ML20062D874
ML20062D874 | |
Person / Time | |
---|---|
Site: | LaSalle |
Issue date: | 05/19/1982 |
From: | COMMONWEALTH EDISON CO. |
To: | |
Shared Package | |
ML20062D872 | List: |
References | |
NUDOCS 8208060250 | |
Download: ML20062D874 (61) | |
Text
l e a REACTOR CONTAINHENT BUILDING INTEGRATED LEAK RATE TEST 1
l LASALLE COUNTY NUCLEAR POWER STATION UNIT ONE May 14-19, 1982 8208060250 820728 PDR ADOCK 05000373-P PDR
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- TABLE OF CONTENTS PAGE INTRODUCTION ....................................................... 1 A. TEST PREPARATIONS ............................................. 2 A.1 Type A Test Procedure .................................... 2 A.2 Type A Test Instrumentation .............................. 2 A.2.a Temperature A.2.b Pressure i
A.2.c Vapor Pressure
, A.2.d Flow j
A.3 Type A Test Measurenent .................................. 3 A.4 Type A Test Pressurization ............................... 3 1 B. TEST METHOD ................................................... 16 B.1 Basic Technique .......................................... 16 B.2 S upp l emen ta l Ve r i f i ca t i on Tes t . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 B.3 Linear Regression Analysis .... ......................... 16 B.4 Ins t rumenta t ion E rror Ana lys is - App l ica tion . . . . . . . . . . . . . 16 C. SEQUENCE OF EVENTS ............................................ 17 C.1 Test Preparation Chronology .............................. 17 C.2 Tes t P ressu ri za t ion Chronology . . . . . . . . . . . . . . . . . . . . . . . . . . . 17 C.3 Temperature Stabilization Chronology ..................... 17 C.4 24-Hour Phase of Leak Rate Test ........................... 18 C.5 Induced Leakage Phase .................................... 19 C.6 Depressurization Phase ............. ..................... 19 C.7 Floor Bypass Phase ....................................... 19 TYPE A TEST DATA .............................................. 21 C.1 24-Hour Phase Date ....................................... 21 C.2 Induced Phase Date ....................................... 21 D. TEST CALCULATIONS ............................................. 22 E. TYPE A TEST RESULTS AND INTERPRETATION ........................ 37 i
E.1 24-Hou r Phase Tes t Res ul ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 37 E.2 Induced Phase Test Results ............................... 37 E.3 Leak Rate Compensation for Non-Vented -
Pene tra tions and Change i n Drywel l Sump Level . . . . . . . . . . . . 37 APPENDIX A TYPE B AND C TESTS ................................. 39 APPENDIX B AS FOUND LEAK RATES ................................ 46 1
. - - . _ ~ _ _ . . - . . . . . - _ , _ , . . - - _ . . , _ _ , _ _ , _ . - , , . , .,,- _ __- _,
ll-f 8 APPENDlX C HYDROSTATIC TEST ................................... 47 APPENDIX D CALCULATIONS ....................................... 50 APPENDIX E TYPE "A", "B", AND "C" TESTING SCHEDULE ............ 57 d
TABLE ONE I ns t rumen t .Speci fi ca t i on . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 TABLE TWO Sensor Physical Locations .......................... 5 TABLE THREE 48 psig Type A Test - 24 Hour Phase ................ 22 TABLE.FOUR 48 psig Type A Test - Induced Leak Rate Phase ...... 32 s
1 TABLE A-1 Type B and Type C Test Results ..................... 40 TABLE C-1 Hyd ros t a t i c Te s t Re s u l t s . . . . . . . . . . . . . . . . . . . . . . . . . . . 48 FIGURE ONE Idealized View of Drywell and Suppression Pool...... 6 FIGURE TWO Sensor Locations per Subvolume ..................... 7-14 4
FIGURE THREE Measuremen t Sys tem Schematic Arrangement . . . . . . . . . . . 15 t
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t *. 1 INTRODUCTION This report presents details of the Integrated Primary Containment Leak Rate Test
, (IPCLRT) successfully performed on May 14 through 19, 1982, at LaSalle County i
Nuclear Power Station, Unit One. The test was performed in accordance with 10CFR50, Appendix J and the LaSalle County Unit One Technical Specifications.
t I
The total primary containnent integrated leak rate, adjusted to include penetrations not tested during the IPCLRT, was found to be 0.3919 wt%/ day at a test pressure of 40 psig, which was within the 0.476 wt%/ day acceptance criterion. The associated
- upper 95% confidence limit was 0.3933 wt%/ day.
Excluding non-testable penetrations, the supplemental Induced phase leakage test
. resul t was 0.8179 wt%/ day. This value should compare with the sum of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> phase result (0 3737 wt%/ day) and the induced leak rate of 5.3 scfm (0.527 wt%/ day) .
- The statistical value of 0.8179 wt%/ day lies within the allowable tolerance band of 0.25LA, + 0.159 wt%/ day.
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2 SECTION A - TEST-PREPARATIONS A.1 Type A Test Procedure The IPCLRT was performed in accordance with Procedure LTS 300-4, Revision 3, and Pre-Operational Test PT-PC-101, Revision 25 Temporary Procedure Change Numbers 52-82, 53-82, and 57-82 were made to LTS 300-4 to correct the proce-dure for system valve lineup changes. The range for Pa was also changed to allow for testing the containment at a higher pressure.
These procedures were written to comply with 10CFR50 Appendix J, ANSI N45.4-1972, ANSI /ANS-56.8-1981, and LaSalle County Unit One Technical Specifications.
A.2 Type A Test instrumentation Table One shows the specifications for the Instrumentation used in the IPCLRT.
Table Two lists the physical locations of the temperature and humidity sensors within the primary containment. Figure One is an idealized view of the drywell and suppression chamber showing the di f ferent subvolumes. Figure Two shows RTO and dewcell locations per subvolume.
- a. Temperature Sensors were suspended to prevent direct thermal influences from any metal surfaces. Sensors were also kept away from any direct air flows.
Each RTD-bridge network was calibrated to yield an output of 60 mV to 120 mV over the range of 60 F to 120 F. Calibrations were done by Volumetrics of Inglewood, Cali fornia. Calibration sheets for the RTD's and their signal conditioning boards is included in Table One,
- b. Pressure Two precision quartz bourdon tube pressure gauges were utilized. Each gauge had a local digttal readout in addition to a Binary Coded Decimal output to the process computer. Primary containment pressure was sensed by the pressure gauges in parallel through a 3/8" tube connected to a test tap on a VQ penetration.
Each precision pressure gauge was calibrated over the range 0. psia to 100 psia in approximately 5 psia increments using a Volumetrics Inc.
VCM 809/1138 calibration standard.
- c. Vapor Pressure Ten Lithium Chloride Dewpoint Temperature Units were installed throughout the Drywell and Suppression Pool. The dewpoint cells were placed in locations where the chance of the dewcell becoming damaged was slight.
A calibration was done on each dewcell network over the range of 45 F to 90 F. Calibration was done to yield an output of 45 mV to 90 mV over the range of 45 to 90 F. Calibrations were performed by Volumetrics using dewcell standard, Volumetrics Inc., Serial No. VMC 209/319
3
, , d. Flow A rotameter flowmeter, Fischer-Porter, calibrated to within
+1.025% by Volumetrics, was used for flow measurement. Tubing connected the rotameter to a test tap on one of the primary containment penetration lines.
A.3 Type A Test Measurement The IPCLRT was performed utilizing a Interface with the Volumetrics Data Acquisition System (DAS) and Prime Computer. Information from the RTD's and dewcells is sent to a Dual Multiplexer Scanner in the Drywell. The Scanner takes the data and sends it through a electrical penetration (E-20) to a System Console. The System Console takes the raw data and converts it into data readable to a computer and the test engineer.
via telephone lines. This information is then sent to the Prime Computer where all needed calculations are performed and a hard copy of the Information is produced. (See figure 3)
A.4 Type A Test Pressurization Two 300 scfm 600 hp electric 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 into the reactor building through an existing PCILRT Pressurizing Line. For case of handling a flexible 4 inch pipe was used outside of the reactor building.
The drywell was pressurized through the "A" containment spray header 16 inch flange with an inboard valve NO 1821-F017A, open during the pressurization process.
TABLE ONE --
INSTRUMENT SPECIFICATIONS 4' .
INSTRUMENT MANUFACTURER MODEL NO. SERIAL NO. RANGE ACCURACY . REPEATABILITY Precision Pressure Volumetrics 2287, 2348 0-100'psiat +0.02% reading 1,0.001% F.S.
Gauges (2)
RTD's (30) Volumetrics 14629.lLRT 5042-1, 5042-16 60 - 120 F +0.1 -
F -+0.1 F 5042-2, 5042-17 5042-3, 5042-18 5042-4, 5042-19 5042-5, 5042-20 5042-6, 5042-21 5042-7, 5042-22
-5042-8, 5042-23 5042-9, 5042-24 5042-10,5042-25 5042-11,5042 5042-12,5042-27 5042-13,5042-28
.. 5042-14,5042-29 5042-15,5042-30
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Dewcells (10) Volumetrics 5042-1, 5042-6 45 - 90 F -+1.0 F -+0.5 F 5042-2, 5042-7 5042-3, 5042-8 5042-4, 5042-9 1 5042-5, 5042-10 Flowmeter (1) Fischer & Porter RMB-57 0-600 scfh 2.3% F.S.
l 1
TABLE TWO 5 IPCLRT INSTRUMENT PHYSICAL LOCATIONS RTD NO. EPN SUBVOLUME INSTRUMENT INSTRUMENT ELEVATION AZIMUTH
- 1 ITE-CT021 1 822', 0 2 ITE-CT022 1 826, 180 3 ITE-CT025 6 730, 90 4 1TE-CT026 6 730, 0 270 5 ITE-CT019 2 804, 115 6 ITE-CT020 2 804, 295 0
7 ITE-CT017 3 811, 0 8 1TE-CT018 3 815, 180 9 ITE-CT016 3 808, 270 10 1TE-CT015 3 797, 90 11 1TE-CT014 4 791, 90 12 1TE-CT013 4 785, 0 13 1TE-CT027 4 791, 270 14 ITE-CT029 4 785, 180 15 ITE-CT012 5 777, 270 16 ITE-CT011 5 772, 180 17 ITE-CT010 5 767, 90 18 1TE-CT009 5 762, 0 19 1TE-CT008 7 758, 270 20 ITE-CT007 7 754, 180 21 ITE-CT006 7 750, 90 22 ITE-CT005 7 746, 0 23 ITE-CT023 6 743, O o
24 ITE-CT024 6 743, 180 25 ITE-CT001 8 708, 13 0
26 ITE-CT003 8 708, 195 27 ITE-CT030 8 708, 78 28 ITE-CT002 8 724, 108 29 ITE-CT028 8 724, 78 30 1TE-CT004 8 724 287 DEWCELL NO. EPN SUBV0LUME INSTRUMENT INSTRUMENT ELEVATION AZIMUTH
- 1 IME-CT036 1 826' O 2 1ME-CT035 3 812' 180 3 IME-CT037- 3 803' 180 4 1ME-CT034 4 791' O 5 1ME-CT033 5 773' 180 6 IME-CT039 5 763' O 7 IME-CT038 6 746' 270 8 IME-CT032 7 752' o o
9 IME-CT031 8 708' 0 195 10 1ME-CT040 8 724' 78
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15
, , SECTION B - TEST METHOD 16 B.1 Basic Technique The absolute method of leak rate determination was used. The absolute method uses the ideal gas laws with measured containment temperature, dew point and air pressure to determine dry air mass in the containment. The leak rate can then be determined from the rate of mass loss.
B.2 Supplemental Verification Test The supplemental verification test superlmposes a leak of known magnitude on the existing leakage. The degree of detectability of the combined leak rate provides a basis for resolving any uncertainty associated with tie 24-hour phase of the test.
B.3 Linear Regression Analysis The leak rate is assumed to be constant during the testing period, ideally yielding a straight-line plot with a negative slope. However, sampling techniques and test conditions are not perfect; consequently, the measured values will deviate from the ideal straight-line' situation.
A least squares fit statistical analysis was performed to determine a regression line for mass versus time af ter each set of data was acquired.
The slope of this regression line was designated to be the statistically averaged leak rate. This quantity was compared to the Technical Specifi-cation allowable operational leak rate LT (0.476 wt%/ day).
Associated with the statistically averaged leak rate was the upper 95%
confidence limit leak rate. The calculation of this upper limit was based upon the standard deviations from the regression line and the one-sided Students-T Distribution function. A procedureal requi rement speci fied that the upper 95% confidence limi t leak rate must be less than the Tech-nical Specification allowable operational leak rate LT (0.476 wt%/ day).
B.4 Instrumentation Error Analysis-Application An instrumentation error analysis was performed prior to the test in accordance with ANSI N45.5-1972. The instrumentation system error was calculated in two parts. The first part was to determine system accuracy and the second part was to determine system repeatability. The system error analysis performed prior to the test yielded a total instrument uncertainty of +0.00850 wt%/ day. During the test one of the dew cells mal functioned (number 3) . This dewcell was removed from the test and a new error analysis was performed. The new error analysis yielded a total instrument uncertainty of +0.00992 wt%/ day.
The instrumentation uncertainty is used only to illustrate the system's ca'pability to measure the required parameters that are necessary for calculation of the primary containment leak rate. The instrumentation uncertainty is always present in the data and is incorporated in the 95%
upper confidence limit in the form of data scatter. Procedures required that the summation of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> statistical leak rate and the total instrument uncertainty be less than LT (0.159 wt%/ day) .
3 SECTION C - SEQUENCE OF EVENTS 17 C.1 Test Preparation Chronology The pretest preparation phase and containment inspection were completed on May 14, 1982 with no visible structural deterioration being found. Major preliminary steps included:
- 1. Completion of all Type B and C tests, component repairs, and retests.
- 2. Completion of IPCLRT pretest valve checklist including isolation of drywell and suppression chamber pressure sensors.
3 Blocking of four drywell to suppression chamber vacuum breakers in the open position for pressure equalization between the drywell and suppression chamber volunes.
- 4. Venting of the reactor vessel to the primary containment via the manual head vent line and the drywell equipment drain sump.
5 Completion of pretest data gathering system, including computer p rog ram, instrument console, and associated wi ring.
C.2 Test Pressurization Chronology Date Time Event
- 5/15/82 0156 Primary Containnent pressurization initiated.
0208 Reactor Scram Alarm at 1.25 psig.
0211 Reactor Scrammed.
0440 Second Ai r Compressor started.
0600 Found leakage on input sensing line of instrument 1821-N048A.
0659 Primary containment pressure reached 55.55 psia.
Pressurization was complete.
C.3 Temperature Stabilization Chronology Date Time Event 5/15/82 1135 Water leakage on ICM01M sight glass found. Repairs initiated.
1448 Test terminated due to instrument and sight glass leaks.
Estimated leakage rate C0 500 SCFM. Repairs initiated.
1630 Inspection for leakage.
1740 Packing leak on valve 1MC033 found. Leakage slight, no repairs initiated.
1940 Final check for leakage.
2200 Computer communication line down, data being sent to Chicago computer.
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C.3 Temparature Stxbilization Chronology (Cont'd.) 18 Date Time Event 5/16/82 0100 Drywell Air Temperature changing by 0.1 F/hr.
0220 Vessel level at 290".
0223 Vessel level raised to 310".
0415 Outage for removal of compressor connection to containment hung.
0330- Spool piece and flange being installed, stabilization 0445 complete.
0725 Trip of reactor building breaker removed power from DAS.
0800 Reactor building power brought back. Data acquisitioner
.DAS reinitiate C.4 24-Hour Phase of Leak Rate Test Date Time Event 5/16/82 1218 Started 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test phase. Data sets being taken every 10 minutes.
1345 Channels 2, 4, 5-9 deleted from data acquisi tioner scan.
2200 Leakage remaining high. Inspection for leaks initiated.
2345 Hydrogen recombiner, Unit 1 Loop seal valve developed a leak (250 SCFM). Test stopped and loop seal refilled.
Test restarted using data set #70.
I Data Acquisitioner stopped sending data. The unit was r 5/17/82 0140
- re i n i t i a ted.
l Restarted 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test using data set #84.
0214 0224 Computer accepting data.
0234 Computer stopped accepting data from acquisi tioner.
0300 Hand entering data.
0530 Sump valves 1RE024 and 25 were found placed in Auto.
Valves have opened and pumped 83 gallons from'the drywell equipment sump.
0830 Conouter pointer repaired, computer accepting data.
0835 Backup computer calculations being checked in Chicago Data is wrong.
l 0840 Two data sets found missing.
F C.4 24-Hour Phase of Leak Rate Test (Cont'd.) 19 Date , Tine Event 5/17/82 1412 Drywell and suppression pool volumes were found to be wrong in the computer program. These were corrected and all data was recalculated.
2115 The data acquisitioner shutdown, due to heat. I t was restarted with no apparent data loss.
2138 1 Data set found missing.
5/18/82 0100 Data acquisitioner output speed increased. Problem resolved. 1-2 data sets lost.
0145 Channel 42 (Dewcell #2) went bad. Dewcell removed and data recalculated.
0302 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test completed. The 95% upper confidence limit leak rate was 0.3933 %/ day well below the allowable leak rate of 0.476%/ day. The statistically averaged leak rate was 0.4624%/ day.'
C.5 Induced Leakage Phase Date Time Event 5/18/82 0345 Chemistry sampled containment atmosphere.
0530 Induced leak rate 320 SCFH ini tiated (OSSht/ day) /
0630 Stabilization complete.
0810 The data acquisitioner stopped sending an'd printing data. Problem resolved, no data lost.
1102 induced leak rate test completed. The measured induced leakage rate was 0.8179%/ day. The measured leakage rate minus induced leakage minus statistically averaged leakage rate (24hr) produced a difference of 0.1098%/ day within the limits of 0.159%/ day.
C.6 Depressurization Date Time Event 5/18/82 1939 Depressurization initiated.
5/19/82 0118 Depressurization stopped at 5.4 psig.
0139 vacuum breaker closed.
0232- Suppression Pool depressurized.
C.7 Floor Bypass Tests Date Tine Event 5/19/82 0232 5 psid floor bypass test started.
f C.7 Floor Bypass Tests (Cont'd.) 20 Date Time Event 5/19/82 0335 5 psid Bypass Floor Test completed. Leakage rate is 7.12 SCFM,'well below the limit of 73 SCFM.
0340 Drywell depressurization restarted.
0416 Drywell depressurization stopped at 1.8 psig.
1.5 psid bypass floor test started.
0521 1.5 psid bypass floor test completed.- Leakage rate 3 32 SCFM, well below the Ilmit of 73 SCFM.
0545 Drywell opened up. Inspection shows no deviations.
NOTE: The Hydrogen Recombiner Loop Seal Vaive was checked after the test and found to have a dirty seating surface.
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SECTION.C - TYPE'A TEST DATA 21 C.1 24 Hour Phase Data Data for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> phase is illustrated in Table Three. Graphic record of this portion of the test is presented' in graphs 1 through 6. This data-has been corrected and the' raw data f rom dewcell 3 has been eliminated.
C.2 Induced Phase Data Data for the induced phase is presented in Table Four. Graphic illustration of the major parameters is presented in graphs 7 through 10. This data has also been corrected and raw data from dewcell 3 has been eliminated.
F SECTION D - TEST CALCULATIONS 22 Calculations for the test were based on LaSalle County Procedure LTS-300-4.
A reproduction of _ this procedure is found in Appendix D. The instrument error analyses are also found in Appendix D.
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Table Three -- 39.6 PSIG TYPE A TEST - 24 HOUR PHASE Page 24 9.67 10:26 57 96.99 1.02760E*05 1.02920005 54.627 0.3743 0 6437 0.381T 0.JPF3
- d. 9.84 10:36 58 97 02 1 02756E+05 1 02920E+05 54 628 0 3776 0 5737 0 3821 0.3RP1 i 10.01 102 6 59 97.02 1 02755E+05 1 02920E*05 54.627 0 3731, 0 1073 0.3e25 0.3684 10 17 14:56 -
60 97.02 1.02755E+05 1 02920t*05 54.627 0.3672 0.0088 0 3823 0.3880
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'i O 17.34 38: 6 103 97.34 1.0a645t+05 1 02918E.05 544600 0 3631 0.0592 0.3756 0.3182 1.02642t+05 1 02988t+05 54.600. 0 3635 0.4055 0.3753 0.3778 7.51 18:16- 104 97.35 0.J776 .54 599 - 0 3859 e.sTS: :)
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97.40 s.02632E 05 1 02917E+05 54.599 0.3597 0.2368 0.3738 0.3762 O se.34 19: 6 109 0.5327 0 3734 0.3758 18.51 19:16 110 97.42 1.02629t+05 1 02917E+05 54 599 0 36)2 54 599 0 3587 e.0811 0 3729 0.3753 k38.67 W 19326 fp 111 g p9764ee. 1.0262st+05? te02917t.85 54.59*- 0 3702 s.0620 0.3730 0.3754 ) O te.99 n 19:4s g o 1:2n 3 97.45 <1402614t*85 it.02911t+05- 0.3753 d{O 19:'131 W 9_M 1134J 97d6 - Id16_l][195 - 1 0291H12 15U 97.47 1.04607E*05 1 02917E+05 0 54.591 59.593 f_.}686 0 3721 0.1798 0.7806 0 3730 0 3732 0.37b5 . 19.32 . 20: 5 114
- 0 1 02917E 05 54 5=3 0.3752 0.742 0 3736 0.3758 O 19 99 20:15 il5 97.50 n.02602E 05 0.3755
.__19.6s 20:25 116 97.47 1.02609E405 t m029)lhg5 59 594 0 56}5 -1 0000 0.}J33 1.d2604t*05 1.02917E+05 59.592 0 3665 0.7236 0 3732 0.3759 h19482i; 20 f 35b r117 ' '197.48 0 3709 0 8947 0 3733 0.3755 0 O Y19 99 ; 20:45 M J18 I 97.51 1.02597t+05 1 02917E+05 54 592 0.3756e ...L11ad ' 22.155 - 119 91e53 __.1 02591t+_Dh_ _ 1 02911(+05. _ 54 19) 0 3721 f.5110 0. 3_735 20.32 28: 5 120 97.53 1 0259hE*05 1 02917E*05 54 590 0 3669 -0 2566 0 3734 0.3755 O 20.49 21:15 121 97.54 1.02534E.05 1 02917f.05 54.5P8 0 3771 1.6207 0 3738 0.3759 v ,
97.53 1.02599E.0a 1 02917E.05 59.5P7 0 3736 -0.0504 0 3790 0.3761 20.65 23:25 122
Table Three -- 39.6 PSIG TYPE A TEST - 24 HOUR PHASE Page 25 97.54 1.02581E*03 1.02917E*05 , 54.500 0. 3183 -0.2873 0 3740 0.3766 20.82 21:35 123 1.02501E*05 'la02917C*05 59.585 0.7084 0 3741 0.3761 i h '20 99 21:45 21:55 124 125 97.54 97 56 .1 02501E+05' '1 02917C+0S- 'S4.507 0.3710
'O.3601 0 0006 0 3740 0 3760 . 21 15 0.3740 0 3760 .
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02111E+05 5 4.H 4 f.1741 4 ;' 54.S03.W 0 3741 0 3641 0 3745 0 3764
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- i INDUCED LEAK RATE PHASE Page 32 ._ . . 4 ,. . .
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