ML20084F709
| ML20084F709 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/10/1984 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20084F695 | List: |
| References | |
| ID-TS-4C-4D, NUDOCS 8405040288 | |
| Download: ML20084F709 (56) | |
Text
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, ID/TS-4C,4D i'
4 1 .! REACTOR CONTAINMENT BUILDING i INTEGRATED LEAK RATE TEST ) i 1
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1 i I 4 9 l QUAD-CITIES NUCLEAR POWER STATION
; . UNIT TWO FEBRUARY 9-10, 1984 i
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s TABLE OF CONTENTS PAGE i TABLE AND FIGURES INDEX. . . . . . .... .. . .. . .. . . . . .3 ~ INTRODUCTION . . . . . . . . . . . .... . . ... ... . . . . .4 f 4 A. TEST PREPARATIONS A.1 Type A Test Procedures . . ...... ... . .. . . . . .5 A.2 Type A Test Instrumentation. .. .. ... . . . . . . . . .5 A.2.a. Temperature . . . ..... . . ... . ..... .9 I A.2.b. Pressure. . . . . . ... . .. .. . . . . . . . .9 A.2.c. Vapor Pressure. . . .... . ... . .. . . . . .10 A.2.d. Flow. . . . . . . ... .. . . . .. . . . . . . 10 i A.3 Type A Test Measurements . ... . . . . .. . . . . . . . .10 i. A.4 Type A Test Pressurization . ..... . . .. . . . . . . .11 B. TEST METHOD B.1 Basic Technique. . . . . .... ... ... .. .. .. . .13 B.2 Supplemental Verification Test . . .. .. . ... . .. . .14 B.3 Instrument Error Analysis. ... .. . ... . .. . ... .14 C. SEQUENCE OF EVENTS C.1 Test Preparation Chronology. ..... ... .... ... .15 C.2 Test Preparation and Stabilization Chronology. .. . .. . .15~ C.3 Measured Leak Rate Phase Chronology. . ..... ..... .'16 ' C.4; Induced Leakage Phase'Chronologyi. . . ... .. .. ... .16 C.5 Depressurization Phase Chronology. . .
..... . . . . . 16 D. ' TYPE A TEST' DATA
~
^D.1 Measured Leak Rate Phase Data . .... ..... .... . 17 D.2 Induced. Leakage Phase Data. ......... ... .. . . . 17
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.s TABLE OF CONTENTS (CONTINUED) I d
PAGE E. TEST CALCULATIONS. . . . . . . . . . . . . . . . . . . . . . . .28 4 F. TYPE A TEST RESULTS F.I Measured Leak Rate Test Results. . . . . . . . . . . . . . .28 F.2 Induced Leakage Test Results . . . . . . . . . . . .. . . .28 F.3 Leak Rate Compensation for Non-Vented Penetrations . . . . .29 F.4 Pre-Operational Results vs. Test Results . . . . . .. . . 30 F.5 As Found IPCLRT Result . . . . . . . . . . . . .. . .. . .31 i 1 APPENDIX A TYPE B AND C TESTS. . . . . . . . . . . . .. . . .32 APPENDIX B SELECTED DATA SETS FOR TYPE A TEST. . . . .. . . .42 1 1 APPENDIX C COMPUTATIONAL PROCEDURES. . . . . . . . . . .. . .48 I 5. t
D 4 TABLES AND FIGURES INDEX PAGE TABLE 1 Instrument Specifications. .. . ... .. . . . . . . .6 TABLE 2 Sensor Physical Locations. .. . ... ... . . . . .7 TABLE 3 Measured Leak Rate Phase Test Results. . .. . . . . . 18 TABLE 4 Induced Leakage Phase Test Results . . . . . . . . . . 23 TABLE A-1 Type B and C Test Results. . . . . . . . . . . . . . . 33 TABLE B-1 Data Set for the Start of the 24 Hour Test . . . . . . 43 , TABLE B-2 Data Set for the Mid Point of the 24 Hour Test . . . . 44 TABLE B-3 Data Set for the Conclusion of the 24 Hour Test . . . 45 TABLE B-4~ Data Set for the Start of the Induced Phase of Test. . .46 TABLE B-5 Data Set for the Conclusion of the Induced Phase . . . 47-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 Statistically. . . .19-Averaged Leak Rate and Upper Confidence Limit FIGURE 4 -Measured Leak Rate Phase - Graph of . . .. . . . . . . 20. Dry Air Pressure FIGURE 5 Measured Leak Rate Phase - .... .... . . . . 21 Total Containment Pressure-FIGURE 6 Measured Leak Rate Phase - Graph -of Volume . . . . . . 22 Weighted Average Containment Temperature
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FIGURE 7- Induced Leakage Phase - Graph of. Statistically . . . . 24-l Averaged Leak Rate and Upper Confidence Limit FIGURE-8 Induced Leakage Phase , Graph of Volume. .. . . . . . .25
- Weighted Average Containment Temperature ,
1 FIGURE 9 Induced Leakage Phase Total. . . . . .. . .....26-Containment Pressure FIGURE 10 . Induced Leakage Phase - Graph of . . . . . .:. . . . . 27 j Dry. Air Pressure t l-i
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l , INTRODUCTION
; This report presents the test method and results of the Integrated Primary
- Containment Leak Rate Test (IPCLRT) .successfully performed on February 9-10, i
1984 at Quad-Cities Nuclear Power Station, Unit Two. The test was performed 1 in accordance with 10 CFR 50, Appendix J, and the Quad-Cities Unit Two Technical
- Specifications.
i f
. This test was conducted using the ANS/ ANSI N45.4-1972, 24 hour Mass Plot method. The calculated leak rate, statistically averaged leak rate, and the
, statistical upper confidence limit were computed in a manner consistent with
- the ANSI /ANS 56.8-1981 standard.
j Simultaneously with the above method, calculations were performed using the i Total Time Leak Rate method of BN-TOP-1, Rev. 1, a Bechtel Corporation Topical l report approved by the Commission for short duration testing. The test duration criteria of BN-TOP-1 were easily satisfied for terminating the test in 10 hours 4 or less. The Commission presently requires adjustments to the IPCLRT result for Type B and C repairs performed during the refuel outage prior to the test. In order to both demonstrate a containment leakage.below the allowable limit and satisfy the "as found" criteria that the adjusted Type A test result be 1 less than 75% of L , it was necessary to perform a 24 hour test. Failure to 4 satisfy the latter* criteria would have made it necessary to perform IPCLRT's on consecutive refuel outages. Without regulatory relief (e.g. a higher "as i found" corrected limit than for the IPCLRT), short duration testing has very ] little advantage to Quad-Cities, except in the circumstance where the test ! will be interpretted as an "as found" failure regardless of the test technique.
- Fortunately, this was not the case for this test. The BN-TOP-1 data is not.
included in this report because it was not used for concluding the IPCLRT. 'l f l i i i I i I l 4-
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5 I SECTION A - TEST PREPARATIONS A.1 Type A Test Procedure The IPCLRT was performed in accordance with Quad-Cities Procedure QTS 150-1, Rev. 10, including checklists QTS 150-S1, S2, S3, S4, S7, S8, S9, S10, S11, j S12 S18, and subsections T1, T2, T3, and T8. Approved Temporary Procedure 2035 was written for the operation of the IPCLRT air compressor and the method
- for pressurizing the containment volume. Approved Temporary Procedure 2036 was written to update QTS 150-S7 (Unit Two valve line-up) for recent modifications to containment attached piping. ,
i j These procedures were written to comply with 10 CFR 50 Appendix J, ANS/ ANSI
- N45.4-1972, and Quad-Cities Unit Two Technical Specifications. The methods j for calculating the containment leakage and upper confidence limit are in compliance with the ANSI /ANS 56.8-1981 standard. Compliance with all. features '
of the ANSI /ANS 56.8-1981 standard was not possible, because the Commission
~
) has not approved the standard for use due to a pending change to 10 CFR 50, j Appendix J. l 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 volumes used for weighting the sensor readings. Plant personnel performed all test instrumentation calibrations using NBS traceable' standards.
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h TABLE ONE INSTRUMENT SPECIFICATIONS INSTRUMENT MANUFACTURER MODEL NO. RANGE ACCURACY REPEATABILITY Precision Pressure-Gages (2)- Volumetrics 0-100-PSIA 1.015 PSI 1.001 PSI Burns RTD's (30) Engineering SPIAl-5\-3A 50-200 F i.5 F .1 F Volumetrics Lithium ' Dewcells (10) (Foxboro) Chloride +140 F 11.0 F 1.5 F h Pall Trinity
' Thermocouple Micro 14-T-2H 0-600 F 12.0 F .1*F Fischer
-Flowmeter- & Porter 83 0-8.44 scfm 1.084 scfm Level Indicator LI;1-263-100A- Yarway_ SCR/M +60"H O 2
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TABLE TWO. SENSOR PHYSICAL LOCATIONS i RTD NUMBER SUBVOLUME ELEVATION AZIMUTH
- i 1 1 670'0" 180*
! 2 1 670'0" 0*
- 3 2 657'0" 20*
. 4 2 657'0" 200*- 5 3 634'0" .70* 6 3 634'0" 265* 7 4(Annular Ring) 643'0" 45* i 8 4 615'0" 225* 9 5 620'0" 5* 10 5 620'0"- 100* 11 5 620'0" 220 l 12 6 608'0" 40* 13- 6 608'0" 130* . 14 6 608'0" 220* 15 6 608'0" -310 16 7 598'0" 70* 17 7 598'0" 160* J 18 7 598'0" 250* 19 7 598'0" 340 20 8 587'0" 10* 21 8 587'0" 100* 22 8 587'0" 190* 23 8 587'0" 280* , i 24 9(CRD Space) 586'0" 0* i 25 10(Torus) 578'0" 0* l 26 10(Torus) 578'0" 60 27 10(Torus) 578'0" 120 28 10(Torus) 578'0" 180* } 29 10(Torus) 578'0" 240* 30 10(Torus) 578'0" 300*: Thermocouple 11(Rx Vessel) (Inlet to CU Hx) i DEWCELL NO. SUBVOLUME ELEVATION AZIMUTH 1 1 670' 180*
; 2 2,3,4 653' 90*
3 2,3,4 653' 270* 4 5 620'- 0* 4 5 6,7 600' 45* 6 6,7 _600' 225*
; 7 8,9 586' 0* ! 8 8,9 586' 180*
9 10 578'- 90* 10 10 -578' -270* Thermocouple (Saturated)' 11 --- '---
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i A.2.a. Temperature - l The location of the 30 platinum RTD's was chosen to avoid conflict with l local temperature variations and thermal influence from metal structures. I i The RTD's were manufactured by Burns Engineering Inc. and are Model SP 1Al-5 -3A. Each RTD and its associated bridge network was calibrated to j yield an output of approximately 0-100 mV over a temperature range of 50-150 F. j Each RTD was calibrated by comparing the bridge output to the true temperature
- as indicated by the temperature standard. Three temperatures were used for
! the calibration. Two calibration constants (a slope and intercept of the regression line) were computed for each RTD by performing a least squares fit l of the RTD bridge output to the reference standard's indicated true temperature. I t The temperature standard used for all calibrations was a Volumetrics RTD Model VMC 701-B used with a Dewcell/RTD Calibrator M: del 07731. The standard was calibrated by Volumetrics on July 27, 1983 to standards traceable to the j' NBS. The sensors used during the test were calibrated within 6 months of the calibration date for the standard, i The plant process computer scanned the output of each RTD-bridge network
- . and converted the output to engineering units using the calibration constants.
I j A.2.b. Pressure ! Two precision quartz bourdon tube, absolute pressure gauges were utilized ? to measure total containment pressure. Each gauge had a local digital readout l and a Binary Coded Decimal (BCD) output to the process 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 penetration to the
- containment.
i Each precision pressure gauge was calibrated from 0-100 PSIA in 5 PSI' increments using a third precision pressure gauge (Volumetrics Model 07726) j- that had been sent to Volumetrics for calibration. The pressure standard was 1 calibreted on July 26, 1983 using NBS traceable reference standa'rds. The pressure instruments used during the test were calibrated within 6 months _of j the standard's calibration. 1 I 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 - 3 pressure as read by the third, reference gauge. No mechanical calibration of the gauges was performed to bring their digital displays ~into agreement with , j true pressure. i 1 1 .
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A.2.c. Vapor Pressure Ten lithium chloride dewcells were used to determine the partial pressure due to water vapor in the containment. The dewcells were calibrated using the Volumetrics standard described in section A.2.a. and a chilled mirror dewcell standard calibrated on August 3, 1983 by Volumetrics. The calibration constants (the slope and intercept of a regression line) for cach dewcell were computed relating the 0-150 mV output of the signal conditioning cards to the actual dewpoint indicated by the reference standard. A.2.d. Flow A rotameter flewmeter, Fischer-Porter serial number 8311A9265R0001, was used for the flow measurement during the induced leakage phase of the IPCLRT. The flowmeter was calibrated on December 7,1983 by Fischer-Porter to within 11% of full scale (.8-8.44 SCFM) using NBS traceable standards. Plant personnel continuously monitored the flow during the induced leakage phase and corrected any minor deviations from the induced flow rate of 6.30 SCFM by adjusting a 3/8" needle valve on the flowmeter inlet. 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, calculate, and print results with minimal manual inputs and without the disadvantages of multiplexers or positioning sensitive electronic hardware inside the containment during the test. The process computer was used to compute the statistically averaged leak rate and upper confidence limit for the ANS/ ANSI mass plot method. Data sets giving instrument outputs were transferred to a Prime 750 computer. The Prime 750 was used to perform the BN-TOP-1 calculations. Key parameters, such as total time measured leak rate, volume weighted dry air pressure and temperature, and absolute pressure were plotted on a Ramtek color terminal. Plant personnel also plotted a large number of other parameters, including temperature and partial pressure of water vapor for each subvolume, reactor water temperature and level, absolute pressure, etc. in real time. In all cases data was' plotted within approximately 30 minutes of the time it was taken. The plotting of data and the computer printed summaries of data allowed rapid identificatin of any problems as they might develop. Figure 2 shows a schematic of the data acquisition system. With the exception of a few brief problems with the process computer, all of the equipment performed perfectly. No instruments inside the containment failed during the test. A.4 Type A Test Pressurization A 3000 SCFM, 600 hp, 4 kV electric oil-free air compressor was used to - pressurize the primary containment. An identical compressor was available in standby during the IPCLRT. The compressors were physically located on a single, enclosed truck trailer located outside the Reactor Building. The compressed air was piped using flexible retal 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, MO-2-1001-26A was open during pressurization. Once the containment.was pressurized, the MO-2-1001-26A valve was closed and the spool piece was removed and replaced with a blind flange. MEAUSREMEllT SYSTEM SCHEMATIC ARRAllGEMENT RTD 3/C LOCAL JUllCT10:1 (4) , BOXES (8) RTD " u (26) (26) POWER SUPPLY BOX (1) DEWCELL 5/C - 3/C (3) (0) Il0V DRYWELL TERMINAL X BOX
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(3) tilSTRUMENT CONSOLE .
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DRYWELL PERSOHNEL litTERLOCK BULKilEAD RTD & DEWCELL SIGilAL 40/C (2) CONDITIONING CARDS PROCESS 32/C (2) C0tiPUTER ltASS PRESSURE GAUGES PLOT 11ETil0D h Il0V PRIME 3:1-TOP-1 COMPUTER METHOD I \ l FIGURE 2
SECTION B - TEST METHOD 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 leak rate, as defined in ANS/ ANSI N45.4-1972. The inputs to the total containment dry air mass calculation include subvolume weighted containment temperature, subvolume weighted vapor pressure, total absolute air pressure, and a total containment volume correction for reactor water level. As the data sets are collected over time a regression line is computed for the measured dry air mass as a function of time. The slope divided by the "y-intercept" of the regression line gives the statistically averaged leak rate. The upper confidence limit is defined as the statistically averaged leak rate plus the product of the one-sided 95% T-distribution and the standard deviation of the regression line slope. The mathematical expressions for these calculations are found in Appendix C. There has been some criticism of this technique on a technical basis (Gogol and Reytblatt) in that the use of a volume weighted temperature in a total containment dry air mass calculation is not mathematically equivalent to computing a dry air mass for each subvolume and totalling the results to obtain a containment dry air mass. While the criticism has some merit in terms of mathmetical exactness, both methods are in fact approximations. When using the volume weighted temperature the assumption is that the dry air mass within the containment can be approximated by an ideal gas that is at thermal equilibrium at the volume weighted temperature. When computing and then totalling the dry air masses for each subvolume, the assumption is that each subvolume is in thermal equilibrium or that sensors are perfectly placed within the subvolume to measure temperature fluctuations within the subvolume. There are studies on going by EPRI and others that would seem to indicate that the two techniques do not give very different results. This certainly is what could be expected since the test gives an excellent verification of the test validity, including both the method of calculation and the subvolume modeling and weighting factors. This verification is in the form of the supplemental verification phase of the test where an induced leak must be measured along with the containment leakage to an accuracy of 25% of L . Since the verification phase of the test normally shows an accuracy much bette$ than the limit, it can only be assumed that the test method has the required accuracy. Any better method of computing the containment leakage should demonstrate an improvement in the verification phase result or show that it is better able to handle troublesome temperature related test problems, such as diurnal effects at PWR's where ambient temperatures fluctuate greatly. i l 1
.. . . ~ - - -. .
i B.2 Supplemental Verification Test The supplemental verification test superimposes a known leak of approximately the same. magnitude as LA (8.16 SCFM or I wt %/ day as defined in the Technical Specifications). The degree of detectability of the combined leak rate (containment calculated leak rate plus the superimposed, induced leak rate) provides a basis for resolving any uncertainty associated with the measured leak rate phase of the test. The allowed error band is i 25% of L
- A There are no references to the use of upper confidence limits to evaluate the acceptablility of the induced leakage phase of the IPCLRT in the ANS/ ANSI standards or in BN-TOP-1, Rev. 1. The induced leak used for this test was 6.30 SCFM or 0.772 wt %/ day.
B.3 Instrument Error Analysis An instrument error analysis was performed prior to the test to demonstrate the adequacy of the data acquisition system. The instrument system error was calculated in two parts. The first was to determine the system accuracy uncertainty. 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 0.0833 wt %/ day ~ and 0.0169 wt %/ day for a 24-hour test, respectively. These values are inversely proportional to the test duration. Since no instruments failed during'the test and the test duration was 24 hours, these values reflect the actual test instrument uncertainties. ! The instrumentation uncertainty is used only to illustrate the system's j ability to measure the required parameters to calculate the primary containment i leak rate. The mathematical derivation of the above values can_be found in j- Appendix D. The instrumentation uncertainty is always present in the data and. , is incorporated in the 95% upper confidence limit. l 1 i I l i l l l 1
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SECTION C - SEQUENCE OF EVENTS C.1 Test Preparation Chronology The pretest preparation phase and containment inspection was completed on February 8, 1984 with no apparent structural deterioration being observed. Major preliminary steps included:
- 1) Completion of all Type B and C tests, component repairs and modifications where appropriate, and retests as required.
- 2) Blocking open three pairs of drywell to suppression chamber vacuum breakers.
- 3) Installation of all IPCLRT test equipment including the sensors, associated wiring, and data acquisition system.
- 4) In situ test of data acquisition system and ccmputer programs for data processing.
- 5) Completion of all repairs and installations in the containment.
- 6) Completion of the pre-test valve line-up.
f C.2 Test Pressurization and Stabilization Chronology DATE TIME EVENT 12-08-84 2000 Began pressurizing the Unit Two containment. 2025 2 PSIG in drywell. 2045 Containment piping and valves are being inspected for apparent leaks. 2250 Compressor tripped dut to 2N leak on auxiliary-oil pump. Containment isolated. 2300 Leak of 5 SCFH found on LT 2-1641-5B. 2327 Compressor re-started and pressurization' continuing. 02-09-84 0145 Compressor unloaded to 50%. Containment pressure
-63 PSIA.
0210 Pressurization complete at 65 PSIA. 0355 Process computer down. Restarted 5 minutes later. 0650 Spool piece removed and blank flange installed at the M0-2-1001-26A valve where the containment was pressurized. The volume weighted containment temperature is decreasing at a rate of .30 .40 degrees per hour. 1 4 C.3 Measured Leak Rate Phase Chronology j DATE TIME EVENT l 02-09-84 0649 The 0649 scan by the process computer will represent the start of the test. j Containment temperature declining .33 degrees F/hr. Instrumentation responding normally. 0900 Reactor water temperature is increasing-steadily and at a rate of less than .2 degrees F/hr. This
- will be no problem for the test.
Reactor water level is decreasing steadily and at a rate less than .5 inch / hour. This will be no j problem for the test. 1900 Decided to continue test for a full 24 hours since i the lower leak rates that can be demonstrated by continuing the test will allow passing the "as found" leakage criteria. 02-09-84 1900 Computer down. } 1920 Computer up. 2020 Still having trouble'with computer. 02-10-84 0653 The 24 hour test ~was' terminated. Total containment pressure is 62.95 PSIA. 1 C.4 Induced Leakage Phase Chronology 02-10-84 0718 Induced leak .75%' scale reading.on. flowmeter, which. corresponds to 6.30 SCFM. Radiation Protection-taking sample for release to Reactor Building. 0819 Stabilization complete. Computer program set for first scan.for,this part-of-the test. 4 1219 Induced leakage phase terminated successfully. Total containment pressure is 63.04-PSIA. C.5 Depressurization Phase Chronology-DATE' TIME EVENT l 02-10-84 1300 -Began de pressurization. J 02-11-84: 0330 Depressurization complete. .Drywell. entry.nade to-verify undisturbed instrumentation and begin~ post'
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A sumnary qf the computed data using the ANSI N45.4 test method can be found in Table.3. E(own in the table are data set number,'; time; since the start of the ,tect (after pr'essurization'and stabilization comple'tt), volume weighted containment temperature',in degrees R. dry air pressure 'in-PS'IA, reactor water ~
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I SECTION E - TEST CALCULATIONS
- Calculations for the IPCLRT using the ANSI method are found in Quad-Cities I procedures QTS 150-T3. A reproduction of these procedures can be found in Appendix C. The origins of these calculations are the N274 draft for ANSI /ANS 56.8.
These calculations are consistent with the standard as it was published in 1981. SECTION F - TYPE A TEST RESULTS F.1 Measured Leak Rate Test Results Based on the data collected over 24 hours on approximately 10 minute time intervals the statistically averaged leak rate was;found to.be 0.385 wt %/ day with an upper. confidence limit of 0.392 wt %/ day. F.2 Induced Leakage Test Results A leak rate of 6.3 SCFM (0.772 wt %/ day) was induced from the containment for this phase of the test. The required accuracy for the test is computed below. Statistically Averaged Leak Rate 0.385 0.385 (Measured Leak' Rate Phase) Induced Leak (6.3 SCFM) 0.772 0.772 I Allowed Error Band (25% L* ) + 0.250 - 0.250 1.407 0.907 Statistically Averaged Leak Rate (Induced Leakage Phase) 1.082 wt %/ day Therefore, the required test accuracy was satisfied. i 1 l 2 i
F.3 Leak Rate Compensation For Non-Vented Penetrations The IPCLRT was performed with the following penetrations not drained and vented as required by 10 CFR 50, Appendix J. The "as left" leak rates for each of these penetrations, as determined by Type C testing, is also listed: THROUGH LEAKAGE SYSTEM STATUS FROM TYPE B AND C TESTING SCFil WT %/ DAY
'A' Rx Feedwater Isolated, Filled, Unvented 0.52 0.00106
'B' Rx Feedwater Isolated, Filled, Unvented 25.80 0.05270 RilR System Isolated, Filled, Unvented 8.34 0.01704 Rx Water CU Used for Core Cooling 0.83 0.00180 ACAD/ CAM Isolated 1.50 0.00306 Primary Sample Isolated 0.18 0.00036 All Electrical Test bellows filled and 1.65 0.00337 Penetrations pressurized with dry N '
2 38.87 0.07939 I This correction yields the following adjusted leak rates: Statistically Averaged Leak Rate (ANSI) 0.464 wt %/ day Upper Confidence Limit (ANSI) 0.471 wt %/ day 1 l
F.4 Pre-Operational Results vs. Test Results Past IPCLRT reports have compared the results of those tests with the pre-operational IPCLRT, performed from August 29 to September 2,1971. For comparison purposes the statistically averaged leak rate corrected for non-vented volumes and corrected upper confidence limit are given for the last three Type A tests on Unit Two. 1976 1980 1983 Statistically Averaged Leak Rate 0.327 0.449 0.464 (wt %/ day) Upper Confidence Limit 0.344 0.459 0.471 (wt %/ day) The above data shows that there has been no significant deterioration of the containment integrity and that the leakages have been consistently below the allowable limit of 0.750 wt %/ day. J l l
F.5 As Found IPCLRT Result The following table summarizes the results of all Type B and C as well as the IPCLRT results to arrive at an "as found" Type A test result. Since the total is less than 0.750 wt %/ day (75 L ), the present schedule of three Type A tests in 10 years can be maintained. D*cumentation for the values listed below can be found in R0 83-15/03L-1, Docket No. 50-265, DPR-30. SLHMARY OF ALL CONTAINMENT LEAK RATE TESTING DflRiNG UNIT WO REFUEL Ol;TAGE FALL, 1983 AS SUUND (SCFH) AS LEFT (SCFH) LLRT (TOTAL WORST CASE LLRT (TOTAL WORST CASE MEASURED) THROUGH LEAKAGE MEASURED) THROUGH LEAKA(f (1) MSIV's @ 25 PSIG 59.92 17.30 27.66 10.06 (2) MSIV's converted 94.67 27.33 43.70 16.37 to 48 P.11G* (3) All 1 pn 3 C Tests 1095.79 144.92 215.66 (Except MSIV's) 109.40 (4) All Typo B Tests 108.31 54.23 22.49 11 32 TOTAL (2 + 3 + 4) 1298.77 226.48 281.85 137.09 (1) Type A Test (Integrated Leak Rate Test) = 0.385 wt %/ day (2) Upper Confidence Limit of Type A Test Result = 0.392 wt %/ day (3) Correction for Unvented Volumes During Type A Test = 0.079 wt %/ day - (4) Correction for Repairs Prior to Type A Test = 0.183 wt %/ day
,(As Found - As Lef t) 4226.48 - 137.09) . 459.59 (5) Correction for Leak Repaired During Type A Test = 0.020 wt %/ day TOTAL (2 + 3 + 4 + 5) 0.674 wt %/ day (As Found ILRT Result)
- Leak Rate at 25 PSIG converts to Leak Rate at 48 PSIG using CONVERSION ~
RATIO OF 1.58. REFERENCE ORNL NISC - 5, Oak Ridge National laboratory, Aug.1965, page 10.55. e l-i APPENDIX A l TYPE B AND C TESTS i
- Presented herein are the results of local leak rate tests. conducted on all penetrations, double-gasketed seals, and isolation valves since the previous
- IPCLRT in February, 1979. All valves with leakage in excess of the individual
- j. valve leakage limit were restored to an acceptable leak tightness prior to the resumption of power operation. Total leakage for double gasketed seals and -
total leakage for all other penetrations and isolation valves following repairs ] satisfied the Technical Specification limits. These results are listed in ! Table A-1. 4 4 i l 1 I 1 i i I i I i l 1 6 a f i i i i 1 } I i i i a I
TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 203-1A Main Steam Line 9.24 09-06-83 9.24 09-06-83 Isolation Valves
- 4.60 09-07-81 4.60 09-07-81 A0 203-2A 34.56 09-06-83 2.30 12-27-83 2.30 09-08-81 0.00 09-11-81 A0 203-1B 4.60 09-05-83 4.60 09-05-83 0.00 09-07-81 0.00 09-07-81 A0 203-2B 4.60 09-05-83 4.60 09-05-83 0.00 09-07-81 0.00 09-07-81 A0 203-1C 2.30 09-05-83 2.30 09-05-83 0.00 09-07-81 0.00 09-07-81 A0 203-2C 2.30 09-05-83 2.30 09-05-83 0.00 09-07-81 0.00 09-07-81 A0 203-1D 9.20 09-04-83 9.20 09-04-83 2.30 09-07-81 2.30 09-07-81 A0 203-2D 9.20 09-04-83 9.20 09-04-83 2.30 09-07-81 2.30 09-07-81 M0 220-1 Main Steam Line Drains 39.27 09-05-83 7.46 01-12-84 MO 220-2 66.30/5.50 09-07-81 8.63 12-23-81 A0 220-44 Primary Sample 0.35 09-27-83 0.35 09-27-83 A0 220-45 0.00 10-16-81 0.0 10-16-81 CV 220-58A Feedwater Inlet 267.3 10-05-83 0.52 01-09-84 Loop "A" Inboard 1.03 09-21-81 1.03 09-21-81 CV 220-62A Feedwater Inlet 2.70 10-06-83 5.26 01-06-84 Loop "A" Outboard 1140.0 09-22-81 6.20 10-07-81 CV 220-58B Feedwater Inlet 1.00 09-13-83 25.80 12-22-84 Loop "B" Inboard 42.40 09-10-81 0.00 11-12-81 CV 220-62B Feedwater Inlet 362.0 09-14-83 28.50 12-30-83 Loop "B" Outboard 1018.0 09-17-81 13.60 11-13-81
- Test Pressure for MSIV's is 25 PSIG. Where the A and B valves in a steam line have identical leakages, the valves were tested as a single volume. The value is a maximum leak rate through the valve assuming that the other valve leaked 0.0 SCFH.
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TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE MO 1001-20 RIIRS to Radwaste 0.00 09-05-83 0.00 09-05-83 MO 1001-21 0.00 12-23-81 0.00 12-23-81 MO 1001-23A RIIRS Containment Sprny - 3.08 01-04-84 3.08 01-04-84 HO 1001-26A System I 1.10 09-15-81 1.10 09-15-81 MO 1001-29A RIIRS Return Loop "A" 0.00 01-04-84 0.00 01-04-84 3.00 09-14-81 3.00 09-14-81 MO 1001-34A RIIRS Suppression Chamber 0.00 01-04-84 0.00 01-04-84 MO 1001-36A Spray - System I 34.60 09-14-81 1.21 11-18-81 , MO 1001-37A MO 1001-238 Ri!RS Containment Spray - 7.88 09-22-83 7.88 09-22-83 MO 1001-26B System II 4.10 09-24-81 4.10 09-24-81 MO 1001-29B RlIRS Return Loop "B" 2.07 09-22-83 2.07 09-22-83 0.00 09-23-81 0.00 09-23-81 MO 1001-34B RIIRS Suppression 2.40/163.83 12-01-83 1.20 12-13-83 MO 1001-36B Chamber Spray 1638.0 09-23-81 6.07 12-19-81 MO 1001-37B System Il MO 1001-47 RilRS Shutdown 0.00 10-20-83 0.00 10-20-83 MO 1001-50 Cooling Suction 7.04 11-20-81 7.04 11-20-81 MO 1001-60 RilHS Ilead Spray 0.38 01-06-84 0.38 01-06-84 MO 1001-63 1.33 12-22-81 1.33 12-22-81 MO 1201-2 Clean-Up System 2.61/1.76 09-28-83 2.39 02-02-84 MO 1201-5 Suction 4.58 10-16-81 4.58 10-16-81 MO 1301-16 RCIC Steam Supply 20.40 09-06-83 3.35 01-18-84 MO 1301-17 29.00 09-07-81 0.46 12-01-81 CV 1301-40 RCIC Condensate Drain 5.03 09-05-83 5.03 09-05-83 3.90 09-09-81 3.90 09-09-81 CV 1301-41 RCIC Turbine Exhaust 24.90 09-05-83 5.78 01-14-84 24.90 09-07-81 1.00 09-30-81 A0 1601-21 Drywell and Suppression 68.10 09-27-83 24.80 01-10-84 A0 1601-22 Chamber Purge 53.60 09-29-81 10.32 12-20-81 A0 1601-55 A0 1601-56 A0 1601-20A Suppression Chamber 6.70 09-23-83 6.70 09-23-83 CV 1601-31A Vent Lines #1 7.60 09-24-81 7.60 09-24-81 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR HEASURED LEAK RATE (SCFil) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 1601-20B Suppression Chamber 7.10 09-12-83 7.10 09-12-83 CV 1601-31B Vent Lines #2 19.90 09-23-81 10.70 09-30-81 A0 1601-57 Drywell and Suppression 0.00 09-15-83 0.Q0 09-15-83 A0 1601-58 Chamber Supply Air 0.05 09-11-81 0.05 09-11-81 A0 1601-59 Purge A0 1601-23 Drywell and Suppression 9.00 09-30-83 9.00 09-30-83 A0 1601-24 Chamber Exhaust 17.99 10-18-81 17.99 10-18-81 A0 1601-60 A0 1601-61 A0 1601-62 A0 1601-63 A0 2001-3 Drywell Floor Drain 8.10 09-08-83 2.81 01-06-84 A0 2001-4 Sump Discharge 0.00 10-27-81 0.00 10-27-81 A0 2001-15 Drywell Equipment 0.014 09-08-83 7.35 01-23-84 A0 2001-16 Drain Sump Discharge 7.50 02-23-83 7.50 02-23-83 0.30 10-27-81 0.30 10-27-81 HD 2301-4 IIPCI Steam Supply 2.30 09-05-83 2.30 09-05-83 MO 2301-5 3.40 09-07-81 3.40 09-07-81 CV 2301-34 IIPCI Condensate Drain 6.76 09-05-83 6.10 01-11-84 7.00 09-08-81 7.00 09-08-81 CV 2301-45 IIPCI Steam Exhaust 0.00 09-05-83 0.00 09-05-83 165.0 09-08-81 12.04 10-06-81 A0 4720 Drywell Pneumatic 0.00 09-15-83 0.00 09-15-83 Suction 0.00 09-11-81 0.00 09-11-81 A0 4721 Drywell Pneumatic 0.00 09-15-83 0.00 09-15-83 Suction 0.00 09-11-81 0.00 09-11-81 A0 8801A 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.10 09-29-81 0.10 09-29-81 A0 8802A 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.10 09-29-81 0.10 09-29-81 i A0 8801B 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.00 09-29-81 0.00 09-29-81 A0 8802B 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.00 09-29-81 0.00 09-29-81 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE A0 8801C 0xygen Analyzer Suction 6.00 10-03-83 6.00 10-03-83 4.40 09-29-81 4.40 09-29-81 A0 8802C 0xygen Analyzer Suction 16.00 10-03-83 1.40 11-29-83 0.40 09-29-81 0.40 09-29-81 A0 8801D 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.00 09-29-81 0.00 09-29-81 A0 8802D 0xygen Analyzer Suction 0.00 10-03-83 0.00 10-03-83 0.00 09-29-81 0.00 09-29-81 A0 8803 0xygen Analyzer Return 0.60 10-14-83 0.60 10-14-83 1.70 10-01-81 1.70 10-01-81 A0 8804 0xygen Analyzer Return 10.00 10-14-83 10.00 10-14-83 9.50 10-01-81 9.50 10-01-81 733-1 Automatic TIP Ball Valve 0.25 11-07-83 0.25 11-07-83 0.70 02-02-83 0.70 02-02-83 0.15 09-25-81 0.15 09-25-81 733-2 Automatic TIP Ball Valve 0.40 11-07-83 0.40 11-07-83 0.00 02-17-83 0.00 02-17-83 0.40 02-02-83 0.40 02-02-83 0.20 09-25-81 0.20 09-25-81 733-3 Automatic TIP Ball Valve 0.70 11-07-83 0.70 11-07-83 0.00 02-02-83 0.00 02-02-83 0.10 09-25-81 0.10 09-25-81 733-4 Automatic TIP Ball Valve 0.00 11-07-83 0.00 11-07-83 0.00 02-02-83 0.00 02-02-83 2.10 09-25-81 2.10 09-25-81 733-5 Automatic TIP Ball Valve 4.50 11-07-83 4.50 11-07-83 0.00 02-02-83 0.00 02-02-83 0.00 09-25-81 0.00 09-25-81 700-743 TIP Purge Check Valve 7.50 11-07-83 7.50 11-07-83 4.70 09-25-81 4.70 09-25-81 SO 2499-1A CAM - Drywell 0.00 10-12-83 0.00 10-12-83 SO 2499-2A 0.10 09-28-81 0.10 09-28-81 SO 2499-3A CAM - Suppression Chamber 0.00 10-14-83 0.00 10-14-83 SO 2499-4A 0.00 09-28-81 0.00 09-28-81 TABLE A-1 ! TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE SO 2499-1B CAM - Drywell 0.00 10-07-83 0.00 10-07-83 SO 2499-2B 0.00 09-28-81 0.00 09-28-81 SO 2499-3B CAM - Suppression 0.00 10-12-83 0.00 10-12-83 SO 2499-4B Chamber 0.00 03-28-81 0.00 09-28-81 A0 2599-2A ACAD to Drywell 5.00/0.00 10-07-83 5.00/0.00 10-07-83 CV 2599-23A 0.20 09-28-81 0.20 09-28-81 A0 2599-3A ACAD to Suppression 0.90/15.10 10-12-83 0.30 11-08-83 CV 2599-24A Chamber 2.00 09-28-81 2.00 09-28-81 A0 2599-2B ACAD to Drywell 1.50/4.00 10-07-83 1.50/4.00 10-07-83 CV 2599-23B 1.70 09-28-81 1.70 09-28-81 A0 2599-3B ACAD to Suppression 0.00 10-12-83 0.00 10-12-83 CV 2599-24B Chamber 0.00 09-28-81 0.00 09-28-81 A0 2599-4A ACAD Drywell Bleed to 1.80 09-23-83 1.80 09-23-83 FCV 2599-5A SBGTS 1.40 09-28-81 1.40 09-28-81 A0 2599-4B ACAD Drywell 6.50 09-23-83 6.50 09-23-83 FCV 2599-5B Bleed to SBGIS U.D. 09-28-81 9.50 12-18-81 X-1 Drywell Equipment llatch 0.00 09-04-83 0.00 02-07-84 0.00 03-28-83 0.00 C3-28-83 0.00 12-23-81 0.00 12-23-81 X-2 Drywell Personnel 24.73 01-14-84 1.37 01-20-84 Airlock 10.30 12-18-81 10.30 12-18-81 X-4 Drywell Head Access 0.00 10-17-83 0.00 11-08-83 Hatch 0.00 10-01-81 0.00 10-01-81 X-6 CRD Removal Hatch 0.00 09-04-83 0.00 01-19-84 0.00 03-26-83 0.00 03-26-83 0.00 12-23-81 0.00 12-23-81 X-35A TIP Flux Mon. Flange 0.00 11-07-83 0.00 11-07-83 0.00 09-25-81 0.00 09-25-81 X-35B 0.00 11-07-83 0.00 11-07-83 0.00 09-25-81 0.00 09-25-81
- Valves tested separately. Individual valve leak rates shown.
4 1 1
] '
TABLE A-1 TYPE B AND C TEST RESULTS f VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE 1 X-35C 0.00 11-07-83 0.00 11-07-83 1 0.00- 09-25-81 0.00 09-25-81 X-35D 0.00 11-07-83 0.00 11-07-83 0.00 09-25-81 0.00 09-25-81 ' 1 X-35E 0.00 11-07-83 0.00 11-07-83 0.00 09-25-81 0.00 .09-25-81 4 X-35F 0.00 11-07-83 0.00 11-07-83 4 0.00 09-25-81 0.00 09-25-81 ] X-35G 0.00 11-07-83 0.00- 11-07-83
, 0.00 09-25-81 0.00 09-25 '
i i X-200A Suppression Chamber. 0.00 09-04-83 0.00 02-14-84
! Access Hatch 0.00 03-28-83 0.00 03-28-83 0.00 12-24-81 0.00 12-24-81 '
X-200B 0.00 09-04-83 0.00 02-06-84 1 0.00 12-24-81 0.00 12-24-81 Drywell Drywell Head 7.50 09-05-83 0.00 02-07 - Head Flange 0.00 12-23-81 0.00 12-23-81 1, 1 SL-1 Shear Lug Inspection 0.00 10-31-83 0.00 10-31-83 Hatches 0.05 09-18-81 0.05 09-18 i ) SL-2 0.00 10-31-83 0.00 '10-31-83 i 0.00 09-18-81 0.00 09-18-81 i j SL-3 0.00' '10-31-83 0.00 10-31-83 0.00 09-18-81 0.00 09-18-81 j SL-4 0.00 10-31-83 -0.00 10-31-83 ! 0.00 09-18-81 0.00 09-18-81 1 SL-5 0.00 10-31-83 0.00 10-31-83 0.00 09-18-81 0.00 09-18-81~ l SL-6 0.00 10-31-83 0.00 '10-31-83 1 0.00 09-18-81 'O.00- 09-18-81 [ SL-7 0.00 10-31-83 0.00 10-31-83 i, 0.00 09-18-81 : 0.00 '09-18.81 i 1 f
._ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ . ____..____.____________._________________m____ _ . . _ _ _ _ _ _ _ . . _ . .
I I TABLE A-1 1 TYPE B AND C TEST RESULTS l l VALVE (S) OR NEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE- AS LEFT DATE SL-8 0.00 10-31-83 0.00 10-31-83
- 0.05 09-18-81 0.05 09-18-81 l X-7A- Primary Steam 0.00 10-27-83 -0.00 10-27-83 0.00 09-10-81 0.00 09-10-81 X-7B 0.00~ 10-27-83 0.00 10-27-83 0.00 09-10-81 0.00 09-10-81 X-7C 0.00 10-07-83 0.00 10-07-83 0.00 09-10-81 0.00 09-10-81 j X-7D 0.00 10-07-83 0.00 10-07-83 1.20 09-10-81 1.20 09-10-81 j
l X-8 Primary Steam 0.00 '10-27-83 . 0.00 . 10-27-83 Drain Line 0.10 09-10-81' O.10 09-10-81 ) X-9A Reactor Feedwater ~0.00 10-27-83 0.00- 10-27-83 , 0.00 09-10-81 0.00 09-10-81 X-9B 0.55 10-07-83 0.55 10-07-83 0.50 09-10-81 0.50 09-10-81 l X-10 Steam to RCIC 0.00 10-07-83 0.00 10-07-83 O.30 09-10-81 0.30 09-10-81' X-11 HPCI to Steam Supply 0.00 10-07-83 0.00 10-07-83. 0.00 09-10-81 0.00 09-10-81~ X-12 RHRS Supply 3.20 10-07-83' 3.20 10-07-83 , 1 1.70 09-10-81 1.70- 09-10-81 3 X-13A RHRS Return 0.00 10-27-83 0.00 10-27-83 0.00 09-10-81 0.00 09-10-81' ! X-13B 0.00 10-07-83 0.00' 10-07-83. I i '0.00 10-81 -0.00 09-10-81 X-14 Cleanup Supply 0.95 10-27-83 0.95- 10-27-83' O.70 09-10-81 0.70 09-10-81 ] X-23 Cooling Water 0.00- 10-07 0.00- 10-07-83 l .0.00 09-10-81 0.00 09-10-81 l X-24 Cooling Water Return 0.00 10-07-83 0.00, 10-07-83
, 0.00 09-10-81 0.00- 09-10-81 1
1 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE X-25 Vent From Drywell 1.95 27-83 1.95 10-27-83 2.20 09-10-81 2.20 09-10-81 2.10 05-08-81 2.10 05-08-81 X-26 Vent to Drywell 1.40 10-27-83 1.40 10-27-83 0.40 09-10-81 .0.40 09-10-81 X-36 CRD Hydraulic 0.00 10-07-83 0.00 10-07-83 System Return 0.00 09-10-81 0.00 09-10-81 X-47 Standby Liquid 0.00 10-07-83 0.00 10-07-83 Control 0.00 09-10-81 0.00 09-10-81 X-17 Reactor Vessel 1.40 10-27-83 1.40 10-27-83 Head Spray 1.20 09-10-81 1.20 09-10-81 X-16A Core Spray Inlet 6.00 10-27-83 6.00 10-27-83 4.00 09-10-81 _4.00 09-10-81 X-16B Core Spray Inlet 19.00 10-27-83 11.00 09-10-81 11.00 09-10-81 ; X-1008 CRD Position 0.05 10-27-83 0.05 10-27-83 Indication .0.00 09-15-81 0.00 09-15-81 X-100C Neutron Monitor 0.20 10-28-83 0.20 10-28-83 0.50 09-21 0.50 09-21 X-100E CRD Position 0.20 10-28-83 0.20 10-28-83 Indication 0.00 09-21-81 0.00 09-21-81 X-100F Power 0.00 11-04-83 0.00 11-04-83 0.00 09-23-81 0.00 09-23-81 X-100G CRD Position 0.35 11-04-83 0.35 11-04-83 Indication 0.00 03-26-83 0.00! 03-26-83 0.00 '09-25-81 0.00 '09-25-81 X-101A Recire Pump 0.20 10-28-83 0.20 10-28-83 0.00 16-81 0.00 09-16 X-101B Recire Pump 0.20 10-28-83 0.20 10-28-83? ; 0.35 09-17-81 0.35 09-17-81 TABLE A-1 TYPE B AND C TEST RESULTS VALVE (S) OR MEASURED LEAK RATE (SCFH) PENETRATION TEST VOLUME AS FOUND DATE AS LEFT DATE X-101D Power 0.20 11-04-83 0.20 11-04-83 0.00 09-25-81 0.00 09-25-81 X-102B Neutron Monitors 0.15 10-28-83 0.15 10-28-83 0.00 09-17-81 0.00 09-17-81 X-103 Neutron Monitor 0.25 10-28-83 0.25 10-28-83 0.15 09-17-81 0.15 09-17-81 X-104A CRD Position Indication 0.00 10-27-83 0.00 10-27-83 0.00 09-16-81 0.00 09-16-81 X-104B Drywell Coolers 0.00 10-27-83 0.00 10-27-83 0.00 09-16-81 0.00 09-16-81 X-104C CRD Position Indication 0.25 10-28-83 0.25 10-28-83 0.00 09-17-81 0.00 09-17-81 X-104D CRD Position Indication 0.25 10-28-83 0.25 10-28-83 0.15 09-21-81 0.15 09-21-81 X-104F Recire Pump Power 0.15 11-04-83 0.15 11-04-83 0.00 09-25-81 0.00 09-25-81 X-105C Neutron Monitors 0.25 10-28-83 0.25 10-28-83 0.10 09-17-81 0.10 09-17-81 X-106A CRD Position Indication 0.05 10-27-83 0.05 10-27-83 0.00 09-16-81 0.00 09-16-81 X-106B The rmocouples 0.25 10-26-83 0.25 10-28-83 0.00 '09-25-81 0.00 09-25-81 X-107A Neutron Monitor 0.25 10-28-83 0.25 10-28-83 0.30 09-21-81 0.30 09-21-81 X-107B Recirc Pump Power 0.30 11-04-83 0.30 11-04-83 0.00 09-25-81 0.00 09-25-81 X-227A ACAD/ CAM 0.00 11-08-83 0.00 11-08-83 0.00 09-28-81 0.00 09-28-81 X-227B ACAD/ CAM 0.00 11-08-83 0.00 11-08-83 0.00 09-28-81 0.00 09-28-81 L
APPENDIX B SELECTED DATA SETS FOR TYPE A TEST Presented herein are data sets at arbitrarily selected points during the Type A test. = Tabic B-1 has the data set at the start of the 24 hour test. Table B-2 has the data set after 12 hours of testing. Table B-3 has the' data set at the conclusion of the 24 hour test. Table B-4 has the data set at the start of the induced phase of the test. Table B-5 has the data set at the conclusion of the induced phase of the test. i i . 4
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2 lle.am its.03 , 3 ttt.es tip.it ' 4 117.44 144.96 / ^'
'9 les,*9 19p.99 103.42 ,
0 94.44 99 44 9 4. 0J 99.07 / 7 St' ns Fr.$0 '04.70 00.07 e' ei 6, 07.ps 'ee.04 40.01 40.lg i r 9 7e 3" r , 10 f t.,=to 99.07 71.94 '71.4% ,?t.14 71.30 ',.# j 11 134',a4'j39 11 , .. f f.uctLLS * ' i 4
.9,,9
%7.A4 99.67 >
'/
9 99',19 's 7 Se.ae 99.37 9 Sn.tt 91.99 / ,,' 10 49.94 48.04 f d flSt et0cm Dats tint- nFaguaE0 ^ Ca'LC. malf. DA' &la at45. t,/ LEAR R&tt CALC L(as UPP90 ptep . ftn6 (F9 mags Top Sat PetSS. este 993 C0est 6 0U69 - 8PSlat 2 4 f*L 80thi sfDay 24.ps 6849844 ff4gite 83.98 Linli 9 '9147974tf 09 0.9464462430 GS 42.949 ' O.4G42 afr.0403 0.3047 0.3929
. "e o /
'Uman' log 04fA t iset ma95 - ! e DElla na91 / PELTA Mobl**t flM6**7 h4sseltME 0.t.699:4E c4 ..teraiete et 0.r9t*ssee 09 e.rsiasare er 0.26ee m E es 0.ss194046 o -
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TABLE B-3 . ,
/
- / h4 #
,# 9
.k'.*.'. g? ^_
O 9 e t 04eh 384496 h4IA ( eht6 gp/lepse eees esav lis ihdna eese
$na Ash 8 98$ tlud f AS eta 3351 ene teg 1 lge'll 66*h9 lle61 d tll*40 6a vS a'dle60 6 tll*4( 94 s'floet s
e tte'90 6 66*6 e l setats 6 882*te 66*86 e*diblE 9 66 tI 66*ed d'dlgt6 a ee'46 66*ed d ttiL6
- e 9e08 61*de J*let64 a de al 6l*de e*lef62 le 45t6 tt*44 e*te699 II ite'ot tte**t 2*Gt66e 6sa slet ta seltit tsieree et59 094v 333 e 546ge all ais e e ' e6 63=es ug ot dn31e 9t*es atasse*206L9 0uase9f'6eet6 ele 9t'546eS wt55e df* va'ts e*6et54696( oG .
e&05 I let*t6 let*et 2 lle ek 54t*eg g t ll,,' e b ll ee e lld.*te 6 i'69 6' 6 leb*t4 184*61 let'99 , 9 4%*hW eW
- 6 6 6D*d6 6,*64 i ge t6 44*9 II 60'9L e,.d.'* 694*00 a ee'94 9e' 9g'46
- e. as,et le se se ss si se al sa 41 se al es lI lt6*6e tte'ee 03a3811$
i, 66 ht 6s'os bs 66 6 66:.6 4 6 66 55
- 6. ==
le 6,s os
.. b,.i a9er s 0 i ,i. =s,s isev .,si avis laen as ova =
- s. o ,ae.u,6s is -
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- si. s ,i.. .n.i.nen 66 o .is6- . , e,a avin .sa 2o.u.
nones sel 1 teiN& llula eissisa sil ee, er .9 e .eti45,ets 66 e .ettet6eba e6 9a .l.u.s e .0191 teG o ei:6 6.#466 ev a t'stne snomealCN gvsv u mt65 031 Gtiaf u tfutse4 W9etel - 6 6649.si.p i a si e:444>*4en e9 o al8v va e. . 64estros el m'a$Sna o 46eGe.fllee4 el.. s 6 teen.luD ea ot l l 1 VEIT H-t l l I 1
e e Soap riflFS Unit 3 1733 42/19#94 ees. Data 977 198UT esse 5"8 vet e avg ft4# ave opw citL avs var i 107.J6 99.96 0.71891 7 111.90 94.84 0.73703 3 99.44 a til.62 8.23791 139.97 es.en e.23733 9 102.91 19.no 0.73497 6 99.93 7 99.32 0.21660 88.77 99.38 8.71660 0 47.73 9 St.e4 0.19994 70.09 St.19 0.I8996 10 71.29 68.e7 0.39093 13 139.34 119.14 F.99973 P Sft ste3 at 131e39 p#tesse gast gafs $tt a tyg te 63.g9469 87e at.9ttr9 WLEvL*30.76 t# wee op.78 uwCL e 43,47 va pn e g. 34 918 geype62.#9701 malle 0.99tepee,93g 09 stOS 1 107.44 te7 24 2 109.94 113 47 3 tit,9e tit.73 4 tip.sa tes.94 . 9 tee.ae 30s.99 103.70 6 96.a8 9a.39 94.99 94.'9
- 7 44,31 77.90 83.69 St.se O
9 67.34 a7.44 68.40 47.79 70.99 18 71.ta 74.91 78.02 71.29 71.70 Pl.te 11 139.84 (19.24 1 99,9a 4 97.99 91.43 9 99.no 7 99'.49 99.72 9 90.a7 9t.73 se ee'. ps on.72 183t CLOC8 Datt itPP 9F atuef0 CALC. MASS Dev age gt R. Vint trl utg3 Tat Pet 33 meat. Lisa satt CALC Lese upfie WOU#$ t # UAT matt 993 CONF (PSlot 10faL P0ths 4.00 12:19t3* 9/ teres 3g.70 g.esgeog*teg g1 c.933172974E 09 62.799 1.0040 9.4728 1/Dai 1.egst limit t.efte Summatio9 Data TIME #495 0(Ll4 mas 9 OELta nalleet ilmfeer massefinE 8.90#9993E of s'.3799764E 97 0.2087949f 44 4 7749973E to 0.13699974 43 8.4919679t 87
-6
' TABLE B-5
. H
.t
.l APPENDIX C COMPUTATIONAL PROCEDURE ,
The procedure for computing the containment parameters, leak rates, and statistical confidence limits is given by Quad-Cities procedure QTS 150-T3, Revision 7. A copy of that procedure is presented here. 4 4 l r
QTS 150-T3 Revision 7 CALCULATIONS PERFORMED FOR IPCLRT DATA October 1982 ID/8B Data collected from pressure sensors, dew cells and RTD's located in the containment are processed using the following calculations. If the test is concluded with a test period of < 24 hours, additional calculations given in QTS 150-T9 will be required. A. Average Subvolume Temperature and Dewpoint. T) = I(all RTD's in the jth subvolume) F (1) Number of RTD's in jth subvolume D.P.) = I(all dewofcells F (2) Number dewincells Jehinsubvolume) j th subvolume where T = average temperature of t.he jtn subvolume D.P.J . = average dewpoint of the j th subvolume B. Average Primary Containment Temperature and Dewpoint. T= b L (VFJ ) * (Tj ) j=1 F O) D.P. = Pot (vr.)*(D.e.j>a F J=1 J (c) where T = average containment temperature t' D.P. = avera.ge containment dewpoint VF = volume fraction of the jth subvolume
- NVOL = number of subvolumes If T) is undefined then T) = Tpt for 1 1 j i (NVOL - 2)
T) = T), for j = NVOL - 1 Tj = estimate for j = NVOL ] hd]; 0?2 'i9. 'i i If D.P. is undefined 3 D.P.) = D.P.pg for 1 1 j i (NVOL - 2) D.P.) = D.P.)_1 for j = NVOL - 1 D.P.) = estimmte for j = NVOL l l
[ d. Calculation of Dry Air Pressura. D.P.( K) = 273.16'+ D.P.( F) - 32 1.8 X = 647.27 - D.P.( K) 3 EXPON = X * (Y + Z
- X + C
- X )
(D.P.("K))*(1 + D
- X)
P* = (218.167) * (14.696) ( e(E%?ON
- In(10))
P = I(all absolute pressure gauges) ,p (5) (p,1,) Number of absolute pressure gauges v where Y = 3.2437814 Z = 5.86826 x 10 ~3
~
C = 1.1702379 x 10
~
D = 2.1878462 x 10 P, = volume weighted containment vapor pressure P = containment dry air absolute pressure C, D, X, Y, Z, and EXPON are dewpoint to vapor pressure conversion constants and coefficients. . D. Containment Dry Air Mass. W = (28.97) * (144) * (P) * (288737 - 25 * (LEVEL - 35 )) (6) 1545.33 * (T + 459.69) where W = containment dry air mass 1 LEVEL = reactor water level 289506 = primary containment volume F0R RECCDCUf" Ogni'J3 LRL
!l NOTE This volume is the summation of the subvolumes calculated in QTS 150-T2. These subvolumes were calculated using QTS 150-T8. Since the measured leak race is a difference-in air masses, this number is just as conservative as using the FSAR number.
l
- l
, 5 tbscured L2nk Rato. a
' L (TOTAL) = (WBASr - W.)
I
- 2400 (7)
%/ DAY "i BASE L,(POINT) = (W g - W )
- 2400 ( }
%/ DAY (Ci - t .1) i
- W i.1 i
where Wg = containment dry air mass at t =0 t. t
=
time from start of test at ith data set
=
t g time from start of test at (i-1).th data set W= dry air mass at ith data set W g,7 = dry air mass at (i-1)th data set L,(TOTAL)= measured leakage from the start of test to ath data set L,(POINT)= measured leakage between the last two data sets' F. Statistical Leak Rate and Confidence Limit. LINEAR LEAST SQUARES FITTING THE IPC'RT DATA The method of "Least Squares" is a statisttcal procedure for findtag tne best fitting regression line for a set of measured data. The crtterion for.the best fitting line to a set of data points is that the sum of the squires of the deviations of the observed points from the line must be a minimum. When this criterion is met, a unique best fitting line is obta:.ned based on all of the data points in the ILRT. The value of the leak rate based on the regression is called the statistically average leak rate. Since it is assumed that the leak rate is constant during the testing period, a plot of the measured containment dry air mass versus time would ideally yield a straight line with a negative slope (assuming a non-zero leak race). Obviously, sampling techniques and test conditions are not perfect and consequently the measured values will deviate from the ideal straight line situation.- Based on this statistical process, the calculated leak rate is obtained from the equation: W = At + 3 j where W = contained dry air mass at time t h hk b$
a,, w a - 5 =- calculated dry air maos at time t c 0 A = :siculated leak rate t = cast duration 1 FOR~ REFERENCE OY. Ory Air P. ass (lbs) . 4 Test Ouration (hrs) The values for the Least Squares fit constants A and B are given by: A = {N
- Z(tt) * (V g ) - Itg
- IW } = I(t - E) * (Wg - 0)
{N "r 1(t ) - (It ) } I(t - E) , __ B = IW - A
- It( = {I(tg)
- Z(W )} - {I(t ) * (W }}
N N
- Z(t() - (It )
t where E = the average time for all data seca . . . _ . . _ W' = the average air mass for all data sets i The second formulas are used in the process computer program to reduce i round-off-error. - ' By definition, leakage out of the containment is considered positive leakage; therefore, the statistically average leak rate is given by: d, = (-A) * (2400) g y) (9) STATISTICAL UNCERTAINTIES In order to calculate the 95% confidence limits of the statistically average leak rate, the standard deviation of the least squares slope and the student's TDistribution function are used as follows. 1 N
- I(Wg )2 , (79 )2 q
)
e={ *( )-A} (N-2) N
- I(t g) - (It g) .
When gerforming these calculations on the process computer, Z(Wg)2 and (IWg )* become so large that they overflow. To avoid this problem AW is substituted for Wg. AW g is the difference between Wgand W W E' t ,
" The singlo sid:d T-Distributica with 2 dsgrees of frsadca is approximated by tha follcwing formula from NBS Ecadbook 91: T.E. = 1.646698 + 1.455393 , 1.975971 (N-2) (N-2)' The uppee confidence limit (UCL) is given by UCL = L "
+ a * (TE)
- 2400 ("eight L' DAY) (10)
B
~
I FOR REEREEE 0!il.Y '; i l 1 (final) i i
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