00 0.4273E+00 190 165 05:26:04 1.343 0.86601875E+05 0.4011E+00 0.4318F+00 191 165 05:36:05 1.509 0.86597359E+05 0.4237E+00 0.4594E+00 192 165 05:46:06 1.677 0.86595640E+05 0.4316E+00 0.4623E+00 193 165 05:56:09 1.844 0.86593906E+05 0.4312E+00 0.4569E+Co 194 165 06:06:09 2.011 0.86590750E+05 0.4340E+00 0.4559E+00 195 165 06:16:10 2.178 0.86590531E+05 0.4245E+00 0.4455E+00 196 165 06:26:10 2.344 '0.86585578E+05 0.4282E+00 0.4467E+00 197 165 06:36:14 2.512 0.86583656E<15 0.4282E+00' O.4444E+00 198 165 06:46:15 2.679 0.86579734E+05 0.4326E+00 0.4474E+00 199 165 06:56:15 2.846 0.86578969E.05 0.4303E+00 0.4437E+00 200 165 07:06:15 3.012 0.86577422E+05 0.4260E+00 0.4386E+00 201 165 07:16:16 3.180 0.86573734E+05 0.4255E+00 0.4368E+00 202 165 07:26:20 3.347 0.86570187E+05 0.4272E+00 0.4375E+00 N

203 165 07:36:21 3.514 0.86568312E+05 0.4271E+00 0.4365E+00 204 165 07:46:25 3.682 0.86567047E+05 0.4246E+00 0.4335E+00 205 165 07:56:25 3.849 0.86563953E+05 0.4236E+00 0.4318E+00 206 165 08:06:26 4.015 0.86562000E+05 0.4220E+00 0.4296E+00 207 165 08:16:28 4.183 0.86559828E+05 0.4201E+00 0.4274E+00 208 165 08:26:30 4.350 0.86555844E+05 0.4205E+00 0.4273E+00 209 165 08:36:33 4.517 0.86554078E+05 0.4199E+00 0.4262E+00 210 165 08: 46:33 4.684 0.86551562E+05 0.4194E+00 0.4253E+00 211 165 08:56:35 4.851 0.86547765E 05 0.4204E+00 0.4259E+00 212 165 09:06:35 5.018 0.85646781E+05 0.4196E+00 0.4249E+00 213 165 09:16:36 5.185 0.86545765E+05 0.4176E+00 0.4229E+00 214 165 09:26:36 5.352 0.86540797E+05 0.4180E+00 0.4230E+00 l 215 165 09:36:37 5.519 0.86539344E+05 0.4175E+00 0.4222E+00 216 165 09:46:39 5.686 0.86538297E+05 0.4160E+00 0.4207E+00 i 217 165 09:56:41 5.853 0.86534469E+05 0.4156E+00 0.4201E+00 j 218 165 10:06:43 6.020 0.86533672E+05 0.4141E+00 0.4186E+00 l

1490H/ -77  !

a TYPE A TEST RESULTS USING MASS - PLOT METHOD INDUCED LEAK PHASE DATA DATA SET TIME TEST ORY AIR LEAK RATE, 95% UP CONF SET # DAY HH MM SS TIME, (HR) MASS, (LBM) (%/0) LIMIT, (%/0) 230 165 12:06:56 0.000 0.86450312E+05 231 165 12:16:57 0.167 0.86441875E+05 232 165 12:27:00 0.335 0.86431859E+05 0.1529E+0! 0.2176E+01 233 165 12:37:04 0.502 0.86424750E+05 0.1437E+01 0.1623E+01 234 165 12:47:05 0.669 0.86415062E+05 0.1453E+01 0.1542E+01 235 165 12:57:05 0.836 0.86406265E+05 0.1640E+01 0.1513E 01 236 165 13:07:06 1.003 0.86401953E+05 0.1383E+01 0.1479E+01 237 165 13:17:06 1.170 0.86394719E+05 0.1336E+01 0.1423E+01 238 165 13:27:08 1.337 0.86385047E+05 0.1332E+01 0.1398E+01 239 165 13:37:10 1.504 0.86376812E+05 0.1332E+01 0.1383E+01 240 165 13: 47:14 1.672 0.86368422E+05 0.1334E+01 0.i376E+01 241 165 13:57:15 1.839 0.86359906E+05 0.1339E+01 0.1374E+01 242 165 14:07:16 2.006 0.86351609E+05 0.1343E+01 0.1372E.01 243 165 14:17:16 2.173 0.86343593E+05 0.1345E+01 0.1370E+01 244 165 14:27:20 2.340 0.86335469E+05 0.1347E+01 0.1368E+01 245 165 24: 37:25 2.508 +0.86327031E+05 0.1349E+01 0.1368E+01 246 165 14:47:28 2.676 0.86318625E+05 0.1351E+01 0.1368E+01 247 165 14: 57:29 2.843 0.86307047E+05 0.1363E+01 0.1382E+01 248 165 15:07:31 3.010 0.86300469E+05 0.1367E+01 0.1384E+01 249 165 15:17:33 3.177 0.86290515E+05 0.1374E+01 0.1391E+01 J

1490H/ -78

MEASURED LEAK RATE PHASE GRAPH OF CALUCLATED LEAK RATE AND UPPER CONFIDENCE LIMIT l

MASS PLOT LEAKRATES VS TIM E 0.90  :  : '

0.80 - -

1

- - - - - - - - - Allowe d Le c k Ro le 0.70 -

5 g 0.60 -

I m

M 0.50 -

~ _

95 x UPPER CONFIDENCE UMIT i 0.40 - -

CALCULATED LEAK RATE O.30 -

+

I 0.20 ,

0.33 1.23 2.13 3.03 3.93 4.83 5.73 6.53 HOURS FIGURE F-1 1490H/ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ >

INDUCE 0 LEAKAGE PHASE GRAPH OF CALUCLATED LEAK RATE I

'l r MASS PLOT LEAKRATES VS TIM E 1.50  :  :  :  :  :

UPPER BOUNOS 1.70 --

i i 1.60 --

i 5 Tor g et Le a k Re t e 4

ac 1.50 -

l j w 1.40 --

J 1.30 ..

CALCULATED LEAK RATE ,

LOWER 80UNOS

1.20 -- I 4

l 1.10  :

l i  :  :

0.33 0.73 1.13 1.53 1.93 2.33 2.73 3.13 HOURS i

l i

l FIGURE F-2 4 1490H/ l

Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, Illinois 61242 Telephone 30,9/654 2241 RLB-88-267 August 15, 1988 Mr. Thomas E. Murley Nuclear Reactor Regulation U. S. Nuclear Regulatory Coonission Washington, D.C. 20555

SUBJECT:

Reactor Containment Building Integrated Leak Rate Test Quad-Cities Nuclear Power Station Docket No. 50-254, OPR-29 Unit One Enclosed please find the report "Reactor Containment Building Integrated Leak Rate Test, Quad-Cities Nuclear Power Station Unit Two, June 12-13, 1988" and the related appendices describing the Type A test. The performance of this test was witnessed and inspected by representatives of the NRC Region III Office.

This report is submitted to ycu in accordance with the requirements of 10 CFR 50, Appendix J Section V.B.I. The information contained in Appendix A of this report is intended to comply with requirements of 10 CFR 50, Appendic J,Section V.B.3. According to 10 CFR 50, Appendix J, Section III.A.6, the test schedule for the next Type A test is to be reviewed and approved by the Commission. The next Type A test for Quad-Cities Unit One is scheduled for the fall of 1989; the Commission's review and approval of this schedule is hereby requested.

Very truly yours.

CCMMONWEALTH EDISON CCHPANY Quad-Cities Nuclear Power Station

• f R. L. Ba's Station Hanager RLB/KRS/klm Attachnent 1490H/ I L