Text

Reactor Containment Bldg Integrated Leak Rate Test Quad- Cities Nuclear Power Station.
	ML20046B578
Person / Time
Site:	Quad Cities
Issue date:	05/19/1993
From:	; COMMONWEALTH EDISON CO.
To:	;
Shared Package
ML20046B575	List: ML20046B574; ML20046B578;
References
	NUDOCS 9308050180
	Download: ML20046B578 (72)
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i REACTOR CONTAINMENT BUILDING !

i INTEGRATED LEAK RATE TEST ,

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t QUAD-CITIES NUCLEAR POWER STATION ;

UNIT TWO [

MAY 17-19,'1993 i i

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TFCH 364 9308050180 930723 PDR ADOCK 05000265 P PDR "[rl hs

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-16BLE OF CONTENTS

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TABLE AND FIGURES INDEX. . . . . .. . . . . . . . . . . . . . . . 1 1

INTRODUCTION , . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 ;

A. IESI_EEEPARATIORS A.1 Type A Test Procedures . . . . . . . . . . . . . . . . . . . 4 !

A.2 Type A Test Instrumentation. . . . . . . . . . . . . . . . . 4 A.2.a. Temperature . . . . . . . . . . . . . . . . . . . . 9 l

A.2.b. Pressure. . . . . . . . . . . . . . . . . . . . . . 9 l A.2.c. Vapor Pressure. . . . . . . . . . . . . . . . . . . 9 ;

A.2.d. Flow. ..... .................10 !

i A.3 Type A Test Pressurization . . . . . . . . . . . . . . . . 10 i f

B. IEST METB00 B.1 Bas i c Techni que . . . . . . . . . . . . . . . . . . . . . . 12 B.2 Supplemental Verification Test . . . . . . . . . . . . . . 13 c

B.3 Instrument Error Analysi s. . . . . . . . . . . . . . . . . 13 [

C. SEQUENCE OF EVENTS f i

C.1 Tnst Preparation Chronology. . . . . . . . . . . . . . . . 14 C.2 Test Pressurization and Stabilization Chronology . . . . . 15 C.3 Measured Leak Rate Phase Chronology. . . . . . . . . . . . 15 C.4 Induced Leakage Phase Chronology . . . . . . . . . . . . . 16 C.5 Depressurization Phase Chronology. ..... . . . . . 16 i i

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EAGE j D. TYPE A TEST DATA !

D.1 Measured Leak Rate Phase Data . . . . . . . . . . . . . . . 17 D.2 Induced Leakage Phase Data. . . . . . . . . . . . . . . . . 17 ~

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E. IESI_C6LCULAIIDHS . . . . . . . . . . . . . . . . . . . . . . . 28 i f'

F. TYPE A TEST RESQLIS F.1 Measured Leak Rate Test Result; . . . . . . . . . . . . . . 29 .

F.2 Induced Leakage Test Results. . . . . . . . . . . . . . . . 30 1

-l F.3 Pre-Operational Results vs. Test Results. . . . . . . . . . 31 :

F.4 Type A Test Penalties . . . . . . . . . . . . . . . . . . . 31 !

i F.5 Evaluation of Instrument Failures . . . . . . . . . . . . . 32

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F.6 As-Found Type A Test Results. . . . . . . . . . . . . . . . 32 I

APPENDIX A TYPE _E_AND_C_IESIS . . . . . . . . . . . . . . . . 33 i APPENDIX B COMPUTATIONAL PROCEDURES . . . . . . . . . . . . . 44 ;

1 APPENDIX C INSTRUMENT ERROR ANALYSIS ............ 56 ,

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APPENDIX D BN-TOP-1. REV. 1 EBRAIA ............. 62 .!

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APPENDIX E 11EE A TESI_RESULIS_USING MASS-PLOT. . . . . . . . 67 :

MEIHQD (ANS/ANS1_SH181 .

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MBLES_ANDl LGURES_lNDEX t

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TABLE 1 Instrument Specifications. . . . . . . . . . . . . . . . 6 TABLE 2 Sensor Physical Locations. . . . . . . . . . . . . . . 7 TABLE 3 Measured Leak Rate Phase Test Results. . . . . . . . . 18 TABLE 4 Induced Leakage Phase Test Results . . . . . . . . . . 19 FIGURE 1 Idealized View of Drywell and Torus. . . . . . . . . . . 8 Used to Calculate Free Air Volumes FIGURE 2 Measurement System Schematic Arrangement . . . . . . . -. 11 !

4 FIGURE 3 Measured Leak Rate Phase - Graph of Calculated . . . . 20 Leak Rate and Upper Confidence Limit !

FIGURE 4 Measured Leak Rate Phase - Graph of . . . . . . . . . 21 Dry Air Pressure FIGURE 5 Measured Leak Rate Phase - Graph of Volume . . . . . 22 Heighted Average Containment Vapor Pressure FIGURE 6 Measured Leak Rate Phase - Graph of Volume . . . . . . 23 Heighted Average Containment Temperature '

FIGURE 7 Induced Leakage Phase - Graph of Calculated. . . . . . 24 >

Leak Rate ,

FIGURE 8 Induced Leakage Phase - Graph of Volume. . . . . . . . 25 Heighted Average Containment Temperature FIGURE 9 Induced Leakage Phase - Graph of Volume. . . . . . . . 26 Heighted Average Containment Vapor Pressure FIGURE 10 Induced Leakage Phase - Graph of . . . . . . .....27 !

Dry Air Pressure a

ncu su 1RTRODUCIl0N This report presents the test method and results of the Integrated Primary

Containment Leak Rate Test (IPCLRT) successfully performed on May 17-19,1993 at Quad-Cities Nuclear Power Station, Unit Two. The test was performed in accordance with 10 CFR 50, Appendix J, and the Quad-Cities Unit One Technical Specifications.

For the ninth time at Quad Cities a short duration test (less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months was !

conducted using the general test method outlined in BN-TOP-1, Revision 1 (Bechtel Corporation Topical Report) dated November 1, 1972. The first short duration test was conducted on Unit One in December, 1982.

Using the above test 0.4373 method, the total primary containment integrated >

leak rate was calculated to be 0.1471 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 0.5064 wt %/ day.

The supplemental induced leakage test result was calculated to be 1.2782 wt

%/ day. This value should compare with the sum of the measured leak rate phase result (0.4373 wt %/ day) and the induced leak of 8.0 SCFM (0.9612 wt %/ day). The <

calculated leak rate of 1.2782 wt 1/ day lies within the allowable tolerance band of 1.3985 wt 1/ day 1 0.250 wt %/ day.

SECTION A - TEST PREPRAIIDHS A.1 Iypt A Teli_Ploceditte The IPCLRT was performed in accordance with Quad-Cities Procedures QCTS 500-1 Rev. 2 and QCTS 500-2 through -6.

These procedures were 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-TOP-1, Rev. 1 Topical Report as a general test method.

A.2 Iype A TeltJR1101LmeniAtlon Table one shows the specifications for the instrumentation utilized in the IPCLRT. Table Two lists the physical locations of the temperature and humidity sensors within the primary containment. Figure 1 is an idealized view of the drywell and suppression chamber used to calculate the primary containment free air subvolumes. Instrumentation calibrations were performed using NBS traceable standards. Quad Cities procedure QCTS 500-2 was used to perform the required In-Situ's prior to testing.

Note: Subvolume 4, which is the annulus region of the containment, was not ,

instrumented. This decision was based on the difficulty associated with placing :

the instrumentation in the annulus combined with its relatively small volume fraction (1.4% of the total containment free air volume). The volume fraction associated with the annulus region was added to the volume fractions of the subvolumes which would be most respresentative of the conditions present in the 2

annulus.

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Also, instrumentation was used inside containment for subvolume 11, which is i the reactor vessel region. In order to acquire vessel temperature, sensors were mounted onto piping associated with the Residual Heat Removal System, Shutdown ;

Cooling Suction Line. Since Shutdown Cooling was running during the test to ~

maintain stable vessel temperatures, this method provided an accurate measurement ;

of reactor vessel temperature. ,

A Graftel, Inc., Smart Sensor Instrumentation System was used in the performance of.this test as shown in Figure 2. The Smart Sensorr allow for the measurement of temperatures and relative humidity during an ILRT, without the aid ,

of a data acquisition system. Each sensor contains its own CPU, memory, signal conditioning, and RS-485 bus interface. All calibration constants are contained in each sensor's nonvolatile memory.

Up to 124 sensors may be connected to a communications port at the same time.

For this test, 42 sensors were connected. Each sensor responds only to its own unique address. Cable runs may be up to 10,000 feet long. For this test cables were between 5 and 250 feet long. Since the output of each sensor is a digital signal, cable lengths have absolutely no effect upon calibration. :

4 The sensors were connected in 8 strings with each string containing both 1 temperature and RH sensors. Although the sensors are physically connected in '

series, they are electrically connected in parallel. This ensures that the failure of cny one sensor will not affect the others. The strings are connected to a standard communications port of an IBM compatible PC.

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TABLE ONE INSTRUMENT iPECIFICATIONS INSTRUMENT MANUFACTURER MODEL NO. SERIAL NO. RRi_0_(

ACCURACY REPEATABILITY Precision Pressure 46847 Gauges (2) Paroscientific 760-100-A 47111 0-100 PSIA t.01%F.S.

SEE TABLE j Thermistors (30) Graftel 9202 TWO 32-158' F 0.5'F 0.01*F SEE TABLE i

Humidity Sensors Graftel 9203 TWO 30-100% RH 2*F (Dew .1% RH Temperature Equivalent Fischer Flowmeter & Porter 10A35555 8210A0360-A4 1.15-11.10 scfm .111 scfm i

Level Indicator 555111BCAA LT 1-6468 *GEMAC 3AAA 0-60" H 2O Used for monitoring purposes only. Leak rates not corrected for changes in vessel level.

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i TABLE TH0 SENSOR PHYSICAL LOCATIONS l l

IHERMISTER N02 SERIALHLLMBEB SUMOLUME ELEV./AZ11L l 1 GT1021 1 670'/180*

2 GT1027 1 670'/ 0*

3 GT1011 2 657'/ 20' !

4 GT1005 2 657'/197*- '

5 GT1029 3 639'/ 70*

6 GT1004 3 639'/255* '

7 GT1009 11 8 GT1015 10 578'/350*

9 GT1012 5 620'/ 5*

10 GT1019 5 620'/100*

11 GT1014 5 620'/220*

12 GT1033 6 608'/ 40* :

13 GT1032 6 608'/130*

14 GT1006 6 608'/220*

15 GT1022 6 608'/310*

16 GT1001 7 598'/ 70*

17 GT1016 7 598'/160*

18 GT1026 7 598'/250*

19 GT1002 7 598'/340*

20 GT1025- 8 587'/ 10*

21 GT1023 8 587'/100*

22 GT1003 8 587'/190*

23 GT1020 8 587'/280*

24 GT1010 9 595'/170* !

25 GT1017 9 580'/170* !

26 GT1007 10 578'/ 70*

27 GT1030 10 578'/140*

28 GT1013 10 578'/210' ;

29 GT1028 10 578'/280* :

RLSEES0RS SIRiaLEUMBIB SUBYO10BE ELEV /AlllL 1 GRH1012 1 670'/180*

2 GRH1014 2,3,4 653'/ 20*

3 GRH1001 2,3,4 653'/197*

4 GRH1013 5 620'/ 5*

5 GRH1006 6 605'/ 40' 6 GRH1005 7 600'/250' 7 GRH1011 8,9 591'/ 10' 8 GRH1007 8,9 591'/190*

9 GRH1010 10 578'l 70*

10 GRH1003 10 578'/280*

Thermistor (Saturated) GT1018 11

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A.2.a. Ielnpnittne i ^ The location of the 29 thermistor's was chosen to avoid conflict with local temperature variations and thermal influence from metal structures. A temperature survey of the containment was previously performed to verify that ; the sensor locations were representative of average subvolume conditions. Graftel, Inc., Model 9202 temperature sensors were used to provide the t containment temperatures. The model 9202 sensor is designed for the measurement of dry bulb temperatures during an ILRT. The sensors utilize superstable precision thermistors. The thermistors are glass hermetic encapsulated and subjected to 1007. Individual in-process screening. . Each thermistor is mated to the signal conditioning circuitry, A/D converter, CPU, EEPROMs and RS-485 network interface. An isolation circuit is l used to isolate each sensor from the network. This provides extra assurance , that the failure of any one sensor will not result in the failure of the entire string. A.2.b. Pg$gg , Two Paroscientific Series 1000 digiquartz Intelligent Transmitters were utilized to measure total containment pressure. Each transmitter was ! calibrated from 0 to 100 PSIA. Primary containment pressure was sensed by the ; pressure gauges in parallel through a tygon tube connected to pressure taps associated with the Unit Two CAM return to drywell penetration. Each instrument consists of a standard Paroscientific pressure transducer l and a digital interface board in an integral package. The digital board has a i microprocessor-controlled counter and RS-232 port. The microprocessor operating program is stored in permanent memory (EPROM). User controllable 4 parameters are stored in user writable memory (EEPROM). The user interacts with the transmitter via the two-way RS-232 interface. The microprocessor monitors incoming commands from the computer. When a sampilng command is received, the microprocessor selects the appropriate-frequency signal source and makes a period measurement using a 124.5 MHz ; timebase counter. The counter integration time is user selectable. Some commands require measurements of both temperature and pressure signals. In that case, the temperature period is measured first, followed by the pressure period. When the period measurement is completed, the microprocessor makes j the appropriate calculations and loads the data onto the RS-232 bus. Each pressure transmitter was calibrated from 0 to 100 PSIA by Pre-Cal Services, Inc. on March 25, 1993. A.2.c. Vapor Pr.elsEe Ten relative humidity sensors were used to determine the partial pressure I due to water vapor in the containment. The humidity sensors used were Graftel, Inc. Model 9203 Relative Humidity Sensors. These sensors utilize a temperature compensated bulk polymer chip. They have an equivalent accuracy - of 2*F dew temperature, and are unaffected by most commonly present chemical vapors. nom . i Each RH sensor is mated to the signal conditioning circuitry, A/D i converter, CPU, EEPROMs and RS-485 network interface. An'RS-485 isolation circuit is used to isolate each sensor from the' network. This provides' extra i assurance that the failure of any one sensor will not result in the failure of ! the entire string. A.2.d. flow , t A rotameter flowmeter, Fischer-Porter serial number 8405A0348A1, was used ; for the flow measurement during the induced leakage phase of the IPCLRT. The flowmeter was calibrated by Fischer-Porter on November 30, 1992, to within 1% . of full scale using NBS tra:eable standards, to standard atmospheric l conditions. Plant personnel continuously monitored the flow during the induced leakage phase and corrected any minor deviations from the induced flow rate of 8.0 SCFM by adjusting a 3/8" needle valve on the flowmeter inlet. The flow meter outlet was unrestricted and vented to the atmosphere. A.3 Iype A Test Pressurization t Two PTS 1500 CFM diesel drive, oil-free air compressors were used to pressurize the primary containment. The compressors were physically located outside the Reactor Building. The compressed air was piped using flexible - metal hose to the Reactor Building, through aa existing four inch fire header penetration, and piped to a temporary spool uiece that, when installed, allowed the pressurization of the drywell through the "A" containment spray ; header. The inboard, containment spray isolation valve, MO-1-1001-26A was ; open during pressurization. Once the containment was pressurized, the MO-1-1001-26A valve was closed and the hoses were disconnected at the fire header penetration. 6 i g i f L b Tecw w4

Figure 2 Temp./R.H. Sensing ,

Device Interconnection Diagram OUTSIDE CONTAINMENT INSIDE CONTAINMENT t String #.. ' - - REPEATER SMART **** SMART CHANNEL #1 - 220 OEM S MSOR SENSOR REPEATER i : < i , CHANNEL #N l SMART **** SMART 220 OHM l SENSOR SENSOR , String #N CONVERTER , I I I PRESSURE I A/B SWITCHING PRESSURE BOX TRANSPa m x TRANSPa m x

1001 # 1002 COMPuuR -******- MODEM COMM MODEM PORT l

i t SECTION 8 - TEST METl100 : B.1 hsklectinLque 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 rates calculation include subvolume weighted containment temperature, subvolume weighted vapor pressure, and tota' absolute air pressure. As required by the Commission in order to perform a short duration test (measured leak rate phase of less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) the measured leak rate was statistically analyzed using the principles outlined in BN-TOP-1, Rev. 1. A least squares regression line for the measured total time leak rate versus i time since the start of the test is calculated after each new data set is scanned. The calculated leak rate at a point in time, tj, is th leak rate on the regression line at the time tj. The use of a regression line in the BN-TOP-1, Rev. 1 report is different , from the way it is used in the ANSI /ANS 56.8 standard. The latter standard r 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-1, Rev. I calculates a regression line for the measured leak rate, which is a function of the change in dry air mass. For the ANSI /ANS 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. I method the ideal slope is , zero, since you presume that the leakage from the containment is constant over time. Since it is impossible to instantaneously and perfectly measure the containment leakage, the slope of the regression line will be positive or i' negative depending on the scatter in the measured leak rate values obtained early in the test. Since 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 titled " Calculated Leak Rate" actually has printed out the regression line values (based on all the measured leak rate data computed from the data sets received up until the last time listed on the printout). The calculated leak rate as a function of time (tj) can only be calculated from data

available up until that point in time, t i. This is significant in that the calculated leak rate may be decreasing over time, despite a substantial positive slope in the last computed regression line. Extrapolation of the regression line is not required by the BN-TOP-1, Rev. 1 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 '

extrapolated to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The distinction between the regression line values and the calculated leak rate as a function of time is made in Section 6.4 of BN-TOP-1, Rev.l. Calculated leak rates, as a function of time, are correctly printed out in the " Trends Based on Total Time Calculations" computer printouts in Appendix B of BN-TOP-1, Rev. 1. um m i Associated with each calculated leak rate is statistically derived upper confidence limit. Just as the calculated leak rate in BN-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 t-distribution used in the ANS/ ANSI standard) and the standard deviation of the measured leak rate data about the computed regression line (which 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. Hith 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 in Appendix E for the statistically averaged leak rate and upper confidence 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 VerificatipB_ Int The supplemental verification test superimposes a known leak of approxi-mately the same magnitude as LA (8.16 SCFM or 1.0 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 i leak rate phase of the test. The allowed error band is i 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. B.3 Instrx.meRLEttor_ analysis Instrument error analysis was not performed. For explanation and justification see Appendix C. It is extremely important during a short duration test to quick'" identify a failed sensor and in real time back the spurious data out of the - ia-lated volume weighted containment temperature and vapor pressure. Failurs . to so , can cause the upper confidence limit value to place a short duratiot, tait in . jeopardy. It has been the station's 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, no instrument failures were encountered during the test. nem i i I SffDDN C - SE00EttCLQF EVENTS C.1 IfL5t Prep 3 ration Chronology The pretest preparation phase and containment inspection was completed on May 18, 1993 with no apparent structural deterioration being observed. Major preliminary steps included:

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

2) Installation of all IPCLRT test equipment in the suppression chamber.

3) Completion of all repairs and installations in the drywell affecting primary containment.

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

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

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

This test was conducted at the end of the refuel outage to test the containment in an "As left" 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. 4 l i l TECH M4 - l4 - l l I c.2 Iesl Pre 55urjZallon_aud_SlabilIIallon_CittQaQlRgy RAIE IIBE EVENT 5-18-93 0008 Began Pressurizing containment. 0045 Snooping began. ! 0115 Small leak found on 1/4" line ' 2-2599-158, ACAD Bleed Vent Valve. Not considered significant. 0122 Top of Torus snooped. Small flange leak on 2-1601-60 valve. Not considered significant. 0125 Reactor Building snooped. Small leak on 1/2" line off of the X-44 penetration. Not considered significant. 0135 Reactor Building Basement snooped. No leaks found. 0215 Snooped MSIV Room. No leaks found. 0607 Pressurization complete. 1058 Containment temperature stable, changing less than 0.5 degrees per hour for last 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . Reactor water level change less than 1.25 inches per hour for last hour. Reactor water , temperature change less than 2 degrees F per hour for last hour. All stabilization criteria satisifed. C.3 lie ASuted_LeLK,_ Rale _ Phaie_Ch ronol ogy DAIE IIME EVENT 5-18-93 1058 Began measured phase. Base data set

62.

l 1400 Sending crews back out to snoop based ' on elevated leak rate results compared to most recent Unit Two ILRT. I itch z. DAIE IJBE EVENT-1540 Leak previously identtified at the X penetration has degraded. Leakage estimated at 25-80 scfh. The 1-4199-127 Fire Header Valve was also found to have a packing leak. This valve is part of the pressurization pathway and is not an Appendix J barrier. The leakage from the 4199-127 valve was eliminated by tightening down ' on the valve packing. k 1730 Leakage from the X-44 penetration. ! determined to be from a crack in the r tubing on the Oxygen Analyzer Sample - Line. Decision made to continue with the test and repair line after the test. 1840 Terminated measured leak rate phase at - 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months 42 minutes, base date set

106. Calculated leak rate was 0.4373 wt%/ day and decreasing over time. The BN-TOP-1 upper confidence limit was 0.5064 wt%/ day.

C.4 IILduallfakage Phaie_Chr2rtology 5-18-93 1850 Valved in flowmeter at 8.0 SCFM and began induced phase stabilization with base date set #107. 2000 Following the I hour stabilization required by BN-TOP-1, the induced phase of the test was begun with base date set #114. 5-19-93 0010 Terminated induced phase at data set

139, calculated leak rate of 0.9612 wt%/ day.

C.5 Deprenurintion 0453 Depressurization 1600 Technical damage and instruments still in place. nu m l l SEEll0LQ - TYPE A TESLDATA short duration test D.2 InducelleAkage r l l [ new3u l TABLE 3 - MEASURED QUAD CITES I 2 l ROG TIME %fday %ldey %Iday 60 68 80.05 0.5092 0.4795 79 190.10 0.5089 0.4980 87 270.15 0.4887 0.4886 88 280.15 0.4884 0.4869 t 90 300.17 100 401.22 l l l i TABLE 4-INDUCED l RDG TIME TT Meas %Iday %lday %fday ; 114 0.00 0.0000 118 40.02 1.1936 119 50.03 1.2375 121 70.03 1.2338 Calculated Total Time Calculated Total Time leek < Phase Chronology 5-19-93 0030 Began depressurization using procedure for venting through the Standby Gas Treatment System. complete. Staff personnel entered drywell. No apparent structural , ; i D.1 Measured _LeALRate_Ehaie_Raia A summary of the computed data using the BN-TOP-1, Rev. I test method for a ! 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 E-1. A summary of the computed data using the ANS/ ANSI standard is found in Appendix E. 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 Mass BN-TOP-1, Rev. 1 method are shown in Figure 7. Containment conditions during the Induced Leakage Phase are presented graphically in Figures 8-10. ! LEAK RATE TEST RESULTS ! TT Meas TT Calc TT UCL 0.00 0.0000 0.0000 0.0000 61 10.00 0.7197 0.0000 0.0000 62 20.02 0.4445 0.4445 0.0000 63 30.02 0.5100 0.4532 1.8002 64 40.02 0.5169 0.4663 1.0591 65 50.03 0.5198 0.4766 0.8802 66 60.03 0.4971 0.4718 0.7818 67 70.03 0.5111 0.4766 0.7384 + 0.7089 69 90.05 0.5066 0.4811 0.6866 70 100.05 0.5411 0.4944 0.6878 71 110.07 0.5220 0.4982 0.6770 72 120.07 0.5174 0.4998 0.6663 73 130.07 0.5062 0.4980 0.6539 74 140.08 0.5089 0.4975 0.6446 75 150.08 0.5068 0.4967 0.6362 76 160.08 0.5106 0.4971 0.6301 77 170.10 0.5166 0.4987 0.6264 78 180.10 0.5065 0.4980 0.6206 ; 0.6160 80 200.12 0.5105 0.4983 0.6124 81 210.12 0.4959 0.4961 0.6062 82 220.12 0.5085 0.4963 0.6032 83 230.13 0.5054 0.4961 0.5999 84 240.13 0.4882 0.4932 0.5941 85 250.13 0.4907 0.4911 0.5893 86 260.15 0.4986 0.4905 0.5863 , 0.5820 , 0.5782 89 290.17 0.4847 0.4850 0.5742 , 0.0000 0.0000 0.0000 3 91 311.17 0.4623 0.4784 0.5664 92 321.18 0.4579 0.4739 0.5603 93 331.18 0.4532 0.4693 0.5543 94 341.18 0.4538 0.4655 0.5488 95 351.20 0.4577 0.4625 0.5443 96 361.20 0.4573 0.4598 0.5401 97 371.20 0.4526 0.4569 0.5358 98 381.22 0.4515 0.4542 0.5318 99 391.22 0.4508 0.4517 0.5280 ' i 0.4503 0.4494 0.5245 101 411.23 0.4494 0.4472 0.5212 102 421.23 0 4465 0.4449 0.5178 103 431.23 0.4438 0.4427 0.5145 104 441.25 0.4436 0.4406 0.5114 105 451.27 0.4472 0.4390 0.5089 106 461.25 0.4449 0 4373 0.5064 l LEAKAGE PHASE TEST RESULTS """" l QUAD CITIES 2 TT Cale TT UCL i 0.0000 0.0000 115 10.00 1.1783 0.0000 0.0000 116 20.02 1.1324 1.1324 0.0000 117 30.02 1.2064 1.1864 1.6606 : 1.1956 1.3700 i 1.2256 1.3433 120 60.03 12254 12340 1.3251 ~ 1.2421 1.3183 122 80.05 1.2458 1.2517 1.3177 123 90.05 1.2359 1.2537 1.3167 124 100.05 1.2653 1.2649 1.3217 125 110.07 1.2529 1.2686 1.3232 126 120.07 1.2468 1.2692 1.3240 127 130.07 1.2612 1.2733 1.3257 128 140.08 1.2531 1.2742 1.3264 129 150.08 1.2553 1.2752 1.3270 130 160 08 1.2524 1.2752 1.3271 131 170.10 1.2511 1.2748 1.3270 132 180.10 1.2733 1.2788 1.3200 133 190.10 1.2647 1.2804 1.3296 134 200.12 1.2611 1.2809 1.3298 135 210.12 1.2721 1.2832 1.3309 136 220.12 1.2605 1.2831 1.3309 137 230.13 1.2558 12822 1.3307 138 240.13 1.2515 1.2806 1.3301 139 250.13 1.2446 1.2782 1.3292 I Leak & Total Time Leak at UCL QUAD CITIES 2 _ Total Time Leak at UCL 2.0 NOTE: Approximately 5 hrs. into the 2

test the pressure tubing to the pressure transmitter disconnected. One data set was affected. This is the reason for the discontinuity on the graph.

1.5 i M I 0' 5 I to d 1.0 w a Y i i.m, { 0E ~ d l c \ 0 , i a j! e) Iu 2 I k7 i \i i 0.0 ,. i r- i i i < < l i. . . . 4 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 Time Hours .. __.._ _ _ _-_______.._-..___. _ __ . - . ~ . . . _ . _ - . . _ - . _ . _ . . . . . . . _ _ _ . ~ . . . _ _ _ _ . ~ . . _ _ . . . Average Pressure QUAD CITIES 2 65.0,-------------------- ---- - - - - - - - - - - - - - - - - - - - - - - -- 64.9 -j I 64.8 ' 64.7 - i l l i 5 e 64.6 j on U l 5 P ! l 64.5 f ~ , . '~x 64.4 d % l _ ___~ ~ - ~ ~.__ ~7 p% _ 64.3 - ' -a I I 64.2 -j l 3 i 64.1 . i i ! l I I 64.0 -t , , c- i 1 : , i , , 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 6.5 7.0 7.5 Time - Hours _ _ . . , _ ~ _ . . . . _ _ _ ._. . __ - .. - _. _ . . . _ _ - . _ . . - _ _ _ . . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . _ m nogm (n 4i - 5 77 ' 0 , 7 ~ , 5 . 6 ~~ i 0 6 _ ~ % ~ - ~ ' 5 ' 5 ~ - ~ 0 ~ - ~- i 5 ~ e ~ ~ r ~ u ~ . 5 s ~ ~ 4 _ s - ~ e r _ s 0 ur P S - ~ _ r 4 oH rE - oT I I - ~ e im pC D 2 - r 5 T aA U - . 3 VQ - .m e g a N 0 3 r , e - v - ~ T 2 5 A - ' - s ~ ' 0 - 7 2 .~ ~ , 5 1 N, -r 0 - s 1 -s 5 x' 0 _ t!l!Iii).I!,IpJ! - 0 - - 0 0 3 6 9 1 4 7 0 0 9 8 7 7 6 5 5 5 4 4 4 4 4 4 4 0 0 0 0 0 0 0 U p ,,e g 6y Average Temperature QUAD CITIES 2 90 5 r- - -- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -~ --- -- - - - - - ' - - - - - - - - l l ! l t i ! ! I l 90.2 i l l gm I {N ',. l ._s_,' ' - 89.8 1 __. ~~. '^'~~~. j ~ ~ ' ~ ~ _ _ $ 4 w - ~ _ _ - 'g ' a 89.5 , e p l 89.2 d l l 88.8 j l I l l 88 5 ? --- , , , , 2 -- ,- r - 7-- l 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 6.0 0.5 7.0 7.5 Time - Hours % n* " iIl. =!ili ! 3ii ' -r0 - 4 . 5 3 0 . - , 3 k - - a - - e - - 5 L - 2 e - i m - + - s T S r u o l E - H aT ~ I _ ~ e tI , 02 rn ~ C 2 oD A T TUQ - - d - . t e - l a -- u - , 5 l c - 1 . a - C - 0 m e o w 1 .- 5 0 Y c. p - {l - - jl ll!!I e ill! : ll;l! , iI 0 7iI , t!!ii-y - - - + O 0 7 4 } 9 6 3 0 2 1 1 } 0 0 0 0 %I d a 1 lY' Average Temperature QUAD CITIES 2 89.60 --- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -

m i

89.55 ,

t k

s.

~.,

N

89.50 i s-s s 2 4 l w __ g y ,

'N._- E i s

's '

p 89.45 4

,'s_--x

~N N s 89.40 - N x

'x

'w -

s.,

8135 -

89.30 , ,

i r T >

0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 Time Hours

%0 9%m *

]

~

0 4

m N

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r 5 3

s

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~

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7 6 6 6 6 6 6 6 _

4 4 4 4 4 4 4 4 ,.

0 0 0 0 0 0 0 0 _

p si a hf _

~

Average Pressure QUAD CITIES 2

641,0 - --- - - - - - - - ---

3 - - - - - - -- ,

I i

L 64.28 -I

64.26 - '

s x

64.24 1 x

' N, x' m i

64.22 9 x N

y hJ c y p N,'N e1 S

s 64.20 a .s

'x -

5 a -x N

\s 64.18 - N N

N N

x 64.16 -

sN

'N 'N

's,'

64.14 - N N x 64.12 64.10 -- i r 7 , r-- -- 7 r r---

0.0 0.5 10 1.5 2.0 2.5 3.0 3.5 4.0 Time Hours

L SECTION E - TEST CALCULATIONS Calculations for the IPCLRT are based on the BN-TOP-1,Rev.1 test method.

A reproduction of the BN-TOP-1, Rev. I method can be found in Appendix C. In preparing for the first Quad Cities short duration test using BN-TOP-1, Rev. 1 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. 1 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 changes may be required by regulations.

A. " Containment Atmosphere Stabilization" Once the containment is at test pressure the containment atmosphere shall be allowed to stabilize for about four hours (4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months required by Quad Cities procedure and actual stabilization: 4 hrs, 51' 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 SEI* AVE J M TAINMERT TEMP. _AI 60 90.005 -

54 90.200 0.195 48 90.473 LZZ3 average 0.234*F/ hour -

Approximate time interval between data sets is 10 minutes.

or

2. "The rate of change of temperature changes less than O.5*F/ hour / hour averaged over the last two hours."

(Not required if A.1 satisfied).

B. Data Recording and Analysis )

1. "The Trend Report based on Total Time calculations shall indicate that the magnitude of the calculated leak rate is tending to .

stabilize at a value less than the maximum allowable leak rate '

(LA) "-

l neen.

= . .

t By Quad Cities procedure the calculated leak rate must be less than 0.75 LA. The actual value was 0.4373 LA, stable, and decreasing (no extrapolation required).

and

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 Cities procedure the upper confidence limit must be less t than 0.75 LA. The actual value was 0.5064 LA- '

and

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 leak rate."

By Quad Cities procedure this average must be less than 0.75 LA* i The actual value was 0.4721 LA for the last five hours, and

4. " Data shall be recorded at approximately equal intervals and in no case at intervals greater than one hour."

At Quad Cities data scans are automatically performed on 10 minute intervals.

aad

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

There were 47 data sets taken for this test. :

and [

6. "In no case shall the minimum test duration be less than six (6) ,

hours."

Quad Cities' procedure limits a short durrtion test to a minimum of six (6) hours.

The data taken during this test supports the ;

argument that a shorter duration test can be conducted. All of the above termination criteria were satisfied in six (6.0) hours.

SECTION F - TYP.E_A TEST RE.SULTS i

, F.1 tienuted_LeaLRatt_le.s.t_Relults Based on the data obtained during the short duration test, the following I results were determined: (LA - 1.0 wt %/ day)

I l

TECH 364 l

1) Calculated leak rate equals 0.4373 wt %/ day and declining steadily over time (<0.7500 wt %/ day).

2) Upper confidence limit equals 0.5064 wt %/ day and declining (<.750 wt

%/ day).

3) Mean of the measured leak rates for the last 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months (31 data sets) ,

equals 0.4721 wt %/ day (<0.750 wt %/ day).

4) Data sets were accumulated at approximately 10 minute time intervals and no intervals exceeded one hour.

5) There were 47 data sets accumulated in 6.166 hours0.00192 days 0.0461 hours 2.744709e-4 weeks 6.3163e-5 months measured phase.

6) The minimum test duration (by procedure) of 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months was successfully accomplished O. 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ).

F.2 Jndged_ Leakage Test Results A leak rate of 8.0 scfm (0.9612 wt %/ day) was induced on the primary containment for this phase of the test. The leak rates during this phase of the test were as follows. ,

BN-TOP-1 Calculated Leak Rate 0.4373 0.4373 (Measured Leak Rate Phase)

Induced Leak (8.0 scfm) 0.9612 0.9612 l Allowed Error Band 0JE00 -0J500 1.6485 1.1485 BN-TOP-1 Calculated Leak Rate 1.2782 wt %/ day (Induced Leak Rate Phase) ;

The induced phase of the test has duration criteria given in Section 2.3.C of ,

BN-TOP-1. The test duration requirements are listed below and were satisfied by the test procedure and the data analysis:

1. Containment atmospheric conditions shall be allowed to stabilize for about one hour after superimposing the known leak. (actual

I hour, 10 minutes)

]

2. The verification test duration shall be approximately equal to half j the integrated leak rate test duration. (actual: 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , 10 minutes for a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months , 42 minute test) r

3. Results of this verification test shall be acceptable provided the correlation between the verification test data and the integrated leak rete test data demonstrate an agreement within plus or minus 25 ;

percent. (actual: see results above)

TECH $64 !

\

l

F.3 Pre-Op.er3tional Results vs Test Resulti Past IPCLRT reports have compared the results of each test with the pre-operational IPCLRT, performed in August of 1971. Over the last 22 years, different test equipment, sensor locations and number of sensors, test methods, and test duration have been used. This test yielded results that compare favorably with recent tests and demonstrate that there has been no substantial deterioration in containment integrity.

TEST DURATION CALCULATED LEAK RATE STATISTICALLY AVE.

lESLDME (HOURS) (BH-TOP-1) LEAK RATE (ANSI /MSl April 1971 24 Not Available 0.111 February 1976 24 Not Available 0.3175 December 1982 12 0.4532 0.3796 July 1984 24 0.4281 0.2297 March 1986 12 0.2286 0.2286 December 1987 6 0.3194 0.3162 November 1989 6 0.3786 0.3714 March 1991 24 Not Available 0.6069 December 1992 6 0.1471 May 1993 7 hrs, 42 min 0.4373 f.4 T EE A TEST PEM&LIlES During the type A test, there were a number of systems that were not drained and vented outside the containment. The isolation valves for these systems or penetrations were not " challenged" by the type A test. Even though these systems would not be drained and vented during a DBA event, historically, penalties for these systems have been added to the type A test results.

AS LEFT MINLMUM PATHHM_LEM&E SffH HI%fDM Primary Sample 0.1 0.00020 A & B Feedwater 1.3 0.00265 TIPS 0.35 0.00071 RHR A 25.1 0.05127 RilR B 13.95 0.02849 SBLC 6.0 0.01225 RHCU 1.86 0.00380 Core Spray 6.0 0.01225 HPCI (Steam Exhaust) 0.75 0.00153 RBCCH 1.1 0.00225 Clean Demin 0.0 0.0 07 Analyzer 1.7 0.00347 CAMS 0.65 0.00133 ACAD _Q115 D,0DD31 Totals 59.01 0.1205 This penalty increases the type A test result to 0.5578 wt%/ day with an upper confidence limit of 0.6269 wt%/ day.

nce .

F.5 EVALUAUO!LQLHISIRVELNT FAILURES There were no instrument failures during the test.

F.6 AS_E0VND_IYELA_IESLRESULIS The following table summarizes the results of all typa B and C testing, as '

well as the IPCLRT results to arrive at an "As Found" type A test result.

This is considered a passing "As Found" type A test, makin) two consecutive- ;

passing "As Found" tests on Unit Two. Due to a Tech Spec exemption relating i to bellows testing, the Station is required to maintain the current schedule of performing an ILRT every refuel outage. :

SUMMARLOCALLCONTAINMENI LEALRATE_IESIlliG_RURItiG UtiLI_THO. REEUEL_ QUI 6GE SPRING. 1992 ASl0VNDlSCD11 AS_LEEL1SCDD MINIMUM PATHHAY MINIMUM PATHWAY j LEAKAGE LEAKAGE (1) MSIV's @ 25 PSIG 19.59 10.22 (2) MSIV's converted 33.89 17.68 to 48 PSIG* i (3) All Type C Tests 90.4 97.81 (Except MSIV's)

(4) All Type B Tests 17.6 15.02 s i

TOTAL (2 + 3 + 4) 141.89 130.51 (1) Type A Test Integrated Leak Rate Test) - 0.4373 wt %/ day *

(2) Upper Confidence Limit of Type A Test Result - 0.5064 wt %/ day i (3) Correction for Unvented -

Volumes During Type A Test - 0.1205 wt %/ day (4) Correction for Repairs :

Prior to Type A Test = 0.1090 wt%/ day ,

(As found - As left)

Total (2 + 3 + 4) = 0.7359 wt%/ day ,

Leak Rate at 25 PSIG converts to Leak Rate at 48 PSIG using conversion I ratio of 1.73. REFERENCE Leaking Characteristics of Steel Containment ,

Vessels & the Analysis of Leakage Rate Determination, Division of Safety ,

l Standards, A.E.C. TID-20583, May 1964, pg. 76.

nen m ,

f

APPENDIX _a TYPE B AND C TESTS F

Presented herin are the results of local leak rate tests conducted on all penetrations, double-gasketed seals, and isolation valves since the previous IPCLRT in April 1990. Total leakage for double gasketed seals and total leakage for all penetrations and isolation valves following repairs satisfied the Technical i Specification limits, I

I ncH

l

\

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

l TEST DIRECTOR Mgy . _ DATE: 5~/27/93 DATE j.E7-f_y OPERATING ENGINEER j OUTAGE lQ2R12 l l TECli STAFF StIPERVISOR # DATE: #/t7/A.F AS FOUND (SCFil) AT 25 PSIG AS LEFT (SCFil) AT 25 PSIG l VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM

DESCRIPTION PENETRATION DATE LEAKAGE PAT 11WAY PATilWAY DATE LEAKAGE PATIIWAY PATilWAY A MSIV AO 203-1A 03/07/93 combined 03/07/93 combined AO 2u3-2A 03/07/93 5 93 2.97 5.93 03/07/93 5.93 2.97 5.93 B MSIV AO 203-1B 03A)7/93 12.62 04A)3/93 combined ,

AO 203-2B 03/07/93 76 7 12 62 76.7 04/03/93 65 3 25 6.5 t -

C MSIV AO 203-lC 03/07/93 combined 03/07/93 combined AO 203-2C - 03/07/93 3.2 1.6 3.2 03/07/93 3.2 1.6 3.2 D MSIV AO 203-ID 03/07/93 combined 03/07/93 combined AO 203-2D 03/07/93 4.8 2.4 4.8 03/07/93 4.8 2.4 4.8 TOTAL p 19.59 90.63

) TOTAL g 10.22 20 43 h3

CORRECTED TOTAL 33.8907 156.7899 )* CORRECTED TOTAI 17.6806 35 3439 <r p%ls s$s emf /*YO P},fa

To determine the corrected leakage of MSIVs (as if they had been tested at 48 psig), multiply the 25 psig total by 1.73.

AS FOUND (SCFil) AS LEFT (SCFil)

VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE hENIMUM MAXIMUM DESCRIPTION PENETRATION DATE I.EAKAGE PAT 11WAY PATIIWAY DATE LEAKAGE PATIIWAY PATIIWAY MSL DRAIN MO 220-1 03/07/93 combined 05/11/93 combined MO 220-2 03/07/93 0 0 0 05/11/93 0 0 0 PRIMARY SAMPLE AO 220-44 03/25/93 combined 03/25/93 combined AO 220-45 03/25/93 02 0.1 0.2 03/25/93 02 0.1 02 A FEEDWATER CK 220-58A 03/31/93 0 03/31/93 0 CK 220-62A 03/31/93 24 0 24 04/27/93 1 0 1 B FEEDWATER CK 220-58B 03/08/93 1.3 03/08/93 1.3 CK 220-62B 03/08/93 3.2 1.3 3.2 04/17/93 4.3 1.3 4.3 PAGE TOTAL 1.4 27 4 PAGE TOTAL 14 55 f*I 'N '

0[

l REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFil) AS LEFT (SCFID l VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIP I'lON PENETRATION DATE LEAKAGE PATIIWAY PATIIWAY DATE LEAKAGE PATilWAY PATilWAY TIP DALL VALVES SO 737-1B 03/08/93 0 0 0 03/08/93 0 0 0 SO 737-lC 03/08/93 0.2 0.1 0.2 03/08/93 0.2 0.1 0.2 SO 737-ID 03/08/93 0 0 0 03/08/93 0 0 0 l SO 737-lE 03/08/93 0.2

0.1 0.2 03A)8/93 0.2 0.1 0.2

.SO 737-lF 03/08/93 0.3 0.15 0.3 03/08/93 0.3 0.15 0.3 TIP PIIRGE CHECK val VE ICK 741 01/08/91I OI O- 0 03/08/911 0 01 0 A DRYWELL SPRAY MO 1001-23A 03/18/93 combined 04/05/93 combined MO 1001-26A 03/18/93 0.8 0.4 0.8 04/05/93 1 0.5 i B DRYWELL SPRAY MO 1001-238 03/18/93 combined 04/22/93 combined MO 1001-26B 03/18/93 20 10 20 04/22/93 0.4 0.2 0.4 A RIIR RETliRN lMO 1001-29A 03/i7/93 4.6 4.6 46 04/30/93 21851 21 85 21.85 B RilR RETURN lMO 1001-29B 03/17/93 4.1 4.1 i 4.1 04/21/93 11 11 11 A TORUS COOLING SPRAY MO 1001-34A 03/17/93 combined 04/30/93 combined MO 1001-36A 03/17/93 combined 04/30/93 combined MO 1001-37 A 03/17/93 3.9 1.95 3.9 04/30/93 5.5 2.75 5.5 B TORUS COOLING SPRAY MO 1001-34B 03/17/93 combined 04/27/93 combined _

MO 1001-36B 03/17/93 combined 04/27/93 combined MO 1001-37B 01/17/93 16 08 16 04/27/93 55 2 75 55 SIIUTDOWN COOLING MO 1001-47 03/17/93 0 03/17/93 0 MO 1001-50 03/17/93 0 0 0 03/17/93 0 0 0 SBLC CK 1101-15 03/23/93 9 03/23/93 9 CK 1101-16 03/23/93 6 6 9 03/23/93 6 6 9 CLEAN UP SUCTION MO 1201-2 03/12/93 12 05/06/93 6.07 MO 1201-5 03/12/93 0 0 12 05/06/93 1 86 1.86 6 07 RCIC STEAM SUPPLY MO 1301-16 03/07/93 combined 05/12/93 combined MO 1301-17 03/07/93 03 0.15 03 05/12/93 6 3 6 PAGE TOTAL 28 35 l 57 PAGE TOTAL 50.261 67.02 C P f U 1f

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFH) AS LEFT (SCFH)

VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM 4

DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATHWAY RCIC VACUUM PUMP EXHAUST CK 1301 40 03/08/93 38 3.8 3.8 03/03/93 3.8 3.8 3R RCIC STEAM EXHAUST CK 1301-41 03/16/93 12.5 12.5 12.5 05/13/93 17 17 17 A CORE SPRAY MO 1402-24A 03/07/93 6 03/07/93 6 MO 1402-25A 03M7/93 7 6 7 03/07/93 7 6 7 B CORE SPRAY MO 1402-24B 03/07/93 6 04/0163 0 MO 1402-25B 03/07/93 4 4 6 04/17/93 10 0 10 h A TORUS / REACTOR BUILDING AO 1601-20A 03/19/93 11.2 05/13/93 1.2 VACUUM BREAKER CK 1601-31 A- 03/19/93 16.5 11.2 16.5 05/13/93 0.8 0.8 1.2 O' B TORUS / REACTOR BUILDINO A.O 1601-20B 03/19/93 1.8 05/13/93 0.3 f 0.8 0.3 0.8 C, VACUUM BRCAKER CK 1601-31B 03/19/93 0.8 0.8 1.8 - 03/19/93

, DRYWELIIFORUS (1) AO 1601-21 03/19/93 0.2 03/19/93 0.2 PURGE SUPPLY AO 1601-56 03/19/93 0 05/13/93 0 AO 1601-22 03/19/93 combined 03/19/93 combined AO 1601-55 03/19/93 4.5 0.2 4.5 03/19/93 4.5 02 4.5 DRYWELl/f0RUS (2) AO 1601-23,62 04/27/93 3.55 04/27/93 3.55 PURGE EXHAUST AO 1601-60.61 03/11/93 1 04/27/93 0.6 AO 1601-24.63 03/08/93 2.7 2.7 4.55 04/27/93 7 4.15 7 DRYWELilf0RUS (3) AO 1601-57 03/19/93 combined 03/19/93 combined NITROGEN PURGE RV 1699-9 03/19/93 5 03/19/93 5 AO 1601-58 03/19/93 0 03/19/93 0 AO 1601-59 03/19/93 0 0 5 03/19/93 0 0 5 PAGE TOTAL 41.2 ;

61.65 PAGE TOTAL 32.25 56.3

Phy Pfcl*

p, p! ,,l6 (1) The MNPLR/MXPLR is the lesser / greater combined leakage value of 1601-21,56 or 1601-22,55 (2) The MNPLR/MXPLR is the lesser / greater combined leakage value of 1601-24,63 or 1 o01-23,62,60, and 61 (3) The MNPLR/MXPLR is the lesser / i;reater of the combined leakage of 1601-58,59 or 1601-57 and RV 1699-9

~

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFH) AS LEFT (SCFH)

VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATIIWAY DATE LEAKAGE PATHWAY PATilWAY DRYWELL FLOOR DRAIN SUMP AO 2001-3 03/25/93 1.6 03/25/93 1.6 AO 2001-4 03/25/93 1.8 1.6 1.8 03/25/93 1.8 1.6 1.8 DRYWELL EQUIPMENT AO 2001-15 03/1663 combined 05/10/93 combined DRAIN SUMP AO 2001-16 03/16/93 12.5 6.25 12.5 05/10/93 8.5 4.25 8.5 Td IIPCI STEAM SUPPLY MO 2301-4 03/0763 combined 03/24/93 combined MO 2301-5 03/07N3 16 0.8 1.6 03/24/93 1.6 0R I.6 ,

HPCI DRAIN POT EXHAUST CK 2301-34 03/08/93 3.7 3.7 3.7 04/22/92 0.75 0.75 0.75 i-D IIPCIEXHAUST MO 2399-40 03/25/93 0.6 05et)6/93 0.4 VACUUM BREAKERS MO 2399-41 03/25/93 0.8 0.6 0.8 05/06/93 0 0 0.4 3 RBCCW SUPPLY MO 3702 04/01/93 0.7 05/06/93 0.5 CK 3799-31 03/31/93 0.4 0.4 0.7 03/31/93 0.4 0.4 0.5 RBCCW RETURN MO 3703 04/01/93 2 04/30/93 1.05 MO 3706 04/0I/93 0 0 2 04/30/93 0.7 0.7 1.05 l

CLEAN DEMIN WATER MNL 4399-45 03/10/93 0.1 03/10/93 0.1 CK 4399-46 03/10/93 0 0 0.1 03/10/93 0 0 0.1 SERVICE AIR MNL 4699-46 03/11/93 0 03/11/93 0 CK 4699-47 03/11/93 18.5 0 18 5 03/19/93 0.1 0 0.1

DRYWELL PNEUMATIC AO 4720 03/l1/93 0 03/11/93 0

! AO 4721 03/11/93 0 0 0 03/11/93 0 0 0 PAGE TOTAL 13.35 41.7 PAGE TOTAL 8.5 14.8 Pk (sf Phl0 p ,lO l

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND(SCFH) AS LEFT (SCFH)

VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATHWAY DRYWELLINSTRUMENT AIR CK 4799-155 03/10/93 1.6 03/10/93 1.6 CK 4799-156 03/10/93 2.4 16 2.4 03/10/93 2.4 1.6 2.4 TORUS INSTRUMENT AIR CK 4799-158 03/16/93 1.2 03/16/93 1.2 CK 4799-159 03/16/93 0.9 0.9 1.2 03/16/93 0.9 0.9 1.2 SRM/IRM PURGE CK 4799-353 03/16/93 0.4 03/16/93 0.4 (UNIT 2 ONLY) CK 4799-354 03/16/93 0.4 0.4 04 03/16/93 04 0.4 0.4 AO 8801A 03/23/93 0.2 03/23/93 0.2 AO 8802A - 03/23/93 1.5 0.2 1.5 03/23/93 1.5 0.2 1.5 AO 8801B 03/23/93 0.6 03/23/93 0.6 AO 88020 03/23/93 1.4 0.6 1.4 03/23/93 1.4 0.6 1.4 OXYGEN ANALYZER AO 8801C 03/23/93 0.5 03/23/93 0.5 AO 8802C 03/23/93 1.6 0.5 1.6 03/23/93 1.6 0.5 1.6 AO 8801D 03/09/93 0.1 04/15/93 1.7 AO 8802D 03/09/93 0.4 0.1 0.4 03/09/93 0.4 0.4 1.7 AO 8803 03/09/93 7.9 05/15/93 0 AO RR04 03/09/93 0 0 7.9 03/09/93 0 0 0 DRYWELL PARTICULATE SAMPLE Manual Valves- 03/16/93 LINES (21 lines) 1(2)-8R03 R-to-V-1/2-H 1(218R00-2/3B V NA 0 5.7 03/16/93 NA 0 5.7 l

PAGE TOTAL 4.3 22.5 PAGE TOTAL 4.6 15.9 i

P p b OY l

l l

l 5

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

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFH) - AS LEFT (SCFID VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATHWAY SO 2499-1A 03/13/93 combined 03/13/93 combined ,

SO 2499-2A 03/13/93 0 0 0 03/13/93 0 0 0 SO 2499-1B 03/13/93 combined 03/13/93 combined CONTAINMENT AIR MONITOR SO 2499-28 03/13/93 0 0 0 03/13/93 0 0 0 SYSTEM (CAM) SO 2499-3A 03/13/93 combined 03/13/93 combined SO 2499-4A 03/13/93 0 0 0 03/13/93 0 0 0 SO 2499-3B 03/l1/93 combined 03/l1/93 combined SO 2499-4B 03/11/93 1.3 0.65 1.3 03/11/93 1.3 0.65 1.3 CONTAINhENT AIR MONITOR PNL 2251(2)-81A 03/13/93 2.9 05/14/93 1.2 SYSTEM (CAM) CK 2499-22A 03/13/93 0 0 2.9 05/14/93 0 0 1.2 PANELS PNL 2251(2)-81B 03/12/93 1.5 05/04/93 2.1 CK 2499-22B 03/12/93 0 0 1.5 05/04/93 0 0 21.

AO 2599-2A 03/19/93 0.8 03/19/93 0.8 CK 2599-23A 03/19/93 0 0 0.8 03/19/93 0 0 0.8 ATMOSPilERIC CONTAINMENT AO 2599-2B 03/19/93 0.5 03/19/93 0.5 ATMOSPilERE DILUTION SYSTEM CK 2599-230 03/19/93 0 0 0.5 03/19/93 0 0 0.5 (ACAD) AO 2599-3A 03/23/93 0.8 03/23/93 0.8 CK 2599-24A 03/23/93 0 0 0.8 03/23/93 0 0 0.8 AO 2599-3B 03/23/93 combined 03/23/93 combined CK 2599-24B 03/23/93 0.3 0.15 0.3 03/23/93 0.3 0.15 0.3 AO 2599-4A 03/10/93 combined 05/22/93 0.7 ,

ACAD TO SBGT AO 2599-5A 03/10/93 2 1 2 05/15/93 0 0 0.7 lO i AO' 2599-4B 03/10/93 3 05/15/93 0

, AO 2599-5B 03/10/93 0 0 3 05/15/93 0 0 0 PAGETOTAL 1.8 13.I PAGE TOTAL 0.8 7.7 pf [ dh u_ - ________m_ . _ _ . . _ . - - ,vr.r.ve. - _-werm si rw,-.m .s~_..m --..-,,.wi

__<v,* w g r. #, ew...wwws wm-. +--%.,s-v.----+6 =%a--w,wr,y , ,ay,w - , ,.-,w-w

.. .,.,.m. .,,

~

i REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFID AS LEFT(SCFID VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE IEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATHWAY SL-l 03/26/93 0 0 0 03/26/93 0 0 0 >

SL-2 03/26/93 0 0 0 03/26/93 0 0 0 SL-3 03/26/93 6 3 6 05/12/93 0 0 0 3

S1IEAR LUG SL-4 03/26/93 0 0 0 03/26/93 0 0 0 INSPECTION HATCHES SL-5 03/26/93 0 0 0 03/26/93 0 0 0

, SL-6 03/26/93 0 0 -0 03/26/93 0 0 0 SL 03/26/93 0.2 0.1 02 03/26/93 0.2 0.1 0.2 SL-8 03/26/93 0 0 0 03/26/93 0 0 0 DRYWELL EQUIPMENT HATCH X1 -

03/07/93 0 0 0 05/16/93 3.2 1.6 3.2 DRYWELL PERSONNEL INTERLOCK X-2 03/06/93 13.74 6.87 13.74 05/15/93 17.17 8.59 17.17 DRYWELL ACCESS HATCH X-4 04/02B3 0 0 0 04/02/93 0 0 0 CRD HATCH X-6 03/07/93 0.4 0.2 0.4 05/21/93 0 0 0 J-L X-35A 03/08/93 0.1 0.05 0.1 03/08/93 0.1 0.05 0.1 X-35B 03/08/93 0 0 0 03/08/93 0 0 0 TIP PENETRATIONS X-35C 03/08/93 0 0 0 03/08/93 0 0 0 X-35D 03/08/93 0.2 0.1 0.2 03/08/93 0.2 .

0.1 0.2 X-35E 03/08/93 0 0 0 03/08/93 0 0 0 ,

^

X-35F 03/08/93 0 0 0 03/08/93 0 0 0 X-35G 03/08/93 0 0 0 03/08/93 0 0 0 DRYWELL HEAD Drywell Head 03/08/93 1.8 0.9 1.8 05/17/93 0 0 0 0 PAGE TOTAL 11.22 22.44 PAGE TOTAL 10.44 : 20.87 fCf N Y$ $ 1f

)

h u

W __ _

t .

I REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

l i

AS FOUND (SCFID AS LEFT (SCFH) l ,

l VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATHWAY l

X-7A 03/07/93 0 0 0 03/07/93 0 0 0 X-7B 03/07/93 0 0 0 03/07/93 0 0 0 X-7C 03/07/93 0.4 0.2 0.4 03/07/93 0.4 0.2 0.4 X-7D 03/07/93 0 0 0 03/07/93 0 0 0 I X8 03/07/93 0 0 0 03/07/93 0 0 0 ,

i X-9A 03/07/93 0 0 0 03/07/93 0 0 0 X-98 03/07/93 0 0 0 03/07/93 0 0 0 l 0 0 0 0 MECIIANICAL X-10 03/07/93 0 0 03/07/93 (BELLOWS) X-11 - 03/07/93 0 0 0 03/07/93 0 0 0 l

PENETRATIONS X-12 03/11/93 1.05 1.05 1.05 03/11/93 1.05 1.05 1.05 j X-13A 03/07/93 0 0 0 03/07/93 0 0 0 X-13B 03/07/93 0.1 0.05 0.1 03/07/93 0.1 0.05 0.1 X-14 03/20/93 1.4 1.4 1.4 04/28/93 0 0 0 !.

i X-16A 03/07/93 2.2 1.1 2.2 03/07/93 2.2 1.1 2.2 X-16B 03/07/93 0.3 0.15 0.3 03/07/93 0.3 -

0.15 0.3 X-17 (U-1) NA NA NA- NA NA NA NA NA X-23 03/07/93 0 0 0 03/07/93 0 0 0 X-24 03/07/93 0 0 0 03/07/93 0 0 0 X-25 03/07/93 0.1 0 05 0.1 03/07/93 0.1 0.05 0I

, X-26 03/07/93 0 0 0 03/07/93 0 0 0 X-36 (U-1) NA NA' NA NA NA NA NA NA X-47 03/07/93 0 0 0 03/07/93 0 0 0

, PAGE TOTAL 4 5.55 PAGE TOTAL 26 4.15 Ph$P lO 5

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFH) AS LEFT (SCFH)

VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM ,

g3CRIPTION PENETRATION DATE LEAKAGE PATHWAY PATHWAY DATE LEAKAGE PATHWAY PATilWAY X-100A NA INSTALLED Q2R12 MOD M4-2-92-13 05/14/93 0 0 0 X-100B 04/06/93 1.33 0.67 1.33 04/06/93 1.33 0 67 1 33 X-100C 04/05/93 0 0 0 04/05/93 0 0 0 X-100D (U-1) NA NA NA NA NA NA NA NA X-100E 03/12/93 0.2 0.1 0.2 03/12/93 0.2 0.1 0.2 ;

04/07/93 0 0 0 04/07/93 0 0 0 1100F X-100G 04/07/93 0 0 0 04/07/93 0 0 0 X-101 A 04/07/93 0 0 0 04/07/93 0 0 0 X-101B . 04/07/93 0 0 0 04/07/93 0 0 0 l X-101D 04/07/93' 0 0 0 04/07/93 0 0 0 X-102A (U-1) NA NA NA NA NA NA NA .NA t ELECTRICAL PENETRATIONS X-102B 04/07/93 0.2 0.1 0.2 04/07/93 0.2 0.1 0.2 l

l X-103 03/12/93 0 0 0 03/12/93 0 0 0

! X-104A (U-2) 04/06/93 0.26 0.13 0.26 04/06/93 0.26 0.13 0.26 X-104B 04/06/93 0.41 0.21 0.41 04/06/93 0.41 0 21 0.41 X-104C 04/05/93 0 0 0 04/05/93 0' 0 0 X-104D (U-2) 04/05/93 0 0' 0 04/05/93 0 0 0 X-104F 04/07/93 0.2 0.1 0.2 04/07/93 0.2 0.1 0.2 X-105A 04/06/93 0 0 0 - 04/06/93 0 0 0 X-105B (U-1) NA NA NA NA NA NA NA NA X-105C 03/12/93 0 0 0 03/12/93 0 0 0 X-105D (U-1) NA NA NA NA NA NA NA NA X-106A (U-2) 04/06/93 0 0 0 04/06/93 0 0 0 X-1068 (U-2) 04m7/93 0 0 0 04/07/93 0 0 0 X-107A 03/12/93 0 0 0 03/12/93 0 0 0 X-107B (U-2) 04/07/93 0 0 0 04/07/93 0 0 0 PAGE TOTAL 1.31 2.6 PAGE TOTAL 1.31 2.6 0 P9 t' g1

- ~

REFUEL OUTAGE LOCAL LEAK RATE TEST

SUMMARY

AS FOUND (SCFH) AS LEFT (SCFH) 4 VALVE / TEST VALVE MINIMUM MAXIMUM TEST VALVE MINIMUM MAXIMUM DESCRIPTION PENETRATION DATE LEAKAGE PATHWAY PATilWAY DATE LEAKAGE PATIIWAY PATHWAY TORUS HATCIIES X-200A 03/07/93 0.4 0.2 0.4 05/23/93 0 0 0 E X 200B 03/07/93 04 0.2 0.4 05/16/93 0 0 0 60 TORUS CAM /ACAD X-227A 03/15/93 0.41 0.21 0.41 03/15/93 0.41 0.21 0.41 PENETRATIONS X-227B 03/15/93 0.41 0.21 0.41 03/15/93 0.41 0.21 0.41 A TORUS LEVEL FLANGE A Torus Lev Flana 03/10/93 0.5 0.25 0.5 03/10/93 0.5 0.25 0.5 .

B TORUS LEVEL FLANGE B Torus Lev Flang 03/10/93 0 0 0 03/10/93 0 0 0 PAGE TOTAL 1 07 2.12 PAGE TOTAL ,c 0 67 1.32 g plKQ W (2) (Pl0 (3)

,@(d htM i , TEST TOTAL (1) l 108 l 256.06 l l 112.83 l 196.16 l (1) The test total is the sum of all page totals in the summary (exclude MSIVs from test total). 51 /

(2) When the maximum pathway leakage exceeds 0.6 La (293.75 SCFH), write a DVR immediately. (T.S. 3.7.A.2.C.)

(3) As left max path must be less than or equal to 220.3 I prior to start-up (NRC commitment) i

__ __ . . _ . _ _. _. . _ . _ _ _ _ _ _ -_ u . . . _ _ . - . _ _ _ - - . _ _ . . .

e i

T t

APPENDIX B COMPUTATIONAL PROCEDURE 1

1

~>

t i

t J

I 5

6 I

l

-i

1

'I

. rec +i w4 l

.l 1

D. INPUT PROCESSING'.

Calculations perfomed by the software are_ outlined below:

D.1 Average temperature of subvolume #1 (Ti )

. The average of all RTD temps in subvolume #1 1 N T; . t T;,3 l x j.1 )

where N . The number of RTDs in subwolume #1 I D.2 Average dew temperature of subvolume #1 (Di )

. The average of all dew cell der temps 'in subvolume #1 i

)

1 N :

Di=- I Di ,j i N j.1 .

where N - The number of RTDs in subvolume si !

D.3 Total corrected pressure #1. ,1 (P ) ,

C1 First correction factor for raw pressure #1 (from program !

initialization data set). -

M1 Second correction factor for raw pressure #1 (from program :

initialization data set).

Pr1 Raw pressure 11. from BUFFILE.

P1 . C; , Mi Pri/1000, for 5' digit pressure transmitters I Pi . C; . M1 Pr]/10000, for 6 digit pressure transmitters D.4 Total corrected pressure #2 (P2 )

t C2 First correction factor for raw pressure s2. -(from program l initialization data set. '

M2 Second correction factor for raw pressure F2, (from program initialization dara set. j Pr2 Raw pressure E2. from BUFFILE.

P2*C2*M2 Pf2/1000, for 5 digit pressure transmitters j i P2*C*M2 2 Pr2/10000, for 6 digit pressure transmitters l

"*"a

_e. 3_ i g , , , , _ _ ,_ _ _ . , _ _ _ _ -. r -

D.5 Hnole Containment Volume Heighted Average Temperature. (TC )

Accrorimate N Netnod Tc. I ft Tj ,

11 1

Exact N fi Nethod I 11 Ti vhere: f i. The volume fraction of the ith subvolume N . The total # of sabvolumes in containment D.6 Average Vapor Pressure of Subvolume 1. (Curve fit of ASME steam tables.) (Pvj)

Pvt . 4.D1529125 . p.0016*3476 Dj 7 (Dj)3

- 1.a4734 X 10-(Di)E

- 2.28128 X 10-9 (Di )4 + 7.081828 3.035a4 X 10- Xt 10II (D )5 D.7 Nhole Containment Average Vapo Pressure. (Pyg)

Approximate' N Method Pvg . I fi Pvt 11 Eract N ft Pvt

. Method Pvc . Tc I 11 Tg N . The total of subvolumes in containment f t. Volume fraction of the ith subvolume D.8 Nhole Containment Average Dew Temperature. (Dg)

Approximate N Method De . I ft 91 11 Exact Mether The whole containment average vapor pressure.

(Pve ) calculated with the exact method is used to ,

fins Dg. An initial value of De is guessed and used with the esustion in D.6 to calculate Pvc -

This value is then compared to the k.nown value frem D.7. A new value of De is guessed and the process ,

is repeated until a value of De is found that results in a calculated value of Pvg that is within .0001 psia of 'the value fres 0.7.

t M

l l

D.9 Average to'tal containment pressure,(P)

P.( P1.P2} '2 ,

Average total containment dry air pressure. (Pd )

Pg = P - Pvc D.10 Total Containment dry air mass, (N)

Pd Vc Type 1: M=

R Tc where: R . Perfect gas constant, Vg - 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 Vg . I Vi and fi . Vg/Vg l 11 where Vi is the user entered free volume in subvolume 1.

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

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

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

C is the actual water level in the reactor vessel, in inches.-

Vgg is the volume of the subvolume k when C eguals b.

The volume fractions (fi ) are then calculated with the corrected volume, and all other calculations are subsecuently performed as previously specified for Type i dry air mass.

TECH 304

D.11 Leatrate C*alculations using Mass-Pict Method:

This method assumes that the leakage r1te is constant during the testing period, a plot of the measured contained dry air mass versus time would ideally yield a straignt line with a negative slope.

Based on the least squares fit to the data ettained, the calcula.ed containment leakage rate is octained frem the ecuation:

M At + B Where M = containment dry air mass at time t (1bs.)

B . calculated dry air mass at time t=0 (1bs.)

Ae Calculated leatage rate (1bs/hr) t = time in,terval since start of test (hours)

B H

(1bs) t (hours) -

The values of the constants A and 8 such that the line is linear least scuares best fitted to the lest rate data are:

MI(ti)(Mt ) - (Itt) (I M 1)

A=

KI(tt)I - (Itt )2 IMt -

Atti 8=

N UCH p4

~

_ ___ _ _- _ _ _ _ _ _ . _ _m _ __ ___ __________-__-______________m__

I i

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

L = C '.) (24001/B (weight 11 day) in orcer to calculate the g5% confidence 11af t of the 1 east scuares averaged leat rate, the standard deviation of the least souares s1cce and the student's T-Olstribution function are used as follows: ',

1/

l~~ 1 NI(Mi )2 - (IM1 )2 ~

j~/2(2400)(weight"

' " ~~ per day) g

, __(N-2) NI(tt)2 -

(It])2 __

UCL . L . a (T) ,

1.6449(N-2)

3.5283

0.85602/CN-2) where T. .

(N-2) + 1.2209 - 1.5162/(N-2) .

l N - Number of data sets

test duration at the ith data set (hours) ti standard deviation of least sguares slope (weight;/ day) e

T . Value of the single-sided T-Olstribution function with 2 degrees of freedom L - calculated 1 eat rate in weight 1/ day

(%/ day)

UCL - 95% upper confidence limit B = calculated containment dry air mass at time. t 0 (1bs.)

D 12 Point to Point Calculations This method calculates the rate of change with respect to time of dry air mass using the Point to Point Method.

nem.

~49-

t l

For every data set, the rate of change of dry air mass between l the most recent. (tt) and the previous time (tg.1) is calculated using '

the two point method shown below:

. 2400 C1 ~ H i /HI -I)

Mr* lt -tM) I Then the least scuare fit of the point to point f eatrates is calculated as described for dry air masses in section 0.11 D.13 Total Time Calculations This method calculates the rate of change with respect to time cf dry air mass using the Total Time Method 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, tg is calculated using the two point method shown below. ,

, 2400 Mt .

(1 e Mj 'Mr) >

(tt-tr) l Then the least sources fit and 95% UCI. of the Total Time -

1eakrates are calculated as shown below. !

I Ag Itti)2 - I tt I At tg :

'~

N I (ti)2 - (I tt)2 l

( N I ti Al - I tg I At )

N I (tt)2 - (I ti)2 i

L. 8 . At ,

1.6449(N-2) + 3.5283 0.85502/(N-2) ,

T=_

(N-2) .1.2209 - 1.5162/CN-2)

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

mm

l l

I (tp - .I (t() / N)2 j F= --

N I (t{ )2 . ( g gg 32/g e

i i

/ F /

I (Mj)2 - 8 I A - A I At ti a=/ /

/ l

/ ;

\/ N \/ ;

UCL = L

Ta Note: This ecuation is calculated for information only from the- :

start of the test up to 2a hours, then it becomes the official teatrates for future times.

D.!A BN-70P-1 .

This method calculates the rate of change with respect to the i

time of dry air mass using the Total Time Method.

Initially, a rkference time (tr) is chosen. For every data set t the rate of change of the data item between tr and the most recent time. (1 ) is calculated using the two point method shown below:

3 l

t 2400 Mg . (1 - Mj/Mr)

(ti - tr) :

Then the least sguares fit of the Total Time leakrates and the I BN-70P-1 95; UCLs are calculated as shown below.

( I At I(tt)2 -

I tt I At tt) ,

8-N I (t{)4 - ( I ti )4 Note: N is the number of data sets minus one.

[

I l

1 e

new an i i

~ . . . .

l l

)

" ~ '

{ N I tl A1 ~

I t{ I At ) l N t (ts)4 - it tg)4 ;

L. B - At 2.37226 2.8225 .

7 1.95996 + +

(M - 2) (N - 2)2 :

F.

1 1 , -- . (to - I (tt) / N 32 N I (ti)2 - CI tg)2 / N ;

2 i i F '/ . .

/

/ I (Mg)2 - 8 I Al - A I Mt ti .

e=;/ j

\/ N \/

UCL = L + 1a- ,

Note: This ecuation is calculated for inforration only from the start of the test up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , then it becomes the ,

official leatrates for future times. i e

D.15 Temperature stabilization checking per ANSI 56.3 1961 t

Tj Weighted average containment air temperature at hour i.

7 1 ,n Rate of change of weighted average containment. air temperature.

over an a hour period at hour 1, using a two point backwares difference method, Ti - T i-n 71 .n = n i

f 3

l l

21 is the AN'SI 56.8-1981 Temperature stabilization criteria at hour i,)

21 l Tg.4 -

Ti .I l i must be 2 4. l Per AN51 55.8-1981, 2 must be less than or egual to 0.5 cilbr NOTE: If the data sampling interval is less than one hour, then:

Option 11 Use data collected at hourly intervals Option r2 Use average of data collected in previou: hour for that hour's data.

D.16 Calculation of Instrument Selection Guide, (ISG) 15G = N00 / 2 (ep/p)' + Z (er /T)' 1 (ed D/ N t \/ N p Kr Ng where: t is the test time', in hours p is test pressure. psia 71s the volume weighed SYerage Cortainment temperature, OR Mp is the number of pressure transmitters Nr is the number of RTDs .

Nd is the number of dew cells op is the combined pressure transmitters

error, psia er is the combined RTDs' error, OR ed is the combined der cells' error, OR ep . I

\/ (S p)2 * (RPp e RSp )2 where: So is the sensitivity of a pressure transmitter RP is the repeatability of a pressure transmitter R5 is the resolution of pressure transmitter er= / -

\/ (Sry2 . (gpr

R5ry2 where: Sr is the sensitivity of an RTD RPr is the repeatability ' an RTD R5p is the resolution of an RTD reew =4 APy tg a /

ate ,

Td

\/ CSd)2 . (gpd

RSd)2 wnere: Se is the sensitivity of a dew cell RPd is the repeatability of a dew cell R5e is the resolution of a dew cell sp, change in vapor pressure ATE d enange in saturation temperature The above ratio is from ASME steam tables and evaluated at the containment's saturation temperature at that time.

D.17 BN-TOP-1 Temperature Stabilization Criteria Calculation i A. The rate of change of temperature is less than 1 *F/Hr averaged over the last two hours.

ci.IT 5 71 11 c2 175 7 1-21 Kt and K2 must both De less than 1 to meet the criteria listed in A.

B. Jhe rate of change of temperature changes less than 0.5 F/ hour / hour averaged over the last two hours.

et . (T i - Ti .1)/(ti - ti.1)

K T1 i 3 2 * (z .1l- T -2)/(ti.1 - ti-2. (ri - (2)/(ti - ti i)I

-2 must be less than 0.5 to meet the criteria listed in 8.

D.18 Reactor Vessel Free Volume Mass Calculation As shown in section D.10. the free volume of the Reactor Vessel subvolume c is given by the below ecuation.

V, . Y,o - a (c-b)

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

Me .144 (P Eve) Ve/ rte Where: He is tr- dry air mass in sabvolume r (1bm)

R is the gas constant of air 5 is the average temperature of subvolume e, (OR) 5, is the average vapor pressure of subvolume c. (pisa)

P is the average containment pressure, (plia) 3 V, is the free air volume in subvolume c. (ft )

TECH 364

O.19 Torus Free Volume Calculation .

Free volume calculations of the Tarus rely upon narrow range Torus ;

rater level inputs. These values range betw:en plus and cinus five ;

incnes. It is assumed that the Torus subvolume free air volume is that subvolume's volume when the Torus level ecuals zero. The user may enter three constants to ac el the variation of Torus air volume with water level. i The ecuations for Torus free volume in subvolume t are given:

3 V t . V to - (at + bL V t-Vto + (-AL

bt2 -ct cL ])when wnen L1L2.0 0 The dry air mass in subvolume t can then be written as:

Mg . 144 d Evt) V t/RT t Where: Nt is the dry air mass in subvolume t, (lba)

P is the average containment pressure. (psla) 5t is the average vapor pressure of subvolume t (pisa)

Vt is the free volume i.. subvolume t. (ft3)

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

L is the Torus level. (inches) a,b.c are Torus level constants

.Vt o is the free volume in subvolume T when L eguals zero, taken from standard free volume inputs, (ft ) 3 E. DUTPUTS E.1 OUTPUT DEVICE TYPES: The below output devices shall be supported.

There are no special constraints on output device locations.

PRINTERS: PRINE Nigh Speed Line Printer 0CDATA 2410 0C DATA 93 LA120 PLOTTERS: Newlet Packard 7475; A.5" X 11-Newlet Packard 7585A 11.5" X 11-Newlet Packard 7585A 11" X 17-CRTs: Wyse Wy75 View Point 60 Asper Dialogue 80 & 81 PRIME PT200 GRAPHICS TERMINALS: RamTech 6200 RamTech 6211

- Tektronir 4107 Tektronir 4208 Tektronir 4014 TECH 364 L

9

- !i 1

1 i

I

1 t

-I k

k APPENDIX C i i

INSTRUMENT ERROR ANALYSIS i i

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1

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4

't I

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F I

l I

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a i

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l l

i TECH m l l

l T

l i

l July 8, 1992 l

l To: D. Nyman l D. Schumacher S. Gupta J. Kuznicki R. Salmi H. King

Subject:

Calculation Of The Instrument Selection Guide For ILRT Instrumentation Systems 10CFR50-Appendix J specifies that all Type A tests be conducted in accordance with the provisions of the American National Standard N45.4-1972. Section 6.4 of that standard requires that the combined precision of all instruments used to perform a Type A test be such that the accuracy of the collected data is consistent with the magnitude of the specified leakage rate.

The Instrument Selection Guide,(ISG) formulation defined in Appendix G of the 1987 Standard, ANSI /ANS-56.8 is an acceptable means of determining the ability of the Type A test instrumentation system to measure the integrated leakage rate of a primary reactor containment system. This rather long formulation is labor intensive to calculate either by hand or by computer.

Section 5.4 of NO Directive NOD-TS.13 specifies that all CECO '

plants shall use a standardized instrumentation system for Type A -

testing. Attachment A lists the resolutions, repeatabilities, and sensitivities which may be expected when the standardized system is used. Also listed are the recommended minimum numbers of each type of sensor.

It is shown in Attachment B, that if the standard Type A test instrumentation specifications and the minimum sensor numbers are met, then the ANS-56.8 ISG acceptance criteria is always satisfied. This eliminates the need to demonstrate by calculation in station procedures that the ISG acceptance criteria is meet.

-The. requirement to calculate Type A Test instrumentation system ISG values may be eliminated from the ILRT procedures of each Ceco >

station. Instead, the instrumentation requirements listed in ,

Attachment A need be included. This letter.along with the ,

attachments may be referenced as the basis for that procedure l change. [

t

/' .

Jim Clover .

Production Services Dept. l

?- _s : _:_v D Q J. Brunner Technical Staff Support ,

Superintendent !

- i G. Vanderheyden R. Shields i

M. Strait R. Walsh P. Johnson J. Brunner W. T'Niemi ,

l t

t e

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'i

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t 6

1 l

l l

ATTACHMENT A !

ILRT INSTRUMENTATION SYSTEM SPECIFICATIONS j j

l l

Pressure Transmitters: Resolution 0.0001 psi Repeatability 0.001 psi Sensitivity 0.0001 psi Minimum Number 1 Temperature channels: Resolution 0.01 "F ~

Repeatability 0.02 *F Sensitivity 0.01 *F Minimum Number 15 Dew Temperature channels: Resolution 0.01 *F Repeatability 0.1 "F Sensitivity 0.1 *F ,

Minimum Number 5 Instrument Parameter Defintions From ANSI /ANS 56.8-1987 Repeatability: The capability of the measurement system to reproduce a given reading from a constant source.

Resolution: The least unit discernible on the display mechanism.

sensitivity: The capability of a measurement system to respond to change in the measured parameter. ,

I I

I

ATIN LB INSTRUMENT SELECTION GUIDE CALCU1.ATIONS FOR ILRT INSTRUMENTATION "These caicuia6 ors are based upon the equations list 3d in Appendix G of ANSI /ANS 56.8-1987*

Pressure Transmitter Parameters Temperature Parameters DewTemperature Parameters SensitMty Sp := 0.0001 prJ Sensdmty Sr := 0.01 F Sensitrvity Sd := 0.1 F Repeatability RPp =0.001 psi Repeatability RPr = 0.02 F Repeatability RPd = 0.1 F Resolution RSp := 0.0001 psi Resolution RSr := 0.01 F Resolution RSd := 0.01 F Number Np = l Number Nr =15 Number Nd = 5 Pressure P > 44. psig Temperature T := 95 F Dew Temp Td := 95. F TEST DURATION t := 8 Pressure Ermr Calculation Measurement System Error Pmse := RPp + RSp Pmse = 0.0011 Pressure Error Pe:=

P Pe = 0.0011 Np' -

Temperature Measurement Error Measurement System Error Tmse :: RPr+ RSr Tmse = 0.03 2

Temperature Error Te (Tmse + Sr[ Te = 0.0082 Nr'#

Dew Temperature Measurement Error Measurement System Error Tdmse :RPd+ RSd Tdmse = 0.11 Calculate the vapor pressure rate of change with dew temp from steam tables A := 0.0886717535 B := 22.452 C := 490.59 d- 32 Z *d A e:p B- Z =0.041 dTd .

(Td- 32+ C),

Measurement System Error Dmse > Z-(RPd+ RSd) Dmse = 0.0045 Dew Temperature Error De := bd) De = 0.0027 Nd*' l 1

I l

Pressue ErrorTerm PE := 2- PE = 7.0813 10

. (P+ 14.7),

Temperature Error Term TE := 2- TE -4J33610 '8

,(T+ 459.68),

DewTemperature ErrorTerm DTE::2- DTE =4317910"

,(P + 14.7),

ISO > 2mo (PE+ TE+ DTE)" ISO = 0.0222 t

ANSt/ANS 56.6 requires that the ISG be less than 0.25La to be acceptable STATION La 0.25La DRESDEN 1.6 0.4 ZION 0.1 0.025 BYRON 0.1 0.025 BRAIDWOOD 0.1 0.025 QUAD CmES 1.0 0.25 LASALLE 0.635 0.156 ,

i a

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APPENDIX D .i 1

I 1

. BN-TOP-1, REV. 1 ERRATA

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AFFINDIX E EN-TOP-1, REV. 1 rnata h Consussion has approved short duration testing for the IPC!JtT provided the Station uses the general test method outlined as the IN-TOP-1, Rev. I topical report. h prLaary difference betwaan that method and the ones previously used is in the statistical analysts of the asasured leak rate data.

Without making any judgments concerning the validity of this test method.

certain errors in the editing of the mathematical azpressions were discovered.

N intent here is not to change the test ethod, but rather to clarify Ene method in a mathematically precise manner that allows its implementation. The errors are listad below.

EOUATION 3A. SEC" ION 6.2 Reads: Lg=A+ beg Should Raad: Lg sA g

R g t g

Reason: The calculated leak rata (L,) at time t is computed using the regression lina c6nstanta A , computed using equations 6 and 7). The summation sth b(equation 6 are a

defined as I e I, where n is the number of data setz up until ist

.ime t N regrassion lias constants change each time a new dada. sat is reestved. The calculatnd leak rate is not a linear.funetton of time.

PARAGRAPH For.!.0VING E0. 3A, SEC* TON 6.2 Reads: h deviation of the seasured leak rata (M) from the calculated leak rate (L) is shown graphically on Figure A.1 in Appendix A and is expressed as:

Daviation a N g -L g Should Read: h deviation of the measured leak rata (M. ) f rom the regression lina (N ) is shown grapnically on Figura A'.1 tn Appendra A and :,s arprassddas:

1 Deviation

M g -N g where N. A

A p +B *t i.

P A,8 s Regression lina constants computed from all data p P sets avatlable free the start of the test to tse last data set at time t ,

t.

t a tune from the start of the test to the ith data set.

TtcH as.

l Ramsaa: The calculated leak rata as a function of trae during the test is based es a - regression line.

The regressies lama coastaats, Ag and I., are chaastag as each additzenal data set is

received.

Equation 3A is used later in the test to compute the upper confidesca limit as a functica of tree. -

For the purpose of this calculation, it is the deviatiaa from the last computed regression line i at stas t, that is saportant.

EDUATION 4, SECION 6.2 Reads: 55Q = I (M g - Lg ):

Should Raad: 55Q = I (M g - Ng)8 ,

Rassen: Same As'Above EOUATION 5, SECTION 6.2 Reads: 55Q = I [ Eg - (A

Beg )j8 Should Read: 55Q = I ( 5i - (AP *3

t i)]8 i P

Reason: Same As Above EQUATION ABOVE EQUATION 6, SECION 6.2 Reads: 3s I"i ~

IIII~ I 1(tg - tJ3

~

Should Read: Ig a U *i IUi~

1(Eg - I)'

Reason: Regression lias coastaat 3. changes over ~ trae las a function of t ) as each ldditional data set is received. d e of "t" left out of demostnator.

Susancion sissa saatted. ;

EQUATION 6, SICION G.2

~

Reads- 3 =

I *i 3 1 IZ *i) IZ 3 )

1 a Lt g' - (1 t g)'

Should Read: I t=* a*iLc"I' ~Ig

i) (

= (L s )'

g "I

Ramses: Same As Above .

nenu i

EDUAT!0N 7 SEC*!0N 6.2 Raads: AsE-Ee Should Asad: A sI-Sg&

f l'

i Reason: Sans As Above EQUATION 10, SECTION 6 2 :

Reads: A=I 8 ) II E D

U E ) G E N) 1 i g i i aIt 3i - (I t.)3 t ,

Should Asad: A g

m.( i} ( E t )

II E ) II Ei L N) i ~

a I t.3 . (I t ja t i ;

Reasos: Same As Above EQUATION 13. SECTTON 6.3 ;

{g . "1 , (t, - t)8 y

?

Reads: ya , ,2 (t g -

t)s should Raad: g aas 2 [3 , *1 , (t,

M }

I (t g- T)8 ;

l where t a time from the start of the test of ths' last data P set for which the standard dettaties of the measured leak rates (N,) from the regressten line (Ng ) is betag computad; ch tg a time -from the start of the test of the i data set; a s number of data sets to time t,;

a I = I ; and ist T= A a

I t..

a t Racson: Appears to be error is editing of the report.

Report does a peer job of defiatag variables.

eten su .65-

ECUATICF 14 SIcn cN 6.3

. Reads: e= s [ 1 + 1" + I", *

N j (c. - t)3 L ,

3hould Read: a= s [ 1 + 1* + I*p ~ ]

Z (t.

L t)3 Reason: Same As Above EQUAMON 15, SECn0N 6.3 Rasds: Condidence Lasit a L = T Should Raad: Confidence Limits a L 2 T a waere L = calculated laak rata at time t ,

T= T distribution value based on a, the number of data seta received up until tsee tP; l ea standard deviation of asasured Isak race values

(!!g) about the regression lies bemed on data fros tae start of the test until tame t .

p Reasos: Same As Above

EOUATION 16. SECn 0N 6.3 Reads: UCL = L

T Should Raad: UCL = L - T

a Reason: Same As Above .

EQUAn0N 11, SECnCN 6.3 Reads: LCL = L - T Should Rand: LCL = L - T

a Rassen: Same As Above i

new m l

o.-

ij 1

i l

t i

i APPENDIX E -l 1

TYPE A TEST RESULTS USING MASS-PLOT {

-METHOD (ANS/ ANSI 56.8) !

i I-

?

t t

i h

i t

l t

t e

ucu m '

i

I MASS POINT- MEASURED PHASE TEST RESULTS OUAD CITIES l 2 i ROG TIME MP leak MP UCL i

%Iday %fday ;

60 0.00 0.0000 0.0000 1 61 10.00 0.7197 0.0000 62 20.02 0.4444 1.8030 63 30.02 0.4759 0.6916 64 40.02 0.4946 0.5974 65 50.03 0.5051 0.5675 66 60.03 0.4959 0.5389 67 70.03 0.5003 0.5316 68 80.05 0.5021 0.5258 69 90.05 0.5021 0.5207 70 100.05 0.5180 0.5405 71 110.07 0.5200 0.5306 72 120.07 0.5194 0.5350 73 130.07 0.5149 0.5289 74 140.08 05126 0.5250 75 150.08 0.5104 0.5213 76 160.08 0.5099 0.5196 77 170.10 0.5114 0.5201 78 180.10 0 5097 0.5176 79 190.10 0.5090 0.5161 80 200.12 0.5090 0.5154 81 210.12 0.5053 0.5122 82 220.12 0.5054 0.5117 83 230.13 0.5048 0.5106 84 240.13 0.5006 0.5073 85 250.13 0.4977 0.5045 86 260.15 0.4969 0.5033 87 270.15 0.4943 0.5008 88 280.15 0.4922 0.4985 89 290.17 0.4897 0.4961 90 300.17 0.0000 0.0000 91 311.17 0.4830 0.4916 92 321.18 0.4768 0.4866 93 331.18 0.4707 0.4815 94 341.18 0.4658 0.4769 95 351.20 0.4623 0.4733 96 361.20 0.4593 0.4700 97 371.20 0.4561 0.4666 98 381.22 0.4532 0.4635 99 391.22 0.4506 0.4607 100 401.22 0.4484 0.4582 101 411.23 0.4463 0.4559 102 421.23 0.4442 0.4535 103 431.23 0.4420 0.4511 104 441.25 0.4400 0.4489 105 451.27 0.4388 0.4474 i 106 461.25 0.4375 0.4458 4

MASS POINT -INDUCED PHASE TEST RESULTS QUAD CITIES 2

RDG TIME MP Leak MP UCL

%fday %l day 114 0 00 0.0000 0.0000 115 10.00 1.1783 0.0000 116 20.02 1.1323 1.3589 117 30.02 1.1944 1.3053 118 40.02 1.1989 1.2506 119 50.03 1.2309 12807 120 60.03 1.2352 1.2688 121 70.03 1.2411 1.2661 122 80.05 1.2497 1.2709 123 90.05 1.2490 1.2656 129 100.05 1.2615 1.2802 125 110.07 1.2635 1.2791 126 120.07 1.2620 1.2751 127 130.07 1.2660 1.2779 128 140.08 1.2656 1.2758 129 150.08 1.2658 1.2747 130 160.08 1.2648 1.2727 131 170.10 1.2635 1.2706 132 180.10 1.2687 1.2769 133 100.10 1.2702 1.2777 134 200.12 12703 1.2771 135 210.12 1.2731 1.2798 136 220.12 1.2723 1.2785 137 230.13 12706 1.2765 138 240.13 1.2681 1.2740 139 250.13 1.2646 1.2711

Mass Point Leak & Mass Point Leak at UCL QUAD CITIES 2

M Mass Point Leak at UCL 2.0 m ass Point Leak- - - - - - - - - - - - - - - - - - - - - - - - - - - -- ----- - - ~ - - - -

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ML20046B578

Contents

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

test duration at the ith data set (hours) ti standard deviation of least sguares slope (weight;/ day) e

Subject:

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ML20046B578

Text

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

SUMMARY

test duration at the ith data set (hours) ti standard deviation of least sguares slope (weight;/ day) e

Subject:

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