ML20078B922
| ML20078B922 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 10/20/1994 |
| From: | Kraft E COMMONWEALTH EDISON CO. |
| To: | Russell W NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation |
| References | |
| STM-94-001, STM-94-1, NUDOCS 9410270243 | |
| Download: ML20078B922 (79) | |
Text
.
0 Cordota. Ilknois 612429740 C:mm:nw:alth Edis:n Oued Cities Nuclear Power Station l
22710 206 Avenue North Telephone 309/654 2241 STM-94-001 October 20, 1994 Mr. William Russell Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission ATTN:
Document Control Desk Washington, D.C.
20555
SUBJECT:
Quad-Cities Nuclear Power Station Reactor Containment Building Integrated Leak Rate Test NRC Docket No. 50-254, DPR-29. Unit One
Dear Mr. Russell:
Enclosed please find the report " Reactor Containment Building Integrated Leak Rate Test. Quad-Cities Nuclear Power Station. Unit One. July 23-24, 1994" and the related appendices describing the Type A test.
This report is submitted to you in accordance with the requirement of 10 CFR 50, Appendix J.Section V.B.1.
The information contained in Appendix A of this report is intended to comply with requirements of 10 CFR 50. Appendix J.
Section V.B.3.
The next Type A test for Quad-Cities Unit One is scheduled for the spring of 1996.
Very truly yours, COMMONWEALTH EDISON COMPANY Quad-Cities Nuclear Power Station E. S. Kraf. J Acting Station Manager ESK/MH/kjv Attachment 1
cc:
J. Martin. Regional Administrator C. Miller, Senior Resident Inspector STMGRwl44 STM u.
j){ h #
/
9410270243 941020 PDR ADOCK 05000254 I
P PDR k
REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST QUAD-CITIES NUCLEAR POWER STATION UNIT ONE JULY 23-24, 1994 TECH 364 k
TABLE OF CONTENTS PAGE TABLE AND FIGURES INDEX..........................
1 INTRODUCTION
............................... 4 A.
TEST PREPARATIONS A.1 Type A Test Procedures 4-A.2 Type A Test Instrumentation.................. 4 A.2.a.
Temperature 9
A.2.b.
Pressure..........................
9 A.2.c.
Vapor Pressure......................
10 A.2.d.
F l o w...........................
10 A.3 Type A Test Pressurization 10 B.
TEST METHOD B.1 Basic Technique.......................
11 B.2 Supplemental Verification Test
...............14 B.3 Instrument Error Analysis..................
14 C.
SEQUENCE OF EVENTS C.1 Test Preparation Chronology.................
15 i
C.2 Test Pressurization and Stabilization Chronology......
16 C.3 Measured Leak Rate Phase Chronology.............
16 C.4 Induced Leakage Phase Chronology 16 C.5 Depressurization Phase Chronology..............
17 D.
TYPE A TEST DATA D.1 Measured Leak Rate Phase Data................
18 D.2 Induced Leakage Phase Data.................
18 TECH 364 1
't i
TABLE OF CONTENTS (Continued)
PAGE E.
TEST CALCULATIONS.........................
29 F.
TYPE A TEST RESULTS F.1 Measured Leak Rate Test Results...............
51 F.2 Induced Leakage Test Results 31 F.3 Pre-Operational Results vs. Test Results
..........32 F.4 Type A Test Penalties....................
32 F.5 Evaluation of Instrument Failures..............
33 F.6 As-Found Type A Test Results 33 APPENDIX A TYPE B AND C TESTS....................
34 APPENDIX B COMPUTATIONAL PROCEDURES.................
50 APPENDIX C INSTRUMENT ERROR ANALYSIS 62 i
APPENDIX D BN-TOP-1. REV. 1 ERRATA
.................68 l
APPENDIX E TYPE A TEST RESULTS USING MASS-PLOT...........
73 METHOD (ANS/ ANSI 56.8) i l
TECl! 364 2
TABLES AND FIGURES INDEX PAGE TABLE 1 Instrument Specifications...................
6 TABLE 2 Sensor Physical Locations...................
7 TABLE 3 Measured Leak Rate Phase Test Results............
19 TABLE 4 Induced Leakage Phase Test Results
.............20 TABLE E-1 Mass Point - Measured Leak Rate Phase Test Results 74 TABLE E-2 Mass Point - Induced Leak Rate. Phase Test Results......
75 FIGURE 1 Idealized View of Drywell and Torus..............
8 Used to Calculate Free Air Volumes FIGURE 2 Measurement System Schematic Arrangement 12 FIGURE 3 Measured Leak Rate Phase - Graph of Calculated 21 Leak Rate and Upper Confidence Limit FIGURE 4 Measured Leak Rate Phase - Graph of.............
22 Dry Air Pressure FIGURE 5 Measured Leak Rate Phase - Graph of Volume 23 Weighted Average Containment V6por Pressure FIGURE 6 Measured Leak Rate Phase - Graph of Volume 24 Weighted Average Containment Temperature 1
FIGURE 7 Induced Leakage Phase - Graph of Calculated.........
25 Leak Rate FIGURE 8 Induced Leakage Phase - Graph of Volume...........
26 Weighted Average Containment Temperature FIGURE 9 Induced Leakage Phase - Graph of Volume...........
27 Weighted Average Containment Vapor Pressure FIGURE 10 Induced Leakage Phase - Graph of
..............28 Dry Air Pressure FIGURE E-1 Mass Point - Measured Phase - Graph of Calculated Leak Rate and Upper Confidence Limit 76 FIGURE E-2 Mass Point - Induced Phase - Grsph of Calculated Leak Rate...........
77 Tncn 364 3
INTRODUCTION This report presents the test method and results of the Integrated Primary Containment Leak Rate Test (IPCLRT) successfully performed on July 23-24, 1994 at Quad-Cities Nuclear Power Station, Unit One.
The test was performed in accordance with 10 CFR 50, Appendix J, and the Quad-Cities Unit One Technical Specifications.
For the tenth time at Quad Cities a short duration test (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> was conducted using the general test method outlined in BN-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 method, the total primary containment integrated leak rate was calculated to be.3003 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 L.).
The associated upper 95% confidence limit was 0.3382 wt %/ day.
The supplemental induced leakage test result was calculated to be 1.2491 wt
%/ day.
This value should compare with the sum of the measured leak rate phase result (0.3003 wt %/ day) and the induced leak of 8.5 SCFM (1.0147 wt %/ day). The calculated leak rate of 1.2491 wt %/ day lies within the allowable tolerance band of 1.315 wt %/ day 0.250 wt %/ day.
SECTION A - TEST PREPARATIONS A.1.
Type A Test Procedure The IPCLRT was performed in accordance with Quad-Cities Procedures Qr.TS 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.
Type A Test Instrumentation 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 representative of the conditions present in the annulus.
Toca 364 4
1 Also, instrumentation was used inside containment for subvolume 11, which is the reactor vessel region.
In order to acquire vessel temperature, sensors were mounted onto piping' associated with the Residual Heat Removal i
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.
4 A Graftel, Inc., Smart Sensor Instrumentation System was used in the performance of this test as shown in Figure 2.
The Smart Sensors' 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 i
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.
The sensors were connected in 8 strings with each string containing both temperature and RH sensors. Although the sensors are physically connected i
in series, they are electrically connected in parallel. This ensures that the failure of any one sensor will not affect the others. The strings are connected to a standard communications port of an IBM compatible PC.
t I
TECH M4 5
TABLE ONE INSTRUMENT SPECIFICATIONS INSTRUMENT MANUFACTURER MODEL NO.
SERIAL NO.
RANGE ACCURACY REPEATABillTY Precision Pressure 56438 Gauges (2)
Paroscientific 760-100-A 56439 0-100 PSIA 101 %F.S.
SEE TABLE Thermistors (30)
Graftel 9202 TWO 32-158o F 0.SoF 10.01 oF SEE TABLE Humidity Sensors Graftel 9203 TWO 30-100% RH 2cF Dew 11% RH Temperature Equivalent Fischer Flowmeter
& Porter 10A35555 R-8405A0348-A1 1.15-11.10 scfm 1111 scfm Level Indicator 555111BCAA LT 1-6468
'GEMAC 3AAA 0-60" H,0
- Used for monitoring purposes only. Leak rates not corrected for changes in vessel level.
TECH 364 6
TABLE TWO SENSOR PHYSICAL LOCATIONS THERMISTER NO.
SERIAL NUMBER SUBVOLUME ELEV./AZIM.
1 0392012-27 1
670'/1800 2
0392012-28 1
670'/ Oo 3
0392012-29 2
657'/ 20o 4
0392012-30 2
657'/197o 5
0392012-01 3
639'/ 70o 6
0392012-02 3
639'/255o 7
0392012-03 11 8
0392012-04 10 578'/350o 9
0392012-05 5
620'/ So 10 0392012-06 5
620'/100o 11 0392012-07 5
620'/220o 12 0392012-08 6
608'/ 40o 13 0392012-09 6
608'/130o 14 0392012-10 6
608'/220o 15 0392012-11 6
608'/310o 16 0392012-12 7
598'/ 70o 17 0392012-13 7
598'/160o 18 0392012-14 7
598'/250o 19 0392012-15 7
598'/340o 20 0392012-16 8
587'/ 10o 21 0392012-17 8
587'/1000 22 0392012-18 8
587'/190o 23 0392012-19 8
587'/280o 24 0392012-20 9
595'/170o 25 0392012-21 9
580'/170o 26 0392012-22 10 578'/ 70o 27 0392012-23 10 578'/140o 28 0392012-24 10 578'/210o 29 0392012-25 10 578'/280o RH SENSORS SERIAL NUMBER SUBV0LUME ELEV./AZIM.
1 0392012-31 1
670'/180o 2
0392012-32 2,3,4 653'/ 20o 3
0392012-33 2,3,4 653'/197o 4
0392012-34 5
620'/ So 5
0392012-35 6
605'/ 40o 6
0392012-36 7
600'/250o 7
0392012-37 8,9 591'/ 10o 8
0392012-38 8,9 591'/190o 9
0392012-39 10 578'/ 70o 10 0392012-40 10 578'/280o Thermistor (Saturated) 0392012-26 11
- See NOTE section A.2.
TECll 3M 7
FIGURE 1 Idealized View of Drywell and Torus Used to Calculate Free Volumes 37'F' y
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A.2.a.-
Temocrature 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 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 100% -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 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.
Pressure 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 One Drywell Pressure-Transmitter, PT l-1624.
Each instrument consists of a standard Paroscientific ' pressure-transducer and a digital interface board in an integral package. The digital board has a microprocessor-controlled counter and RS-232 port.
The microprocessor operating program is stored in permanent memory (EPROM).
User controllable 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 sampling 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 integr'ation 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 the appropriate calculations and loads the data onto the RS-232 bus.
Each pressure transmitter was calibrated from 0 to 100 PSIA by Comed, S.0. A.D. during April and May of 1994.
TECH 364 9
A.2.c.
Vapor Pressure Ten relative humidity sensors were used to determine the partial pressure 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 2oF dew temperature, and are unaffected by most commonly present chemical vapors.
Each RH sensor is mated to the signal conditioning circuitry, A/D 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 assurance that the failure of any one sensor will not result in the failure of the entire string.
A.2.d.
Flow 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 June 14, 1994, to within i1% of full scale using NBS traceable standards, to standard atmospheric conditions.
Plant personnel continuously monitored the flow during the induced leakage phase and corrected any minor deviations from the induced flow rate of 8.5 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.
Type A Test Pressurization 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 an existing four inch fire header penetration, and piped to a temporary spool piece that, when installed, allowed the pressurization of the drywell through the "A" containment spray header.
The inboard, containment spray isolation valve, M0-1-1001-26A was open during pressurization.
Once the containment was pressurized, the M0-1-1001-26A valve was closed and the hoses were disconnected at the fire header penetration.
I I
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1 SECTION 8 - TEST METHOD B.I.
B_asic Technioue a
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, subvulume weighted vapor pressure, and total absolute air pressure.
1 i
TECil 364 1}
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FIGURE 2 I
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OUTSIDE CONTAINMENT INSIDE CONTAINMENT
'mummmme String #1 REPEATER 220 OEM SMART **** SMART CIDLNNEL #1 SENSOR SENSOR i
I 3
3
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} CHANNEL #N
~
SENSOR SENSOR String #N r"1 CONVERTER
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PRESSURE PRRSSURE A/B SWITCEING TRANSMITTER TRANSMITTER BCE
- 1001
- 1002 COMPUTER COMM ICDEM MODEM PORT Tren 364 12
l 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), the measured leak rate was statistically analyzed using the principles outlined in BN-TOP-1, Rev. 1.
A least squares regression line for the measured total time leak rate versus time since the start of the test is calculated after each new data set is scanned.
The calculated leak i
rate at a point in time, t,, is the leak rate on the regression line at the time t,.
The use of a regression line in the BN-TOP-1, Rev. I report is different from the way it is used in the ANSI /ANS 56.8 standard. The latter standard uses the slope of the regression line for dry air mass as a function of time to derive a statistically averaged leak rate. In contrast, BN-TOP-1, Rev. 1 calculates a regression line for the measured leak rate, which is a function of the change in dry air mass.
For the ANS1/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 pr ume 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 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
- r. n Total Time Calculations" attached to the BN-TOP-1, Rev. I top' cal 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 aata computed from the data sets received up until the last time listed on the printout). The calculated leak rate as a function of time (t,) can only be calculated from data available up until that point in time, t,.
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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The distinction between the regression line values and the calculated leak rate as a function of time is made in Section 6.4 of BN-TOP-1, Rev.1. 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.
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).
ncu m 13 l
i
There are teo important conclusions that can be derived from data analyzed using the BN-TOP-1, Rev.1 method:
- 1) the upper confidence limit for the same measured leak rate data can be substantially greater than the value calculated using the ANSI /ANS method, and 2) the upper confidence limit does not converge to the calculated leak rate nearly as quickly as usually observed in_ the latter method as the number of data sets becomes large. With this in mind, the upper confidence limit i
can become the critical parameter for concluding a short duration test, i
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 i
made by referring to Figure 3 for the BN-TOP-1 and in Appendix E for the statistically. averaged leak rate and upper confidence limit based i
on ANSI /ANS 56.8-1981. This data supports the contention of many that l
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 E is provided for information only. The reported test results are based on BN-TOP-1, only.
B.2 Supplemental Verification Test t
The supplemental verification test superimposes a known leak of approximately the same magnitude as L. (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 l
uncertainty associated with measured leak rate phase of the test. The l
allowed error band is 25% of L,.
There are no references to the use of upper confidence limits to 1
evaluate the acceptability of the induced leakage phase of the IPCLRT in the ANS/ ANSI standards.
B.3.
Instrument Error Analysis Instrument error analysis was not performed.
For explanation and l
justification see Appendix C.
j It is extremely important during a short duration test to quickly identify a failed sensor and in real time back the spurious data out of the calculated volume weighted containment temperature and vapor pressure. Failure to do so can cause the upper confidence limit value to place a short duration test in jeopardy. It has been the 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.
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Il SECTION C - SEQUENCE OF. EVENTS C.I.
Test Preparation Chronology
.The pretest preparation phase and containment inspection was completed on July 23, 1994 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 l
4
- 4) Venting of the reactor vessel to the drywell by opening the manual i
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 i
drywell, and associated wiring.
l
- 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.
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C.2.
Test Pressurization and Stabilization Chronoloay DATE TIME EVENT 7-21-94 2155 Began Pressurizing containment.
2300 Snoeping began.
7-22-94 0005 Discovered water leak from the 1-1001-36A, RHR Torus Cooling Return Valve.
0020 Pressurization halted at 18 psig to evaluate 36A valve leak.
0230 Decision made to depressurize containment and repair 36A valve leakage.
0445 Depressurization complete.
7-23-94 1111 Repairs to 36A valve complete. Containment pressurization began.
1240 Began snooping for leaks.
1520 All accessible areas in Reactor Building snooped. No leaks identified.
1740 Pressurization complete.
2240 Containment temperature stable, changing less than 0.5 degrees per hour for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
Reactor water level change less than 1.24 inches per hour for last hour.
Reactor water temperature change less than 2 degrees F per hour for last hour. All stabilization criteria satisfied.
C.3.
Measured Leak Rate Phase Chronology DATE TIME EVENT 7-23-94 2240 Began measured phase.
Base data set #438.
7-24-94 0445 Terminated measured phase at data set #475. Calcul ated leak rate was 0.3003 wt% / day and decreasing over time.
The BN-TOP-1 upper confidence limit was 0.3382 wt%/ day.
C.4.
Induced Leakage Phase Chronology DATE TIME EVENT 7-24-94 0452 Valved in flowmeter at 8.5 SCFM and began induced phase stabilization with base date set #476.
0552 Following the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> stabilization required by BN-TOP-1, the induced phase of t'e test was begun with base date set #482.
0912 Terminated induced phase at data set #490. Calculated leak rate of 1.2491 wt%/ day.
rcen 364 16
C.S.
Depressurization Phase Chronology DATE TIME EVENT 7-24-94 1000 Began depressurization using procedure for venting through the Standby Gas Treatment System.
1400 Depressurization complete.
1800 Test personnel entered containment.
No apparent i
structural damage and instruments still in place.
6 l
l TECII 364
}7 l
SECTION D - TYPE A TEST DATA D.I.
Measured Leak Rate Phase Data A summary of the computed data using the BN-TOP-1, Rev. I test method for a short duration test can be found in Table 3.
Graphic results of the test are found in Figures 3-7.
For comparison purposes only, the statistically averaged leak rate and upper confidence limit using the ANS/ ANSI 56.8-1981 standard are graphed in Figure E-1.
A summary of the computed data using the ANS/ ANSI standard is found in Appendix E.
D.2.
Induced Leakage Phase Data A summary of the computed data for the Induced Leakage Phase of the IPCLRT is found in Table 4.
The calculated leak rate and upper confidence limit using the BN-TOP-1, Rev. 1 method are shown in Figure 7.
Containment conditions during the Induced Leakage Phase are presented graphically in Figures 8-10.
i n cu 364 18
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1 Table 3 - Measured Phase Results QUAD CITIES 1
RDG TIME TT Maas TT Calc TT UCL
%/ day
%/ day
%/ day 438 0.00 0.0000 0.0000 0.0000 439 10.02 0.2360 0.0000 0.0000 440
.20.02 0.3359 0.3359 0.0000 441 30.02 0.3565 0.3697 0.6836 1
442 40.03 0.3120 0.3474 0.6042 443 50.03 0.3304 0.3471 0.5195
)
444 60.03 0.3146 0.3379 0.4796 445 70.05 0.3309 0.3397 0.4569 446 80.05 0.3407 0.3446 0.4453 447 90.07 0.3056 0.3343 0.4311 448 100.07 0.3258 0.3340 0.4219 449 110.07 0.3208 0.3321 0.4135 450 120.08 0.3247 0.3318 0.4075 451 131.08 0.3282 0.3326 0.4036 452 141.08 0.3118 0.3287 0.3969
)
453 151.10 0.3095 0.3251 0.3907 454 161.10 0.3229 0.3252 0.3877 455 171.10 0.3191 0.3245 0.3843 456 181.12 0.3160 0.3233 0.3808 457 191.12 0.3147 0.3221 0.3776 458 201.12 0.3178 0.3216 0.3751 459 211.13 0.3161 0.3209 0.3727 460 221.13 0.3078 0.3188 0.3694 461 231.13 0.3097 0.3174 0.3666 462 241.15 0.3107 0.3163 0.3642 403 251.15 0.3078 0.3150 0.3617 464 261.15 0.3001 0.3127 0.3586 465 271.17 0.3032 0.3111 0.3561 466 281.17 0.3037 0.3098 0.3538 467 291.17 0.3062 0.3089 0.3520 468 301.18 0.3005 0.3075 0.3497 469 311.18 0.3054 0.3068 0.3482 j
470 321.18 0.3013 0.3057 0.3463 471 331.20 0.2989 0.3044 0.3443 472 341.20 0.2944 0.3028 0.3421 473 351.20 0.3013 0.3021 0.3407 474 361.22 0.3020 0.3015 0.3395 475 371.22 0.3003 0.3009 0.3382 Trcli m 19
e Table 4 - Induced Phase Results QUAD CITIES 1
RDG-TIME TT Meas TT Calc TT UCL
%/ day
%/ day
%/ day 482 0.00 0.0000 0.0000 0.0000 483 10.02 1.2087 0.0000 0.0000 484 20.02 1.2081 1.2081 0.0000 485 30.02 1.2777 1.2660 1.5434 486 40.03 1.2835 1.2886 1.3956 487 50.03 1.2246 1.2619 1.4103 488 60.03 1.2416 1.2564 1.3738 489 70.05 1.2408 1.2525 1.3511 490 80.05 1.2437 1.2511 1.3365 491 90.05 1.2454 1.2507 1.3265 492 100.07 1.2419 1.2492 1.3181 493 110.07 1.2426 1.2483 1.3117 494 120.07 1.2550 1.2512 1.3100 495 130.08 1.2479 1.2514 1.3065 496 140.08 1.2325 1.2476 1.3009 497 150.08 1.2373 1.2457 1.2966 498 160.10 1.2373 1.2442 1.2928 499 170.10 1.2413 1.2436 1.2903 500 180.10 1.2320 1.2416 1.2866 501 190.12 1.2355 1.2404 1.2839 502 200.12 1.2337 1.2391 1.2811 Tocn 364 20
y Calculated Total Time Leak & Total Time Leak at UCL
=
QUAD CITIES
- '"'8 1.0 O.9-0.8-0.7-(
\\
0.6-(
g
\\
M
~
i
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0.5-N a
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s O.4 -
~%_
~
4
~.
O.3-0.2-0.1 -
I 0.0 i
O.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 Time - Hours
ngEm
- 0
,6 5
,5 0
,5 5
,4
,0 4
e ru s
5 s
,3 s
e u
r rS o
E H
PT I
IC 0 e e D1
,3 im gA T
U aQ re 5
v
,2 A
,0 2
, 5 1
,0 1
5
,0 0
0 8
6 4
2 0
8 6
4 2
- 0. 0 5
4 4
4 4
4 3
3 3
3 3
6 6
6 6
6 6
6 6
6 6
6 Psg a g:. I jl, l
s 4
a.
4-
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m
- uml FIGURE 5 O
~ d 1
- i
\\
O
~ ui C
~ M Ww0 C
us
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u)
G wb
- n.
f-wO=
z as Eb
>o-4
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(
- W
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o o
o o o co t%
C m
e t
O C
C C
C d
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,2 evA 0
,2
, 5 1
, 0 1
5
,0 0
0 O.
- 0. O 8
7 6
9 9
9 O p N5%
L L
n Calculated Total Time Leak a=
QUAD CITIES
{
1 2.0 E
~*
j d
1.0-a Y
r I
O.O i
O.0 0.3 0.5 0.8 1.0 1.3 1.5 1.8 2.0 2.3 2.5 2.8 3.0 3.3 Time - Hours
2 3
i 3 0
i 3 8
i 2 5
i 2 3
e i 2 r
u ta 0
r 2
e s
p ru mS
. 8. Ho E
1 I
eT e
I TC m
i D1 eU i 5. T A
1 gQ a
re i 3 1
v A
0 1
8 0
5 0
3 0
0 0
0 0
0 0 0 7
6 5
4 3
6 8
6 6
6 9
9 9
9 9
o p gy l
l
i-1l 1,g 3
k 0
3 8
5 e
3 r
u sse O.
k r
P s
r r
u oS
- 8. H o
1 E
pT I
e aC m
I i
V D1
- 5. T A
1 U
eG g
L a
3 r
1 evA 0
1 8
0 5
0 3
0 0
N-0 5
4 3
2 1
0 9
8 7
6 5
4 4
4 4
4 4
3 3
3 3
3 6
6 6
6 6
6 6
6 6
6 6
0 0
O 0
0 0
0 0
0 0
0 S; a 5y m%
ll l1lf'
g:c n
3 3
,0 3
8
,2 5
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r 0
u
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u PT
, 8. Ho rS E 1
I I
e C
m e D1 aQ
, 5. Ti gA U
1 revA
, 3 1
,0 1
8
,0 5
,0 3
,0 0
0 7
4 F
8 5
2 9
6 3
0 0 9
8 6
8 7
7 7
6 6
6 6
3 3
3 3
3 3
3 3
3 3
3 6
6 6
6 6
6 6
6 6
6 6
P 8
g rm o
- 4. 5 {
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.
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 <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> required by Quad Cities procedure and actual stabilization:
4 hrs, 19 min).
The atmosphere is considered stabilized when:
- 1. The rate of change of average temperature is less than 1.0oF/ hour averaged over the last two hours.
DATA SET
- AVE. CONTAINMENT TEMP.
AI 438 97.915 432 98.208 0.293 426 98.531 0.323 average 0.308oF/ hour
- Approximate time interval between data sets is 10 minutes.
or
- 2. "The rate of change of temperature changes less than 0.5oF/ 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 (L,)...".
By Quad Cities procedure the calculated leak rate must be less than 0.75 L.
The actual value was 0.3003 L,, 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 than 0.75 L,.
The actual value was 0.3382 L,.
and TncH 364 29
- 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 L,.
The actual value was 0.3115 L, 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.
and
- 5. "At least twenty (20) data points shall be provided for proper statistical analysis."
There were 37 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 duration 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.
TncH 39 30
~
SECTION F - TYPE A TEST RESULTS 1
F.1 Measured leak Rate Test Results Based on the data obtained during the short duration test, the following results were determined:
(L, - 1.0 wt %/ day)
- 1) Calculated leak rate equals 0.3003 wt %/ day and declining steadily over time (<0.7500 wt %/ day).
l
- 2) Upper confidence limit equals 0.3382 wt %/ day and declining (<.750 wt
%/ day).
L
- 3) Mean of the measured leak rates for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (31 data sets) equals 0.3115 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 37 data sets accumulated in hour measured phase.
- 6) The minimum test duration (by procedure) of 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> was successfully accomplished (> 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />).
F.2 Induced Leakage Test Results A leak rate of 8.5 scfm (1.0147) wt %/ day) was induced on the primary containment for this phase of the test. The leak rates during this phase-l of the test were as follows.
i BN-TOP-1 Calculated Leak Rate 0.3003 0.3003 (Measured Leak Rate Phase)
Induced Leak (8.5 scfm)'
1.0147 1.0147-Allowed Error Band
+0.2500 -0.2500' 1.565 1.065 BN-TOP-1 Calculated Leak Rate 1.2391 wt %/ day (Induced Leak Rate Phase)
The induced phase of the test has duration criteria given in Section 2.3.C l
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)
- 2. The verification test duration shall be approximately equal to half the integrated leak rate test duration.
(actual: 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, 20 minutes for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, 12 minute test)
- 3. Results of this verification test shall be acceptable provided the i
correlation between the verification test data and the integrated leak rate test data demonstrate an agreement within plus or minus 25 percent.
(actual:
see results above) r Tccu 364 31 i
?
m
~
l F.3 Pre-Operational Results vs Test Results 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 i
been no substantial deterioration in containment integrity.
TEST DURATION CALCULATED LEAK RATE STATISTICALLY AVE.
TEST DATE (HOURS)
(BN-TOP-1)
LEAK RATE (ANSI /ANS)
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 July 1994 6
0.3003 F.4 TYPE A TEST PENALTIES During the type A test, there were a number of systems that were not drained and vented outside the 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 MINIMUM PATHWAY LEAKAGE SCFH WT%/ DAY Shutdown Cooling Suction 1.2 0.00245 Primary Sample 0.3 0.00061 A & B Feedwater 2.8 0.00571 TIPS 5.1 0.01041 RHR A 10.35 0.02112 RHR B 0.4 0.00081 SBLC 1.2 0.00243 RWCU 1.59 0.00325 Core Spray 1.6 0.00326 HPCI (Steam Exhaust) 0.1 0.00020 RBCCW 5.0 0.01021 Clean Demin 1.3 0.00265 0, Analyzer 1.45 0.00296 CAMS 0.83 0.00169 ACAD 1.1 0.00225 Totals 34.32 0.07001 This penalty increases the type A test result to 0.3703 wt%/ day with an upper confidence limit of 0.4082 wt%/ day.
TEcu m 32
c F.5 EVALUATION OF INSTRUMENT FAILURES There were no instrument failures during the test.
F.6 AS FOUND TYPE A TEST RESULTS The following table summarizes the results of all type B and C testing, as well as the IPCLRT results to arrive at an "As Found" type A test result.
This is considered a passing "As Found" type A test, making two consecutive passing "As Found" tests on Unit One.
Due to a Tech Spec exemption relating to bellows testing, the Station is required to maintain the current schedule of performing an ILRT every refuel outage.
SUMMARY
OF ALL CONTAINMENT LEAK RATE TESTING DURING UNIT TWO REFUEL OUTAGE SPRING. 1992 AS FOUND (SCFH)
AS LEFT (SCFH)
MINIMUM PATHWAY MINIMUM PATHWAY LEAKAGE LEAKAGE (1)
MSIV's @ 25 PSIG 9.22 6.62 (2)
MSIV's converted 15.95 11.45 to 48 PSIG*
(3)
All Type C Tests 117.08 57.87 (Except MSIV's)
(4)
All Type B Tests 58.51 33.08 TOTAL (2 + 3 + 4) 191.54 102.4 (1)
Type A Test Integrated Leak Rate Test)
= 0.3003 wt %/ day (2)
Upper Confidence Limit of Type A Test Result
= 0.3382 wt %/ day (3)
Correction for Unvented Volumes During Type A Test = 0.0700 wt %/ day (4)
Correction for Repairs Prior to Type A Test
= 0.2086 wt%/ day (As Found - As Left)
Total (2 + 3 + 4)
= 0.6168 wt%/ day Leak Rate at 25 PSIG converts to Leak Rate at 48 PSIG using conversion ratio of 1.73.
REFERENCE Leaking Characteristics of Steel Containment Vessels & the Analysis of Leakage Rate Determination, Division of Safety Standards, A.E.C. TID-20583, May 1964, pg. 76.
Tr.cn 39 33
l i
APPENDIX A TYPE 8 AND C TESTS Presented herein are the results of local leak rate tests conducted on all penetrations, double-gasketed seals, and isolation valves since the previous IPCLRT.
Total leakage for double gasketed seals and total leakage for all penetrations and isolation valves following repairs satisfied the Technical Specification limits.
Toen 364 34
OCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 1 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
LLRT COORDINATOR Mo-kd d, Q4 nATE: 8-U-@
'/ f/ </(/
OUTAGE lQlR13 l
UNIT OPERATING ENGINEER :
//[7M,//
S DATE:
SYSTEM ENGINEERING SUPERVISOR :
' bt ([ib C DATE: 8-Il-94 gg g $qmmc 9 AUTHORIZED NUCLEAR INSERVICE INSPECTOR :
A O A ELEV (L och DATE: 6 tt- %
AS FOUND (SCFH) AT 25 PSIG AS LEET (SCFH) AT 25 PSIG DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY FATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY A
MSIV (2)
AO 203-1A 3/13/94 15.85 6/23/94 combined AO 203-2A 3/14/94 0.35 0.35 15.85 6/23/94 0.57 0.29 0.57 B
MSIV (2)
AO 203-1B 3/13/94 combined 6/9/94 combined AO 203-2B 3/13/94 5.74 2.87 5.74 6/9/94 5.46 2.73 5.46 C
MSIV (2)
AO 203-1C 3/13/94 combined 6/3/94 combined AO 203-2C 3/13/94 8.8 4.4 8.8 6/3/94 0
0 0
D MSIV (2)
AO 203-1D 3/13/94 combined 5/24/94 combined l AO 203-2D 3/13/94 3.2 1.6 3.2 5/24/94 7.2 3.6 7.2 TOTAL 9.22 33.59 TOTAL 6.62 13.23
- CORRECTED "'OTAL 15.9506 58.1107
- CORRECTED TOTAL 11.4526 22.8879 9/T94
% Bfk %
V 8/II/M Bllhi
- To determine the corrected leakage of MSIVs (as if they had been tested t 48 psig), mu iply the 25 psig tota by 1.73.
.~
1
- - - ~
w
- - < ~
.a
~
a r-
a OCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 2 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH) i DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE-LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY MSL DRAIN (2)
MO 220-1 3/13/94 6.4 3/13/94 6.4 MO 220-2 3/14/94 0.6 0.6 6.4 3/14/94 0.6 0.6 6.4 PRIMARY SAMPLE (2)
AO 220-44 5/12/94 combined 5/12/94 AO 220-45 5/12/94 0.6 0.3 0.6 5/12/94 0.6 0.3 0.6 A'
FEEDWATER (2)
CK 220-58A 4/28/94 0.7 4/28/94 0.7 CK 220-62A 4/28/94 1.8 0.7 1.8 4/28/94 1.8 0.7 1.8 B
FEEDWATER (2)
CK 220-58B 3/17/94 5/9/94 2.1 CK 220-62B 3/17/94 0.7 0.7 monwn.d 6/1/94 6
2.1 6
Reactor Vessel Level CK - 263-944A N/A new installation 7/14/94 0.4 Instrumentation System CK 263-945A N/A new installation 7/14/94 0.4 0.4 0.4 (RVLIS)
(2)
CK 263-944B N/A new installation 7/15/94 0.4 CK 263-945B N/A new installation 7/18/94 0.4 0.4 0.4 CK 263-947A N/A new installation 7/14/94 0.4 CK 263-948A N/A new installation 7/14/94 0.4 0.4 0.4 CK 263-947B N/A new installation 7/15/94 0.4 CK 263-948B N/A new installation 7/15/94 0.4 0.4 0.4 PAGE TOTAL l
2.3 8.8 g PAGE TOTAL 5.3 16.4 o
w==% - oom wM m a 7 to-5%, Twe. w. Pmmsest
% tat _ RE FWt_w Twg QoAMsa4te. %%4, ON. AC TV AL Tbh LEA 1t AQ W JMDCitttA wgb
- - -a
OCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 3 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE-LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY TIP BALL VALVES (1)
SO 737-1B 3/21/94 0
0 0
3/21/94 0
0 0
SO 737-1C 3/21/94 0.2 0.2 0.2 3/21/94 0.2 0.2 0.2 SO 737-1D 3/21/94 0.6 0.6 0.6 3/21/94 0.6 0.6 0.6 SO 737-1E 3/21/94 0.3 0.3 0.3 3/21/94 0.3 0.3 0.3 SO 737-1F 3/21/94 0.3 0.3 0.3 3/21/94 0.3 0.3 0.3 TIP PURGE CHECK VALVE (1)
CK 743 3/21/94 3.7 3.7 3.7 3/21/94 3.7 3.7 3.7 A
DRYWELL SPRAY (2)
MO 1001-23A 4/13/94 4.5 6/9/94 combined MO 1001-26A 4/13/94 5.5 4.5 5.5 6/9/94 8.5 4.25 8.5 B
DRYWELL SPRAY (2)
MO 1001-23B 4/13/94 0
4/13/94 0
MO 1001-26B 4/13/94 3.9 0
3.9 4/13/94 3.9 0
3.9 A
RHR RETURN (1)
MO 1001-29A 5/1/94 6
6 6
5/1/94 6
6 6
B RHR RETURN (1)
MO 1001-29B 5/1/94 5
5 5
6/6/94 0.4 0.4 0.4 A TORUS COOLING SPRAY (12)
MO 1001-34A 5/4/94 1
7/20/94 combined MO 1001-36A
-3/21/94 combined 7/20/94 combined MO 1001-37A 3/21/94 2.2 1
2.2 7/20/94 0.3 0.15 0.3 PAGE TOTAL 21.6 27.7 PAGE TOTAL 15.9 24.2 h
a
GCYP 130-1 (CGE)
UNIT 1(2)
REVISION 1 3
ATTACHMENT C (Page 4 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
l AS FOUND (SCFH)
AS LEFT (SCFH) l DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY B TORUS COOLING SPRAY (12)
MO 1001-34B 5/4/94 m. min.d 7/15/94 0.1 I
MO 1001-36B 3/17/94 combined 7/16/94 cembined MO 1001-37B 3/17/94 43 43 unne
=n.d 7/16/94 0
0 0.1 SHUTDOWN COOLING (2)
MO 1001-47 4/10/94 3.8 6/16/94 1.2 l
MO 1001-50 4/10/94 0.8 0.8 3.8 6/16/94 8.2 1.2 8.2 SBLC (2)
CK 1101-15 4/26/94 8
6/7/94 1.2 CK 1101-16 4/26/94 une. an.d 8 une non.e 6/9/94 2.9 1.2 2.9 CLEAN UP SUCTION (2)
MO 1201-2 3/23/94 anom. man.a 4/26/94 combined MO 1201-5 3/24/94 3.8 3.8 m.iwn.e 4/26/94 3.18 1.59 3.18 RCIC STEAM SUPPLY (2)
MO 1301-16 3/13/94 combined 7/9/94 combined MO 1301-17 3/13/94 0.4 0.2 0.4 7/9/94 0
0 0
RCIC VACUUM PUMP EXHAUST (1)
CK 1301-40 3/15/94 0.5 0.5 0.5 3/29/94 0.4 0.4 0.4 RCIC STEAM EXHAUST (1)
CK 1301-41 3/19/94 0.5 0.5 0.5 3/29/94 4
4 4
A CORE SPRAY (2)
MO 1402-24A 3/16/94 combined 3/16/94 combined MO 1402-25A 3/16/94 0
0 0
3/16/94 0
0 0
B CORE SPRAY (2)
MO 1402-24B 4/8/94 1.6 4/8/94 1.6 MO 1402-25B 4/8/91 2
1.6 2
7/31/94 0.3 0.3 1.6 PAGE TOTAL 58.4 7.2 7 PAGE TOTAL 8.69 20.38
$ ~6ue 70 0Jbe" tee-esaet mmCc usoc.tami w ww Twe no - soos - 343, tg.- i to t-do Ab Mb-tLH-t 3 TtW @'x. 7AOtW % Mt. M LE't_% OPbM M 4AWh hale LEArV.%E. Actuen_. TCfD'h CoJAb NOT f6%. h%4 i
__m___._
QCTP 130-1 (CGE)
UNIT 1(2)
REVislON 1 ATTACHMENT C (Page 5 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY A TORUS / REACTOR BUILDING AO 1601-20A 3/19/94 1.1 3/19/94 1.1 VACUUM BREAKER (2)
CK 1601-31A 3/19/94 0.3 0.3 1.1 3/19/94 0.3 0.3 1.1 B TORUS / REACTOR BUILDING AO 1601-20B 3/19/94 0
3/19/94 0
VACUUM BREAKER (2)
CK 0601-31B 3/19/94 1.4 0
1.4 3/19/94 1.4 0
1.4 DRYWELL / TORUS AO 1601-21 3/18/94 0
3/18/94 0
PURGE SUPPLY (3)
AO 1601-56 3/18/94 0
3/18/94 0
AO 1601-22, 55 3/18/94 1.6 0
1.6 3/18/94 1.6 0
1.6 DRYWELL / TORUS AO 1601-23, 62 3/16/94 2.1 3/16/94 2.1 PURGE EXHAUST (4)
AO 1601-60, 61 3/15/94 12 3/15/94 12 AO 1601-24, 63 3/16/94 9.5 9.5 14.1 3/16/94 9.5 9.5 14.1 DRYWELL / TORUS MO 1601-57 3/18/94 combined 5/26/94 combined NITROGEN PURGE (5)
RV 1699-9 3/18/94 une.m 5/26/94 2.6 AO 1601-58 3/18/94 2
3/18/94 2
AO 1601-59 3/18/94 0
2 unen. men.4 3/18/94 0
2 2.6 PAGE TOTAL 11.8 18.2 @
PAGE TOTAL 11.8 20.8 wh M BJJ-1 Mo) *)g M @% 9ermwg %To t._
r ftECt.Et.% @q M 40A*Jh9 i A4LE urvW6GE,
htt"V A % %meAY. %e. c.c42 4Ur M D E~~TE8Lo^ $ 4 D.
OCTP 130-1 (CGE)
UNIT 112)
REVISION 1 ATTACHMENT C (Page 6 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND'(SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY DRYWELL FLOOR DRAIN -
AO 2001-3 4/28/94 0.4 4/28/94 0.4 SUMP (2)
AO 2001-4 4/28/94 0.4 0.4 0.4 4/28/94 0.4 0.4 0.4 DRYWELL EQUIPMENT -
AO 2001-15 3/23/94 combined 3/23/94 combined DRAIN SUMP (2)
AO 2001-16 3/23/94 1.3 0.65 1.3 3/23/94 1.3 0.65 1.3 HPCI STEAM SUPPLY C1 MO 2301-4 3/13/94 combined 7/10/94 1
MO 2301-5 3/13/94 5
2.5 5
7/16/94 0
0 1
CK 2301-34 3/15/94 0.5 0.5 0.5 3/29/94 2.5 2.5 2.5 HPCI EXHAUST -
MO 2399-40 3/13/94 0.35 3/13/94 0.35 VACUUM BREAKERS (2)
MO 2399-41 3/13/94 0.1 0.1 0.35 3/13/94 0.1 0.1 0.35 SO 2499-1A 3/18/94 combined 3/18/94 combined SO 2499-2A 3/18/94 0
0 0
3/18/94 0
0 0
SO -2499-3A 3/22/94 combined 3/22/94 combined CONTAINMENT AIR MONITOR SO 2499-4A 3/22/94 0
0 0
3/22/94 0
0 0
SYSTEM (CAM)
(2)
SO 2499-1B 3/18/94 combined 3/18/94 combined 50 2499-2B 3/18/94 1.45 0.73 1.45 3/18/94 1.45 d.73 1.45 SO 2499-3B 3/22/94 combined 3/22/94 combkwd SO 2499-4B i
3/22/94 0
0 0
3/22/94 0
0 0
PAGE TOTAL 4.88 9
PAGE TOTAL 4.38 7
.~
QCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 7 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY CONTAINMENT AIR MONITOR PNL 2251(2)-81A 3/21/94 combined 7/15/94 0.9 SYSTEM (CAM)
(11)
A - Inlet lines 3/21/94 8
3/21/94 8
CK 2499-22A 3/21/94 0
0 8
7/15/94 0.05 0.05 8.9 PNL 2251 (2 )-81B 3/21/94 combined 7/20/94 0.05 B-Inlet lines 3/21/94 4.8 3/21/94 4.8 CK 2499-22B 3/21/94 0.1 0.1 4.8 7/20/94 0.1 0.1 4.85 AO 2599-2A 3/23/94 combined 3/23/94 combined CK 2599-23A 3/23/94 0.5 0.25 0.5 3/23/94 0.5 0.25 0.5 AO 2599-3A 3/14/94 combined 3/14/94 combined ATMOSPHERIC CONTAINMENT CK 2599-24A 3/14/94 0.1 0.05 0.1 3/14/94 0.1 0.05 0.1 ATMOSPHERE DILUTION AO 2599-2B 3/23/94 0.5 3/23/94 0.5 SYSTEM (ACAD)
(2)
CK 2599-23B 3/23/94 6.9 0.5 6.9 3/23/94 6.9 0.5 6.9 AO 2599-3B 3/14/94 combined 3/14/94 combined CK 2599-24B 3/14/94 0.6 0.3 0.6 3/14/94 0.6 0.3 0.6 AO 2599-4A 3/16/94 0
3/16/94 0
AO 2599-5A 3/16/94 0
0 0
3/16/94 0
0 0
AO 2599-4B3, 3/16/94 0
3/16/94 0
AO 2599-5B 3/16/94 0.6 0
0.6 3/16/94 0.6 0
0.6 PAGE TOTAL 1.2 21.5 PAGE TOTAL 1.25 22.45 m.
OCTP 130-1 (CGE)
UNIT 1(2)
REVislON 1
~-
i ATTACHMENT C (Page 8 of 14) i REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
1 AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY RBCCW SUPPLY (2)
MO 3702 5/3/94 6
7/21/94 1.5 CK 3799-31 5/3/94 6
6 6
5/3/94 6
1.5 6
RBCCW RETURN (2)
MO 3703 5/3/94 4
7/21/94 7
MO-3706 5/3/94 17 4
17 7/22/94 3.5 3.5 7
CLEAN DEMIN WATER (2)
MNL 4399-45 4/22/94 1.3 4/22/94 1.3 CK 4399-46 4/4/94 www.nve=4 1.3 unen.rn*=4 4/22/94 2.3 1.3 2.3 SERVICE AIR (2)
MNL 4699-46 4/22/94 2.3 4/22/94 2.3 CK 4699-47 4/22/94 1
1 2.3 4/22/94 1
1 2.3 DRYWELL PNEUMATIC (2)
AO 4720 3/24/94 0
3/24/94 0
AO 4721 3/24/94 0.1 0
0.1 3/24/94 0.1 0
0.1 DRYWELL INSTRUMENT AIR (2)
CK 4799-155 4/22/94 3
4/22/94 3
CK 4799-156 4/22/94 0
0 3
4/22/94 0
0 3
TORUS INSTRUMENT AIR (2)
CK 4799-158 3/15/94 0
3/15/94 0
CK 4799-159 3/15/94 0
0 0
3/15/94 0
0 0
PAGE TOTAL 12.3 28.4 7 PAGE TOTAL 7.3 20.7 we Tuct-%%-g T%ime w w m WTott Q&hert T. S oNCf TwE QuAerT*sAaut WWE AC.T. OM _ Toh t Wa v:.A 6E Coot.J) v At:rt Be D N teJED.
r
.4
,.-.--,-....-..-.,..-.w%,.
w w-
- =
4--v..
.a-
,..r
QCYP 130-1 (CGE)
UNIT 112)
REVis10N 1 ATTACHMENT C (Page 9 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY SRM / IRM PURGE (2)
CK 4799-353 NA NA NA NA (UNIT 2 ONLY)
CK 4799-354 NA NA NA NA NA NA NA NA AO 8801A 4/27/94 0
4/27/94 0
AO 8802A 4/27/94 0.5 0
0.5 4/27/94 0.5 0
0.5 AO 8801B 4/27/94 0
4/27/94 0
OXYGEN ANALYZER (2)
AO 8802B 4/27/94 2.7 0
2.7 4/27/94 2.7 0
2.7 AO 8801C 4/27/94 1
4/27/94 1
AO 8802C 4/27/94 1
1 1
4/27/94 1
1 1
AO 8801D 3/22/94 0.5 3/22/94 0.5 AO 8802D 3/22/94 0.2 0.2 0.5 3/22/94 0.2 0.2 0.5 AO 8803 3/17/94 1.6 3/17/94 1.6 AO 8804 3/17/94 2.1 1.6 2.1 7/15/94 0.25 0.25 1.6 DRYWELL PARTICULATE Manua1 valves erre m er ow.m SAMPLE LINES (21 LINES) 1(2)-8800-2/3B-V 3/22/94 *we 1.8 3.6 3/22/94 ww 1.8 3.6 1(2) 8803B-1/2-H (6)
PAGE TOTAL 4.6 10.4 PAGE TOTAL 3.25 9.9 1
,,,-.m,.
,.,-e,
. - - +
w
2----
2-A
QCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 10 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUsrD (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
' MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY j
SL-1 5/27/94 4.6 2.3 4.6 5/27/94 4.6 2.3 4.6 SL-2 5/27/94 4.3 2.15 4.3 5/27/94 4.3 2.15 4.3 SL-3 5/27/94 4.4 2.2 4.4 5/27/94 4.4 2.2 4.4 SHEAR LUG INSPECTION SL-4 5/27/94 4.6 2.3 4.6 5/27/94 4.6 2.3 4.6 HATCHES (2)
SL-5 5/27/94 4.4 2.2 4.4 5/27/94 4.4 2.2 4.4 SL-6 5/27/94 4.4 2.2 4.4 5/27/94 4.4 2.2 4.4 SL-7 5/27/94 4.3 2.15 4.3 5/27/94 4.3 2.15 4.3 4
SL-8 5/27/94 6
3 6
5/27/94 6
3 6
DRYWELL EQUIPMENT HATCH (2)
X-1 3/13/94 0
0 0
5/21/94 0.4 0.2 0.4 DRYWELL PERSONNEL INTRLCK(2)
X-2 3/12/94 0
0 0
7/21/94 6.183 3.09 6.183 DRYWELL ACCESS HATCH (2)
X-4 4/7/94 0
0 0
4/7/94 0
0 0
CRD HATCH (2)
X-6 3/13/94 0
0 0
7/19/94 0.4 0.2 0.4 X-35A 3/24/94 0
0 0
3/24/94 0
0 0
X-35B 3/24/94 0.5 0.25 0.5 3/24/94 0.5 0.25 0.5 TIP PENETRATIONS (2)
X-35C 3/24/94 0.4 0.2 0.4 3/24/94 0.4 0.2 0.4 X-35D 3/24/94 0.1 0.05 0.1 3/24/94 0.1 0.05 0.1 X-35E 3/24/94 0.2 0.1 0.2 3/24/94 0.2 0.1 0.2 X-35F 3/24/94 0.1 0.05 0.1 3/24/94 0.1 0.05 0.1 X-35G 3/24/94 0.1 0.05 0.1 3/24/94 0.1 0.05 0.1 DRYWELL HEAD (2)
Drywell Head 3/13/94 1.3 0.65 1.3 7/21/94 0.85 0.43 0.85 PAGE TOTAL 19.85 39.7 PAGE TOTAL 23.12 46.233 i
IJ m
-~.
-v
,, ~,
QCTP 130-1 (CGEl UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 11 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY X-7A 3/13/94 0
0 0
3/13/94 0
0 0
X-7B 3/31/94 0
0 0
3/31/94 0
0 0
X-7C 3/13/94 1.5 0.75 1.5 3/13/94 0
0 0
X-7D 3/13/94 1
0.5 1
3/13/94 0
0 0
X-8 3/13/94 0.6 0.3 0.6 3/13/94 0.1 0.05 0.1 X-9A 3/13/94 0.4 0.2 0.4 3/13/94 0.4 0.2 0.4 X-9B 3/13/94 0.4 0.2 0.4 3/13/94 0.4 0.2
-0.4 X-10 3/13/94 0.1 0.05 0.1 3/13/94 0.1 0.05 0.1 MECHANICAL X-11 3/13/94 0
0 0
3/13/94 0
0 0
(BELLOWS)
X-12 3/13/94 0.4 0.2 0.4 3/13/94 0.4 0.2 0.4 PENETRATIONS (7)
X-13A 3/13/94 0.2 0.1 0.2 3/13/94 0.2 0.1 0.2 X-13B 3/13/94 0.5 0.25 0.5 3/13/94 0.1 0.05 0.1 X-14 3/13/94 1.1 0.55 1.1 3/13/94 0.1 0.05 0.1 X-16A 3/13/94 0
0 0
3/13/94 0
0 0
X-16B 3/13/94 0.1 0.05 0.1 3/13/94 0.1 0.05 0.1 X-23 3/13/94 4.5 2.25 4.5 5/12/94 0.3 0.3 0.3 X-24 3/13/94 0
0 0
3/13/94 O
O O
~
X-25 3/16/94 0.5 0.5 0.5 3/16/94 0.5 0.5 0.5 X-26 3/18/94 0
0 0
3/18/94 0
0 0
X-47 3/13/94 0.4 0.2 0.4 3/13/94 0.4 0.2 0.4 PAGE TOTAL 6.1 11.7 PAGE TOTAL 1.95 3.1
.. =. -. - - - - - -. - - - -...
QCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 12 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY X-100A 4/5/94 3
1.5 3
4/5/94 3
1.5 3
X-100B 4/7/94 0
0 0
4/7/94 0
0 0
X-100C 3/25/94 0
0 0
3/25/94 0
0 0
X-100D (U-1) 3/25/94 1 ')
0.5 1
3/25/94 1
0.5 1
X-100E 3/30/94 0.5 0.25 0.5 3/30/94 0.5 0.25 0.5 ELECTRICAL PENETRATIONS (2)
X-100F 4/7/94 0
0 0
4/7/94 0
0 0
X-100G 4/7/94 0
0 0
4/7/94 0
0 0
X-10LA 3/25/94 4
2 4
3/25/94 4
2 4
X-101B 3/25/94 0
0 0
3/25/94 0
0 0
X-101D 3/31/94 0
0 0
3/31/94 0
0 0
X-102A (U-1) 3/25/94 1.1 0.55 1.1 3/25/94 1.1 0.55 1.1 X-102B 4/7/94 0
0 0
4/7/94 0
0 0
PAGE TOTAL 4.8 9.6 PAGE TOTAL 4.8 9.6
QCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1-ATTACHMENT C (Page 13 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM NINIMUM MAXIMUM PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY X-103 3/25/94 0.61 0.31 0.61 3/25/94 0.61 0.31 0.61 X-104A (U-2)
NA NA NA NA NA NA NA NA X-104B 4/5/94 1
0.5 1
4/5/94 1
0.5 1
X-104C 3/25/94 0
0 0
3/25/94 0
0 0
X-104D (U-2)
NA NA NA NA NA NA NA NA ELECTRICAL PENETRATIONS (2)
X-104F 4/7/94 0.1 0.05 0.1 4/7/94 0.1 0.05 0.1 X-105A 4/7/94 0.1 0.05 0.1 4/7/94 0.1 0.05 0.1 X-105B (U-1) 3/30/94 0
0' O
3/30/94 0
0 0
X-105C 3/30/94 2.6 1.3 2.6 3/30/94 2.6 1.3 2.6 X-105D (U-2) 3/31/94 0
0 0
3/31/94 0
0 0
X-106A (U-2)
NA NA NA NA NA NA NA NA X-106B (U-2)
NA NA NA l
NA NA NA NA NA X-107A 3/30/94 1
0.5 1
1 3/30/94 1
0.5 1
X-107B (U-2)
NA NA NA NA NA NA NA NA PAGE TOTAL 2.71 i
5.41 PAGE TOTAL 2.71 5.41
~
4 1
~
~
r--ma-
-c w'v e
~ < ~ ~
s.-
QCTP 130-1 (CGE)
UNIT 1(2)
REVISION 1 ATTACHMENT C (Page 14 of 14)
REFUEL OUTAGE LOCAL LEAK RATE TEST
SUMMARY
i-AS FOUND (SCFH)
AS LEFT (SCFH)
DESCRIPTION VALVE /
MINIMUM MAXIMUM MINIMUM MAXIMUM a
PENETRATION TEST DATE LEAKAGE PATHWAY PATHWAY TEST DATE LEAKAGE PATHWAY PATHWAY I
NORTH TORUS HATCH (2)
X-200A 3/13/94 0
0 0
7/21/94 0.5 0.25 0.5 SOUTH TORUS HATCH (2)
X-200B 3/13/94 0
0 0
7/21/94 0.4 0.2 0.4 TORUS CAM / ACAD -
X-227A 3/14/94 0
0
-0 3/14/94 0
0 0
PENETRATIONS (2)
X-227B 3/14/94 0.1 0.05 0.1 3/14/94 0.1 0.05 0.1 A TORUS LEVEL FLANGE (1) 1641-5A 3/16/94 0
0 0
3/16/94 0
0 0
B TORUS LEVEL FLANGE (1) 1641-5B 3/16/94 25 25 25 4/14/94 0
0 0
PAGE TOTAL 25.05 25.1 PAGE TOTAL 0.5 1
(9) (10)
TEST TOTAL (8) l 175.59l 222.71lg l
90.95l207.173]
(1) Single Pethway - The min /mex pathe are both ecuel to the leakage rete i'
(2) Duel Pathway - For indrwidual leakage retoe the min /mex pathe are the lesser / greater of the two leakage rates, for a combined lenkege rate the min path is 1/2 the leakage rate and the max path is equel to the leakage rete.
(3) The MNPLR/MXPLR is the lesser / greater combined leekege value of 1801-21, 56 or 1801-22, 55.
(4) The MNPLR/MXPLR is the lesser / greater combined leakage value of 1601-24. 63 or 1601-23,62. 60 and 61 (51 The MNPLR/MXPLR is the lesser / greater of the combined leakege of 1801-58,59 or 1801-57 and RV 1899-9.
l (6b The rnen path is e5 the lesser *.eekagea of each line added together, the max path le all the greater leakages of each line added together. See the specific test report l.
for the individual leakages.
l (7) The min /mex path le calculated by notee (1) or (2) above depending on specific test pmcedure.
l (8) The test total is the sum of all page totele in the summary texcluding MSIV test totet). (T.S.)
(9) When the maximum pathway leakage exceede 0.6 La (2g3.75 SCFH1, wdte a PtF immediately. (T.S.)
l (10) As left max path must be less than or equel to 220.31 prior to etert-up (NRC commitment IN 50-254(265)/89024).
(11) The MNPLR/MXPLR is the lesser / greater combined leakege value of CK 2499-22A/B or PNL 2251(2)-81 A/B and A/8-Inlet Enes.
l (12) The MNPLR/MXPLR le the lesser / greater of the combined leekoge value of 100136A/B. 37A/8, or 1001-34A/S. If the leakage for the three velves is combined then the MNPLR le l
1/2 the leakage rate end the MXPLR is equel to the leakege rete.
(
I tarry TwE As-Fou"> TEEL 3, Titt Awn. #1W PATW'4h'Y l
TDTAt /?.gFcat25 WLv n+t a 0A*/N #te et.*r u74x4dE.
r l
...... - - -... tn
~
PROCEDURE: QAP 200-19 QAP 200-T4 Revision 3 VERBAL APPROVAL TRACKING FORM June 1991 l
DOCUMENT:
Temporary Procedurn No.
Maint/ Modification Rev.
Work Request No.,,_
Other Q C.r? tw-t "It es SumtnN2 Y "
Performed By vaih x l
N.
Contact Approval Section:
Person Contacted:
h Ace CA.vLt=v (7 tom Comments:
G Avc A9tr App /t.MW To b oe v%wr Date e/n /94 Time i 3: 2.0 Performed By: '
Wdy l
Person Contacted:
Comments:
Date Time Performed By:
l Person Contacted:
Comments:
Date Time Performed By:
l Person Contacted:
Comments:
Date Time Performed By:
l Person Contacted:
Comments:
Date Time Performed By:
l Person Contacted:
Comments:
Date Time Performed By:
l (final)
APPROVED M l 6 199) 18/0641a Q.C.O.S.R.
_-J,-
APPENDIX B COMPUTATIONAL PROCEDURE l
i ucn m 50
D. INPUT PRDCISSING.
Calculations perfomed by the software are outlined below:
D.)
Average temperature of subvolume #1 (7 )
t
. The average of all ATD temps in subwolume si i
N Ti.-
r T,3 i
m j.
where N. The number of RTDs in subwolume #1 D.7 Average dew temperature of subvolume #1 (D )i
. The average of all des cell der temps in subvolume si 1
N ct. -
r oi,3 N
31 where N - The number of RTDs in subwolume #1 D.J Total corrected pressure #1. (P )
I C;
First correction factor for raw pressure #1. (from program i
initialiation data met).
Mi Second correction factor for raw pressure #1. (from program
- initialintion data set).
Pri Raw pressure #1 from RIFFIM.
P1.C1.M1 Pri/1000, for 5 digit pressure transmitters Pi.C1.Mt Pri/10000, for 5 digit press $rre~tr$nsmitters
~
D.4 Total corrected pressure #2 (P )
2 C2 First correction factor for raw pfessure s2. (from program initiallation data set.
M2 Second correction factor for raw pressure F2 (from program initialtution data set.
Pr2 Raw pressure EZ, from ElFFIE.
2*C*M2 Pr2/1000, for 5 digit pressure transmitters P
2 2*C*M2 Pr2/10000, for 5 digit pressure transmitters P
2 um.
005 Wncle Containeen2 Volume Heighted Average Temperature. (T )
c Accrorisate N
Mernoc Te,-
I fl Tj 11 1
Exact N
fl Method I
11 It f. The volume fraction of the ith suivolume where:
iN. The total # of subvolumes in containment 0.6 Average vapor Pressure of Subrolume 1. (Curve fit of ASME steam i
tables.) (Pvt)
Pvi. 4.01529125
.0015l3475D1 1
- 2.28128 X 10-9 ((0 2D )4 + 7.081828 X 10- (D
- 1.44734 X 1 i
1
+ 3.03544 X 10-I (Dj)5 D.7 Mhole Containment Average Vapor Pressure. (Pvg)
Approximate' N
Method Pvc.
I fi Pvt
)
11 f 'Pvg Exact N
t Method Pvc. Tc I 11 Tj N. The total of subwolumes in containment f n Volume fraction of the ith subv'olGme 7'
i D.8 Nhole Containment Average Dew Temperature. (Dc)
Approximate N
Method De.
I fi 51 11 Exact Metho' The whole containment average. vapor pressure.
(Pw ) calculated with the exact method is used to e
fins Oc. An initial value of Oc is guessed and used vtth the soustion in D.5 to calculate Pv.
e This value is then compared to the known value frer D.7.
A new value of De is puessed and the process is repeated until a valus of De is found that results in a calculated value of Pvc that is within.0001 psia of'the value from D.7.
~
l TWCH3e4 i
D.9 Average to'tal containment pressure.(P)
P.(P3.P2)/2 Average total containment dry air pressure. (P )
d Pg P - Pvc D.10 Total Containment dry air mass. (M)
Pd Vc Type 1:
M.
R Tc where: R. Perfect pas constant Vc = Total containment free volume.
Type 2:
Type 2 dry air mass accounts for changes in Reactor Vessel level.
For uncorrected dry air mass, (Type 1) the below definitions appiy.
N Vc. I Vi and fj. Vj/Vg 11 where V{ is the user entered free volume in subvolume 1.
For corrected dry air mass, (Type 2) the same definitions for Ve and ft apply, except that one of the Vis is corrected for enanges in vessel level.
If k is the subwolume number of the corrected subvolume then:
Vg = Vgo - a(C - b)
_ _.p a is the number of cubic feet of free volume per inch of vessel level.
A 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 equals b.
The volume fractions (f ) are then calculated with the t
corrected volume, and all other calculations are subsesuently perfermed as previously specified for Type 1 ary air mass.
m
D.11 Lestrate C~niculations using Mass-Plot Method:
This method assumes that the leakage rate is constant during the testing period. A plot of the measured contained cry air mass versus time would ideally yield a straight line with a negative slope.
Based on the least sguares fit to the data obtained. the calcula.ed containment leakage rate is octained from the ecuatter.:
M. At + B Nhere M. containment dry air mass at time t (1bs.)
5 calculated dry air mass at time t=0 (1bs.)
A. calculated leakage rate (1bs/hr) t. time in,terval since start of test (hours) g m
11 (1bs) t (hours)
The values of the ' constants A and 'l such -that-the line is linear least savares best fitted to the leak rate data are:
Etti)(Mj) - (Iti) (I M )t A.
Etti)2 - (Itl )I Att{
INg 8
N 1
l I
w
+
+-
-- -m
l l
By definition leakage out of the containment is considered positive leakage. Therefore, the statistically averaged least souares containment leakage rate in weight percent per day is given ny:
L = ( '.) (2400)/B (weight Uday)
In order to calculate the 95% confidence limit of the least sguares averaged. leak rate, the standard deviation of the least souares slooe anc the student's T-01stribution function are used as follows:
1/
I""
1 NICM )2 (IMj)2
/2 (2400) (weight !
]
t
- a2 per day)
(It])2 g
, _,.(N-2)
NI(tt)2 UCL = L e a (T) 1.6M 7th2) 3.5283 0.85502/(b2) where T.
( b 21 1.2209 - 1.5162/.(b 2)
Number of data sets N
test duration at the ith dats set (hours) it
=
standard deviation of least sguares slope (weight;/ day) a Value of the single-sided T-Oistribution ~
c' T
=
function with 2 degrees of freesom calculated lest rate in weight Uday L
=
95% apper confidence limit
(%/ day)
UCL calculated containment dry air mass at time. t=0 (1bs.)
8 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.
i o
M l
I
For every data set, the rate of change of dry air mass between the most recent, (tt) and the previous time (tl.1) is calculated using the two point morned shown below:
2400 Mi. -
(1 - Mg/M.;)
t Then the least scuare fit of the point to point leaktates is calculated as described for dry air masses in section D.11 u
D.13 Total Time Calculations This method calculates the rate of change with respect to time cf I
dry air mass using the Total Time Method Initially, a referenge time (tr) is chosen. For every data set the rate of change of dry air mass between tr and the most recent time, ti is calculated using the two point method shown below.
2400 Mi.
(1 e Ni'Mr) i Then the least seurres fit and f5% UCL of the Total Time leakrates are calculated as shown below:
I Ag !(tt)2 - I tt I A tt t
N I (ti)2 - (I tt)2 (NItgA-It{!A) t t
N I (tt)2 - (I tt)2 L.
8. At 1.54a9(N-2) 3.5283 0.85502/(N-2)
(N-2). 1.2209 - 1.5162/(N-2)
Note: N is the number of data sets sinus one.
j
I (to
.I (t() / N)2 p,
N I (ti)2 - ( I tg )2 / N l
F l I (A )2 - 8 I A - A I A tg e/
/
1 t
j j
\\/
N
\\/
UCL e t. + ia Note: This ecuation is calculated for information only from the start of the test up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then it becomes the official lestrates for future times.
D.la BN-TDP-1 This method calculates the rate of change with respect to the J
time of dry air mass using the Total flee Method.
Initially, a r6ference time (tr) is chosen. Fo every data set the rate of change of the data item between tr and the most recent time. (t ) is calculated using the two point method shown below:
i l
2400 ng.
. (1 - Mj/Mr)
(tg - tr)
Then the least savares fit of the Total T!ae ',es'altes and the BN-IDP-1 95 UCLs are calculated as shown below... 7 2
I A tq)
( I A Itti)2 I tg t
^
t N I (t114 - ( Z tt 14 i
Note: N is the number of data sets minus one.
l
?
TWCH 304 s
I t{ I A )
( N I tt At i
N Z (ti)4 - (Z ts)4 L.
8. At 2.37226 2.8225 T. 1.95996 +
(N - 2)
(N - 2)2 32 1
(tg - I (tt) / N F.
1..
N Z (tt)2 - CZ tt)2 /N l'
F
'/
e.;/
\\/j/ I (Mt)2 - 8 I A - A I M t
t ti j
\\/
N UCL. L. Te Note: This ecuation is calculated for inferration only from the start of the test up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then it becomes the official leak, rates for future times.
D.15 Temperature stabilization checking per ANSI 56.8-1981 T{
Neighted average containment air tadperature'at hour 1.
T,n Rate of change of weighted average containment air temperature t
over an a hour period at hour 1. using a two point bactuares difference method.
Ti-Ta i
Tj,n =
a
.r NO
21 is the AN'SI 56.8-1981 Temperature stabilization criteria at hour 2 t. l 7.4 Tj,1l 1 must be 2,4.
1 Per ANSI $6.S-1981, 2 must be less than or equal to 0.5 0Flhr NOTL: If the data sampfing interval is 1ess than one hour, then:
Option #1 Use d.ta collected at hourly intervals Option 12 Use average of data col 1ected in 'previou hour for that hour's data.
D.16 Calculation of Instrument Selection Guide. (ISC) 15G 1800
/ Z (ep/p>'
- 2 (e /T)4,,L, tegtyp r
t
\\/ 5 Nr Nd p
where: t is the test time'. in hours p is test pressure, psia T is the volume weighed average containment temperature #R N is the number of pressure transsitiers p
Nr is the nunper of RTDs i
Nd is the number of des cells
-e, is the combined RfDs' error, ogis the combined pressure or og is the combined dew ce!!s* error, og e.
/
\\l E5pI * (**9
- R5 )2
_ p where: 5, is th'e sensitivity of a pressure transmitter RP is the repeatability of a pressure transmitter R5,# is the resolution of pressure transmitter j
er=
/
\\/ (Sr)2, (apr + RSry2 where: Se is the sensitivity of an RfD l
RPr is the repeatability.,
- an RfD RS is the resolution of an RfD p
m
j eg a
./
A7g Td \\/ (Sg).. (RPd
- ES )2 d
1 where:
So is the sensitivity of a dew cell RPd is the repeatability of a dew ceII RS: is tne resolution of a dew cell APy change in vapor pressure MI 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-TDP-1 Temperature Stabilization Criteria Calculation A.
The rate of change of temperature is less than 1 'F/Hr averaged over the last two hours.
1 - T 11 K2-fT i - 7 21 ci.17 1
i 1
K1 and K2 must both at less than 1 to meet the criteria listed in A.
8.
Jhe rate of change of temperature changes less than 0.5 F/ hour / hour averaged over the last two hours.
i - T.1)/(ti - ti 3)
K1. (T i
2. (Tg_t - T.2)/(t1 1 - ti-23 K
1 z. lcri - K )/(ti - ti- )I 2
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 subwolume e is given by the below ecuation.
Y,. Y o - 4 (C-6) a The dry air mass in subvolume e can then be written as:
Mr.144 (EJve) Vs/ rte Where: Mr is tP-dry air mass in s shvolume z (1ba)
R is the pas constant of air (istheaverage,temperatureofsubvolumez.(8R) 5, is the average vapor pressure of subvolume n. (pisa)
E is the average containment pressure. (psia) 3 V, is the free air volume in subwolume e. (ft )
Free valune calculations of the Torus rely upon narrow range Terus tater icvel inputs.
These valLes raIge between plus and cinus five inches.
It is assumed that the Tcrus subvslume free air volume is i
that subwolume's volume when the Torus level eeuals zero.
The user may enter three cNstants to ar. el the variation of Torus air volume with water level.
The ecuations for Torus free volume in suevolume t are given:
3 Vt*Vo-(al+bl+cL])whenL20 t
Vg = V o
- t-AL
- bL2 -CL when LL 0 t
The dry air mass in subvolume t can then be written as:.
Mt
- I'd (5 vt) V /RTt t
Where:
Nt is the dry air mass in subvolume s. (1bs)
P is the average containment pressure, (psla) 5t is the average vapor pressure of subvolume t (pisa) 3 Vt is the free volume i.. subwolume t (ft )
R is the gas constant of air Tt is the average temperature in subvolume t (OR)
L is the Torus level (inches) a.2,c are Torus level constants
.Vto is the free volume in subvolume 7 when L equals zero, 3
taken from standard free volume inputs, (ft )
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
.(KIDATA 2410 (KIDATA f3 LA120 PLOTTERS:
Newlet Packard 7475A 8.5" X 11" Newlet Packard 7585A 8.5" X 11" Newlet Packard 7585A 11" X 17" CRTs:
Nyse WyT5 Ylow Point 80 Amp.ee Dialogue 80 & 81 PRIE PT200 GRAPHICS TERMINALS:
RamTech 8200 Ranfech 5211 Taktronts 4107 Taktroniz 4208 Tettroniz 4014
2 i
APPENDIX C INSTRUMENT ERROR ANALYSIS 4
1 TECH 364 62 1
j
July 8, 1992 A
To: D. Nyman D. Schumacher S. Gupta J. Kuznicki R. Salmi H. King i
i subjects calculation of The Instrument selection Guide For ILRT f
Instrumentation Systems 10CFR50-Appandiv J specifies that all Type A tests be conducted in accordance with the prcwisions 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 1
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 deter =4n4 = the ability of the Type A test instrumentation system to measure the integrated leakage rate of a primary reactor contain= ant system. This rather long formulation is labor intensive to calculate eitner by hand or by compu,ter.
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 reconsended 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 asc.pt.ance criteria is always satisfied. This eliminates the need to demonstrate by calculation in station pE-: tm that the ISG acceptance criteria is meet.
l e
a.
q--<-r
-,-g
The requirement to_ calculate Type A Test instrumentatien cystem ISG values may be al4=4 = ted 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 change.
/'
Jim Glover Production Services Dept.
)
?-
__s y :_r t -
J. Brunner Te cal Staff Support Superintendent G. Vanderheyden R. Shields M. Strait R. Walsh P. Johnson J. Brunner W. T'Niemi b
.i
ATTAC1 DENT A ILRT INSTRUMENTATION.2ISTEM EFECIFICATIONS Pressure Transmitters:
Resoluti v 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 Mini =n= Number 5
Instrument Parameter Defintions From'AMBI/RMS 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 merhanism.
i sensitivity:
The capability of a mammurement system to respond to change in the measured parameter.
INSTRUhENT SELECTION CUIDE CALCUt.ATIONS FOR ILRT INSTRUMENTATION "These e=Wu=inms are based upon the equatums listed in Appendet G of ANSFANS 56.8-1987" Pressure TransmWor Parameters Temperature Parameters DowTemperature Parameters Sensibvity Sp = 0.0001 pel Sensibvity Sr := 0.01 F Senalbvity S d > 0.1 F
t Repeatability RPp =0.001 pel Roehmky RPr =0.02 F Par =*W RPd =0.1 F Resolubon RSp > 0.0001 pai Resoluten RSr > 0.01 F P==ah %
RSd := 0.01 F Number Np = l Number Nr =15 Number Nd = 5 Pressure P > 44.
peig Temperature T:= 95 F DowTemp Td
- 95. F TEST DURATION t := 8 Pressure Error r* %
Measurement System Ermr Pese := RPp+ RSp Pese = 0.0011 Pressure Error Pc:=
Pe = 0.0011 y8 p
i I
Temperature MeasurementErmr Measurement System Error Tese::RPr+ RSr Tase = 0.03 Temperature Error Te (Tase
- g 2
Te = 0.0082 Nr" DowTemperature Mnemurement Ermr r-Measurement System Ermr Tdese =RPd+ RSd Tdese =0.11 P=hd=t= the wepor pressure rues of change uth dew temp from sleem tables A 20.0886717535 B 2 22.452 C 2490.59 Z 2b Aexp B-Z = 0.041
~
dTd (Td-32 + C) i 1
Moesurement System Error Does > Z-(RPd+ RSd)
Dese = 0.0045 i
3,..[D
'uZ.3d>"
]
o,,7%,,,,,
ud" l
i l
l 1
.. _ ~
h N
Pressus EnorTerm PE m 2-PE =7.0813 IO
,(P+ 14.7),
Te Temperature EnorTerm TE 22-TE =4333610' (T4 45948),
DowTemperature EnorTerm DTE*:2-DIE =4.317910"
,(P + 14.7),
Iso > 2400h (PE+ TE+ DTE)*#
150 =0222 t
ANSUANS 56.8 regaares #ist the ISG be less ther 0.25La to tie aca ge.ha.
STATION La 0.25La DRESDEN 1A 0.4 ZION 0.1 0.025 BYRON 0.1 0.025 BRAIDWOOD 0.1 0.025 QUAD CmES 1A 0.25 LASALLE OA35 0.156 e
m O > **
e e
O t
b e
e g
. =.
i APPENDIX D BN-TOP-1, REV. 1 ERRATA Tscii 364 68 i
w e-ru l
AN-TDP-1. ELT. 1 EIRA1A
& ConsLission has approved short dursues testtag for the IFCJtT provided the Station uses the general test asthed out11and sa the EN-TOP-1. Rev. 1 topical report.
b prsmary difference bietween that method and the ones preetously used is in thz stantstacal analysu of the asasured Isak rate data.
Without asking any judgments concerning the validity of this test method.
certata errors is the edittag of the machemsucal empresstems were discovered.
h iatent here is amt to change tas test ethod, but rather to clar:fy ene method ta a mathamstically preesse asaner that allows its suplementatzen.
The errors are listed below.
EDUATION 3A, SEC" ION 6.2.
Reads:
Lg*A*3Eg Should Read:
I sag *Eg g t
g Reason:
b calculated leak rate (L ) at time t is camputed assas the regresstes line The summataea sah, b(equation 6 are taats A computed ustag equations 6 and 7).
a defined as I e I where a is the aanber of data sets up until 1st
.ine t N regressima 11am constaats change eset time a newdada. set is recetvef..
The calculated leak rate is not a linear.fuscuss of taan.
PARAGRAPM FCTIDWTNG ED. 3A, SEC" TON 6.2 Reads:
h dovution of the measured leak rate (N) from the calculated leak rate (L) is sheen graphically on Tigure A.1 La Appeantz A and is expressed as:
-r Devsaties a E
-L g
g Should Read: The deviatisa of the measured leak rata (N ) from the regressten line (N ) is shews grapascally em Tigarr A 1 &a Appendia A and :,s empressdd as:
Devtaties a N
-N g
g where Ng
- A,
- 3,
- E,
g A,3 s Regression 11am constasta computed from all data p
F sets avaMie from the start of tas test to tae last data set at taas t,,
t a tsaa from the start sf the test to the ith data set.
g l
I WW rM 1
w w
-r-
1 Recesa:
The saiculated laat rasa as a functz:n of time i
dursag the test is based-en a regreassea 1sas.
l The regresstaa laas constaats, A and E. are g
g changsag as each additamaal data set as received.
Equattaa 3A is ased later in the test ts compute the upper confidence limit as a functzen of tzme.
l For tan purpose of this calculatten, it is the devtatism from the last camputed regressten laae at taas t, that is important.
EDUAM ON 4 SECMON 6.2 Raads:
55Q = I (Hg-L)*
g Should Amad:
55Q = I (H -N):
g g
1 Reassa:
Sams As'Above EDUAM ON 5, SECM ON 6.2 Reads:
SEQ = I [ 5 - (A
- Bt )}8 g
should Emad:
SEQ = I [ 5i - (A
- 3
- t )]8 p
p i
1 1
Ramses:
Same As Above EDUAM ON ABOVE ECUATION 6, SECMON 6.2 Reads:
3e I*i - t)(E *- I) g 1(tg - t)*
ZI('i - t)(H - I)]
Should Road:
S a g
g Zit - I)*
g Reassa:
Regression lies coastaat 8, changes ever time tas a functzen of t ) as esca Additzenal data set is recessed.
BEr 'of "t" left out of desamtsator.
Sumascies signs entsted.
EQUAM ON 6, SECM ON 6.2 Roads:
8='
- i 31
- i "I
L a It ' - (I a )'
g g
Skou14 naad:
E a*
't *L
'LE G *i
~
g a Lt ' - (L s )*
g g
Reases:
Saas As Ab m I
I TECHase
1 I
EDUATION 7, SEC"70N 6.2 Reads:
A*I-It g*I-S E Should Amad:
A g
same As Above Rossaa:
E00ATION 10, SEC" TON 6 2 G i> G Ei)*NE)EE E)
Roads:
Aa g
g g
aIa a - g & ya g
m.N 8 3 U E ")
- G E ) G E 5) 1 i
g g
g should Amad:
A g
a L t ' - (1 s ja g
Reases:
Same As Above EDUATION 13 SEC" TON 6.3 a.,2 {g. 1 (t, - t)8 y Roads:
s (tg - tJa s,,a [g 1, (t, - D s )
should Baad:
e a
Z (tg - T) where t a ties from the start of the test of the last data E
set for which the standard dettaties of the measured leak rates
)' from the regressten hae- (N ) is g
betag cespu ts,,,
t a time from the start of the test of the i g
g set; number of data sets to time t,;
s a a
i I e Z and ist Te E Lt.
i a
i i
Reassa:
Appears ta be error is editing of the report.
Report does a peer jet of defiatag wartaties.
e T504See
k EQUAU DF 14, SECMON 6.3 s[1+1*
8,**I J
Reads:
aa (c. - t)3 s [ 1 + 1
- II, * * )
]
should Amad:
aa I (t - i)8 g
Asases:
Sams As Abswa EDUATIDW 15, SECn0N 6.3 Raads:
Confidence Limit a L 2 7 Should Raad:
Confidence Limits
- L 2 7 x a whers L = calenlated lank rate at tian t,,
Ta T distributies vaine based as a, the rmber of data sets rossived my until t1as t,;
aa standard deviatias of asassrod leak rate values (5,) shest the regression lias based es data from thestartofthetestuntiltaastg.
Esases:
Sams As Aheve -
EDUATION 16, SECM ON 6.3 Reads:
UCL = L
- T Should Raad:
UCL = L
- T
- a Reases:
Same As Aheve EQUATTON 17, SECTION 6.3 i
Raads:
LCL = L - T l
l Should Raad LCL = L - T
- a Raassa:
Saas As Above
i APPENDIX E TYPE A TEST RESULTS USING MASS-PLOT METHOD (ANS/ ANSI 56.8)
Teen 364 73
TABLE E-l' Mass Point - Meas. Phase Results QUAD CITIES 1
%/ day
%/ day 438 0.00 0.0000 0.0000 439 10.02 0.2360 0.0000 440 20.02 0.3359 0.8300 441 30.02 0.3644 0.4546 442 40.03 0.3329 0.3927 443 50.03 0.3341 0.3696 444 60.03 0.3239 0.3504 445 70.05 0.3284 0.3481 446 80.05 0.3359 0.3529 447 90.07 0.3228 0.3422 448 100.07 0.3240 0.3397 449 110.07 0.3227 0.3356 450 120.08 0.3233 0.3342 451 131.08 0.3252 0.3346 452 141.08 0.3206 0.3299 453 151.10 0.3166 0.3256 454 161.10 0.3179 0.3260 455 171.10 0.3178 0.3250 456 181.12 0.3169 0.3233 457-191.12 0.3159 0.3217 458 201.12 0.3159 0.3212 459 211.13 0.3155 0.3203 460 221.13 0.3132 0.3181 461 231.13 0.3118 0.3165 462 241.15 0.3110 0.3154 j
463 251.15 0.3097 0.3139 464 261.15 0.3070 0.3118 465 271.17 0.3055 0.3101 466 281.17 0.3043 0.3088 467 291.17 0.3038 0.3080 468 301.18 0.3024 0.3066 469 311.18 0.3021 0.3060 470 321.18 0.3012 0.3050 471 331.20 0.3000 0.3037 472 341.20 0.2983 0.3022 473 351.20 0.2979 0.3016 474 361.22 0.2977 0.3012 475 371.22 0.2973 0.3006 TEcn m 74
TABLE E-2 Mass Point - Induced Phase Results "*""
QUAD CITIES 1
%/ day
%/ day 482 0.00 0.0000 0.0000 483 10.02 1.2087
-0.0000 484 20.02 1.2081 1.2100 485 30.02 1.2707 1.3770 486 40.03 1.2892 1.3444 487 50.03 1.2516 1.3083 488 60.03 1.2462 1.2846 489 70.05 1.2431 1.2710 490 80.05 1.2431 1.2641 491 90.05 1.2439 1.2604 492 100.07 1.2429 1.2562 493 110.07 1.2425 1.2535 494 120.07 1.2472 1.2576 495 130.08 1.2477 1.2566 496 140.08 1.2427 1.2519 497 150.08
'1.2407 1.2490 498 160.10 1.2393 1.2467 499 170.10 1.2394 1.2460 500 180.10 1.2369 1.2433 501 190.12 1.2300 1.2417 502 200.12 1.2348 1.2401 TECH 364 75
Mass Point Leak & Mass Point Leak at UCL 3
QUAD CITIES 1
Mass Point Leak Mass Point Leak at UCL 0.90 k
O.80-
\\
.__f O.70-i l
O.60-
\\
=
m 0.50-d
\\
'\\
a Y
0.40-
'\\
x\\
h O.30-
^
~ ~~
0.20-0.10-0.00 0.0 0.5 1.0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 6.5 6.0 Time - Hours
~
N Mass Point Leak 5
QUAD CITIES E
1 2.0
/
E A
m j
d 1.0 -
a Y
0.0 i
i i
0.0 0.3 0.5 0.8 1.0 1.3 1.5 1.8 2.0 2.3 2.5 2.8 3.0 3.3 Time - Hours
.