ML20206F464
| ML20206F464 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/16/1988 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20206F462 | List: |
| References | |
| NUDOCS 8811210150 | |
| Download: ML20206F464 (81) | |
Text
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-. 24 g,
REACTOR CONTAINHENT BUILDING INTEGRATED LEAK RATE TEST QUAO-CITIES NUCLEAR POWER STATION UNIT TWO JUNE 12-13, 1988 ss11210150 881116 ADOCK0500g5 DR m
IABLEOFCONVENTS o
PAGE TABLE AND FIGURES INDEX......................
3 INTRODUCTION............................
4 A.
TEST PREPARATIONS A.] Type A Test Procedures...................
4 A.2 Type A Test Instrumentation.................
4 A.2.a.
Temperature...............,,...
8 A.2.b.
Pressure.
8 A.2.c.
Vapor Pressure...................
8 A.2.d.
Flow.
9 A.3 Type A Test Measurements..................
9 A.4 Type A Test Pressurization................
10 B.
TEST METH00 B.1 Basic Technique....,.................
12 B.2 Supplemental Verification Test..............
13 8.3 Instrument Error Analysis.............
13 C.
SEQUENCE OF EVENTS i
C.1 Test Preparation Chronology................
14 C.2 Test Preparation and Stabil12ation Chronology.......
15 C 3 Measured Leak Rate Phase Chronology,...........
16 C,4 Induced Leakage Phase Chronology.............
16 C.5 Depressurization Phase Chronology.............
16 1
l l
l 1490H/ 1 I
TABLE OF CONTENTS (CONTINU(0)
PAGE 0.
TYPE A TEST DATA 0.1 Heasured Leak Rate Phase Data..............
17 0.2 Induced Leakage Phase Data................
17 E.
T ES T CALCUL AT IONS....
32 F.
TYPE A TEST RESULTS F.1 Measured Leak Rate Test Results......
......33 l
F.2 Induced Leakage Test Results'...............
34 F.3 Pre-Operational Results vs. Test Results.........
35 F.4 Type A Test Penalties..................
35
(
L F.5 Evaluation of Instrument Failures............
36
[
F.6 As-Found Type A Test Results...........
. 37 i
APPEN0!X A TYPE B AND C TESTS...............
38
(
l APPENDIX B TEST CORRECTION FOR SUMP LEVEL CHANGES.....
47 I
L APPEN0!X C COMPUTATIONAL PROCEDURES............
53
[
APPENDIX 0 INSTRUMENT ERROR ANALYSIS 65 I
I t
APPENDIX E BN-TCP-1. REV. I ERRATA............
71 i
APPEN0fX F TYPE A TEST RESULTS USING MASS-PLOT.......
76 METHOD (ANS/ANS! 56.8)
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i r
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TABLES AND FIGURES INOFX PAGE TABLE 1 Instrument Speelfications................
5 TABLE 2 Sensor Physical Locations................
6 TABLE 3 Measured Leak Rate Phase Test Results.........
18 l
TABLE 4 Induced Leakage Phase Test Results...
19 FIGURE 1 Idealized View ef Drywell and Torus....
7 Used to Calculate Free Air Volumes FIGURE 2 Measurement System Schematic Arrangement.......
11 FIGURE 3 Measured Leak Rate Phase - Graph of Cliculated....
20 Leak Rate and Ucper Confidence Limit FIGURE 4 Measured Leak Rate Phase - Graph of Total.......
21 Time Measure Leak Rate and Regression Line I
FIGURE 5 Measured Leak Rate Phase - Graph of
........22 Dry Air Pressure l
FIGURE 6 Hessured Leak Rate Phase - Graph of Volume......
23 Weighted Average Containment Vapor Pressure l
l l
FIGURE 7 Measured Leak Rate Phase - Graph of Volume,,....
24 l
Weighted Average Containment Temperature i
t FIGURE 8 Induced Leakage Phase - Graph of Calculated......25 Leak Rate i
FIGURE 9 Induced leakage Phase - Graph of Total -Time......
26 Measured Leak Rate and Regression Line j
i FIGURE 10 Induced leakage Phase - Graph of Volume........
27 i
l Weighted Average Containment Temperature
[
l FIGURE 11 Induced Leakage Phase - Graph of Volume........
28 Weighted Average Containrent Vapor Pressure FIGURE 12 Induced leakage Phase - Graph of..........,, 29 Ory Air Pressure l
FIGURE 13 Graph of Reactor Water Level.............
30
[
Through Testing Period FIGURE 14 Graph of Torus Water Level..............
31 I
Through Testing Period l
f FIGURE F-l Statistically Average Leak Rate and Upper.......
79 confidence Limit ( ANS/ ANSI 56.8 Method)
FIGURE F-2 Statistically Averaged Leak-rate and Target.
80 Leak-rate (ANS/ ANSI 56.8 Method) 1490H/ ;
i
INTRCOUCTION This report presents the test method and results of the Integrated Primary Containment t.eak Rate Test (IPCLRT) successfully performed on June 12-13, 1988 at Quad-Cities Nuclear Powel Station, Unit One.
The test was performed in accordance with 10 CFR 50, Appendix J, and the Quad-Cities Unit One Technical Specificaticns.
For the fourth time at Quad-Cities a short duration test (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) was conducted using the general test method outlined in BN-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 methed, the total primary containment integrated leak rate I
was calculated to be 0.4155 wt 7./ 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 0.4621 wt %/ day.
A The supplemental induced leakage test result was calculated to be 1.3542 wt
%/ day. This value should compare with the sum of the measured leak rate phase result (0.4155 wt %/ day) and the inducted leak of 8.82 SCFM (1.0814 wt
/ day).
The calculated leak rate of 1.3542 wt %/ day lies within the allowable tolerance band of 1.4969 wt %/ day 3 0.250 wt 1/ day.
SECTION A - TEST PREPARATIONS A.1 Type A Test Precedure The IPCLRT was performed in accordance with Quad-Cities Procedure QTS 150-1, Rev. 15, including checklist QTS 150-52, 53, 55, 56, 57, 58, 510. Sll, 512, 513, 517, S18, S19, and subsections T2, T6, 78, T10 Til, T12 T13, T14 T15.
Approved Temporary Procedures 5537, 5540, 5541, 5542, 5543, and 5547 were written in conjunction with the test.
Precedure 5537 was written to cover the various manual isolation valves not included in the IPCLRT valve checklist QTS 150-57.
Procedure 5540 was written to alicw resetting of the scram after original jumper Installation.
Procedure 5541 was written to cover exceptions to the manual isolation valve checklist.
Procedure 5542, 5543, and 5547 were written to cover l
exceptions to the valve checklist of QTS 150-57.
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 SN-TCP-1, Rev. 1 Topical i
Report as a general test methed.
A.2,Ty e A Test Instr E n_tation Table One shows the specifications for the instrumentation utilized in the IPCLRT.
Table Two lists the physical locations of the tercerature and humidity sensors within the primary containment.
Figure 1 15 an idealized view of the drywell and suppression chamber used to calculate the primary containment free air i
subvolutes.
Plant personnel performed all test instrumentation calibrations using N6s traceable standards.
Quad Cities procedure QTS 150-9 =as used to perform the calibration.
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TABLE ONE INSTRUMENT SPECIFICATIONS INSTR'JMENT MANUFACTURER MODEL NO.
SERIAL NO.
RANT ACCURACY REPEATABILITY Precision Pressure 846,847 0-100 PSIA 1 015 PSI 1 001 PSI Volumetrics Gages (2) 44210 - 44222 44224 - 44232 RTD's (30)
Engineering SP1A1-5 1/2-3A 44234 - 44238 50-150*F 1 5*F f.1*F Burns inclusive 191501. 191509, 191522 5835-1, 5835-2 5835-3, 6084-4 6084-9. 5835-6e 6084-7, 5835-9 1 0*F 1 5'F Volumetrics Lithium 1
De cells (10)
(Fomboro)
$835-10, 6084-8 104*F 1 0*F 1 1*F 2
Pall Trinity 0-600*F 14-T-2H Thermocouple Micro 0.927-11.23scfm 1 0% of 1
Fischer 8405A0348A1 10A3555S man f1o.
i Porter Flo meter Level Model 180 indicator Type VSI 0-400" H O 2
LI 263-101 Wodel 50-553122CAAU2
~
CE LT 263-61 10.85"H 0=10mA 2
15.84"H 0=30mA 2
Torus 1151DP3812tB 106958 Rosemount 20.84"H 0 50mA 2
Level 1
Indicator 075GH/0306Z i
TABLE TWO SENSOR PHYSICAL LOCATIONS RTO NUMBER SERIAL NUM8ER SUBVOLUME ELEVATION AZIPUTH' 1
191522 1
670'0" 180' 2
44210 1
670'0" O'
3 44211 2
657'0" 20' 4
44212 2
657'0" 197*
5 44213 3
639'0" 70' 6
44214 3
639'0" 255' 7
44215 4(Annular Ring) 643'0" 55' 8
44216 4
615'0" 225' 9
44217 5
620'0" 5'
10 44218 5
620'0" 100' 11 44219 5
620'0" 220' 12 44220 6
608'0" 40' 13 44221 6
608'0" 130' 14 44222 6
608'0" 220' 15 191509 6
608'0" 310*
16 44224 7
598'0" 70' 17 44225 7
598'0" 160' 18 44226 7
598'0" 250' 19 44227 7
598'0" 340' 20 44228 8
587'0" 10' 21 44230 8
587'0" 100' 22 44232 8
587'0" 190' 23 191501 8
587'0" 280' 24 44234 9(CRD Space) 595'0" 170*
25 44235 9(CR0 Space))
580'0" 170' 26 44236 10(Torus) 578'0" 70*
27 44237 10(Torus) 578'0" 140' 28 44238 10(Torus) 578')"
210' 29 44229 10(Torus) 578'0" 280' 30 44231 10(Torus) 578'0" 350' Thermocouple (inlet to 11(R Vessel) clean-up HX)
DEWCELL NO.
SERIAL NUNBER SUBVOLUME ELEVATION AZIPUTH I
5835-1 1
670'0" 180' 2
5835-2 2,3,4 653'0" 90' 3
5835-3 2,3,4 653'0" 270' 4
6084-4 5
620'0" O'
5 6084-9 6
605'0" 45' 6
5835-6 7
600'0" 220' 7
6084-7 8,9 591'0" O'
8 6054-8 8,9 591'0" 202' 9
5835-9 10 578'0" 90' 10 5835-10 10 578'0" 270' Thermocouple (Saturated) 11 1490H/
Idealized Vlee of Orytell and Torus Used to Calculate Free Volurres I
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FIGURE 1 i
1490H/
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,A.2.a.
Temperature The location of the 30 platinum RTO's was enosen to avoid conflict with local temperature variations and thermal influence from metal structures, A i
temperature survey of the containment was previously performed to verify that the sensor locaticns were representative of average subvolume conditions.
The RTO's were manufactured oy Burns Engineering Inc. and are Model SP 1Al-5 1/2-3A.
Each RTO and its associated bridge network was calibrated to yield an output of approvimately 0-100 mV over a temperature range of 50-120'F.
Each RTO was calibrated by comoaring the bridge cutput to the true temperature as indicated by the temperature standard.
Four temperatures were used for the calibration.
Two calibration constants (a slope and intercept of the regression line) were computed for each RTO by performing a least squares fit of the RTO bridge output to the reference standard's indicated true temperature.
The temperature standard used for all calibrations was a Volumetrics RTO Model VMC 701-B used with a Oeweell/RTO Calibrator Model 07782, The standard was calibrated by Volumetrics on January 20, 1988 to standards traceable to the NBS.
The plant process computer scanntd the cutput of each RTO-bridge network and converted the output to engineering units using the calibration constants.
A.2.b.
Pressure Two precision cuart2 bourdon tube, absolute pressure gauges were utilized to measure total containment pressure.
Each gauge had a local digital readout and a Binary Coded Decimal (BCO) output to the procrss computer.
Primary containment pressure was sensed by the pressure gauges in parallel through a 3/8" tygon tube connection to a special one inch pipe cenetration to the containment.
Each precision pressure gauge was calibrated from 62.A-65.A PSIA in approximately 0.5 PSI increments using a third precision pressure gauge (Volumetrics Model 07726) that had been sent to Volumetrics for calibration.
The pressure standard was calibrated on February 19, 1988 using NBS traceable reference standards.
The digital readout of the instruments were in "counts" or arbitrary units. Calibration constants (a slope and intercept of a regression line) were entered into the computer program to convert "counts" into true atmospheric pressure as read by the third, reference gauge.
No mechanical calibration of the gauges was performed to bring their digital displays into agreement alth true pressure.
A.2.c.
Vapor Pressure Ten lithium chloride dewcells were used to determine the partial pressure due to water vapor in the containment.
Tne dewcells were calibrated using the Volumetrics calibrator described in section A.2.4. above and a chilled mirror dentell standard (Volumetrics S/N 1263) calibrated on January 20, 1988 by 1490H/
,Volumetrics.
The calibration constants for eacn dewcell (the slope and intercept of a regression line) were cerouted relating the 0-100 mV cutout of the signal conditioning cards to the actual dewootnt indicated by the reference standard.
A.2.d.
Flow A rotameter flowmeter, Fischer-Porter serial number 8405A0348Al, was used for the flow measurement during the induced leakage phase of the IPCLRT.
The flommeter was calibrated by Fischer-Porter on February 19, 1988, to within
+1".
of full scale (0.927-11.23 SCFM) using NBS traceable standards.
Plant personnel continuously monitored the flow during the induced leakage phase and Corrected any minor deviation 3 from the induced flow rate of 8.82 SCFM by adjusting a 3/8" needle valve on the flowmeter inlet.
The flow meter outlet was unrestricted and vented to the atmosphere.
The fic* meter was calibrated to standard atmospheric conditions.
A,3 Type A Test Measurement The IPCLRT was performed utilizing a direct interface with the station process computer.
This system consists of a hard-wired installation of temperature, dewpoint, and pressure inputs for the IPCLRT to the process computer. The interface allows the process computer to scan the inputs and send the data, still as a millivolt signal or BCD (binary coded decimal) in the case of pressure, to the PRIME computer with minimal manual inputs and without the disadvantages of multipleners or positioning sensitive electronic hardware inside the containment during the test.
The PRIME computer was used to compute and print the leak rate data using either the ANSI /ANS mass plot method (ANSI /ANS 56.8), a total time method based on ANSI /ANS N45.4, or the SN-TOP-1 method.
Key parameters, sucn as total time measured leak rate, volume weighted dry air pressure and temperature, and absolute pressure were monitored using a Tektroni 4203 terminal and a Tektronix plotter.
Plant nersennel also ple>tted a large number of other parameters, including reactor water level and temperature, torus water level, dry air mass, volume weighted partial pressures and ter;erature, total time leak rate, statistically averaged leak rate and UCL, and all sensor outputs in engineering units.
In all cases, data was plotted hourly and computer summaries were obtained at 10 minute time intervals.
The clotting of data and the computer printed summaries of data allowed rapid identification of any problems as they might develop.
Figure 2 shows a schematic of the data acquisition system.
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A.4 Type A Test Pressurization A 3000 SCFM, 600 hp. 4kV electric oil-free air compressor was used to pressurize the primary containment. An identical compressor was available in standby during the IPCtRT.
The compressors were physically located on a single enclosed truck trailer located outside the Reactor Building.
The compressed air was piped using flexible metal hose to the Reactor Building, 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. HO-1-1001-26A was open during pressurization. Once the containment was pressurtzed, the M0-1-1001-26A valve was closed and the spool piece was removed and replaced with a blind flange.
The outboard containment spray value HO-1001-23A was closed and out-of-service for the test.
1 i
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J 1490H/ l
Measurement System Schematic Arrangement l
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1490H!
11-l l
E SEC7 ION E - TEST METHOO B.1 Basic Technique-The absolute method of leak rate determination was used.
The absolute method uses the ideal gas laws to calculate the measured liak rate, as defined L
in ANSI N45.4-1972.
The inputs to the nieasured leak rate calculatter, include i
subvolume weighted containment temperature, subvolume weighted vapor pressure, and total absolute air cressure.
l l
As required by the Conmission in order to perform a short duration test (measured leak rate phase of less then 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />), the reasured leak rate das statistically analyzed using the principles ouillned in BN-TCP-1, Rev. 1. A least squares regression line for the treasured total time leak rate versus l
time since the ste-t of the test is calculated after fach new data set is i
scanned.
The calculated leak rate at a point in time, tg, is the leak rate r
i on the regression line at the tirre tg.
I t
The use of a regression line in the BN-TCP-1, Rev. I report is different from the wai it is used in the ANSI /ANS 56.8 standard.
The latter standard j
uses the slcce of the regression line for dry air mass as a function of time to derive a statistically averaged leak rato.
In cont *ast BN-TCP-1, Rev. I f
i calculates a regression line for the'reasured leak latI, witch is a function i
of the ch..nge in dry air mass.
For the ANS1/ANS calculations one would espect to always see a negative slope for the regre.tston line, because the dry air j
mass is decreasing over time due to leakage from the cantainment.
For the l
l regression line corrouted in the BN-TOP-1, Rev.I method the ideal slope is l
j zero, since you presume that the leakage from the cont.tinment is constant over f
i time. Since it is impossible to instantaneously and pirfectly measure the l
j containment leakage, the slope of the regression line nill be Dositive or negative depending on the scatter in the measured leak rate values ebtained I
9 j
early in the test.
Since the measured leak rate is a total time calculation, tht values computed early in the test will scatter much rnore than the values j
computed after a few hours of testing.
The cceputer printouts titled "Leak Rate Based on Total Time Calculations"
]
attached to the BN-TOP-1. Rev. I topical report are misleading in that the column titled "Calculated Leak Rate" actually has printed out the regression 4
i line values (based on all the measured leak rate data cerrouted from the data d
sets received up until the last time listed on the printout).
The calculated leak rate as a function of time (t ) can only De calculated from data t
available up until that poir't in time, t.
This is significant in that the i
i calculated leak rate may be d ureasing over time, despite a substantial positive slope in the last computed regression line.
Extrapolation of the 1
regression line is not required by the BN-TOP-1, Rev. I criteria to terminate i
a short duration test.
What is required 15 that the calculated leak rate te decicasing over time or that an increasing calculated leak 7te be estrapolated to 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 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 l
Bt
, Rev. 1.
Calcu ated leak rates, as s function of time, are correctly j
prir'+
et in the Trends Based on Total Time Calculations" computer prit. >
- a #ppendix B of BN-TOP-1, Rev. 1.
a l
1490H/ _
. Associated with each calculated leak rate is a statistically derived upper confidence'llmit.
Just as the calculated leak rate in BN-TOP-1, Rev. I and' the statistically averageo leak rate in the ANSI /ANS standards are not the same (and do not necessarily yield nearly equal values), the upper confidence limit calculations are* greatly different.
In the BN-TOP-1, Rev. I topical report the upper' confidence limit is defined as the calculated leak rate plus the product of the two sided 97.5% T-distribution value (as opposed to the one-sided 95% T-distributirn used in the ANS/ ANSI standard) and the standard deviation of the meatured leak rate data about the computed regression line (which has ne relationship to the value computed in the ANSI /ANS standards).
There are two important conclusions that can be derived from data analyzed using the.BN-TOP-1, Rev. I method:
- 1) the upper confidence limit for the same measured leak rate data can be substantially greater than the value calculated using th) ANSI /ANS method, and 2) the upper confidence limit does not converge to the calculated leak o te nearly as quickly as usually observed in the latter method as the nu u r of data sets becomes large.
With this in mind.
[
the upper confidence limit can become the critical parameter for concluding a short duration test, even when the measured leak rate seems to be well under the maximum allowable leak rate.
A graphical comparison of the two methods i
can be made by referring to Figu e 3 for the B*i-TOP-1, Rev. I calculated leak i
rate and upper confidence limit (nd to Figure F-1 in Appendix F for the i
statistically averaged leak rate and' upper confidence limit based on ANSI /ANS 56.8-1981.
This data supports the contention of many that BN-T09-1, while it i
may not give the best estimate of containment leakage, is a conservative i
method of testing.
The ANSI /ANS 56.8 data contained in Appendix F is provided for information only.
The reported test results are based on BN-TOP-1, only.
B.2 Supplemental Verification Test l
The supplemental verification test superimposes a known leak of approximately the same magnitude as LA (8.16 SCFM or 1.0 wt %/ day as defined in Technical Specifications).
The degree of detectability of the combined leak rate (containment calculated leak rate plus the seperimposed, induced leak rate) pro /tdes a basis for resolving any uncertainty associated with measured leak rate phase of the test.
The allowed error band is 1 25% of L.
A There are no referencts to the use of upper confidence limits to evaluate the acceptability of the induced 1%kage phase of the IPCLRT in the ANS/ ANSI standards or in BN-TOP-1, Rev. 1.
8.3 Instrument Error Analysis An instrument error analysis was performed prior to the test in accordance with BN-TOP-1, Rev. 1 Section 4.5.
The instrument system error was calculated in two parts.
The first was to determine the system accuracy uncertainty.
i The second and more important calculation (since the leak rate is impacted most by changes in the containment parameters) was performed to determine the system repeatability uncertainty.
The results were 0.1801 wt ~./ day and
.0265 wt %/ day for a 6-hour test, respectively.
These values are inversely proportional to the test duration.
The instrumentation uncertainty is used only to illustrate the system's abi'ity to measure the required parameters to calculate the primary containment leak rate.
The mathematical derivation of the above values can be found in Appendix 0.
The method of calculating the equipment uncertainty is in conformance with the method outlined in BN-TOP-1.
1490;il -
It is extremely important during a short duration test to quickly identify a failed sensor and in real time back the spurious data out of the calculated volume weighted containment temperature and vapor pressure.
Failure to do so "can cause the upper confidence limit value to place a short duration test in jeopardy.
It has been'the stations experience that sensor failures should be removed from all data collected, not jus, subsequent to the apparent failure, in order to minimize the discontinuity in computed values that are related to the sensor failure (not any real change in containment conditions).
For this test, however, no instrument failures after t.7c start of the test were encountered. Howeve*, a single RTD failed in the drywell, RTD 8 in subvolume 4, prior to the start of the test for spiking high and then reading high.
The effect of this failure is analyzed in section F.5 of this report.
The instrument error analysis in Appendix D reflects the instrument failure and unused instrument.
SECTION C - SEQUENCE OF EVENTS C.1 Test Preparation Chronology The pretest preparation phase and containment inspection was completed on June 12, 1988 with no apparent structural deterioration being ot' served.
Major preliminary steps included:
- 1) Blocking open three pairs of drywell to suppression chart.W vacuem treakers.
2)
Installation of all IPCLRT test equipment in the suppression chamber.
- 3) Completion of all repairs and installations in the drywell affecting primary containment.
- 4) Venting of the reactor vessel to the dryo ll by opening the manual head vent line to the drywell equipment dra m sump.
l 5)
Installation of the IPCLRT data acquisition system including computer programs, instrument consolo, locating instruments in the drywell, and associated wiring.
- 6) Completion of the pre-test valve line-up.
This test was conducted at the end of the refuel outage to test the containment in an "As LLft" 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.
l l
l 1490H/ l 1
C.2.' Test' Pressurization and Stabilization Chronology DATE TIME EVENT 06-12-88 0300 Began pressurizing containment.
0550 Drywell-Head, X-1, and X-4 snooped.
No leaks observed.
Snooped all accessible penetrations in reactor building. No leaks observed.
0613 2-1402-48 leaks excessively through packing.
0807 Stopped pressurization due to reactor water and torus water level decreasing at an unacceptable rate.
Increased reactor water level to.approximately 87".
0820 Closed the 2-1001-26A and 2-4799-12? valves, Unioaded-the compressor and stopped pressurization.
Raised reactor water level to approximately 100".
0900 Tightened packing on the 2-1402-48, 2-1001-28A, 34A valves. Closed the 2-2301-6 val.e to fully seat.
1952 Containment is pressurized to 65 PSIA.
Beginning containment stabilization phase.
1200 Attempts are being made to determine a leak of approximately 500 SCFH.
All systems are being snooped.
2050 Closed the 2-1001-25A valve on the outboard side of the 2-1001-26A valve.
No effect on the leakage rate.
2355 Leakrate has stabilized at 1.3LA still searching for the leakage.
4 6-13-88 0225 Locked out RTD #8 in subvolume #42-2499-20A was found e
blowing air inside the hydrogen monitoring panel.
1 Heater sample box was disconnected and removed.
0230 2-2499-20A valve was closed.
The leakage path was found.
f t
0405 All stabilization criteria have been satisfied.
l 1490H/,
C.3, Measured-Leak Rate Phase-Chronology DATE TIME
' EVENT 3
06-13-88 0405 Containment' temperature stable below 0.1*F/ hour.
Reactor' vessel level drop of approximately 0.5 inches / hour.
Reactor water temperature stable below l'F/traor.
0405,
Starte3 seausred leak rate phase.
Base data set #181.
1006 Terminated measured leak rate phase at 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> point, base data set #218. Calculated leak rate was 0.4155 wt
%/ day and d9 creasing over time.
The average measured leak rate over the last five hours was 0.4194 wt %/ day.
The upper confidence limit was 0.4621 wt%/ day. All other BN-TOP-1, Rev. I criteria for terminating the test were satisfied.
C.4 Induced Leakage Phase Chronology DATE TIME EVENT 06-13-88
'1040 Valved in the flowmeter at 8.82 SCFM (80% scale reading).
Radiation Protection is collecting a sample of containment air.
1106 Stabilization began for induced phase.
Data set #224.
1206 Began induced phase of the test.
Base Data set #230.
The one hour stabilization required by BN-TOP-1 was compited.
1517 Terminated induced phase.
Last data set was #249.
Calculated leak rate was 1.2542 wt%/ day.
With an upper confidence limit of 1.4626.
Data indicates a successful 1
test.
C.5 Depressurization Phase Chronology OATE TIME EVENT j
06-13-88 1650 Began containment depressurization using procedure for venting through the Standby Gas Treatment System (SBGT).
Flowmeter isolated.
l 1810 Depressurized down to 52.24 PSIA to perform special test 2-81.
1490H/,
1
DATE TZME EVENT 06-13-88 2010.
. Completed special test 2-81 preparing to-depressurization again.
x-2210 Depressurl:ed to 27 PSIA. Opered 2-1601-63 wide open
';3 -
for final.depressurization.
c 06-14-88 0315 Technical Statt personnel entered drywell.
No apparent structural damage. Verifled all Instruments. remained in place.
Removed all instrumentation in the'drywel).
0604 Made initial' entry to suppression chamber. Verified all instrument remained in place and removed all reAalning-Instruments.
Sump levels in drywell checked ead recorded.
SECTION O - TYdE A TEST DATA W
0.1 Measured leak Rate Phase Data A summary of the computed data using the BN-TOP-1, Rev. I test method for a short duration test can be found in Table 3.
Graphic results of the test are found in Figures 3-7.
For comparison purposes only, the statistically averaged leak rate and Upper confidence limit using the ANS/ ANSI 56.8-1981 standard are graphed in Figure F-1.
A summary of the computed data using ti.a ANS/ ANSI standard is found in Append 5x F.
0.2 Induced Leakage Phase Data I
A summary of the competed data for the Induced Leakage Phase of the IPCLRT Is found in Table 4 The calculated le:ik rate and upper confidence limit using the BN-TOP-1, Rev. I method are shown in Figure 8.
The measured leak rate and last computed regression line ar9 shown in Figure 9.
Containment conditions during the Induced Leakige Phase are presented graphically in Figures 10-12.
t i
1490H/,
l
Measured Leak Rate Test Results TABLE 3 DRY AIR.
REACTOR.
MEAS.
CALC.
UPPER DATA TEST
- AVE.
PRESSURE LEVEL LEAK LEAK CONF.
SET #
TIME DURATION TEMP.
(PSIA)
(INCHES)
RATE RATE-LIMIT 181 04:05:31 0.000 93.1 63.6012 91.9940 182 04:15:33 0.167 93.1 63.5971 91.8900 0.4937 183 04:25_33 0.334 93.1 63.5935 91.7510 0.4135 184 04:35:35 0.501 93.1 63.5907 91.7510 0.3569 0.3529 0.4471 185 04:45:35 0.668 93.1 63.5850 91.6120 0.4342 0.3893 0.6826 186 04: 55:36 0.835 93.1 63.5825 91.5080 0.3943 0.3828 0.5716 187 05:05:39 1.002 93.1 63.5781-91.5080 0.4414 0.4050 0.5728 188 05:15:39 1.169 93.0 63.5752 91.3690 0.3843 0.3916 0.5297 189 05:16:01 1.175 93.0 63.5752 91.3690 0.3823 0.3885 0.5031 190 05:26:04 1.343 93.0 63.5714 91.3690 0.4185 0.3923 0.5006 191 05:36:05 1.509 93.0 63.5675 91.3690 0.4552 0.4087 0.5208 192 05:46:06 1.677 93.0 63.5636 91.2650 0.4381 0.4164 0.5223 193 05:56:09 1,844 93.0 63.5608 91.1260 0.4244 0.4184 0.5169 194 06:06:09 2.011 93.0 63.5576 91.1260 0.4328 0.4223 0.5150 195 06:16:10 2.178 93.0 63.5547 90.8830 0.4024 0.4171 0.5053 196 06:26:10 2.344 93.0 43.5505 90.8830 0.4323 0.4207 0.5047 197 06:36:14 2.512 93.0 63.5473 90.7440 0.4247 0.4217 0.5017 198 06:46:15 2.679 93.0 63.5434 90.7440 0.4387 0.4257 0.5026 199 06:56:15 2.846 93.0 63.5419 90.6400 0.4205 0.4250 -0.4988 200 07:06:15 3.012 93.0 63.5389 90.5010 0.4115 0.4226 0.4938 201 07:16:16 3.180 92.9 63.5352 90.3620 0.4219 0.4226 0.4913 202 07:26:20 3.347 92.9 63.5324 90.3620 0.4302 0.4241 0.4906 i
203 07:36:21 3.514 92.9 63.5300 90.2580 0.4246 0.4244 0.4887 204 07:46:25 3.682 92.9 63.5282 90.2580 0.4147 0.4230 0.4855 205 07:56:25 3.849 92.9 63.5249 90.2580 0.4190 0.4225 0.4833 206 08:06:26 4.015 92.9 63.5206 90.0840 0.4151 0.4214 0.4806
]
207 08:16:28 4.183 92.9 63.5198 90.0840 0.4129 0.4202 0.4780 208 08:26:30 4.350 92.9 63.5168 89.9450 0.4224 0.4205 0.4768 209 08:36:33 4.517 92.9 63.5147 89.8070 0.4176 0.4200 0.4751 210 08:46:33 4.684 92.9 63.5131 89.8070 0.4176 0.4197 0.4735 211 08:56:35 4.851 92.9 63.5091 89.7020 0.4249 0.4203 0.4730 1
212 09:06:35 4.018 92.9 63.5084 89.7020 0.4162 0.4197 0.4714 213 09:16:36 5.185 92.9 63.5070 89.5630 0.4082 0.4183 0.4691 214 09:26:36 5.352 92.9 63.5033 89.5630 0.4212 0.4185 0.4684 215 09:36:37 5.519 92.9 63.5020 89.5280 0.4158 0.4181 0.4670 216 09:46:39 5.686 92.9 63.5003 89.3900 0.4086 0.4169 0.4651 217 09:56:41 5.853 92.9 63.4975 89.2510 0.4151 0.4166 0.4639 218 10:06:43 6.020 92.9 63.4971 89.2510 0.4072 0.4155 0.4621 1
I i
1490H/
Induced Leakage Phase Test Results TABLE 4 ORY AIR REACTOR MEAS.
CALC.
UPPER DATA TEST AVE.
PRESSURE LEVEL LEAK LEAK CONF.
SET #
TIME DURATION TEMP.
(PSIA)
(INCHES) RATE RATE LIMIT 230 12:06:56 0.000 93.0 63.4372 88.4520 231 12:16:57 0.167 93.0 63.4308 88.3130 1.3986 232 12:27:00 0.335 93.0 63.4242 88.3130 1.5294 233 12:37:04 0.502 93.0 63.4189 88.1750 1.4124 1.4537 2.4337 234 12:47:05 0.669 93.0 63.4132 88.1750 1.4618 1.4615 1.8206 235 12:57:05 0.836 93.0 63.4075 88.1750 1.4628 1.4652 1.6916 236 13:07:06 1.003 93.0 63.4023 88.0010 1.3386 1.4018 1.6317 237 13:17:06 1.170 93.0 63.3975 88.0010 1.3192 1.3566 1.5575 238 13:27:08 1.337 93.0 63.3905 87.8620 1.3553 1.3442 1.5174 239 13:37:10 1.504 93.0 63.3857 87.8620 1.3568 1.3373 1.4926 240 13:47:14 1.672 93.0 63.3806 87.7580 1.3598 1.3341 1.4774 241 13:57:15 1.839 93.1 63.3743 87.6190 1.3649 1.3340 1.4692 242 14:07:16 2.006 93.1 63.3695 87.6190 1.3661 1.3347 1.4635 243 14:17:16 2.173 93.1
'63.3651 87.6190 1.3635 1.3348 1.4578 244 14:27:20 2.340 93.1 63.3589 87.4450 1.3623 1.3349 1.4528 245 14:37:25 2.508 93.1 63.3532 87.4450 1.3645 1.3356 1.4495 246 14:47:28 2.676 93.1 63.3476 87.3070 1.3663 1.3369 1.4473 247 14: 57:29 2.843 93.1 63.3411 87.3070 1.3991 1.3451 1.4569 248 15:07:31 3.010 93.1 63.3369 87.2020 1.3821 1.3485 1.4579 249 15:17:33 3.177 93.1 63.3307 87.2020 1.3962 1.3542 1.4626 1490H/
HEASUREO LEAK RATE PHASE GRAPH OF CALCULATED LEAK RATE AND UPPER CONFIDENCE LIMIT B N -TO P - 1 LEAKRATES VS TIM E 0.80 1
'Al lo wed Lea k Ra te 0.70 0.60
- j 1
-8 95 x UPPER CONFIDENCE LIMIT 0.50 g
c.
44 0.40
~
1 CALCULATED LEAK RATE i.
0.30 0.20 l
0.10 O.33 1.23 2.13 3.03 3.93 4.83 5.73 6.63 HOURS i
t r
i i
FIGURE 3 i
t e
I l
i 1490H/ t
v MEASURED LEAK RATE PHASE
. GRAPH OF TOTAL TIME MEASURED LEAK RATE AND REGRESSI0t1 LIf4E TOTAL TIM E LEAKRATES VS TIME 0.80,
0.70 0.60
>-8 0 50 25 vt4sueto ' En urE c
AA 0.40
- VU.
n
~^^
v
~ -
~
at:atssics tst 0.30 0.20
+
l 0.10 0.33 1.23 2.13 3.03 3 93
- 4. 8'3
- 5. 7'3 6.63.
HOURS I
L t
i FIGURE 4 I
i i
1490H/ 1 i
MEASURED LEAK RATE PHASE GRAPH OF DRY AIR PRESSURE t
t
^
i CONTAINMENT LORY. AIR PRESSURE VS TIME 1
i 63.65 I
t 63.60 i
2 63.55 63.50
. -l i.
4
]
63.45 l
63.40-i-
i 63.35 L
L 4
63.30 i
j 0.00 0.90 1.S'O 2.7'O 3.60 4.50 5.40 6.30 l HOURS f
I r
a l
l l
l i
I j-I 1
FIGURE 5 t
I i
i 1490H/ I i
I si
4 MEASURED LEAK RATE PHASE-GRAPH OF VOLUME WEIGHTED AVERAGE CONTAINMENT VAPOR PRESSURE CONTAINMENT VAPOR PRESSURE VS TIM E 0.4920 0.4900 0.4880 -
0.4860 5
0.4840 -
0.4820 0.4800 -
0.4780 i
O.00 0.90 1,80 2.70 3.60 4.50 5.40 6.20 HOURS FIGURE 6 1490HI 2
MEASURED LEAK RATE PHASE GRAPH OF VOLUME HEIGHTED. AVERAGE CONTAINMENT TEMPERATURE CONTAINMENT AIR' TEMPERATURE VS TIME 93.15 93.10 93.05 u.
e.o 93.00 d
1 92.95 t
F 92.90 l
i 92.85 i
l 92.80 O.00 0.90 1.8'O 2.70 3.60 4.50 5$0 6.30 HOURS l
t i
g.
i l
l TABLE 7 1490H/
24
m r-INDUCED: LEAKAGE PHASE GRAPH OF CALCULATED LEAK RATE BN-TOP-1 LEAKRATES VS-TIME 1.80 ~
UPPER BOUNOS 1.70 1.60
+
>-5 Tar 1.50
getLeckReter g
a.
M i
1.40 CALCULATED LEAK RATE
+
~
1.30 LOWER SOUNDS 1.20
+
1.10 1.83 2.33 2.83 3.33 3.83 O.33 0.83 1.33 HOUR 5 FIGURE 8 1490H/
INDUCEO LEAKAGE PHASE GRAPH OF TOTAL TIME HEASURED LEAK RATE AND REGRESSION LINE TOTAL TIM E LEAKRATES VS TIM E -
i 1.80 1.50 UPPER BOUNDS 1.70
-1.70
/
1.60 '
- 1.60 l u
25 1.50 g
-1.50 m
w!ASUREO Li u RAri 1.40
-1.40 V
- !GRESSICN LINE 1.30
-1.30 1.0WER BOUNDS I
i i
1.20 T 1.20
+
i t
i 1.10 2.83 3.33 3.83 10 1
r 0.33 0.83 1.33 1.83 2.33 r
HOURS i
FIGURE 9 5
l l
1490H/.
?
w INDUCED LEAKAGE PHASE GRAPH OF VOLUME HEIGHTED AVERAGE CONF 4"HENT TEMPERATURE
- t.
I
~
f CONTAINMENT AIR TEMPERATURE VS TIME.
r t
93.15 u.
i
+
s 93.10 s
i j
93.05 i
4 l
e 93.00 i
8
^
1I 92.95 p.
92.90 4
l t
92.85 1
I 1
I s
ii 92.80 0.00 0.50 t.00 I.50 2.00 2.50 3.00 3.50 '
4 HOURS i
d'.
3 4
0 h
4 3
FIGURE 10
[
1490H/
- t h
-.- -,__ I
h.
9')
INCUCED LEAKAGE PHASE GRAPH OF VOLUME HEIGHTED AVERAGE CONTAINHENT VAPOR PRESSURE -
- v
. i.
1 CONTAINMENT VAPOR PRESSURE 'VS TIMI
,l:.
0.4845 l-t t
0.4840 -
,)
~
0.4835 f
0.4830 j
3 0.4825 -
1 0.4820 l
0.4815 h
1 0.4810 0.00 0.5'O 1.0'O 1.50 2.00 2.50 3.00 3.50 HOURS FIGURE 11 s
1490H/ <
\\
f
INDUCE 0 LEAKAGE PHASE GRAPH OF DRY AIR PRESSURE CONTAINM ENT ORY AIR PRESSURE VS TIME 63.44 1
63.42 63.40 l
t 63.38 63.36 2.
i i
63.34 4
f 63.32 63.30 0.00 0.50 1.00 1.50 2.00 2.50 3.00 3.50 HOURS i
t i
1 e
FIGURE 12 1490H/
29 4
i k
e GRAPH OF REACTOR WATER LEVEL THROUGH TESTING PERIOD RX VESSEL LEVEL VS TIM E i
92.00 1
91.00 4
1 90.00
~
?
t t0
=
89.00 M_._
88.00 1
}
l l
87.00 l
86.00
+
l 85.00 1
0.00 1.60 3.20 4.80 6.40 8.00 9.60 11.23 ;
i HOURS i
I i
i FIGURE 13 j
i j.'
h I
t t
l l
l 14WH/ i l
,a GRAPH F TORUS HATER LEVEL THROUGH TESTING PERIOD TORUS LEVEL V5 TIME 0.10,
0.00
-0.10 83
=
-0.20 d
-0.30 x
-0.40
\\
\\
\\
-0.50
+
x
-0.00 0.00 1.60 3.20 4.B0 6.40 8.00 9.60 11.20 HOURS FIGURE 14 1490H/.
SECTION E - TEST CALCULATIONS Calculations for the IPCLRT are based on the BN-TOP-1, Rev. I test method and are found in the functional requirements specification CECO Generic ILRT computer code document 10# 555-88-002 Dated April 1, 1988. A reproduction of the BN-TOP-1, Rev. I test method can be found in Appendix C.
In preparing for the first Quad Cities saort duration test using BN-T00-1, Rev. I a number of editorial errors and ambiguous statements in the topical report were
-identified.
These errors are presented in Appendix E and are editorial in nature only.
The Station has made no attempt to improve or deviate from the methodology outlined'in the topical report.
Section 2.3 of BN-TOP 1, Rev. I gives the test duration criteria for a short duration test.
By station procedure some of these duration criteria have been made more conservative and in some cases these 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 an( actual stabilization:
17 hrs. 57 min)
The atmosphere is considered stabilized when:
1.
The rate of change of average tempetature is less than 1.0*F/ hour averaged over the last two hours DATA SET
- AVE. CONTAI MENT TEMP.
ai 180 93.153 174 93.237 0.084 168 93.294 0.057 average:
0.0705'F/ hour
- Approximate time interval between data sets is 10 minutes or 2.
"The rate of change of temperature changes less than 0.5'F/ hour / hour averaged over the last two hours."
(Not required if A.1 satisfied)
B.
Data Recording and Analysis 1.
"The Trend Report based on Total Time calculations shall indicate that the magnitude of the calculated leak rate is tending to stabilize at a value less than the maximum allowable leak rate (Lg)..."
By Quad Cities procedure the calculated leak rate must be less than 0.75 L.
The actual value was 0.4155 L, stable, and A
A decreasing (no extrapolation required).
a,3,d 1490H/
2.
"The end of the test upper 95% confidence limit for thQ calculated leak rate based on total time calculations shall be less than the maximum allowable leak rate."
~
l By Quad Citles procedure the upper confidence limit must be less than 0.75 L.
The actual value was 0.4621 L -
A A
a.nd 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 0.4194 LA for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.
A and 4.
"Data shall be recorded at approximately equal inte vals and in no case at intervals greater than one hour."
At Quad Cities data scan's are automatically performed on 10 minute intervals. No data sets were missed or lost during the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test period.
No computer failures were encountered, dil$
5.
"At least twenty (20) data point shall be provided for proper statistical analysis."
There were 38 data sets taken for this test.
8.2.$
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 would support the argument that a shorter duration test can be conducted.
All of the above termination criteria were satisfied in six (6) hours.
SECTION F - TYPE A TEST RESULTS F.1 Heasured Leak Rate Test Results Based upon the data obtained during the short duration test, the following results were determined:
(LA = 1.0 wt %/ day)
I) Calculated leak rate at 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> equals 0.4155 wt %/ day and declining steadily over tire (<0.7500 wt %/ day).
i i
1490H/ '
- 2) Upper confidence lim.t equals 0.4621 et t/ day and decilning (<0.750 et
%/ day).
- 3) Mean of the measured leak rates for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> (32 data sets) equals 0.4194 wt %/ day (<0.750 wt %/ day).
- 4) Data sets were accumulated at approximately 10 minute time intervals and no intervals exceeded I hours.
- 5) There were 38 data sets accumulated.in 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> measured phase.
- 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 8.82 scfm (1,0814 wt %/ day) was induced on the primary containment for this phase of the test.
The leak rates during this phase of the test were as follows.
BN-TOP-1 Calculated Leak Rate 0.4155 0.4155 (Heasured Leak Rate Phase)
Induced Leak (8.79 scfm) 1.0814 1.0814 Allowed Error Band
+0.2500
-0.2500 1.7469 1.2469 BN-TOP-1 Calculated Leak Rate 1.4626 wt %/ day (Induced Leak Rate Phase)
The induced phase of the test has a dur& tion criteria given in Section 2.3.C of BN-TOP-1.
The test duration requirements are listed below and were satisfled 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 /> for 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test) 3.
Results of this verification test shall be acceptable provided the 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)
I 1490H/
-3a-
F.3 Pre-Operational Results vs Test Results Past IPCLRT reports have compared the results of each test with the pre-operational IPCLRT, performed April 20-21, 1971. Over the last 16 years, different tdst equipment, sensor locations and number of sensors.
test methods, and test duration have been used.
This test yielded results that compare favorably with recent tests and demonstrate that there has been no substantial deterioration in containment integrity.
L TEST DURATION CALCULATED LEAK RATE STATISTICALLY AVE.
TEST DATA (HOURS)
(BN-TOP 1)
LEAK RATE (ANSI /ANS)
August, 1971 24 Not Available 0.1112 1976 24 Not Available 0.327 1980 24 Not Available 0.449 1983 24 Not Available 0.464 e bruary, 1984 24 Not Available 0.385 e
May, 1985 24
.3670 0.4071 October, 1986 8
.3225 0.3294 June, 1987 6
.4155 0.4141 F.4 TYPE A TEST PENALTIES r
Ouring the type A test, there were a number of systems th&t 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.
1 l
i I
t l
1490H/ !
i
AS LEFT MINIMUM PATHWAY LEAKAGE SCFH WT%/ DAY Primary' Sample Valves 0.00 0.00 ACAD 3.30 0.00674 RHR A 2.45 0.00500 RHR 8 1.65 0.00337 Feedwater OWF05 0.75 0.00153 DWE05 0.40 0.00082 RCIC steam exhaust 3.88 0.00792 RCIC drain 1.65 0.00337 HPCI' steam exhaust 3.22 0.00658 HPCI Orain 2.10 0.00429 All electrical penetrations 0.20 0.00041 0xygen analyzer 16.0 0.03268 Tip purge check valves 3.0 0.00613 CAM-Isolation Valves & Panels 0.00 0.00 MSIV drain valves 0.00 0.00 SRM/IRM Purge 0.00 0.00 Total 38.60 SCFH 0.0788 wt%/ day F.5 EVALUATION OF INSTRUMENT FAILURES Prior to the start of the test, RTO No. 8, located behind the biological shleid, failed.
The instrument spiked high, then read high.
The failure was noted and locked out approximately one hour forty minutes prior to the measure phase.
The effect of this instrument failure on the instrument error reported in section 8.3 of this report is minimal.
The system accuracy uncertainty becomes 0.1801 wt %/ day and the system repeatability uncertainty becomes 0.0265 wt %/ day for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test.
j i
i i
)>
i 1490H/
.F.6 AS FOUND TYPE A TEST RESULTS The following table summarizes the results of all type 8 and C testing, as well as the IPCLRT results to arrive at an "As found" type A test result.
Since the total is mors than the 0.750 wt %/ day, the present schedule of performing a type A test every refuel outage must be maintained.
SUMMARf 0F ALL CONTAINMENT LEAK RATE TESTING CURING UNIT NO REFUEL OUTAGE SPRING, 198_8 AS FOUND (SCFH)
AS LEFT (SCFH)
MINIMUM PATHNAY MINIMUM PATHNAY LEAKAGE LEAKAGE (1) MSIV's 0 25 PSIG 17.28 17.28 (2) MSIV's converted 27.30 27.30 to 48 PSIG*
(3) All Type C Tests 1511.84 64.94 (Except MSIV's)
(4) All Type B Tests 12.5 12.2 TOTAL (2 + 3 + 4) 1508.92 121.72 (1) Type A Test Integrated Leak Rate Test) 0.4155 wt %/ day (2) Upper Confidence Limit of Type A Test Result
- 0.4621 wt %/ day (3) Correction for Unvented Volumes During Type A Test 0.0788 wt %/ day (4) Correction for Repairs Prior to Type A Test 2.956 wt %/ day (1568.92 - 121.72)
(As Found - As Left) 489.59 (5) Correction for Change 0.000 wt %/ day in Sump Levelt TOTAL (2 + 3 + 4 5) 3.497 wt %/ day (As Found ILRT Result)
REFERENCE ORNL - NISC - 5, Oak Ridge National Labor & tory, Aug. 1965, page 10,55, 1490H/
o APPENDIX A TYP," 8 AND C TESTS Presented herin are the results of local leak rate tests conducted on all penetrations, double-gasketed seals, and Isolation valves since the previous IPCLRT in October 1986.
Total leakage for double gasketed seals and total leakage for all penetrations and isolation valves following repales satisfied the Technical Specification limits.
1490H/
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APPENDIX B TEST CORRECTION FOR SUMP LEVEL CHANGES s
l 1
i i
4 4
i l
l s
f 1490H/
47
The total tire measured leak rate, given by the functional reauirements soecification Ceco Generic ILRT Computer Code Cocument IO # SSS-38-002 Dated April 1, 1988 (see Appendix C), assumes that the containment free air space is 280,327.5 ft3 at a water level in the reactor of 35, torus water level is zero, and that any charige in reactor water level is due to a water leakage from the containment changing the free air volume.
If the water leakage is from the containment and due to the operation of the shutdown cooling mode of RHR to maintain reactor water temperature, this leakage would not be representative of accident conditions when shutdown cooling would be isolated.
During the stabilization phase of the test considerable effort went into rcpucing the rate of level decline to approximately 0.45 inches / hour (11.25 fth 5r or 1.10 GPM) that was experienced during the test.
Since the leakage coulc not be reduced further and level indication for the suppression pool L
indicated that most of the water leaving the reactor was not entering the suppression pool, but leaving contalement, the computer program option for including the vessel level in the leak rate calculation was selected.
The test verification during the induced phase of the test demonstrates the accuracy of this model and the cnange was completely explained to the NRC inspector witnessing the test.
A hind calculation, using a comp 1ete water balance, is included in this Appendix to show that the leak rate reported is not significantly a#fected by a more detailed analysis. including changing subvolume free at space due to water leaking from the reactor vessel to the drywell sumps and suppression pool.
Toperforma1/$kratecalculationwithachangingcontainmentfreeair space, the dry air mass for each containment $Ubvolume is calculated using the following equation:
Hg - 2.6995 X Pi XVi (Tj + 459.69) where Pt = dry air pressure in ith subvolume, Vt = free air space in the ith subvolume, and i = average temperature in the i th subvolume.
The total containment dry air mass is given by the sum of the dry air masses for all of the subvolumes.
11 Ht
{ wg i=i 1490H/
The computed leak rate till be the total time leak rate an6 is given by:
L - - 2400 X W1 - W*
t
~
H W*
where W* = dry air mass of the containment at the start of the test.
Wt = dry air mass of the containment at time t.
H = duration of the test from start to time t in hours, and Lt = total time leak rate at time t.
There are 3 subvolumes to consider in evaluating the effects of water leakage from the vessel:
the vessel itself (subvolume 11), the suppression pool (subvolume 10), and the subvolume for the drywell equipment drain sump (0WE05) and the drywell floor drain sump (OWF05) (subvolume 9).
Anv water leaking from the vessel in excess of that added to the sumps and suppression pool will be assumed to have leaked from the containment thrcugh the shutdown cooling mode of RHR.
DATE TIME DWFDS*
DWEOS*
~
06/21/88 0300 10 8.0 06/14/88 0315 24.0 6.2 Rate of level change 0.290 0.0373 (in/hr) kate of frte air vol
-1.108 0.142 change (ftJ/hr);
- The sumps are assumed to have filled at a constant ratt wuring the period when the containment was fully pressurized.
Each sump holds 1200 gallons and is 42" deep.
The following table gives the extrapolated values of the subvolume free air spaces using the above data:
6 HOUR TEST INDUCE 0 TEST SUBVOLUME t=0 yj vg t=6 t0 yg t=3 NO. (1)
Vi 1
10.550 10,550 10,550 10,550 2
9,596 9,596 9,596 9,596 3
10,990 10.990 10,990 10,990 4
3,783 3,783 3,783 3,783 5
24,125 24,125 24.125 24,125 6
32,265 32.265 32,265 32,265 7
27,6 8 27,618 27,618 27,618 8
26.071 26,071 26.071 26,071 9'
8,808 8,802 8,800 8,797 10*
119,580 119,658 119,700 119,714 11' 5,146 5,215 5,235 5,266 f
1490H/
49-
t t
i
= 8,901
,f
- V9 DWF05 X 1200 X.13368 !-1 0HE05 X 1200 X.13368 l
( 42
/ \\ 42
/
3 V o = 119,268 - 863.75 (ft ) X Torus level (in) i in V11 = 6571.0 - 25(Level -35)
Using the subvolume vapor pressure, subvolume temperature, and the subvolume free air space, the dry air mass for each subvolume can now be calculated.. The following table gives the necessary data for the start of the test as 04:05:31 on 06/1J/88(Data Set No. 181).
ORY AIR SUBVOLUME SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS NO.
(PSI)
(PSIA)
'F (Ibs, mass) 1
.473 63.620 104.456 3211.72 2
.482 63.611 110.334 2890.76 i
3
.482 63.611 109.135 3317.68 4
.482 63.611 109.428 1141.43 5
.494 63.599 106.536 7314.94 6
.496
' 63.597 101.419 9871.98 7
.458 63.635 96.697 8526.97 8
.443 63.650 86.329 8204.11 9
443 63.650 87.720 2764.68 10
.481 63.612 83.287 37,818.08 11 2.264 61.829 130.436 1455.46 1
11 N'
I Wi.86,517.81 11 The following table gives the necessary data for the end of the 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test at 10:06:43 on 06/13/88 (Data Set No. 218).
DRY AIR SUBVOLUME l
SU8 VOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS i
NO.
(PSI)
(PSIA)
'F (1bs. mass)
I i
1
.458 63.522 102.829 3216.05 2
.467 63.513 109.441 2890.84 3
.467 63.513 109.030 3313.18 4
.467 63.513 109.397 1139.73 5
.481 63.499 106.680 7301.59 6
.481 63.499 101.512 9855.14 7
.446 63.534 96.630 8514.46 8
444 63.536 86.203 8191.31 9
.444 63.536 87.616 2758.38 10
.475 63.536 83.043 37,796.08 l
11 2.218 61,762 129.686 1475.25 W6-66,452.01 1490H/
The leak rate for Qhe 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test is:
L6th
- 2400 X 86.452.01 - 86.517.81 6.020 86,517.81 L6hr =.3032 wt % / day (compared to.4072 computed ignoring sump level changes)
The following table gives the necessary data for the start of the induced phase of the test at 12:06:56 on 06/13/88 (Data Set No. 230).
ORY AIR SU8 VOLUME SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS I
NO.
(PSI)
(PSIA)
'F (1bs. mass) l 1
.456 63.463 103.329 3210.21 2
.463 63.456 109.392 2888.49 3
.463 63.456 109.154 3309.48 4
.463 63.456 109.580 1138.34 5
.476 63.443 106.780 7293.86 6
.479 63.440 101.555 9845.23 7
.443 63.476 96.648 8506.41 8
.447
' 63.472 86.206 8183.01 9
.447 63.472 87.621 2754.95 i
10
.475 63.444 83.051 37,772.47 11 2.234 61.685 129.949 1478.40 start H
86,380.85 Induced The following table gives the necessary data for the end of the induced l
phase of the test at 15:17:33 on 06/13/88 (Data Set No. 249).
ORY AIR SUBVOLUME SUBVOLUME VAPOR PRESSURE PRESSURE TEMPERATURE ORY AIR MASS i
NO.
(PSI)
(PSIA)
'F (Ibs. mass) 1 456 63.359 104.369 3199.04 2
.463 63.352 109.674 2882.33 3
.463 63.352 109.394 3302.67 4
.463 63.352 109.883 1135.87 l
5
.477 63.338 106.971 7279.33 6
.478 63.337 101.668 9827.26 7
.442 63.373 96.703 8491.77 i
8
.455 63.361 86.166 8169.30 i
9
.455 63.361 87.740 2748.60 10
.476 63.339 83.148 37,707.63 l
11 2.273 61.542 130.586 1482.11 eiid 86,225.91
[
W Induced
?
[
1490H/ [
t
The leak rate for the Induced phase is L (induced) = - 2400 X (86,225.91 - 86.380.85) 3.177 86,380.85
- 1.3550 wt % / day (compared to 1.3962 computed ignoring sump level changes)
The above calculations show that the leakage from the reactor vessel did not significantly affect the reported leak rate and that the reported values are conservative values with respect to the actual leakage.
1490H/
1 I
i
+
APPENDIX C COMPUTATIONAL PROCEDURE 0
1490H/
O. INPUT PROCESSING.
Calculations perfomed by the software are outlined below:
0.1 Average temperature of soavolume #1 (Tj)
The average of all RTO temps in subvolume #1 1
N T i I
Tj,j N
j-1 where N - The number of RTDs in subvolume #1 0.2 Average dew tem erature of subvolume #1 (Dj)
- The average of all dew cell dew temps in subvolume #1 1
N 0 1-I Oj,j N
j-1 where N - The number of RTOs in subvolume #1 0.3 Total corrected pressure #1, (P )
1 C1 First correcticn factor for raw pressure #1, (from program initialization data set).
Hj second correction factor for raw cressure #1, (from prcgram initialization data set).
Pr1 Raw pressure #1, frem SUFFILE.
P1C1+M1 Pr1 /1000, for 5 digit pressure trcnsmitters P1C1+M1 Pr1 /lC000, for 6 digit pretsure transmitters 0.4 Total corrected pressure #2, (P )
2 C
First correction factor for raw pressure #2, (from progra, initialization data set.
H2 Second correction factor for raw pressure #2, (from crogra, initialization data set.
Pr; Raw pressure #2, frca BUFFILE.
P2C29 Pra/1000, for 5 digit pressure transmitters P2-C2+M2 Prg/1C000, for 6 digit cressure transmitters 54 WP,/COC. 7
~
0.5 Whole Containment Volume Weighted Average Temperature, (Tc)
Approximate N
Method Tc "
E fi Tj i=1 1
Exact N
ft Method I
i=1 I t where:
fj The volume fraction of the ith subvolume N - The total # of subvolumes in containment 0.6 Average Vapor Pressure of Subvolume 1 (Curve fit of ASME steam tables.) (Pvj)
Pvj-0.01529125+g.0016g34760 1
- 1.44734 X 10-
- 2.28128 X 10-9 (D j )4 + 7.081828 X 10-7 (0g)3 (0 )
+ 3.03544 X 10-II (D j )5 1
0.7 Whole Containment Average Vapor Pressure, (Pv )
c Approximate N
Method Pvc=
I ft Pvg l
i1 Exact N
ft Pvj Method Pvc = Tc I i=1 Tj N
The total of subvolumes in containment f. Volume fraction of the ith subvolume t
0.8 Whole Containment Average Dew Temperature, (Oc)
Approximate N
Method De.
I ft Dj i.1 Eract Method The whole containment average vapor pressure, (Pv ) calculated with the exact method is used to e
find De.
An initial value of De is gues ud anc used with the equation in D.6 to calculate Pv.
i This value is then compared to the known value frc, l
D.7.
A new value of De is guessed and the prc:ess is repeated until a value of De is found that results in a calculated value of Pv that is c
=ithin.0001 psia of the value frem'D.7.
t 55 WP./DCC. 7
o 0.9 kverage to'tal containment pressure,(P)
P-(F1+P2)/2 Average total containment dry air pressure, (P )
d Pd P-Pvc 0.10 Total Containment dry air mass, (H)
Type 1:
M=
R Tc where: R Perfittt gas constant, Vc - Totcl containment free volume.
Type 2:
Type 2 dry air mass accounts for changes in Reactor Vessel level.
for uncorrected dry air mass, (Type 1) the below definitions apply.
N VcI Vj and ft - Vj/Ve i=1 where Vj is the user entered free volpme in subvolume 1.
For corrected dry air mass, (Type 2) the same definitions for V c and f j apply, except that one of the Vj s is corrected for changes in vessel level.
If k is the subvolume number of the corrected subvolume then:
Vg - V o - a(C - b) k a is the number of cubic feet of free volume per inch of vessel level.
b is the base level of the reactor vessel, in inches.
C is the actual =ater level in the reactor vessel, in inches.
Vko if the volume of the subvolume k when C ecuals b.
The
.ume fractions (fj) are then cilculated with the corrected volume, a.d all other calculations are subsequently performed as previously specified for Type 1 dry air mass.
56 WP+/COC. 7
D.11 Leakrate C'alculations using Hass-Plot Hethod:
This method assumes tnat the leakage rate is constant during the testing period, a plot of the measured contained dry air mass versus time would ideally yield a straight line with a negative slope.
Based on the least squares fit to the data obtained, the cal:ulated containment leakage rate is obtained from the equation:
M = At + B Where H = containment dry air mass at time t (Ibs.)
B = calculated dry air mass at time t=0 (Ibs.)
A = calculated leakage rate (Ibs/hr) t = time in,terval since start of test (hours)
B H
(lbs) t (hours)
The values of the constants A and B such that the line is linear least squares best fitted to the leak rate data are:
NI(ti)(Hj) - (Iti) (I Hj)
A=
NI(t))2 - (Itj )2 IHj AItj B=
N j
57 hP+/ DOC. 7
By definition, leakage out of the containment is considered positive leakage. Therefore, the statistically averaged least squares containment leakage rate in weight percent per day is given by:
L = (-A) (2400)/B (weight %/ day)
In order to calculate the 95% confidence limit of the least squares averaged leak rate, the standard deviation of the le1st squares slope and the student's T-Distribution function are use: as follows:
1/
1 NI(Hj)2 (IMj)2
/2 (2400) (weight *.
-A o.
__(N-2)
NI(tt)2 (Itj)2 8
UCL - L + o (T) 1.6449(N-2) + 3.5283 + 0.85602/(N-2) where T-(N-2). 1.2209 - 1.5162/(N-2)
N Number of data sets test duration at the ith data set (heurs) ti standard deviation of least squares slope (weight %/ day) e T
Value of the single-sided T-Distribution function with 2 degrees of freedom calculated leak rate in weight %/ day L
UCL 95% upper confidence limit
(%/ day)
B calculated containment dry a eass at time t 0 (lbs.)
=
0.12 Point to Point Calculations l
This method calculates the rate of change with respect to time of dry air mass using the Foint to Point Method.
t 1
38 hP+/DCC, 7
For every data set, the rate of change of dry air mass between the most recent. (ti) And the previous time (tj.j) is calculated using the two point method shown below:
2400 Mi=
(I - M /M -1) l i
)
Then the least square fit of the point to point leakrates is calculated as described for dry air masses in section 0,11 0.13 Total Time Calculations This method calculates the rate of change with respect to time cf dry air mass using the Total Time Method Initially, a reference time (tr) is chosen. For every data set the rate of change of dry air mass between tr and the most recent time, tj is calculated using the two point method shown belcw.
2400 Mi =
(1 - Hj/M )r (t -to t
Then the least squares fit and 957. UCL of the Total Time leaktates are calculated as shcan below:
I Aj I(t))2 - I t) I Aj ti N I (tt)2 _ (g ;g)2 A.
-( N I tj Nj - I ti ! Sj )
N I /tj)2 - (I tj)2 L=
B + At 1.6449(N-2) + 3.5283 + 0.85602/(N-2)
(N-2) 1.2203 - 1.5162/(N-2)
+
Note: N is the number of data sets minus ene.
59 o./ DOC 7 n
I (tp - I (t ) / N)2 i
N I (t )2
-( I tg )2 /N t
/
/
/
F
// I (Hg)2 - B I A. A I $j tj o,/
\\/
N
\\/
UCL = L + Te
=
Note: This equation is calculated for information only frem the start of the test up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, then it beccmes the official leakrates for future times.
0.14 BN-TOP-1 This method calculates the rate of change with respect to the time of dry air mass using the Total Time Method.
Initially, a reference time (tr) is chosen. For every data set the rate of change of the data ite"t between tr and the most recent time (ti) is calculated using the two point method shown below:
2400 Mg -
(1 - Hj/M )r (tj - tr)
Then the least squares fit of the Total Time leakrates and the BN.TCP-1 95% UCLs are calculated as shown telow.
( !At (t )2 I tt I$1 ti) i
~
N I (tj)2 - ( I tj )Z Note: N is the haber of data sets minus one, 60 n?./CCC. 7
(NItt At I ti I At)
~
N I (t )2 - (I tt)2~ ~
t L=
B + At T. 1.95996 + 2.37226 2.8225
.+
(N - 2)
(N - 2)2 I
(tp - I (tt) / N)2 7,
N I (tt)2 - (I tt)2 /N
/
/
/
T
'/
\\/j
\\/j/ I (A )2 - B I A - A I A tt o=/
t t
t N
UCL = L + Te Note: This equation is calculated for infor.aation only frem 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 becones the official leakrates for future times.
0.15 Temperature stabilization checking per ANSI 56.8 '981 Ti Heighted average containment air temperature at hour 1.
Tj,n Rate of change of weighted average containment air temperature over an n hour period at hour i, using a two point backwards dif ference method.
T i
T j,n.
i - T -n l
n t
F i
I t
i 61 hP / DOC. 7 I
21 is the AN'SI 56.8-1981 Temperature stabilization criteria at hour I.
Zj - l Tj,4 Tj,1 l 1 must be 1 4 Per ANS: S6.8-1981, 2 must be less than or equal to 0.5 0F/hr NOTE: If the data sampling interval is less than one hour, then:
Option #1 Use data collected at hourly intervals Option #2 Use average of data collected in previous hcur for that hours data.
0.16 Calculation of Instrument Selection Guide, (ISG)
ISG _2400_
/ 2 (ep/p)Z + 2 (e /I)2 + 2_ (ed p)2 t
\\/ N Nr
/
r p
Nd where: t is the test time', in hours p is test pressure, psia T is the volume weighed average containment temperature, OR N
is the number of pressure transmitters N
is the number of RTOs Nd is the number of dew cells ep is the combined pressure transmitters' error, psia er is the ccmbined RTOs' error, OR ed is the comb;ned dev cells' error, oR
/
ep = \\/ (Sp)2, (RPp, RSp)2 where: Sp is the sensitivity of a pressure transmitter
)
RP is the repeatability of a pressure transmitter RS is the resolutien of pressure transmitter er.
/
\\/ (Sr)
. (RPr
- RSr)2
.here: Sr is the sensitivity of an RTO RPr is the repeatability of an RTO RSp is the resolutien of an RTO 62 h?+/DCC. 7
aPy ed =
/
\\/ (S )2. (ppd + RSc)2 aid Td d
.here:
Sq is the sensitivity of a dew cell RPd is the repeatability of a dew cell RSd is the resolution of a dew cell AP change in vapor pressure y
ATT Td change in saturation temperature The above ratio is from ASME steam tables and evaluated at the containment's saturation temperature at that time.
0.17 BN-TOP-1 Temperature Stabilization Criteria Calculation A.
The rate of change of temperature is less than 1 'F/Hr averaged over the last two hours.
K1 lTj - Tj.)]
K2-7.1 - T -2l 1
i K1 and K2 must both be less than 1 to meet the criteria listed in A.
S.
Jhe rate of change of temperature changes less than 0.5 F/ hour / hour averaged over the last two hours.
K) = (Tj - Tj.1)/(tl - ti.1) 2. (Tg.)l-T -2)/(ti.)
K i
- ti-2)
Z=
(K)
- K )/(tj - ti.1)]
2 Z eust be less than 0.5 to meet the criteria listed in B.
0.18 Reactor Vessel Free Volume Mass Calculation As shown in secticn 0.10, the free volume of the Reactor Vessel subvolume e is given by the belcw equation.
/,. V,o - a (c-b)
The dry air mass in subvoly e r can then be written as:
Mc. 144(P-Pve)Vc/Ric l
Where:
Mc is the dry air mass in subvolv?e r,
(Ibm)
R is the gas constant of air l
T, is the average temperature Of subvolume
- r. (og) l j
i$c is the average va:Or pressure of sutvolume c.
(pisa)
P is ne average contain ent pressure, (psia) l 3
V, is the f ree air volute in subol.'.me c.
(ft )
l n?+/DCC. 7 e3 I
F L.
0.19 Torus Free Volume Calculation Free volume calculations of the Torus rely upon narren-range Torus water level inputs.
These values range between plus and minus five inches.
It is assumed that the Torus subvolume free air volume is that ;ubvolume's volume when the Torus level equals zero.
The user may enter three constants to model the variation of Torus air volume with water level.
The equations for Torus free volume in subvolume t are given:
3 Vt*Vo-(al+bl+cL})whenL10 t
t*Vto + (-al + bl2 -cL when Li 0 V
The dry air mass in subvolume t can then be written as:
Mt " I44 (5 E ) V /RT vt t
t hhere:
Mt is the dry air mass in subvolume t, (lbm)
P is the average containment pressure (psia)
Pvt is the average vapor pressure of tubvolume t (pisa) 3 Vt is the free volume in subvolume t, (ft )
R is the gas constant of air Tt is the average terrperature in subvolume t (OR)
L ic the Torus level (inches) a,b,c are Torus level constants V o is the free volume in subvolume T. hen L equals :ero, t
3 taken frcm standard free volume inputs, (ft )
E. C'UTPUTS E.1 CUTFUT DEVICE TYPES:
The belcw output devices shall be supported.
There are no sprcial constraints on output device locations.
PRINTERS:
PRIME High Speed Line Printer C(ICATA 2410 CKICATA 93 LAl20 PLOTTERS:
Henlet Packard 7475A S.5" X l
Hewlet Packard 7H5A 8.5" X l'"
tie =let Packard 7535A 11" X 17" CRTs:
Wyse Hy75 i
View Point 60 Ampex Dialogue 50 & Si l
PRIME PT200 GRAPHICS TE.iHINALS:
RamTech 6:00 RamTecn 6:11
'ektrcniv 4107 l
- iktrenti 4:C3 Te(trenis 4014 i
g
.?.100:. 7
V t
q.
4 P
APPENDIX 0 INSTRUMENT ERROR ANALYSIS
.I L
t l
l I
t I
L l
l i
i I
t i
i i
i i
i 1490H/
65-L i
__ - -.. ~ - ~. _. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _.. _ _.,
IPCLRT SAMPLE ERROR ANALYSIS FOR SHORT DURATION TEST A.
ACCURACY ERROR ANALYSIS Per Tepleal Report BN-TOP-1 the measured total time leak rate (M) in weight percent per day is computed using the Absolute Method by the formula:
T P M (% / OAY). J400
- 1 I
N (1)
N 1 where: Pi
= total (volume weighted) containment dry air pressure (PSIA) at the start of the test; PN
- total (volume weighted) containment dry air pressure (PSIA) at data, point N after the start of the test:
H
= test duration from the start of the test to data point N in hours; T1
= containment volume weighted temperature in 'R at the start of the test; TN = containment volume weighted temperature in 'R t.t the data point N.
The following assumptions are made:
A A
l Eg. PN.P where P is the average dry air pressure of the containment (PSIA) during the test; A
A it. Ty. T where T is the average volume weighted primary containment air temperature ('R) during the test; 1
Pg. PN where P 15 the total contain ent atmospheric pressure l
(PSIA);
1 l
Pyg Pyg Where Py is the partial pressure of water vapor in l
the primary containrent.
l I
l 1490H/
66-
r Taking the partial derivative in terms of pressure and temperature o9 (1) equation and substituting in the above assumotions yleids the following equation found in Section 4.5 of SN-TOP-1 Rey, 1:
e e ~%
eg
+ 2400
- 2 ( A >2 + 2 ( 1 )2 H
A A
P T
where ep = the error in the total pressure measurement system.
I i
t ep.
+ ((epT)# + ('PV)3 I II2 ept. (instrument accuracy error) / / no. of inst, in reasuring total containment pressure; epy (Instrument accuracy error) / / no, of inst. In reasuring vapor partial pressure; et * (instrument accuracy error) / / no of inst in measuring containment temperature; eg = the error in the measured leak rate; H = duration of the test.
NOTE Subvolume #11, the free air space above the water in the reactor vessel, is treated separately from the rest of the containment volume.
The reason for the separate treatment is that neither the air temperature or the partial pressure of water Napor is measured directly.
The terperature of the air space is assured to be the temp:rature of the reactor water, as measured in the shutdown cooling or clean-up demineralizer ptptng before the heat enchangers.
The partial pressure of water vaccr is computed assuming saturation conditions at the temperature of the water. Volume weighting the errors for the two voluees (Subvolute ell and Subsolumes #1-10) is the method used.
1490H/ -
! i..
8.
EQUIPMENT SPECIFICATIONS FL0hMEiER THERMCCOUPLE INSTRUMENT RTO ('F)
' PPG (PSIA)
DEWCELL (*F)
(SCFM)
(*F)
Range 50-150 0-100 20 - 104 0.927-11.23 0 - 600 Accuracy 2 50
- .013
.1 z.111 20 2
Receat-abl1ity
.10
- .001
.50 2 02
. 10 C.
COMPUTATION OF INSTRUNENT ACCURACf UNCFRTA!NTY 1.
Computing " et Volume Fraction for Volume #11. 02344 Volume Fraction for Volumes #1-10. 97656 ei = 1 (.97656
.50 +.t2344
- 2_
)
/29
/1 er 3 1376'R 2.
Computing " 'pf "
'p r. 1.:2M
/T
'pr. 3 0106 PSIA 3.
Coeputing " 0py "
i At a dewpoint of 65'F (assumed), an accuracy of. I'F correspo.nds to. 011 PSIA.
For suevolume all at an averate temperature of T
140 F, an accuracy of 3 2*F corresponds to.
150 PSI.
'py.. ;.97656. 011,.02344 *.150 >
/10
/1
'py.
.0063 PSIA 4.
Ceeputing " en a
ep = 1 ( (.0106)3. (.0069)* 11/2 ep. 2 0126 PSIA 14908/ - _ _ - _ _ _ _ _ _ _ _ - _ - _ - _ _ _ _
m p
Computingtotalinstrumentaccuracy.uncerrainhy"eg^"
5.
4
'/ '
A 7
i 2400
- 2*I.0126I2'+2*I 0.1376' 2
eM H
63.5 j (552.6j A-assuming'P = 63.5 PSIA A.
~
T = 552.6*R Therefore, for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test (H),
A eM = 1 1801 wt % / OAY 0.
COMPUTATION OF INSTRUMENT REPEATABILITY UNCERT/.INTY 1.
Computing " et "
eT " t O
/30 eT " 1 0183*R 2.
Computing " epT "
ePT " 1 001
/g ePT
- 1 0007 PSIA 3.
Computing " epy "
epy = 1 (.97056 *.006 +.02344 *.008 )
{
'/ j o
/1 epy =
.0020 PSIA 4.
Computing " ep "
ep w ( (.0007): + (.0020)2 1 1/2 e,. = 1 0021 PSIA 1490H/ -
~
g
~
O
- O n
~
p
.5. ^ Computing the total Instrument repeatability uncertainty " eg".
,o R
X
~
eH = 2400
- 2f.002)(2 +2 0.0183h2 f
c 63.5j
'H 552.6 i i
F Therefore, for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test,
.R eg = 1 0265'wt % / DAY E.
COMPUTING TOTAL INSTRUMENT UNCERTAINTY
. eg.
2 ues.. (eb. 2 v2 og - 2 2
- C (.1801)2 +-(.0265): 31/2
~
SM - i.3641 weight % / OAY for a 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> test.
.1 1490H/
~
1 APPENDIX E BN-TOP-1, REV 1 ERRATA 1490H/...
APPEND 8X E BN-TOP-1, RIV. 1 ERRATA the Station uses the general test method outlined ovt:ed topical report.' The prLaary difference between that sethod
, Rev. t previously used is in the stattstical analysts of the sessured lean rate and the ones ata.
Without making any judgments concernts: the validity of this test The intent bare is not to change the test sethod, butcertain e
- metaed, covered.
method to a sachematically precise sanner that allows tes implementa rather to clartty the errors are listed below.
The EQUATION 3A, SECTION 6.2 Reads:
L. = A
- 3 t t
t Should Read:
Lg=Ag g
g
+S t
Reason:
The calculated leak rate (L ) at ttze t ts computed using the regression line e nstants A, 3 The summation stkas kn(equation 6 are computed using equations 6 apd 7).
a defined as I
- I, where n is the number of data sets up unt
121 time t,.
The regression late constants enante caca :tme a new dafa set is received.
linear function of :tme.
tha calculated leak rate.s a::
2 PARAGRAPM TOLLC9ING EQ. 3A, SECT:0N 6.2 Reads:
The deviation of :he measured lean rate (M)ft:m tae :a.':2.'a:e:
leac rate (L) ts snovu grapnacal'y :n itgure A.1
'a Appen: x A and ts expressed as:
Oeviation a M.
L.
I t
$bould Read: The deviation of the measured lean rate (M ) fr:m ne regress :-
' '. n e ( N, ) is snown gripnt:4'ly m it gure A '.
in Appen:tx A s.- '
.5 I
expressdd as :
i Ceviation : M
-N t
-cere N = A 3
t p
p i.
A 3
Regresst:n line constants ::mpu:ed fr:m a'.'
=
- 2:2 sets avatlaole ft:3 :se start of the tes: :: :e
'ast data set at time :
t, a
tme from tr.e 2: art of :..e tes: to :ne t:n :a 4 se.
72
Reasca:
Tho eticulated leak race as a funceton of ttco durtig the test is bastd on a regresston Line.
The regression lius constanta, A and 3. are g
k changing as each additional data set ts recetved.
Equation M is ased later in the test to.:rrpute
'he upper ceifidence limit as a funettee. of tt.me.
For the purpese of this calculation, it ts toe deviation from the last computed regressten itse at time c that is taportant.
EQUATQl14, SECTION 6.2 Reads:
SSQ = I (M I, ) 2 should Read:
SSQ = I (M N )2 Reasod:
Same As'Above EQUATION 5, SECTION 6J Reads:
SSQ = I ( M (A + 8t )]
Should Amad:
SSQ s I ( M (A
3 *ti)]2
+
i P
P Reason:
Same As Above EQUATION A.50VE EQUATION 6, SECT /Cd 6.2 (t.
t)(M. - M)
Reads:
3s t
t I(c. - t)d i
I{(*
)(M
' Should Reac:
- 3. s t
i ~ I(t - I)3 i Reason: Rsgression lime constant 3, changes over ttme is a function of e ) as eaca Iddtttonal data set is received. 3Er af "t" left out :f ten:mt..at:: Suassation signs orut tted. EQCAT'.i Q _ 510 TION 6.2 Reads: 3=* t i n 4t, ' (* t,,- r should Read: 3 = nit M. (I t) (1 M ) 1 t l a It 3 (I tt,' t Reason: Same As Above 73
EQUATICK ?, SECTION 5.2 Reads: A=$-8t Should Reed: Ag*5-8 t g Reason: Same As Above EQUATION 10, SECTION 6.2 Reads: A = N d ) II E ) * (I L() (I t( M() i i a I c.3 (I e ja t i s. (I *1 ) (I C ) Should Reed: (I t() (I C( M() A( 1 i aIe3 (I e ja Reason: Same As Above EQUATION 13, SECTION 6.3 Reads: e2 [g. 1, (t, t)2 2 a s c)3] (t i Should Read: c 32 [t. 1. (t, - t)2 2 1 I (t - T)E g where t = time f ram the sta rt of the test of the last data E for which the standard deviation of tae measurec set leak rates (M,) fres :se regression itse (N ) is betas computed, t a g tsae from tae start of tae test of tae L IA fata set; 3 = sumber of data sets to tue : a I
- I and 181 I
I 1*, a a L Reason: Appears to be error is editing af the report. Report does a poor job of deftsing vartaoles. l 74
EQUATION 14, SECTION 6.3 s ( 1 + 1 + (C, )* j
- t Reads:
a= .)3 se g ( 1 + 1 + (E ) Should Read: a= p ) I (t t)2 Reason: Same As Above EQUATION 15, SECTION 6.3 Reads: Confidence Limit = L : 7 Should Read: Confidence Limits a L: 7xe where L = calculated leak rate at tiae t T= T distribution value based on n, the number :f data sets recetved up until time t p, oa standard deviation of seasured leak rate values (M ) about the regressten line based on data fr:m t the start of the test untti time t,. Reason: Sase As Above EQUATION 16, SECTION 6.3 Reads: UCL = L * ! l Should Read: UCL = L * !
- 7 Reason:
Same As Above EQUATICN 17, SECTION 6.3 Reads: LCL = L - T Should Read: LCL=L Tt : Reason: Same As Above 75
O APPENDIX F TYPE A TEST RESULTS USIN7 NASS - PLOT HETHOD MEASURED LEAK RATE PHASE l l 14909/.
i TYPE A (EST RESULTS p USING MASS - PLOT METH00-MEASURED LEAK RATE PHASE DATA 0ATA SET TIME ' TEST ORY AIR LEAK RATE, 95% UP CONF SET # DAY HH MM SS TIME, (HR) MASS, (LBM) (%/0) LIMIT, (%/0) 181 165 04:05:31 0.000 0.86622156E+05 i 182 165 04:15:33 0.167 0.86619172E+05 l-183 165 04:25.33 0.334 0.86617172E+05 0.4136E+00 0.8110E+00 184 165 04: 35:35 0.501 0.86615703E+05 0.2545E+00 0.4720E+00 l 185 165 04:45:35 0.668 0.86611687E+05 0.4051Ee00 0.4926E+00 l 186 165 04:55:36 0.835 0.86610281E+05 0.3950E+00-0.4483E+00 187 165 05:05:39 1.002 0.86606187E+05 0.4217E+00 0.4690E+00 188 165 05:15:39 1.169 0.86605937E+05 0.4012E+00 0.4422E+00 l 189 165 05:16:01 1.175 0.86605937E+05 0.3918E+00 0.4273E+00 190 165 05:26:04 1.343 0.86601875E+05 0.4011E+00 0.4318F+00 191 165 05:36:05 1.509 0.86597359E+05 0.4237E+00 0.4594E+00 l 192 165 05:46:06 1.677 0.86595640E+05 0.4316E+00 0.4623E+00 l 193 165 05:56:09 1.844 0.86593906E+05 0.4312E+00 0.4569E+00 194 165 06:06:09 2.011 0.86590750E+05 0.4340E+00 0.4559E+00 195 165 06:16:10 2.178 0.86590531E+05 0.4245E+00 0.4455E+00 196 165 06:26:10 2.344 'O.86585578E+05 0.4282E+^0 0.4467E+00 197 165 06:36:14 2.512 0.86583656E+05 0.4282E+00-0.4444E+00 198 165 06:46:15 2.679 0.86579734E+05 0.4326E+00 0.4474E+00 199 165 06:56:15 2.846 0.86578969E+05 0.4303E+00 0.4437E+00 200 165 0~/:06:15' 3.012 0.86577422E+05 0.4260E+00 0.4386E+00 201. 165 07:16:16 3.180 0.86573734E+05 0.425]E+00 0.4368E+00 202 165 07:26:20 3.347 0.86570187E+05 0.4272E+00 0.4375E+00 203 165 07:36:21 3.514 0.86568312E+05 0.4271E+00 0.4365E+00 204 165 07:46:25 3.682 0.86567047E+05 0.4246E+00 0.4335E+00 l 205 165 07:56:25 3.849 0.86563953E+05 0.4236E+00 0.4318E+00 206 165 08:06:26 4.015 0.86562000E+05 0.4220E+00 0.4296E+00 207 165 08:16:28 4.183 0.86559828E+05 0.4201E+00 0.4274E+00 208 165 08:26:30 4.350 0.86555844E+05 0.4205E+00 0.4273E+00 209 165 08:36:33 4.517 0.86554078E+05 0.4199E+00 0.4262E+00 210 165 08:46:33 4.684 0.86551562E+05 0.4194E+00 0.4253E+00 211 165 08:56:35 4.851 0.86547765E+05 0.4204E+00 0.4259E+00 212 165 09:06:35 5.018 0.85646781E+05 0.4196E+00 0.4249E+00 213 165 09:16:36 5.185 0.86545765E+05 0.4176E+00 0.4229E+00 214 165 09:26:36 5.352 0.86540797E+05 0.4180E+00 0.4230E+00 215 165 09:36:37 5.519 0.86539344E+05 0.4175E+00 0.4222E+00 216 165 09:46:39 5.686 0.86538297E+05 0.4160E+00 0.4207E+00 217 165 09:56:41 5.853 0.86534469E+05 0.4156E+00 0.4201E+00 218 165 10:06:43 6.020 0.86533672E+05 0.4141E+00 0.4186E+00 1 1490H/ _ _ - _ _ _ _ _ _ _
o TYPE A TEST RESULTS C USING MASS - PLOT METHOD INDUCE 0 LEAK PHASE DATA DATA SET TIME " TEST ORY AIR LEAK RATE, 95% UP CONF SET # DAY HH MM SS TIME, (HR) . MASS, (LBM) (%/0) LIMIT, (%/0) 230 165 12:06:56 0.000 0.86450312E+05 ~231 .165 12:16:57 0.167 0.86441875E+05 232 165 12:27:00-0.335 0.86431859E+05 0.1529E+01 0.2176E+01 233 165 12:37:04 0.502 0.86424750E+05 0.1437E+01 0.1623E+01 234 165 12:47dO5 0.669 0.86415062E+05 0.1453E+01 0.1542E+01 235 165 12:57:05 0.836 0.86406265E+05 0.1640E+01 0.1513E+01 236 165 13:07:06 1.003 0.86401953E+05~ 0.1383E+01 0.1479E+01 237 165.13:17:06 1.170 0.86394719E+05 0.1336E+01 0.1423E+01 238 165 13:27:08 1.337 0.86385047E+05 0.1332E+01 0.1398E+01 239 165 10:37:10 1.504 0.8637E812E+05 0.1332E+01 0.1383E+01 240 165 13:47:14-1.672 0.86368422E+05 0.1334E+01 0.1376E+01 241 -165 13:57:15 1.839 0.86359906E+05 0.1339E+01 0.1374E+01 242 165 14:07:16 2.006 0.86351609E+C1 0.1343E+01 0.1372E+01 243 165 14:17:16 2.173 0.86343593E+05 0.1345E+01 0.1370E+01 .244 165 14:27:20 2.340 0.86335469E+05 0.1347E+01 0.1368E+01 245 165 24: 37:25 2.508 'O.86327031E+05 0.1349E+01 0.1368E+01 246 165 14:47:28 2.676 0.86318625E+05 0.1351E+01 0.1368E+01 247 165 14: 57:29 2.843 0.86307047E+05 0.1363E+01 0.1382E+01 248 165 15:07:31 3.010 0.86300469E+05 0.1367E+01 0.1384E+01 249 165 15:17: 33 3.177 0.86290515E+05 0.1374L+01 0.1391E+01 1490H/ -
MEASURED LEAK RATE PHASE GRAPH OF CALUCLATED LEAK RATE AND UPPER-CONFIDENCE LIMIT MASS PLOT LEAKRATES VS TIME 0.90 1 0.80 Allowed Leck R - - - - - - - -, - - - - - - - - _ _ _..a t e 0.70 1 1 5 1 0.60 g .l o I 0.50 95 x UPPER CONFl0ENCE LIMIT ~ - 0.40 -V CALCULATED LEAK RATE O.30 l l i 0.20 3.03 3.93 4.83 S.73 6.53 0.33 1.23 2.13 l HOUR 5 f FIGURE F-1 1490H/ -79
i. INDUCED LEAKACE PHASE GRAPH OF CALUCLATED LEAK RATE MASS PLOT LEAKRATES VS TIM E 1.80 UPPER BOUNOS 1.70 1.60 i!!i Target ' Leak Rete 1.50 = 44 1.40 CALCULATED LEAK RATE 1.30 7 LOWER BOUNDS 1.20 I i 1,10 l 0.33 0.73 1.13 .53 1.93 2.33 2.73 3.13 HOURS ) FIGURL F-2 1490H/.. _ _ - _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _,}}