ML19317G694
| ML19317G694 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 01/31/1978 |
| From: | SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | |
| References | |
| NUDOCS 8003260823 | |
| Download: ML19317G694 (27) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ - _ _
i NOTICE -
THE ATTACHED FILES ARE OFFICIAL RECORDS OF THE l
DIVISION OF DOCUMENT CONTROL. THEY HAVE BEEN CHARGED TO YOU FOR A LIMITED TIME PERIOD AND MUST BE RETURNED TO THE RECORDS FACILITY BRANCH 016.
PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE(S) FROM DOCUMENT FOR REPRODUCTION MUST BE REFERRED TO FILE PERSONNEL.
ANCHO SECO nuclear generating station C'
DEADLINE RETURN DATE.
- *% ? / 9
~
'.Y. ll /.f UNIT ONE en...
m.
CLAY STATION. CALIFORNI A i
RECORDS FACILITY BRANCH
.l r
3 Reac':or Containmen:
Buicinc n~:ecra~:ec v
_ea< Ra:e - est t
First Type A Test Report JANUARY 1978
$SMUD
~
t ll SACRAMENTO MUNICIPAL UTILITY DISTRICT 8003 260 M3 g
- ' O RANCHO SECO nuclear generating station UNIT ONE UNITED STATES NUCLEAR REGULATORY COMMISSION DOCKET NUMBER 50317 OPERATING LICENSE DPR-54 r
m Reac~:or Containmen~:
Buicing n:egratec
_.ea < Ra':e ~~es :
t l
JANUARY 1978 Docht #5bOtx First Type A Test Report 0 c cl e r t or v e %
3
{. UL,
,0f 00C :mgTk.
..a rits i
1 i
i$SMUD SACRAMENTO MUNICIPAL UTILITY DISTRICT L
REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST FIRST TYPE A TEST REPORT l
Rancho Seco Unit 1 Docket No. 50-312 Operating License DPR-54 SACRAMENTO MUNICIPAL UTILITY DISTRICT l
JANUARY 1978 l
P -
- RANCHO SECO NUCLEAR GENERATING STATION
-UNIT I - REACTOR-CONTAINMENT BUILDING lNTEGRATED LEAK RATE TEST TEST REPORT (FIRST TYPE A REPORT)
D I STR I BUT I ON.. L I ST '
COPIES
. Nuclear Regulatory Commission Director :of Regulatory.0perations '(Washington) 15 Director MIPC
.2 W. C. Walbridge i
J. J.'Mattimoe 1
D. G. Raasch.
3 R. J. Rodriguez 1
'R. W. Colombo 4
R. P. 0ubre' 2
J.-V. McColligan 3
D. C. Browning i
D; B. Cass 1
L. G. Schweiger'(QA Files) 1
=J.TJanis (B&W Company, Lynchburg, VA) 1 L. R. Kellman I
- Surveillance Procedures. File (J. Price) 1 Document Contro11 Center 1
Rancho Seco-Library 1
-SMUD. Main. Library, 6201 'S' St., Sacramento 1
R.~Berchin, Babcock s Wilcox Company','Lynchburg 1
1 lJ..Bayshore,Bechtel-Company,NorwalkL 1
s
I s
.m
-4, 1w.
s 4
JTEST' SYNOPSIS:
~
-Pressurizat1on'of the. Reactor Building ~for the ILRT at Rancho Seco Nuclear
' Generating' Station 1 Unit 1 comm'enced at 0830,' Sunday, October 2, 1977.
Pres-
.surization.was secured when the containment' pressure reached 12 PSIG at'1430 (the same day.-~An. external 11eak survey was-performed at this pressure.in laccordan'ce with the test procedure..'During the leak survey, analysis of
'the containment atmosphere: data _ indicated a containment leakage rate'of: approx-
.imately 50lSCFM or eight times the maximum allowable leakage rate, La, of 0.1% 'per; day. LThe external survey of all-penetrations with systems vented toithe containmentJatmos'phere'per the valve' lineup was completed at 1700 with the?followingJreported~results. A v'ery small leak was, detected at Penetration No. 43, PlantiAir, through the. vent path provided external to the containment,.
SASJ478.- Containment 11 solation valve, SAS-052, a. locked closed (during,
normal operation) manual gate valve was found partially open and was closed to comply?with"the' procedure position.
This action had no apparent effect on'.the containment' leakage-rate. Furthermore, leakage detected at.SAS-478 could;well have been leakage of plant air throughfblock valve SAS-479,-which
.was. shut?(with a vent path provided between'the plant air block valve, SAS-749, and the-outboard containment isolation valve, SAS-052, through SAS-478) in order to prevent any possibility of plant air leakage into the containment during the.ILRT. Considering the external survey results and the continuing exces'sive leakage: rate,_a containment entry was made to check for leakage into the. secondary 1 sides of the steam generators.
Simultaneously, the main steam
~
lines ~outside. containment, which were'open to atmosphere due to turbine stop valve removal,'were fitted with plastic covers.
The plastic covers sealed the secondary volume outside containment and very quickly showed evidence of pressure build,upfin;the' secondary system by billowing outward from the pipe
. ends-. _ Thel internal = survey and the associated surveillance at the main steam line plastic covers ~was terminated at 2100. The following actions were taken
-during the: internal survey a:esulting in _a reduction of the containment leakage rate to a value-well below the' maximum allowable leakage rate.
FWS-470, a normally closed root. valve'.for a ' spare instrumentation nozzle on steam gen-erator. E-205B, wasi found open providing direct. communication between contain-lmentfatmosphere:and the secondary system.
This valve, which was instal. led during this outage and~wasfnot on-the valve lineup, was closed.
(The valve wouldehave-been closed had it been included in the valve lineup.)-
The contain-ment leakage observed _at the. plastic covers on the main steam lines decreased-Leo'a barelyfdetectable~1eakage rate.
MSS-516', PT-20520 vent root valve', and
- MSS-549,'PT-20520 1'nstrumentoisolation valve we-found. partially open. When these. valves were closed to' comply-with the procesure position, containment
- 1eakage at !the steam line -plastic covers' was.no longer detectable.
After con-firming the7 reduction inL leakage rate by analys'isfof ' containment atmosphere da,ta1 pressurization tol peak test pressure commenced at.2200.
s Ac.approximatelyf1200-on 10/3/77, the Nuclear Service ' Cooling Water (NSCW)
- System ' surge 'tanke level. for both loops 'was reported to be rising.
The NSew 1"B'?. loop safety. features: v,16es c andl the. "A"' loop outlet SFV valves-were then E
closed:(thej"A"floo'p rinlet SFV valves had previously been closed due to loop
- toperations 'in support ~of.decayt heat.' removal during the test). The surge tank levels continued.co rise with allLvalvesLclosed until the surge tanks were soli,d1(at -0200,' :10/4/77). As..thefNSCW s'ystem is.a closed system inside'and 7
outside containment andLisiclassifiedfSeismicL1,7 Quality'1,-the ILRT was per--
i formed with'thisLNSCW system: status; which meets the requirements of Appendix J
~
itoL10:CFRJ50 1 After; blowdown,'one-of the-SFV valves, chosen at random,1 L
(SFV-50009,Toutlet: from'A-500Al Emergency : Building Cooler) was removed and-
~
o 1
b-
~
' i 1}
4 s
N J
s m
s
inspected.
No obvious defects with the seat'or disc were found.
The valve was put back into the system and all eight SFV valves and four coolers were leak tested with water, the valves at 115 psig and the coolers at 90 psig.
lle valves were found to be sealing properly and they were considered operational at that time.
It was determined that in fact only two coolers were leaking.
In NSCW loop "A",
the A Emergency Building Cooler was leaking through a high point vent.
Capping the vent stopped the leakage and as a precaution, the vents on all coolers were capped.
The "D" Emergency Building Cooler in NSCW loop "B" was found to be leaking through a head gasket.
Two nuts were found to be loose permitting the leakage and they were tightened, stopping the leakage. Again, as a precaution, the tightness of all head bolts on all four coolers were checked against the. vendors recommended torque value.
At 1300, 10/3/77, the Component Cooling Water (CCW) System surge tank level was also reported to be rising, and the CCW outlet safety features valves were closed.
The^ surge tank level increase stopped with valve closure, and the valves remained closed for the ILRT.
It.was determined after blowdown that a CCW system vent-root valve, CCW-475, at reactor coolant pump A was open during the ILRT, thus venting the CCW system to the containment atmosphere. The external system was vented to the surge tank air space.
Therefore any-leakage through the CCW system after safety features valve closure was accounted for in the reported integrated leakage rate.
The above discussion pertaining to valve manipulations supports the position that the ILRT was performed with the containment in as close to the "as is" condition as practical and per the requirements of Appendix J to 10 CFR 50, Section III A.
The ILRT pressure of 52 PSIG i.as reached at 2040, 10/3/77, and the containment atmosphere stabilization cciteria were met at 0045, 10/4/77.
However, as the water level in the NSCW surge tanks was still rising, and the surge tanks did not come solid until 0200, the ILRT was started at 0215.
The ILRT was successfully completed using calculations based on containment atmosphere total pressure, not partial pressure of dry air, in accordance with Section 2.2.C of Bectel Topical Report, BN-TOP-1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants", with a test duration of twenty-nine and one-half hours.
BN-TOP-1 i
Section 2.2.C states:
l "In general, the number of sensors that can be lost without having to abort the test is a function of the number of sensors used, the sensor locations, and the volume fractions assigned to the sensors.
However, if' data recorded over the past five hours indicates that dewpoint temperatures, i. e., partial pressure of water vapor, have stabilized and any changes are not of an order to cause error in leakage rate calculations, then malfunction of any or all of the dewpoint _ censors shall not require aborting the test (See ANSI N45.4-1972, - Section 7.9). Otherwise, at least two-thirds of the dewpoint temperature sensors must be functioning properly during the test."
Analysis of containment atmosphere data for a six-hour period, following the stabilization perioc, showed that the containment leakage rate using the partial pressure of dry air and the containment leakage rate over the same period using' containment atmosphere total pressure agreed within 0.003% per day, or three percent of the maximum allowable leakage rate.
This is in-dicative of the fact that the partial pressure of the water vapor in the containment atmosphere had stabilized and that any changes were not of an b
y
~
y
)
- ~ ~ ~
order:tolcause error'in leakage rate. calculations. 'The. dewpoint temperature
~
~
- system'1oss was caused by sensor heater element power supply failure.
The 4 erratic behavior early in the test was caused by the~ inability of this power
' supply)toiproperly regulate current flow in the heater element power circuitry.
Spikes--in: current: flow to the heater elements overloaded the power supply
~
causingJits' failure.
Eight.een hours into the test,-after modifications to the heater element cir-7 cuits and the installation of a new power supply,.three of the. original six dewpointisensors were restored to service.
As two-thirds of the original
' sensors were'not functioning,.a short duration test.using the partial pressure
-of, dry air in accordance with'BN-TOP-1 was precluded, and calculations were continued lusing the. containment atmosphere total pressure. To establish "that Jthe partial pressure of the water vapor 'in the. containment atmosphere continued stable late in the test,. leakage rate calculations using the last eleven.and one-quarter hours.'of containment atmosphere data were performed.
lThe containment leakage rate using the partial pressure.of dry air and the containment-leakage rate using containment atmosphere total pressure' agreed within 0.001% per day or one percent of the maximum allowable leakage rate.
z
- Therefore', changes -in partial-pressure of the water vapor in the containment atmosphere _ late in the test were not of an order to' cause error in leakage rate calculations.-
Following the successful completion of the ILRT, an.ILRT verification test was performed.. The. verification test consisted of introducing a known leak from the containment equal in magnitude to the maximum allowable leakage c
rate, La, through a chlibrated flow' device.
The verification test results verified that a leakage rate equivalent to theimaximum allowable' leakage rate can be accurately-measured with the'ILRT measurement system.
The ILRT.~ veri-
~
fication test leakage rate calculations were also performed using the contain-ment'atmosphre total pressure, for-proper comparison with the ILRT results.
In addition, verification test-leakage rate. calculations were performed using the partial pressure of dry air.
These results' agreed with the results based on total-pressure calculationswithin 0.005% 'per -day or five percent of the maximum. allowable leakage rate.
Therefore, changes in partial pressure of
- tta water vapor in the~ containment atmosphere during the ILRT verification test"were not of an order co cause error in leakage rate calculations. Approx-
- imately three hours after the-introduction of the-imposed. leak, the main
- power' supply'to the ILRT measurement' system failed, deenergizing the system.-
The power-was; restored to the system in;approximately fifteen minutes, and
.the ILRT measurement system was reenergized.. Prior to-the' power failure, the containment atmosphere total' pressure had been increasing at an average rate
.of..~004' psi per hour. -When powe'r was restored to the system, the precision pressure gage'o? record' indicated an increase'of 0.02 psi ~over the last reading i prior, to the power failure (approximately fif teen minutes had elasped).
This in' crease was prob 3bly)due to a power-failure-caused perturbation of-instrument
. operation and1not an actual. increase in' containment atmosphere' pressure.
After-consultation.'with'the pressure-gage vendor, it was determined that the. shift.
Linireading.wasjprobably due to cooldown and:heatup cf the pressure gage-
~
s
.bourdon capsul _e controlled temperature chamber'during the failure and restor-Jacion of_'panelLpower. During a-one' lour' period lfollowing power restorations.
+
- thel precision pressure u ge~was checked:for proper operation and repeatability'
~
~in"accordance with vendor instructions. The ILRT verification test was restarted N
at'l1215,10/5/77 after successful completion of the above checks. "It should;
~
the notedC hat 1the containment;atmosphe'reftotal pressure continued to increase t
E atithe same rate.~ascit;had prior:to the power failure.
The ILRT verification'-
E
~ 5 test was successfully completed-~at~1830,:10/5/77.L Blowdownicommenced at'1955 e
b
- and%thel containment 1 reached atmospheric pre'ssurerearly in the morning'of'Thurs-p day-?10/6/77..
w 4
g.
Reactor Building Integrated Leakage Rate Test Test Summary Data A.
PLANT -'INFORMATION Owner:
Sacramento Municipal Utility District Docket No.:
50-312 Plant:
Rancho Seco Nuclear Generating Station - Unit 1 Location:
Herald, CA.
Type:
Babcock and Wilcox PWR, Dry, Post-tensioned concrete Date Test Completed:
October 5,1977 B.
TECHNICAL DATA 1.
Containment net free air volume 1,980,000 ft3 2.
Design pressure 59 psig 3.
Calculated peak accident pressure 52 psig 4.
Containment temperature limits for ILRT 40-120 F C.
TEST DATA - TYPE A TEST 1.
Test Method Absolute 2.
Data Analysis Techniques Mass Point and Leakage Rate (Total-Time Per BN-TOP-1) 3.
Test Pressure 52 psig 4.
Maximum Allowable Leakage Rnte (La) 0.1%/ day 5.
75% of-la 0.075%/ day Upper 95%
6.
Calculated Leakage Rate:
Leakage Rate Confidence
(%/ Day)
Limit,
-a.
Mass Point Method 0.023 0.026 b.
Total-Time Method 0.022 0.069 7.
Verification Test imposed Leakage.
0.102 Rate, Li, %/ day l
1
Re et*r Building Integratzd Leakage Rate Test - Test Summary Data h
leakage Rate
(%/ Day) 8.
Verification Test Measured Leakage Rate, Lvm, %/ day a.
Mass Point Method 0.124 b.
Total-Time Method 0.133 9.
Verification Test Limits a.
Upper (Li + lam + 0.25 la) i) Mass Point Method 0.150 ii) Total-Time Method 0.149 b.
lower (Li + lam - 0.25 La) i) Mass Point 0.100
- 11) Total-Time 0.099 10.
Report Printouts Attached are the Report Printouts for the ILRT and the ILRT verification test.
Printouts are provided for the Mass Point and Total-Time Analyses.
Information provided on Report
' Printouts includes:
.ontainment average drybulb temperature and absolute total containment atmosphere pressure for each data set, calculated leakage rate at the upper 95% confidence limit and measured leakage rates.
D.
INTEGRATED LEAKAGE RATE MEASUREMENT SYSTEM 1.
Pressure (1)*
Precision Pressurt Gage - Texas Instruments Model 145-02 with 8-4-2-1 B.C.D. optical shaft encoder installed.
Range:
0-100,000 counts Ar. curacy:
20.015% of reading or better Resolution:
0.001% F.S. or 10.001 PSIA Repeatability:
0.001% F.S. or 0.001 PSIA Bourdon Tube Copsule for Precision Pressure Gage, above, Texas Instruments Type 811.
Range:
0-100 PSIA Calibration Date:
September 22, 1977 12.
Drybulb Temperature (18)
Resistance Temperature Detector - Leeds and Northrup 100-ohm copper thermohm, Catalog No. 8197-10-S, wired in 4-lead e
~
Re cter Building - Intsgrr.tzd Lenkege Rnte Tcat - Test Summ,ry D9tn
-\\-~
Callendar compensating loop configuration. Thermohms conform to the resistance-versus-temperature curves published in Leeds and Northrup Company Standard Conversion Tables for L&N Thermohm Resistance Thermometers, 77-21-0-4, Issue 4.
Range:
32-250 F Limit.of error:
0.5 F Drybulb Temperature Measurement System - Volumetrics 18-channel RTD bridge completion /linearization/ signal conditioning system compatible with the above described resistance temperature' detectors.
Range:
0.00 to 150.00 F Accuracy:
10.5 F Repeatability:
0.1 F Output:
1 mv./ F Calibration Date:
Sept, ember 30, 1977 3.
Dewpoint Temperature * (6)
Dewpoint _ Temperature Measurement System - Volumetrics Model 15229-6, 6-channel system consisting of the following major components:
6 ea. Foxboro VN1201AT "Dewcell" elements with integral "Dynatherm" 3-wire resistance temperature detector conforming to Foxboro curve No. NR226.
I ca. "Dewcell" heater winding power supply.
6 ea.
Resistance temperature ' detector bridge completion /
linear scaling / signal conditioning network circuit boards with resistance temperature detector power supply.
Range:
0.0 to 140.0 F dewpoint Accuracy:
il F for dewpoint range of 40-90*F Repeatability:
0.5 F or better R-c'2 tion:
0.1 F 1 mv./ F Calibration date:
September 30, 1977 4.
Verification Flow (1)
Thermal Mass Flowmeter - Volumetrics Model No. 14627 vith power supply.
3.
Reacter Building - Intngrated Lankage Rate Test - Test Summary Deto Range:
0-10 SCFM
,~
. Output:
0-5 volts square root Accuracy:
1% FS Repeatability:
0.2% FS Calibration Date:
September 23, 1977 5.
.Date Acquistion, Display and Printout Data acquisition system - Volumetrics Model 16711 consisting of an Acurex Autodata Nine microprocessor controlled data acqusition
- and recording system.
In addition to ROM and RAM memory, scanner, required interfacing and clock, the system includes:
1 ea. High resolution integrating digital voltmeter-1 ea. Eighteen-column digital printer I ea. 7-segment LED digital display Drybulb Temperature:
0.00 - 150.00 F Dewpoint Temperature:
0.00 - 140.00 F Time: Hours, minutes, seconds Date:
Julian Date Channel I.D.:
000-999
. 6.
Overall System Figure of Merit (based on repeatability error):
20.025%/ day 7.
Drybulb and Dewpoint Temperature Sensor locations.
(See Table on Page 5 of Test Summary Data) i a
l
^
~
1 4
i
Rret~r Buildina~
Intxgrated 'Lerknge ' Rate Test' - Test Summary Dhta C
Elevation-Aximuth Distance From Volume i--
- Dewpoint'#.
-(Ft)
(Deg.)
Cinter (Ft)
Fraction 1.
105
-0 0
. 2715 2.
65 140 34
.2715 3.
46 035 39
.151 4.
26 138
'32
.166
~ 5.
7 077 40
.086
'6.
-20.
080 42
.054 1.000
_RTD '# -
1.
160 200 7
.175-2.
45 320 25
.0175 3.
65 040 34
.092 4.
65 300 43
.092 5.
65 240 43
.092-6.
65 140 34
.092 7.
46 157 45
.029 8.
46 225 50
.029~
9.
46' 300 40
.029 10.
'45 2 15 23
.0175
- 11. :
46-
.035 39
.029
- 12. -
27' 300 58
.083
-13.
26 138 32
.083 14.
7' 010 48
.043 15;
_7 235.
60
.043 l
16.
-20:
000-40
.018-
- 17.- 210 45
. 018 E 18.
- -20~
080 42
.018
^
s
[
1.000 l
'5.
Reactor Building'- Integrated Leakage Rate Test - Test Summary Data
\\
't NOTE: During pressurization to test pressure, the optical shaft encoders on' the-precision pressure gages- (Item D.I. above) malfunctioned and produced erratic output to the data acquisition system, for.the test ~ duration. The erratic behavior of the shaft encoders did
-not,.however, effect the proper functioning of the gages. Pressure was manually recorded, using the six-decade digital connter provided on the face of each instrument, on the data acqusition system printer record in the appropriate location. These values were entered into the computer program and used in the leakage rate calculations.
Approximately six hours ~into the test, at peak test pressure, the
~
dewpoint temperature measurement system started and continued to provide very erratic readings.
These readings could not.be attri-buted to any plausible physical behavior of the water vapor pressure of the containment. atmosphere..Three of the six "dewcell" elements failed later in the test. 'As a result, the leakage rate calculations were performed using containment atmosphere total pressure, i.e., not the partial pressure of dry air, in accordance with the applicable criteria of-Bechtel Topical Report BN-TOP-1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants." This subject is discussed in the Test Synopsis section of this report.
E.
TEST RESULTS - TYPE B and TYPE C TESTS A Summary of Results of Type B and Type C tests is provided by Sacramento Municipal Utility District.
F.
,INFORMATION RETAINED AT JOBSITE-The following information is not included in the summary but is retained sat the jobsite and available for review:
1.
Data and Data Reduction Raw data-sheets showing ILRT data as recorded from the instru-a.
mentation and as entered in the computer.
d b.
Computer printouts of raw data reduction giving weighted average containment absolute air temperature and pressure suitably ' corrected for calibration, vapor pressure, and volume fractions.
Formulas used by computer for calculation of leakage rate, c.
regression analyses and confidence limits.
d.
' Data ~to verify temperature stabilization.
-2.
_ Systems Status (at time of ILRT)
_ A system-line-up showing valve-positions and status of piping
.a.
systems.(drained, vented, etc.) for all plant systems associated with ILRT.
J f
.6
Reactor Building - Integrated Leakage Rate Test - Test Summary Data
- \\[
-b.
Identification of normal plant instrumentation used in conjunction with-the ILRT.
Equipment protection list identifying action taken to prevent c.
equipment damage due to high containment atmosphere pressure.
3.
Reactor Building Penetration Index 4.
Event Log-A continuous log of ILRT events.
5.
Instrumentation Documentation Calibration data and certificates.
6.
Test Procedure The workirg copy of test procedure including signature sign offs.
7.
Local Leakage Rate Tests The procedure and data to verify completion of penetration and valve testing (Type B and C tests) including measured leakage rates, significant problems found, and' applicable corrective action, and total, overall leakage rate.
8.
Quality Assurance The Quality Assurance audit plan or checklist that was used to monitor'the ILRT.
9.
Local Leak Survey During ILRT Identification of any leakage (into or out of containment) found during ILRT and corrective action taken.
10.
System Restoration-
' Checklist for restoration to normal status of non-standard system 3
-or instrumentation conditions after completion of the'ILRT.
l i
1 a
1 l
f:
6 l
\\
SUMMARY
LATA
--RM4CHO SECD ILRT (HOVAP)
ALMAX = 0.100-VUL = 1980000.00 TIME DATE-TEMP PRES 3URE 215 1004 548.633 67.4170 230 1004 548.637~.67.4170-d45 1004~ 548.655 67.4170 300 1004-548.644 67.4170' 315 1004 548.645 67.4170 330 1004 548.667 67.4170
'345 1004 548.665 67.4180 4 00 E 1004 548.655 67.4190 415 1004 548.681 67.4190
-430 1004 548.582 67.4190
-445 1004 548.700 67.4190 500 1004 548.699 67.4200 515 1004 548.712 67.4210 530 1004 548.718 67.4220 545 1004 ~548.718 67.4220 600 1004 548.745 67.4230 615 1004 548.741 67.4240 630 1004 548.755 67.4250 645 1004 548.765 67.4250 700 1004 548.778 67.4260 715 1004 548.782 67.4260
=730 1004 548.7?7 67.4270 745 1004-543.804 67.4280 300 1004 548.813 67.42?O 815 1004 548.809 67.4290 830 1004 548.828 67.4310 845 1004 548.828 67.4330 900 1004 548.846 67.4340 915 1004 548.853 67.4350 930 1004 548.877 67.4360
-945 1004-548.'891 67.4380 1000 1004 548.905 67.4390 1015~1004 548.923 67.4400 1030-1004 548.914
'67.4410 1100 2004 548.967
~67.4440
-1115 1004 548.949 67.4450 1130 1004 548.980 67.4460 1145 1004 -548.991 67.4470 1200 1004 548.994 67.4480
)
1215 1004-549.028 67.4490 1230 100.4 -549.020
~67.4500 11245 1004 549.~050 67.4510 1
1300 1004 549.070 67.4530 1315.2004 549.064.
67.4540
-1330 1004 549.0S2.
67.4550
-1345-1004. 549.0?1 67.4560
'1400-1004 549.'089 67.4570-1415 1004 549.104:
.67.4590 I430 1004: 549.118 67.4600 1445'1004 549.143 67.4610 1500,1004 549.143
'67.4630
.1515.1004-549.157-67.4650 1530;1004 154521004 - 549.172 67.4650-549.187
-67.4670
- 1C 00 1004 : - 549.193
,/67 469(i) 0 m
1d30.1004~
'549.238 67.4710 1645 1004 549.259 67.'4730 1700 1004 549.267 67.4740
'1715 1004 549.264 67.4760
- \\
1730 1004 549.273
.67.4760 1745 1004 549.294 67.4800 1800 1004. 549.309 67.4810 1815 1004 '54?.339 67.4830 1830 1004' 549.354 67.4850 1845 1004 549.345 67.4860 1900 1004 549.357 67.4880 1915 1004 549.354 67.48?O 1930 1004 54?.392 67.4?00 1945 1004 549.404 67.4920 2000 2004-549.415 67.4?40 2015 1004 549.441 67.4950 2030 1004 549.442 67.4970 2045 1004' 549.447 67.4??0 2100 1004 -549.459 67.5000 2115 1004 549.484 67.5020 2130 1004 549.493 67.5040 2145 1004 549.512 67.5050 2200 1004 549.527 67.5070 2215 1004 '549.527 67.5080 2230-1004 54?.550 67.50?O 2245-1004 54?.556 67.5110 2300 1004 549.563 67.5130 2315.1064 549.58?
67.5140
-2330 1004 549.618 67.5160 2345 1004-549.615 67.5170' 0 1005 549.626 67.5190 15 1005 549.635 67.5200 30 1005 549.648 67.5220 45 1005 549.658 67.5240 100 1005 54?.683
-67.5250-115 1005 549.731 67.5260 130 1005 54?.739
-67.5270 145 1005 549.726' 67.5290 200 1005 549.657 67.5180 215 1005 549.575 67.5140 230 1005 549.586 67.5130
'245 1005 54?.575 67.5120 300 1005 549.558-67.5110 315 1005 549.549 67.5120
--330 1005 549.-539
-67.5120 345~1005 549.563 67.5120
~4 00 1005 54?.565 67.5120 415-1005 549.568 67.5130
-430 1005 549.589 67.5140
~445 10 05 ' -549.576 67.5150 500 1005 549.591 67.5160 515-1005 549.608 67.5180 530 1005 549.634 67.5200 545 1005 549.649 67.5220-
"600 1005-549.663 67.5230
'615!1005' 549.685 67.5250 630-1005 549.671 67.5260 645 1005 549.677 67.5280
'70 0 L i O O5. 54 9. 724 -
67.5290 715 1005 549.700 67.5310-1730:1005 '549.730-67.5330
'-745'1005' 549.755' 67.5340 9.
L n
w e-cua
RANCHO SECD-ILRT <HOVAP)
TREND PEPORT T
LEAKAGE PATES udEIGHT PERCENT / DAY)
L\\
'EAIED DH TOTAL-TIME-CALCULATIDHS a
TIME AND DATE AT ITAPT OF TEIT:
215 1004 ELAP5ED TINE:
29.50 HOURS HD. DATA ELAPIED HEAD MEASUPED CALCULATED CHG IN CALC L/R UPPEP 95%
PDIHTS TIME LEAKAGE PATE LEAKAGE FATE FPDM LAST POIHT COHF LEVEL
_-=_=-
-10 2.25 0.058
-0.026 0.166
- 11 ~
2.50 0.061 0.000 0.026 0.202 12 2.75 0.061 0.012 0.012 0.205 13 3.00 0.062 0.021 0.00?
0.206 14 3.25 0.062 0.027 0.005 0.201 15 3.50 0.061 0.030 0.003 0.195 16 3.75 0.062 0.037 0.007 0.196 17-4.00' 5 0.062 0.038 0.002 0.190 18 4.25 0.062 0.040 0.002 0.186 19 4.50 0.062 0.043 0.003 0.184 20 4.75 0.062 0.046 0.003 0.182
-21 5.00 0.062 0.048 0.002 0.180 22 5.25 0.062 0.051 0.002 0.178 23 5.50 0.063 0.052 0.001 0.176
-24 5.75 0.063 0.053 0.001 0.173 25 6.00 0.062 0.053
-0.000 0.170 26 6.25
~ 0. 062 0.053
-0.000 0.166
~27 6.50 0.061 0.051
-0.002 0.161 28 6.75 0.061 0.050
-0.001 0.158 29 7.00 0.060 0.048
- 0. 001 0.154 30 7.23 0.060 0.048
-0.000 0.152 31 7.50-0.060 0.048
-0.000 0.149 32 7.75 0.060 0.048
-0.000 0.147 33 8.00 0.060 0.048 0.000 0.145 34' 8.25 0.05?
0.047
-0.001 0.142 35 8.75 0.05?
0.047
-0.000 0.141 36 9.00 0.05?
0.046
-0.001 0.138 37 9.25' 0.058 0.046 0.000 0.137 38 9.50 0.058 0.046 0.000 0.135
- 39 9.75 0.058 0.046
-0.000 0.133 40 10.00 0.058 0.047 0.001 0.133 4if i0.25 0.058 0.046
-0.000 0.131 42 10.50 0.058 0.~ 047 0.001 0.131 43 10.75 0.058 0.048 0.001 0.130 44 11.00 0.058 0.048
-0.000 0.'129 45 11.25
-0.058 0.048 0.000 0.123 46
.I1.50-
- u. Uu.::
'O.048 0.000 0.127 47 11.75 0.057 0.048
-0.000 0.126
.48 12.00 0.057 0.047
-0.000 0.124 J49 12.25 0.057 0.047
-0.000 0.123
'50 12.50 0.057 0.047 0.000 0.122 51 12.75 0.057 0.047
-0.000 0.121
-52 13.00 0.056 0.046
- 0. 001 0.120 53' 13.25 0.056
'0. 046
-0.000 0.119
~54 13.50-0.056 0.046
-0.000 0.118 1
-55 13.75 0.056:
0.045
-0.000 0.117 l
. ' 56
-14.00 0.056 0.045
-0.000 0.116 1
,57 14.25 0.056-0.0.45 0.000 0.115 j
1 158 14.50:
0.056-0.045 0.000 0.115
' 5 9_ '
14.75:
0.056 0.045 0.000 0.114
rnec a HD. DATA ELAP2ED HEAH HEASUPED CALCULATED CHG IN CALC L/R UPPER 95*4 POINTS TIME.
LEAKAGE RATE _ LEAKAGE RATE FROM LAST POINT CONF LEVEL 61 15.25 0.055 0.044
-0.001 0.112 62 15.50' O 055 0.044
-0.000 0.110 63-15.75
-0.055 0.043
-0.000 0.109 64.
16.00 0.055-0.043
-0.000 0.10?
-65 16.25 0.054 0.043
-0.000 0.108 66 16.50 0.054 0.042
- 0. 001 0.107 67 16.75 0.054 0.042
-0.001 0.106 68 17.00 0.054 0.041
-0.001 0.104 6?-
17.25 0.053 0.041
-0.000 0.104 70 17.50 0.053 0.040
-0.000 0.103 71 17.75 0.053 0.040
-0.000 0.102 72 18.00 0.053 0.040
-0.000 0.101 73-18.25 0.053 0.039
-0.000 0.100 74 18.50 0.052 0.039
- 0. 001 0.099 75 18.75 0.052 0.033
-0.001 0.0?8 76 19.00 0.052 0.033
-0.000 0.0?7 77 19.25 0.052 0.037
-0.001
- 0. 096.
78 19.50-0.052 0.037
-0.000 0.095 79 19.75 0.051 0.036
-0.000 0.0?4 30 20.00 0.051 0.036
-0.001 0.094 Si 20.25 0.051 0.035
-0.000 0.0?3-82 20.50 0.051 0.035
-0.000 0.0?2 83 20.75 0.051 0.034
-0.001 0.091 64 21.00 0.050 0.034
-0.000 0.0?O 65 21.25 0.050 0.034
-0.000 0.0?0 66 21.50 0.050 0.034
-0.000 0.089 87 21.75 0.050 0.033
-0.000 0.083
.88 22.00 0.050 0.033
-0.000 0.087 89 22.25 0.049 0.032
-0.000 0.087 90 22.50 0.049 0.032
-0.000 0.086 91' 22.75 0.049 0.031
-0.000 0.085 92 -
23.00 0.049 0.031
-0.000 0.085 93 23.25 0.049 0.031
-0.000 0.085 94 23.50 0.049 0.031
-0.000 0.084 95 23.75 0.048 0.031
-0.000 0.084 96 24.00 0.048 0.031
-0.000 0.083 97 24.25 0.048 0.030
-0.000
- 0. 082.
98 24.50 0.048 0.030
-0.000
'O. 082 9?
24.75 0.048 0.029
-0.000 0.081 100 25.00 0.047 0.029
- 0. 001 0.080 101 25.25 0.047 0.028
-0.001 0.079
-102 25.50 0.047 0.028
-0.000 0.078 103.
25.75 0.047 0.027
-0.000 0.078 104 26.00 0.047 0.027
-0.000 0.077, 105 26.25 0.046 0.027
-0.000 0.076 106 26.50 0.046 0.026
-0.000 0.076 107 26.75
- 0. 046 0.026
-0.000 0.075 108 27.00 0.046 0.025
-0.000 0.074 109 27.25 0.046 0.025
-0.000 0.074 110 27.50 0.045 0.025.
-0.000 0.073 111 27.75 0.045 0.024
-0.000 0.073 112 28.00 0.045 0.024
-0.000 0.072
~
113 28.25 0.045 0.024
-0.000 0.072
.114 23.50 0.045 0.023
.0.000 0.071
-115 28.75 0.645 0.023
-0.000 0.070 116 29.00 0.044-0.023
-0.000 0.070 117 29.25 0.044 0.022
-0.000 0.069
- 118 L29.50 0.044
_0.022
-0.000 0.069
' i RANCHO SECD ILRT <HOVAP)
LEARAGE.PATE GIEIGHT PERCENT / DAY)
BASED DH-TDTAL TIME CALCULATIDd5 TIME add DATE AT START OF TEST
- 215 1004 ELAP5ED TIME:
29.50 HOURS 7Inc i CMP..
PPE5SURE MEASUPED (R)
(PSIA)
LEAKA6E RATE 215 548.633
.67.4170 230 543.637 67.4170 0.070 24u v43.655 67.4170 0.192 300 548.644 67.4170 0.064 315 548.645 67.4170 0.052 330 548.667 67.4170 0.119 345 548.665 67.4180 0.070 400 548.655 67.4190 0.014 415 548.681 67.4190
-0.069 430 548.582 67.4190
-0.131 445 548.700 67.4190 0.089 500 548.699 67.4200 0.066-515 548.712 67.4210 0.068 530 548.718 67.4220 0.060 545 548.718 67.4220 0.055 600 548.745 67.4230 0.074 615 548.741 67.4240 0.056 630
~548.755 67.4250 0.059 645
-548.765-
'67.4250 0.065
-700 548.778
.67.4260 0.066 715 543.782 67.4260 0.066 730 548.797 67.4270-0.069 o
745 548.804 267.4280 0.065 800' 548.813 67.4290 0.063-815 548.809 67.4290 0.057
~830 548.828 67.4310 0.057 845 548.~ 828 67.4330 0.044 900 548.846 67.4340 0.04S 915-548.853 67.4350 0.046
-930 548.877 67.4360 0.054 945
'548.891 67.4330.
0.051 1000 548.905 67.4390 0.052 1
1015 548.923 67.4400 0.056
~1030
-548.914-67.4410 0.045-G t
4 e
y e
..4-e 2
12.
PAGE 2 LEAKAGE-PATE (WEIGHT PEPCEtiT/ DAY)
EAIED Ott TOTAL TIi1E CALCULATIUii3 TIf1E-TEl1P.
PPE55UPE (1EA50 PED (P)
- PIIA)
LEAKAGE PATE
=
1100 548.967 67.4440 0.057 1115:
548.449 67.4450
~ 0. 04 3 1130-548.980 67.4460 0.052 1143 048.9?1 67.4470 0.052 1200 548.9?4 67.4480 0.049 1215-54?.028 67.44?O 0.059 1230 549.020 67.4500 0.051 1245-549.050 67.4510 0.058 1300
'549.070 67.4530 0.059 131o 949.064 67.4540 0.052 1330 549.082 67.4550 0.054 1'345 549.091 67.4560 0.053 1400 549.089 67.4570 0.049 1415-549.104 67.4590 0.047 1430 549.118 67.4600 0.048 1445 549.143 67.4610 0.053 1500 549.143 67.4630 0.046 151o 049.157 67.4650 0.045 1530 549.172 67.4650 0.04?
154u 049.187 67.4670 0.048 1600 54?.193 67.4680 0.046 1615 54?.222 67.4700 0.049
.1630
~549.238 67.4710 0.051 1645 54?.259 67.4730 0.051
.1700 54?.267 67.4740 0.050 11715' 549.264 67.4760 0.044 1730 549.273 67.4780 0.041 174o o49.294 67.4800 0.042 1800 549.309 67.4810 0.043 1815 549.33?
67.4830 0.046 1830-549.354-67.4850 0.045 1845
-549.345 67.4860 0.040 1900 549.357
-67.4880 0.038 191o
-o49.354 67.4890 0.035 1930-549.392 67.4900 0.042 1945 549.404 67.4920 0.040 2000 549.415 67.4940 0.038 2015-549.441 67.4950 0.042 2030
~ 54 ?. 442 67.4970 0.038 2045 549.447 67.49?O 0.035 2100 549.459
.67.5000 0.035 2115 549.484 67.5020' O.037 2130 549.493 67.5040 0.034 2145-549.512 67.5050 0.036 2200 549.527 67.5070 0.036' 2215
~549.527 67.5080 0.034 2230-549.550' 67.5090 0.036 2245-549.556 67.5110 0.034 r2300 549.563
.67.5130 0.031 4~
~2315' 549.589
'67.'5140 0.035
~
nn-
- u. _
PMet o
' LEAKAGE RATE GJEIGHT PERCENT /DAV) b BASED DH TOTAL TIME-CALCULATIONS
. 4:. It
___.w
--.. l e.
. Fe ts o de_.c_
(1er.. d. _ _ D ico
- n. et s ro, s.es 4 Me, tcMNMet eMic 2530:
54?.618 67.5160 0.037 2345 549.615 67.5170 0.034 0
549.626 67.5190 0.033 15 549.635 67.5200 0.033.
L30 549.648 67.5220 0.031 45 549.658 67.5240 0.030 100
'549.683 67.5250 0.033 115 549.731 67.5260
- 0. 04 0 130 549.739 67.5270 O.040 145 549.726 67.5290.
0.034 200 549.657 67.5180-0.037 215 549.575 67.5140 0.028 230-549.586 67.5130' O.031 240 049.575 67.5120 0.030 300
'549.558 67.5110 0.028 315 549.549 67.5120 0.025 330 549.539 67.5120 0.023 34 49.563 67.5120 0.027 400 549.565 67.5120 0.027 440 U4.t.3%d.
O r. U 4 4..U U. U...do 430 549.589-67.5140 0.028 445 549.576 67.5150 0.024 500 549.591 67.5160 0.025
_. o_
_4.2. e. V..,
e<.-.
u
- 0. u..,a_
vi 0
o uio m
530
.54?.634 67.5200 0.026 545 549.649 67.5220
'0.026 600 549.668 67.5230 0.027 615' 549.685 67.5250 0.027 630 549.671 67.5260 0.023 645 549.677 67.5280 0.022 700' 549.724 67.5290 0.027 715 549.700 67.5310 0.021 730 549.730 67.5330 0.023 745 549.755 67.5340 0.025 L
MEAH DF MEASURED LEAKAGE RA7EI
=
0.044
- D _... M i 4 Dil Or_ titMe d. _ _D. _ _.,n. _-
M i t s ev4
.._.. et ttMn et r.
=
0.
o siD
,o_..IMdit ALLDotABLE J LEAKAGE ' RATE i1AX
=
0.100
.. i r
. D r_ H. M a,..1d M..M LLDi.JM E.tt LtMAMot MMit-
=
- 0. 0,< _a 0.022
.7HE CALCULATED teMr Met kMTE
=
-THE-C LC. LEAMAGE RATE'A7 95% CONFIDENCE LEVEL 0.022 2 0.047 A
=
k :
f 9
y
- 14..
RANCHO IECD ILRT (iiDVAP)
(ilEIGHT PERCEHT/ DAY)
LEAKAGE RATE t
MASS PDIMT MALYSIS TIME AND DATE AT START OF TEST:
215 1004 ELAP5ED TIME:
29.50 HOURS
.Da.,
i D i. H v'<..
HsH.,
L a
..s entsa ke sr1Ha a
____.d.--
iMs. H4n
-. te-
-- te_
i ci e as (R)-
(PSIA)
MASS (LBM)
(LBM)
LDS5 (LBM/HR)
.-- 3 cau u4 0. ed o, e r. 4,4 < U eue<wi d. U.
v4c e..,
er.4.
0 euerie 4.0 1 8..4 3
J<
A<
c 4 e>
v44.oup c.c.4.,0 eu c e r,.
ca.u uw,. o 1<
o,00 v4o e.44 o<.4.
v-eue < 0o, 20.c.
4<.o 4c 315 548.645 67.4170 656706 1.2 14.4 330 -548.667 67.4170 6retto 26.3 32.6
. t. U o~u v4 o, c.. -ou os.4.
u.
- c. oerc 1d.1 i
se 400 548.655 67.4190 656714
-21.7 3.9 415 548.681 67.4190 656683 31.1 19.0 430 -548.582 67.4190 656801
-118.5
-35.8 445 548.700' 67.4190 656660 141.2 24.3 500 548.69?
67.4200 656671
-10.9 18.1 uA.,s u4d.<A2 o,<. 4 c. O evoted
- u. d.
20.-0 A
530 548.718 67.4220 656668
-2.6 16.3 545 548.718 67.4220-656668 0.
15.1 600 548.745 67.4230 656645 22.6 20.2 615' 548.741 67.4240 656660
-14.5 15.3
-v
- e. ee.uo.
<.0 to.0 au e.,<.4eu0
.<r-e30 u4 e.
645 548.765 67.4250 656641 12.0 17.8
,a4 e.,
-- s e.<.4d..u.
ovee.su 0.6 s o..1
,00
.<<e e
1 715 548.-782-67.4260
'656630 4.' 8 18.1 730 -548.797 67.4270 656622 8.2 18.8 745 548.804 67.4280
-656623
-1.4 17.7 800 548.813 67.4290 656622
- 1. 0 17.1 815 548.809 67.42?0 656627
-4. 8 15.6 830- 548.828 67.4310 656624 3.3 15.5
- 845 548.828 67.4330 656643
-19.5 11.9 900 548.846 67.4340 656631 11.8 13.2 915 548.853 67.4350 656633
-1.4 12.6 o930 548.~877 67.4360-.
656614 19.0 14.7 945. 548.891' 67.4380 656617
-2.7 13.9 1000- 548.905 67.4390-656610 7.0 14.3 1015'.548.923
-67.4400 656598 11.8 15.4-15.
y
LEAKAGE RATE <h!EIGHT PERCENT / DAY)
PAGE 2 NASS PDIHT AHALYSIS
~
TIME TEMP
' PRESSURE ~
CTMT. AIR MAS 5 LDSS 707. AVG. NASS
'\\.
'<R)
(PSIA)
MASS (LBM)
(LBM)
LDSS. (LBrkHR) 1030 548.914 67.4410 656618
-20.5 12.4~
1100 548.967-67.4440 656584 34.2 15.6 1115 548.949 67.4450 656615
-31.3 11.7 1130 548.980 67.4460 65653S 27.3 14.4 1145 548.991 67.4470 656535 3.4 14.3 1200- UJ3.994 67.4480 656591
-6.1 13.3 1215 549.028 67.4490 656560 30.9 16.1 1230 549.020 67.4500 656579
-19.3
'13.8 1245 549.000 67.4510 656553 26.1 16.0 1300 549.070 67.4530 656549 4.5 16.0 1315 549.064 67.4540 656565
-16.9 14.1 1330 549.082.
67.4550 656554 11.8 14.9 1345 '549.091 67.4560 656553 1.0
.14.6 4U.0 un. t. 06?
o r. 4_,c 0 ovouou i d..1 14.4 1
u 1415 549.104 67.4590 656566
-1.5-12.9 1430 549.118 67.4600 656559
- 7. 0 13.2 1445 549.143 67.4610 656539 20.2 14.5
._su00 e4t.143 o<.4o. 0 ovouvf 12.u a d..c a..
3 Au._
u W., 3., _,<
o,r.4o. 0
- eseves,
- d.,<
24.e
.u su u
r 3
.1530 54?.172 67.4600 656543 17.9 13.4
.c sa4u_
_4 t. s.,,
o,,. 4 s.,0 ousu4u_
~1.0 10 0 v
or r
1600 549.193 67.4680 656547
-2.6 12.6
_4_.cdw3 or.4<00 e u e d o,c.
v1 401o
.3 3
iv.m 2v.o 1630 54?.'23S' 67.4710 656523 9.4 13.9 1645 549.259 67.4730 656017 5.6 14.0 1700 549.267 67.4740 656517
- 0. 2 13.8 1715 549.264 67.4760 656540
-23.0 12.0 1730. 549.273 67.4780 656549
-3.7 11.3 1745 549.294 67.4800 656543 5.6 11.4 1800 549.309 67.4810 65653u d.2 11.8 1815.549.339 67.4830 656519 16.4 12.6 1830.549.354 67.4850 656520
-1.5 12.3 1845 549.345 67.4860 656541
-20.5 10.9 1900 549.357 67.4880 656546
-5.1 10.4 1915-549.354 67.4890 656559
-13.3 9.5 1930 549.392 67.4900 656524 35.7 11.4 1945. 549.404 67.4920.
656529
-5.1 11.0 2000 549.415 67.4940 656535
-6.3 10.5 2015 549.441
.67.4950 656514 21.4 11.5 2030 549.442
-67.4970 656532
-18.3 10.3 2045 549.447 67.4990 656545
-13.o v.5 2100 549.459 67.5000 656541' 4.6 9.6 2115 549.484 67.5020 656530 10.4 10.0
'2130' 549.493
.67.5040 656539
-S.c v.4 2145 549.512.
67.5050
-656526 13.0 10.0
~2200 ~549.527 67.5070 656528
-1.5 9.8 2215-549.527 67.5080 656537
-9.7 9.2 2230 549.550 67.5090 656520 17.8 9.9
'2245-549.556' 67.5110 656532
-12.3
~9.2 2300 549.563 67.5130~
656543
-11.1 8.6 2315 549.589
.67.5140 656522 21.3 9.5 12330 J5.49. 618 67.5160 656506 15.2 10.1
~
16.
iEARAGE RATE'< WEIGHT PERCEtiT/ day >
-PA(
3 44 ASS POIriT 6tiALYSIS "TIl1E TEt1P PRESSURE' CTt17. AIR (1 ASS LDSS TOT. AVG. r1 ASS
}
(R)
(PSIA >
- f1 ASS <LBtD (LBr0 LDSS
. LBileHP) 2345 '549.615.
67.5170 656520
-13.3 o -
0 '549.626 67.5190 656526
-6.3 l'h
~*
15 -549.635 67.5200-d.56525 1.0
,3 o 30 549.648 67.5220 6.56529
-3.9 g,"g 45 549.658 67.5240 656536
-7.5 8"2
^ i 00 549.683 67.5250 656516 20.I 9~ 0 115 549.731-67.5260 656469 47.6 r.[0 130 549.739 67.5270 656469
-0. 2
. 's i45 549.726 67.5290 656504
-35.0 o2
' ((~ 2 200 549.657 67.5180 656479 24.5
.215 549.575 67.5140-656538
-5[4 5'I 1
7 -
230 549.586 67.5130 656516 2
o 245 549.575 67.5120 656519
-3.'d 5
'2 300 549.558 67.5110 656530
-10.6 I~'-
313 549.549 67.5120 656550
-20 e 330 54i4.539 67.5120 656562
--12' b, EI
?"
345 -549.563 67.5120 656533 28 '
400 549.565 67.5120 656531 2*b 1'i
'415 549.568 67.5130 656537
-6"i i'I 430 549.589 67.5140 656522
-_ $.5 * $
445 549.576 67.5150
.:.n6547
" "r *"
bb vi -
U----
500 54 4. 5 :+ 4 o~<.e oO boo 3W 8'2 3
D, 513 549.608 67.5180 656538 0~ o 530 549.634 67.5200 65652'6 II*d i'*
545 549.649 67.5220 656528 I' $:-
i' 600 549.668 67.5230 656515 I
l' e15 -549.685 67.5250 656514 0o 630: 549.671 67.5260 656540
-26'k
(*
E*i e45-549.677 67.5280 656553
-1":'3 D5 700 549.724 67.5290-656506
'4
$*2 715 549.700 67.5310 656554
-48 i.
730 549.730 67.5330 656538 16$4
[6lh 745 549.755 67.5340 656518 20+ 1 9
rRe-t H2R VOLUilE USED (i1ILLIDiiS OF CU. FT.)
1.930
=
REGRESSIDri LIifE IliTERCEPT (LBl0 spooso.
SLDPt stBt1/HR)
-o. 2 11AXIi1Ui1 ALLOWABLE LEAKAGE. RATE 75 % OF 't1AXIi1Uti-ALLDi> TABLE LEAKAGE RATE
[
f **.
THE CALCULATED LEAKAGE RATE
'Y THE CALC.. LEAKAGE RATE AT 95% CDjiFIDEliCE LEVEL E
32 0.003 1.
b.
g
- ~. (
'I. L
- 17.'
t M,,
- - 0. -
m' X.
x 4-2UMMARY DATA RANCHO SECD'ILRT-VERIFICATION (HOVAP)
ALMAX = 0.100 VOL = 1980000.00
- VRATET~=-0.124-VRATEP = 0.102 VRATEM = 0.125
-e TIME-DATE-TEMP PRESSURE 1215 1005 550.065-67.564 1230 1005'.550.075 67.565 1245 1005' 550.086 67.565
'-1300 1000 v30.113:
67.565 1315.1005.L550.142
~67.565 1330-1005 550.129 67.565 1345 1005' 550.147 67.566
- 1400 1003 030.168 67.563 1415 1005' 550.'203
~67.569 1430.1005 550.185.
67.570 1445-1005 550.210 67.571
.-4000,000
- 0. c,, o, e r. o n, co t
4 1515 1005 550.255 67.573 1530'1005 550.264 67.574 1545 1005 550.285 67.575 1600 1005 550.313 67.576
.1615 1000 0u0.303 67.577 163.0/1005 550.320 67.579 1645L1005 550.328 67.530 1700 1005 550.350 67.581 1715 1005 550.363 67.532-1730.1005' 550.393
-67.584 1745 1005 :550.;437' 67.584 1800.1'005: 550.412
'67.586 1815 1005-550.421 67.587
. 1330 1005 '550.439 67.538 JG 0
- 0. 0 -
- 0. 0 4
t p
- 18 ' -
A g
a w'
4 i*
RANCHO SECD ILRT VEPIFIC ATIDH '(HOVAP)
. LEAKAGE PATE-(WEIGHT PERCENT / DAY)
BAIED DH TOTAL TIME CALCULATIDMS-TIME'AHD DATE AT START OF TEST:
1215 1005 ELAPSED TIME:
6.25 HOURS TIME TEMP.
PRES 5URE MEASURED (R)
-(PSIA >
LEAKAGE RATE
.-----==__=-
1215
'550.065 67.0640 1230 550.075 67.5650 0.032 1245 550.086 67.5650 0.112 1300 550.113 67.5650 0.232 1315 550.142 67.5650 0.300 1330 550.129 67.5650 0.195 1345 550.147 67.5660 0.191 1400 550.168 67.5680 0.176 141o o00.208 67.'5690 0.223 1430 550.185 67.5700
~0.138 1445
~550.210 67.5710 0.154 1500 550.218 67.5720 0.139 1515' 550.255 67.5730 0.170 1530 550.264 67.5740 0.158 1545 550.285 67.5750 0.163 1600 550.318
- 67.5760 0.181 1615 550.303 67.5770 0.144 1630 550.320 67.5790 0.136 1645 550.328 67.5800 0.129 2
1700 550.350 67.5810 0.135 1715' 550.363 67.5820 0.132 1730 550.393 67.5840 0.137
-\\
1745 550.437' 67.5840 0.166 1800 550.412-67.5860 0.127 o
1815 550.421 67.5870 0.123 1830 550.439 67.~ 588 0 0.125
.l
\\
' STD.~DEVIATIDH DF MEA 5URED LEAKAGE RATES 0.049
=
i 1
VERIFICATIDH TEST LEAKm_,c knit UPPER LIMIT =
0.149
- VERIFICATION TEST LEAKAGE RATE LOWER LIMIT.=
0.099
.THE~ CALCULATED LEARAGE RATE 0.133
=
S 4
19.
C
. i
V N
RANCHO SECD ILRT VERIFICATIDlf <tiDVAP)
LEAKAGE RATE (i4EIGHT PERC EiiT/ DAY)
MASS PDIriT AHALYSIS TIDE AHD-DATE AT-STAPT OF TEST:
1215 1005-ELAPSED TIME;
. 6.25 HOURS TIME-TEMP PRESSURE tiMT. AIR MASS ~LDSS TOT. AVG. HASS (R) 4 PSIA)
HASS (LBM)
(LBd>
LDSS <tBM/HP) 1215 550.065 167.5640-656439 1230 -550.075 67.5650 656437 2.2 S.3 1240. ov0.086 67.5650 656424 13.1 30.7 1300 550.113 67.5650 656392 32.2 63.4 1315 550.~142 67.5650 656357 34.6 82.2 s w,., u.
- v.,s a. t or.awoo o v o m,O.
10 0 o,.. o.
ou e.-
1345 550.147 67.5660 656361 11.8 52.3 1400 550.168 67.5680 656355 5.6 48.0 1415 550.208 67.5690 656317 38.0
- 61. 0 1430 550.185 67.5700 656354
-37.2 37.7 1445 550.210 67.5710 656334 20.1 42.0 1500 550.218 67.5720 656335
-0.2 38.1 1515 550.255 67.5730 656300 34.4 46.4 1530 550.264 67.5740 65629?
1.0 43.2
- 1545 550.235 67.5750 656284 15.3 44.5 1600 550.318
.67.5760 656254 29.6 49.4 1~615' 550.303 67.5770 656282
-27.6 39.4 1630 550.320 67.5790 656281
- 0. S 37.3 1645 550.328 67.5800 656281
-0. 2 35.2 1700 550.350 67.5810 656264 16.5 36.8 1715 550.363
-67.5320 656259 U.S 36.1 1730- 550.3?3
-67.5840 656242 16.4 37.5 1745.550.437 67.5840 656190 52.5 45.4 1800 550.412- -67.5360.
65623?
-49.2 34.8
. 1815 550.421 67.5870 656233
- 1. 0 33.5
,1830 550.439 67.5830 656226 II.8 34.1 FREEinIR VOLUME USED (MILLIDilS DF CU. FT.)
1.980
=
.RE6RESSIDri LINE
-INTERCEPT (LEM)
=
656413 SLDPE. (LEM/HR)
-33.9
=
-VERIFICATIDif TEST LEAKAGE RATE UFPER LIMIT ~=
0.150 VERIFICATIDH TEST LEAKAGE FATE LOWER LIMIT =
.0.100 THE CALCULATED LEARAGE RATE 0.124
=
- N A -
O k N n
e-
.q.+-
20.
h.i.i;