ML19270G936
| ML19270G936 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 04/21/1979 |
| From: | COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML19270G937 | List: |
| References | |
| TASK-06-06, TASK-6-6, TASK-RR NUDOCS 7906210230 | |
| Download: ML19270G936 (53) | |
Text
, .
t DRESDEN UNIT 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST s
2239 234 APRIL 21-23, 1979 790621023o
DRESDEN UNIT 2 ILRT REPORT ABSTRACT A. INTRODUCTION A.1. Purpose A.2. Test Requirement A.3 Summary of Results B. TEST METHOD UTILIZED B.1. Basic Technique B.2. Supplemental Verification Test B.3 Linear Regression Analysis C. TEST INSTRUMENTATION AND CALIBRATION C.1. Types of Sensors Used C.2. ILRT Console C.3 Data Acquisition System C.4. Instrumentation Calibration C.S. Instrument Error Analysis - Application D. CONTAINMENT REPRESENTATION D.1. Structural Data D.2. Containment Survey D.3 Instrumentation Placement D.4. Pressurization System E: CALCULATIONS PERFORMED E.1. Volume Weighting Factors E.2. Data Reduction E.3 Least Squares Fit E.4. Computer Program E.5 Leak Rate Compensation for Non-Vented Penetrations F. CONTAINMENT PRESSURIZATION F.1. Preparation F.2. Containment instrumentation F.3 Log Entries From ILRT Pressurization
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t ,
G G. TWENTY-FOUR HOUR TEST EXECUTION G.I. Twenty-Four Hour Test Log G.2. Final Calculated Leak Rate H. SUPPLEMENTAL TEST H.1. Purpose of Test H.2. Magnitude of Induced Leakage
- 1. TEST EVALUATION APPENDIX A: Type A Test Instrument Accuracy Error Analysis APPENDIX B: Type A Test Data APPENDIX C: Type B and C Test Results
,_ 2239 236
O 1
r ABSTRACT The 1979 Dresden Unit 2 Integrated Leak Rate Test (ILRT) was per-formed in accordance with the requirements of 10 CFR Part 50, Appendix J, Section V.B.3 f rom April 21 to April 23 Type A, B, and C test yleided a total containment leakage of .3858 WT%/ day, which was well below the Dresden Technical Specification for the allowable operational leak rate of 1.2 WT%/ day.
2239 237
. i A. INTRODUCTION A.1. Purpose of Test The purpose of the Dresden Unit 2 Integrated Leak Rate Test is to measure the reactor primary containment leak rate while at a test pressure equal to that which would occur during loss of coolant accident conditions.
This report is designed to give a detailed description of the test efforts and the final results. These results are reported in accordance with 10 CFR 50, Appendix J, " Primary Reactor Containment Leakage Testing For Water Cooled Power Reactors."
A.2. Test Requirements All Leak Rate Tests performed during the recent refueling outage were done in accordance with schedules and acceptance criteria established by 10 CFR Part 50, Appendix J, American National Standard ANSI N45.4 1972, and by the Unit Technical Specifications. The maximum acceptable leak rates are:
Type A Test
- a. 24-Hour Phase
- 1. 1.6 weight %/ Day (L to) Maximum Allowable
- 2. 1.2 weight %/ Day (Lp) Maximum Operational
- b. Supplemental Phase
+[0.40 weight %/ Day (0.25 Lp)
Type B and C Tests
- a. Double-gasketed seals 10% Lt o total combined leakage
- b. Testable penetrations and isolation valves 30% Lto total com-bined leakage.
- c. Any one penetration or isolation valve except the main steam isolation valves.
5% Lt o
- d. Any one main steam isolation valve 11.5 SCFM @ 25 PSIG.
The Type A test was conducted in accordance with Technical Staff sur-veillance procedure DTS-1600-7, revision 3 This procedure incorporates all the test requirements.
A.3 Summary of Results The Dresden Unit 2 total primary containment integrated leak rate was found to be 0.3858 weight %/ Day at a test pressure of 48 PSIG. This total leak rate includes the 24-hour phase Type A test result and several Type C
-u- 2239 238
test results for process lines not drained and vented as required by 10 CFR Part 50, Appendix J. The associated upper 95% confidence limit was 0.3935 weight %/ day.
The supplemental tes': result was 0.4530 weight %/ day with an upper 95% confidence limit of 0.5054 weight %/ day. This result is to be com-pared with the sum of the 24-hour phase uncompensated result of 0.2515 weight %/ day and the induced leakage of 0.2515 weight %/ day.
2239 239 m
B. TEST METHOD UTILIZED B.1. Basic Technique Two techniques may be used in performing the Type A test. The first technique, which is no longer used at Dresden, is the Reference Vessel Method. This method was last used for the Unit 1 Type A test performed in 1974. The second technique is the Absolute Method. The Absolute Method, which was used on the most recent Unit 2 Type A test, uses the ideal gas law to calculate changes in dry air mass as a function of pres-sure and temperature. Comaensation for water vapor pressure is taken into account when the dry air mass within the containment is calculated.
Leakage of mass (which is assumed to be constant) from the containment during the Type A test Interval can be determined by estabilshing the rate of mass loss.
B.2. Supplemental Verification Test The verification test (induced leakage) was performed by intentionally inducing a controlled leak of a magnitude approximately equal to that measured during the 24-hour phase of the Type A test. This induced leak was superimposed on the previously determined leak rate. The degree of detectability of the combined leakage provided a basis for resolving any uncertainties associated with the 24-hour phase of the test.
B.3. Linear Regression Analysis Since it is assumed that the leak 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 (assuming a non-zero leak rate).- Obviously, sampling techniques and test conditions are not perfect and consequently the measured values will deviate from the ideal straight line situation.
A "Least Square" statistical analysis was performed to establish a regression line for the mass versus time parameters af ter each set of data was obtained. The slope of the regression line is called the statistically averaged leak rate. It was this quantity that was compared to the Techni-cal Specification Limit L to-Associated with the statistical leak rate is an upper 95% confidence limit leak rate. The calculation of this upper limit is based on the standard deviation of the regression lines and the one-sided Student's T-Distribution function. A procedural requirement specified that the 95%
confidence limit was to be less than the Technical Specification Limit L . p Both the regression line and the associated confidence limit were cal-culated after each set of data was obtained.
2:239 240
C. TEST INSTRUMENTATION AND CAllBRATION C.1. Types of Sensors Used Two types of sensors were placed inside of the primary containment during the test. The first type of sensor used was a resistance tempera-ture device (RTD) designed to measure dry bulb temperature. The RTD's used during the test were supplied by two different manufacturers. Burns Engi-neering, Inc. of Minneapolis, Minnesota, supplied 18 RTD's; while Hy-Cal Engineering of Santa Fe Springs, California, supplied the remaining 12 RTD's. The RTD detects changes in temperature through varying amounts of resistance within a platinum wire, responding linearly to AT. The second type of sensor used during the test was manufactured by the Foxboro Company, Foxboro, Massachusetts. It was designed to measure dew point, using a lithium chloride salt and a heating element in conjunction with r RTD, which as a unit responds to ambient dew point. There were 8 dew calls used during the ILRT.
C.2. ILRT Console All primary containment dry bulb termperatures, reactor level pressures, and (ew point temperatures in addition to test time were permanently re-corded and digitally displayed on the Volumetrics ILRT console 14627 LED displays enabled the console operator to visually monitor the raw data as it appeared at regular scan intervals or manually select specific channels for specific data. The operator also received, at regular intervals, two permanent records of the scan data. One record was a typed paper tape dis-playing the raw test data. The second appeared in the form of a binary punched tape which was fed into the on-site process computer in order to perform all required test calculations.
In addition to the display electronics enclosed in the console, there were two precision pressure gages and two clocks. The clocks and pressure gages were redundant features included within the console to insure rella-bility.
A diagram of the ILRT console and related electronics is shown in Figure C.2.a. All sensor information sent to the data acquisition console was transmitted through shielded cable penetrating the primary containment.
C.3 Data Accuisition System The ILRT Volumetric Console, sensors, and multiplexer comprise the ILRT Data Acquisition System, which was used to perform the Type A test at Dresden. A description of the ILRT console and sensors was given in Section C.I. and C.2. The system would not be complete without the multiplexer located within the containment throughout the test.
In order to minimize the number of conductors penetrating the primary containment, the Data Acquisition System Instrumentation was subdivided into two major parts. The multiplexer unit was the tocal point for all the re-sistance temperature detectors (RTD) and the dewcells. This subsystem con-sisted of the solid state signal conditioning bridge circuit boards that are used to calibrate the system and the dual redundant electronic scanners which feed the sensor signal through the primary containment to the console 2239 241
outside. The second major part of the system was the Data Acquisition Unit (DAU). The DAU assembled all the scan data and produced two permanent records.
These components seen as a whole system provide a full automatic multi-point data measuring and processing system capable of measuring absolute pressure, dewpoint temperature, dry bulb temperature, and test duration.
During the supplemental test, it also monitored the induced leak rate.
(See figure C.3.a for a block diagram of the system interconnections.)
C.4. Instrument Calibration A major portion of the time spent in preparation for the U-2 ILRT was devoted to instrument calibration. All RTD's were calibrated to within
+ .5*F of actual temperature by using an oil bath and an RTD standard which is traceable to the National Bureau of Standards (NBS). The dew cells were calibrated to within + 3.0*F of actual temperature by using a dew point hygrometer (traceable to NBS) and various atmospheres maintaining con-stant relative humidities.
The precision pressure gages were calibrated to within j; .015 PSI A of actual pressure using a portable standard traceable to NBS.
The flowmeter used for the induced leakage portion of the ILRT was cali-brated using a transfer standard which was traceable to NBS and accurate to within f; .25 SCFM.
Table C.4.a shows the specifications for the instrumentation utilized in the Type A test. All of the instruments were calibrated prior to use, as required by ANSI N45.4-1972. The quantity of sensors used was based on the containment size and the system error analysis.
Throughout the test, ambient atmospheric conditions were monitored as
' required by ANSI N45.4-1972. All of the instruments used were calibrated prior to the test and were calibrated using a minimum of 3 reference points to establish an accurate calibration curve.
C.S. Instrumentation Error Analysis - Application To ensure that the instrumentation used during the ILRT was accurate enough to measure minute changes in containment mass, an i ns t rumen ta t ion error analysis was performed prior to the test in accordance with ANSI N45.4-1972. The instrumentation system error was calculated in two parts. The first, and most important calculation, was performed to determine the error due to system repeatability; the second, to determine the error due to system accuracy. The results were 0.00175 WT%/ Day and 0.14902 WTt/ Day, respectively.
Combining these two errors yielded a total system error of 0.14903 WTt/ Day.
The instrumentation error is used only to illustrate the system's capa-bility to measure the required parameters that are necessary for calculation of the primary containment leak rate. The instrumentation error is always present in the data and is incorporated in the 95% confidence limit in the form of data scatter. Procedures required that the error due to accuracy and repeatability be less than .25 Lp (0.4 VT%/ Day) .
2239 242
PAPER PUNCH AMBIENT MULTI- RTD.
ELEXER .
AMBIENT PRESSURE MASS FIDI
~
DATE ACQUISITION CONSOLE
, PJOB 29 8 .
RTD's DEW CELLS 2239 243 ILRT CONSOLE AND INPUT SYSTEMS FIGURE C.2.a O
_9_
29 RTD's PPG 1 PPG 2 o a u DIGITAL DIGITAL 29 RTD DISPLAY DISPLAY SIGNAL ENCODER ENCODER PAPER CONDITIONERS TAPE PUNCH u . o o n 4
DATA SCANNER ACQUISITION RAW DATA
[I[
PRINTER 8 DEWCELL SIGNAL MASS FLOW CONDITIONERS PANEL, DISPLAY
.. h g AMB PRESS AMB TEMP RTD #30A & B SIGNAL SIGNAL SIGNAL CONDIT ONER CONDIT ONFR CONDITIONER MASS FLOW n h o 1, 8 DEWCELLS SIGNAL CONDITIONER AMB PRESS AMB TEMP h SENSOR RTD RTD #30A & B MASS FLOW SENSOR TO DEWCELL HEATERS .
28 VAC
'8 TRANSFORMER
=: 28 VAC RELAY ILRT SYSTEM BLOCK DIAGRAM Ps) Figure C.3.a rN) TRANSFORMER led 28 VAC N
4 A
TABLE C.4.a -
INSTRUMENT QUANTITY / USAGE RANGE ACCURACY REPEATABILITY Precision Pressure 2 - Containment Pressure 0-100 psia j- 0.015 psia f; 0.001 psia Gauge RTD 30 - Containment Temp. 32-250*F j; 0. 38* F f; 0.0$* F Dewcell 8 - Containment Dewpoint 32-140 F +;2.74*F . j; 0.0$* F s.
Mass Flow Meter 1 - Induced Leak Rate 0-10 SCFM f;.25 SCFM f;0.0 SCFM i
Ambient Temp. RTD 1 - Ambient Temp.32-250'F f; 0. 38* F j 0.0$*F Ambient Press. 1 - Ambient Press. 0-20 psia --- ---
Sling Psychrometer 1 - Relative Humidity 0-100% R.H. --- ---
N N
LeJ N
- b LT1
8 D. CONTAINMENT REPRESENTATION D.1. Structural Data The Unit 2, primary containment provides a multibarrier pressure sup-pression containment enploying containment-in-depth principles in design.
The containment systems are composed of a primary containment and the Pressure Suppression System, which when taken together enclosed a total free air space of 288966 ft3 The primary containment consists of a dry-well, which encloses a reactor vessel, a pressure suppression chamber which stores a large volume of water, a connecting vent system between the dry-well and the water pool, isolation valves, containment cooling systems, and other service equipment. See Figure D.2.a.
The performance objectives of the primary containment system are: (1) to provide a barrier which in the unlikely event of a loss-of-coolant acci-dent, will control the release of fission products to the secondary con-tainment, and (2) to rapidly reduce the pressure in the containment re-suiting from the loss-of-coolant accident. In order to meet these objectives, the containment was designed to withstand a design pressure of 62 psig with a leakage of 0.5 WT%/ Day. To assure that the containment could structurally meet these criteria, the drywell was designed using a steel pressure vessel with a spherical lower portion and a cylindrical upper portion. See Figure D.2.a. The steel head and shell of the drywell are fabricated of SA-212 GRB plate manufactured to A-300 requirements. The top head closure is made with a double tongue and grove seal, which will permit periodic checks for tight-ness without pressurizing the entire vessel. The drywell is enclosed in re-Inforced concrete for shielding purposes and to provide additional resistance to deformation and buckling of the drywell over areas where concrete backs up
, the steel s, hell.
An integral part of the containment is the pressure suppression chamber, which is also pressurized during the ILRT. The pressure suppression chamber is a steel pressure vessel in the shape of a Torus below and encircling the drywell which contains 112,203 f t.3 of water in its 109 f t. major diameter.
The Torus free air volume is 118529 ft3 D .' 2 . Containment Survey .
In order to establish the containment temperature and humidity tendencies for regional variations, an area survey was performed. This survey complied with ANSI N45.4-1972 and was performed by Technical Staff personnel prior to the instrumentation installation. The sensor locations as specified by this survey are indicated in Table D.2.a. (Refer to Figure D.2.a for an ideal-Ized view of the containment structure and the zoning configuration used.)
D.3. Instrumentation Placement Figures D.3.a through D.3.g indicate exactly where the RTD's and dew cells were placed within the primary containment. The dew cell placement is indicated by the initial D, and the RTD placement is indicated by the initial R.
To avoid local temperature variations, all RTD's and dew cells were placed at least three feet from any pipe, wall, pump, motor, etc.
_i2 2239 246
I All sensors were placed in the containment immediately before the ILRT to minimize the possibility of sensor wire or sensor damage due to main-tenance and cleanup work being performed while the containment was open.
A special effort was made to place two RTD's in that subvolume between the reactor and the biological shield. See Figure D.3.b. This was done to minimize the transients in test data caused by AT change, in that sub-volume due to changes in reactor temperature.
Two fans were placed inside the Torus as indicated in Figure D.3 9 To insure that RTD 26 and RTD 28 were not affected by the draf t caused by the fans, they were placed off to the side of the fans at a distance greater than 3 feet.
Due to the impracticality of installing temperature and humidity sensors inside the vessel (Subvolume 10), several assumptions were made concerning the air space within. The reactor vessel air space was assumed to be saturated and at an equilibrium temperature with the water. To measure the reactor water temperature, an RTD was placed in the chutdown cooling loop between the shutdown cooling pump and the heat exchanger. This temperature was then used as the drybulb and wetbulb temperature for subvolume 10.
D.4. Pressurization System Primary containment pressurization was accomplished with two 3000 SCFM electric compressors connected to a 4" pressurization line.
A condenser-af ter cooler was located outside the reactor building with the air compressors. Refer to Figure D.4.a for a plan view.
2239 247
s TABLE D.2.a DRESDEN U-2 ILRT SENSOR LOCATION SENSOR TYPE I.D. NUMBER SUBVOLUME ZONE ELEVATI0f; AZIMUTH RTD R1 1 601' 190*
RTD R2 1 601' 10*
Dewcell D1 1 601' 190*
RTD R3 2 556' 330*
RTD R4 2 556' 150*
RTD R5 3 574' 270*
RTD R6. 3 574' 30*
RTD R7 3 574' 150*
Dewcell D2 3 574' 2 70*
RTD R8 4 545' 350' RTD R9 4 545' 220*
RTD RIO 4 545' 120*
Dewcell D3 4 545' 120*
RTD R11 5 531' 0*
RTD R12 5 531' 190*
RTD R13 5 531' 270*
RTD R14 5 531' 90*
Dewcell DS 5 531' 260*
RTD R15 6 520' 165*
RTD R16 6 520' 60*
~
RTD R17 6 520' 300*
Dewcell D6 6 520' 165*
RTD R18 7 505' 5*
RTD R19 7 505' 185*
RTD R20 8 509' 140*
RTD R21 8 509' 230*
RTD R22 8 509' 50*
RTD R23 8 509' 320*
Dewcell D4 8 509' 50' RTD R24 9 504' 223*
RTD R25 9 504' 168*
RTD R26 9 504' 280*
RTD R27 9 504' 336*
RTD R28 9 504' 101*
RTD R29 9 504' 45" Dewce11 D9 9 504' 168*
Dewcell 010 9 504' 336' RTD R30B 10 Located in Shutdown Cooling Loop 8 2239 249 Subvolume 1, 589'-3" to 604' N
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I Subvolume 2.
and biological shleid 52 c :p l' $s\ 4 /
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UNIT 2. PRESSURE SUPPRESSION CONTAINMENT SYSTEH FIGURE D.2.a
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Core Spray 1403-10" a e r
1302-14" b k l
Elevation 601'
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e Spray 1404-10" UNIT 2 DRYNELL
, ELEVATION 574' .
FIGURE D.3.a Core Spray 1403-10"
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,I-HPCI 2305-10"
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ore Spray 1404-10" UNIT 2 DRWELL ELEVATION 556' 02b9 L
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r Shutdown Cooling 1001A-16" k
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1, UNIT 2 DRYWELL I c' ELEVATION 545' 2239 252 FIGURE D.3.c
Shutdown Coolino C 1001A-16" B Recire i Motor
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UNIT 2 DRYWELL ELEVAT!0N 531' 22
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FIGURE D.3.d i Lo PJ 32048-18" - FV 3204A-18" 4
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B Recire M HOtOr 8 '
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2018-28" 1506-16" I
- e-Recirc 20lA-28" 5 -16" ,
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UNIT 2 ORYWELL ELEVATION 520' D FIGURE D.3.e 2239 254 1
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326' 34*
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, Header 1501-24" El. 483' 8' 214
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UNIT 2 TORUS FIGU,, D.3.g w .
2239 256 fom N )k AI3bs a
U-2 Primary Containment 4" Pipe U-2 Containment (Seconda ry) l After Cooler
_1_ _1_
Y ELECTRIC AIR rnwoorgsno ,_
T ELECTRIC AIR COMPRESSOR 2239 257 CONTAINMENT PRESSURIZATI ON SYSTEM FIGURE D.4.a
E. CALCULATIONS PERFORMED E.1. Volume Weighting Factors Due to the size and shape of the primary containment, a mathematical model was developed to account for the effects of temperature stratification and local temperature variations. The containment volume was theoretically divided into ten subvolumes with weighting factors assigned to each. (The value of the weighting factor is equivalent to the fractional part of the total containment volume occupied by the associated subvolume.) The volumes of the larger pieces of equipment were taken into account when calculating the subvolumes. (See Figure D.2.a for a diagram of the idealized contain-ment and zoning configuration used.) Table E.1.a IIsts the subvolume weighting factors associated with each zone.
E.2. Data Reduction Before the ideal gas law could be applied for obtaining the contained dry air mass, the raw data had to be reduced to a single dry air pressure and temperature. The total containment absolute pressure was determined by arithmetica11y averaging the two precision pressure gauges. The average containment temperature and dewpoint were obtained by utilizing the same application of the volume weighting factors. Like sensors within a sub-volume were arithmetically averaged to determine the mean atmospheric con-ditions for the subvolume. Any subvolume void of a sensor type was assumed to have the same average value as the next subvolume in sequence. The sum of the products of the subvolume averages and respective weighting factors yielded the average containment temperature and dewpoint. The dewpoint was then converted to vapor pressure and subtracted from the average total con-
, tainment pressure, yielding absolute dry air pressure. The following mathe-matical egressions summarize the data reduction process.
Average Subvolume Temperature and Dewpoint.
TJ = I(al1 ooerable RTD's in J th, subvolume) ,p Number of operable RTD's in the jth subvolume D.P.J = E(all operable dewcells in the J th subvolume) o g Nirmber of operable dewceiIs in j n subvolume where TJ = average temperature of the j th subvolume D.P.j average dewpoint of the jth subvolume Primary Containment Temperature and Dry Air Pressure
- NVOL I (VFj ) (TJ )
- F j=1 if TJ = undefined, then TJ = T(J + 1) for 1 < J < (NVOL-2)
TJ = T(j - 1) for j = NVOL - 1 TJ = estimate for J = NVOL}g }}g D.P. = Ny0L (VFj) (D.P.j)
- F
~
J-1 If D.P.J = undefined, then D.P.J = D.P(j + 1) for 1 < J < (NVOL-2) D.P.J = D.P(J - 1) for J = NVOL-1 0.P.J = estimate for J = NVOL D. P. (* K) = 273.16 + D. P . (* F) - 32 1.8 X = 647.27 - D.P. (*K) A = 3.2437814 Z = 5.86826 x 10-3 C = 1.1702379 x 10-8 D = 2.1878462 x 10-3 EXPON = X(A + ZX + CX3 ) (D.P. (' K)) (1 + DX) py , (218.167)(14.696) pg,
,(EXPON in 10)
Pt = Pj+P2 2 PSIA P = Pt - Pv PSIA W = (28.97)(144)(P)((total volume - (leve1 - 50)(28.635)) Lbs. 1545.33 (T + 459.69) where: NVOL = number of primary containment subvolumes VFJ = volume weighting factor of the Jth subvolume T = volume weighted containment temperature D.P. = volume weighted containment dewpoint X, A, Z, C, D, EXPON = dewpoint to vapor pressure conversion constants and coefficients Pv = volume weighted containment vapor pressure Pt = total absolute containment pressure P = contained dry air absolute pressure W = contained dry air mass Level = reactor water level NOTE: The subvolume numbering sequence is from the top to the bottom of the containment. E.3. Least Squares Fit The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured data. The criterion for the best fitting line to a set of data points is that the sum of the squares 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 obtained based on all of the data points. Based on this statistical process, the calculated statistical leak rate is obtained from the equation: W = At + B where W = contained dry air mass at time t (Ibs) 2239 259
-2 5-
I where B = calculated contained dry air mass at time t = 0 (1bs) A = calculated leak rate (1bs/hr) t = test duration (hours) The values of the constants A and B such that the regression line is best fitting to the data, while maintaining minimum round-off error, are: A = E((tl - B (WI - U)) (E(tl - T)4) B = ((I(ti)2)(IWI)) - ((Iti)(I(ti)(WI))) (NE(ti)2) - (Sti)4 Be definition, leakage out of the primary containment is considered posi-tive leakage; therefore, the statistically average leak rate in weight percent per day is given by: Ls = (-A)(2400)/(B) (weight %/ day) In order to calculate the 95% confidence limit of the statistically average leak rate, the standard deviation of the least squares slope and the Student's T-Distribution function are used as follows: [, 1 NE(Wi)2 , (39;)2 -A 2 1/2 (N-2) NE(ti)4 - (Sti)4 (TE)(2400) UCL = Ls+ B where TE = 1.645 + 1.5068 + 1.7136 (N-2) (N-2)2 N = number of data sets ti = test duration at the Ith data set WI = contained dry air mass at the Ith data set 8 = standard deviation of least squares slope TE = value of the single-sided T-Distribution function with 2 degrees of freedom Ls = calculated leak rate in weight %/ day UCL = 95% upper confidence limit in weight %/ day E.4. Computer Program in order to expedite the data reduction and statistical computations, the Unit 2/3 process computer was utilized. The raw data was recorded on paper tape by means of a paper punch system connected to the ILRT concole. The com-plete data set was then transferred to the computer room where it was fed into the computer by a paper tape reader. The number of sensors within a subvolume and the associated weighting factors were programmable constants established prior to the start of the test. Once entered, the raw data was duplicated for verification, stored in memory for future reference, reduced, and statistically analyzed. All pertinent computational results were printed with the data verification checklist. Data was recorded and analyzed at 10 minute intervals. In addition to the above mentioned computations, included with each data set output were the " total time" and " point-to-point" measured leak rates.
- 2 6-2239 260
These quantitles are based on the following expressions: q Lm(TOTAL) = W Base - WI 2400 %/ day
, t; W Base W
Lm(POINT) = i Wi 2400 %/ day tg - t[_; Wg _1 where W Base = mass of contained air at t = 0 (1bs) WI = mass of contained air at t = I hours (1bs) ti = test duration at the Ith data set (hours) E.5 Leak Rate Compensation for Non-Vented Penetrations The actual result of the Type "A" test as performed was .2515 weight
%/ day with a 95% confidence level of .2592 weight %/ day. The test was performed with the following penetrations not drained and vented. Included with each penetration listed is the maximum through leakage as determined by Type C testing.
Leak Rate Penetration SCFH Weight %/ day X 107 ASB Feedwater Check Valves 27.10 0.05533 X 149 ASB Core Spray 6.90 0.01408 X 145/150 LPCI 15.69 0.03204 X 111 A5B Shutdown Cooling 0.00 0.0 X 138 SBLC 1.26 0.00257 X 122 Primary Sample 0.02 0.00004 X 108 Isolation Condenser 1.61 0.00328 CAM Sample 0.78 0.00159 CRD Return 4.04 0.00825 Reactor Cleanup 8.36 0.01707 Total 65.76 0.1343 2239 261
-27
f TABLE E.1.a TEMPERATURE AND HUMIDITY WEIGHTING FACTORS SUB VOLUME VOLUME (FT3 ) WElGHTING FACTOR 1 11373 0.03936 2 3081 0.01066 3 20281 0.07018 4 23043 0.07974 5 30819 0.10665 6 26363 0.09123 7 7226 0.02501-8 41828 0.14475 9 118529 0.41018 10 6423 0.02223 2239 262
-2 8-
F. CONTAINMENT PRESSURIZATION F.1. P repa ra t ion The following major events were completed prior to containment pres-surization as required by 10 CFR Part 50, Appendix J, and ANSI N45.4-1972:
- 1. Satisfactory completion of all Type B & C Leak Rate Tests.
- 2. Primary containment temperature and humidity survey.
3 Calibration of all instrumentation.
- 4. Instrumentation error analysis calculation.
5 Visual containment inspection.
- 6. Venting of the reactor vessel to the primary containment atmosphere.
Two fans were installed in the torus to provide air recirculation. This was done to comply with earlier recommendations made by Sargent and Lundy. Training was provided to all tech'nical personnel involved in the ILRT. The six hours of training was designed to familiarize personnel with the test instrumentation, computer program, and necessary scheduling for the successful completion of the 1979 ILRT. Two 3000 SCFM 4KV electric compressors were brought on site to supply clean dry air to the primary containment through a four-inch pipe tied into the LPCI system. These compressors not only served as a source of oil free air but enabled Dresden personnel to realize 48 PSIG containment pressure in a minimal amount of time. To reduce air temperature out of the compressor from 100* F to 60* F, a 4800 SCFM water cooled af tercooler was placed between the electric compressor and the containment. F.2. Containment Instrumentation ILRT sensces were placed within the containment shortly before the test. Care was taken so as to place the sensors in those areas dictated by the temperature and hunidity survey performed before the test. All sensors were kept at a distance of three feet or farther from any pump, motor, or piece of piping. This was done so local temperature vari-ations would not overly influence the real average subvolume temperature re-corded by the sensor in that subvolume. In preparation for the test, special care was taken to keep all sensors out of any airflow which might be caused by the compressor during pressuri-zation or the ventilation fans placed in the torus. F.3 Log Entries From ILRT Pressurization At 1925 hours on April 21, drywell pressurization began. Subsequent proceeding events are as follows: 2239 26}
ILRT LOG Day Time Event 4/21/79 1925 Started pressurizing 1935 Reached 2 psig. Technical Staff personnel began " snooping" for leaks. 2045 Compressor shut down after containment reached 15 psig. 4/22/79 0040 Completed 15 psig hold. Containment is stabilized. 0050 Started to pressurize after 15 psig hold point 0400 Containment pressure is 49.8 psig. Com-pressors are being shut down holding for stabilization. 2239 264 30-
G. TWENTY-FOUR HOUR TEST EXECUTION G.I. Twenty-Four Hour Test Log The Unit 2 primary containment stabilized at test pressure from 0412 hours to 0912 hours on 4/22/79 4/22/79 0912 Containment was stabilized and 24-hour test was begun. Reactor water level 51". Torus water level -3". Shutdown cooling temperature 139'F. 1200 Calculated leak .4744 Ut%/ Day UCL 5366 Wt%/ Day 2102 Calculated leak 3484 Wt%/ Day UCL 3641 it%/ Day 2115 Reactor water level 51" Torus water level -2.7" Shutdown cooling temperature 134*F 4/23/79 0912 24-hour test complete. 144 data sets taken during test. 0912 Calculated leak .2515 wt%/ Day UCL .2592 Wtt/ Day G.2. Final Calculated Leak Rate The final calculated leak rate was found to be .2515 Wt%/ Day. The upper 95% confidence limit was .2592 wt%/ Day. Since these values are well within the Technical Specification limit of 1.2 Ut%/ Day for reactor start-up, the Unit 2 primary containment integrity remains intact. 2239 265 H. SUPPLEMENTAL TEST H.1. Purpose of Test The purpose of the induced portion of the ILRT is intended to verify that instrumentation and method which was used and recorded during the 24-hour portion of the ILRT is valid. The Supplemental Test portion of the ILRT pro-cedure involves placing the calibrated leak system into operation af ter the leakage-rate test in progress is completed. The flowmeter readings are then recorded at least hourly. Concurrently, readings from the ILRT data acqui-sition system are analyzed to determine the magnitude of the total containment leakage. If the criteria established by the following equation is satisfied, the ILRT calculated leakage is considered acceptable and the test is termi-nated. L (induced phase total) - L (24 hour phase) + L (Superimposed) < 0.25 Lp containment calcu- - calculated leck Leak Rate -" lated leak rate H.2. Maanitude of Induced Leakage The induced portion of the ILRT began at 1020 hours on 4/23/79 and was terminated at 1512 hours on 4/23/79 A flow of 2.07 SCFM was induced to an ambient pressure of 14.7 Psi. The new calculated leak rate was 0.4530 Wt%/ Day with an upper 95% confidence limit of 0.5054 wt%/ Day. The induced leakage was allowed to run for more than four hours to account for transients which occurred as a result of valving adjustments in the reactor shutdown cooling loop. During the .duced portion cf the test, adjustments were made to the lineup of the Rx uollding Closed Cooling Water System, which caused a change in the shutdown cooling water temocrature. The result of the supplemental Induced leakage test are acceptable, provided that the difference between the supplemental test data and the Type A test data is within 0.25 Lp. Since the difference recorded during the test was 0.05 WT%/ Day, all requirements were met to stay within the 0.4 Wt%/ Day limits. 2239 266 I. TEST EVALUATION Both the statistical leak rate and the upper confidence limit, corrected for process lines not vented or drained, were well within all Technical Specification ilmits. , Reactor vessel temperature transients were minimized by leaving the shut-down cooling system (B heat exchanger) in steady-state operation throughout the test. Reactor water temperature was controlled by varying the reactor building closed cooling water (RBCCW) supply flow rate to the heat exchanger. Remote throttling of the RBCCW discharge valve provided this method for stabilizing reactor water temperature. Approximately 2 hours and 30 minutes into the induced leakage portion of the test, the reactor water temperature decreased f rom 139' F to 131 F in 20 minutes. By throttling the RBCCW discharge valve, the temperature was stabilized at 131* F and then slowly increased to 135* F, where it remained until the end of the test. This temperature transient was attributed to the change over of RBCCW pumps and HT exchangers by the coerating Department. Upon depressurizat f or., the drywell access lock and one torus access hatch were opened for removal of test instrumentation. A Type "B" Local Leak Rate Test was performed on both the drywell access lock and torus access hatch after final closure. Both tests exhibited zero leakage. The station considers the test method to have met or exceeded all Type A test requirements; therefore, the calculated containment leak rate of 0.3858 4t%/ Day is considered to be a valid result which compares favorably with the operational limit of 1.2 Wt%/ Day. 2239 267
APPENDIX x TYPE A TEST INSTRUMENT ACCURACY ERROR ANALYSIS 2239 268 e e
.p_
APPENDlX A INSTRUMENT ACCURACY ERROR ANALYSIS Per ARSI N45.4-1972, the computation of the leak rate is given by the equation: L(%) = 2_4, (100) W1 -W2 = 2400 1 - TIP2 _H ,, Wj , H , T2Pj where L = primary containment leak rate (%/ day) H = time interval between data sets #1 & #2 (hours) W1 = weight of the contained dry air mass at test data set #1 (lbs) W2 = weight of the contained dry air mass at test data set .#2 (1bs) Tj = volume weighted primary containment temperature at test data set #1 (* R) T2 = volume weighted primary containment temperature at test data set #2 ( R) P1 = dry air absolute pressure at test data set #1 (psla) P2 = dry air absolute pressure at test data set #2 (psia) The standard variation on L due to the uncertainties in the measured vari-ables is given by: 2 (L) = 2400 BL g (P1 ) 2 + BLf(P) 2 + BL[(Tj) + BL[(T) 2 8 Pj 8P 8T H _ _ _2 , 8T) _ _2 , _ substituting H = 24 hours BL = TP7 _J 3 8 Pj T2PjZ ~ Pj BL = T1 _J SP2 -T 2j P - P) BL = P7 _J B T) -T P21 T-2 BL = TP3 3 _J BT2 TP2j 'T 2 assuming P 1 = P2 = F and Tj= T2
- Y where F = average absolute dry air pressure (psia)
T = average volume weighted primary containment absolute temperature ( R)
Therefore, 1
$(L) = 100 2 $(P) + 2 f(T) 2
. . P. .. T. __
- 1. Calculation of5(T)
" NVOL I (VFJ) (Tave, j)
J=1 where VFJ = the volume weighting factors NVOL = the number of containment subvolumes Tave, J = the average absolute temperature in the Jth subvolume Tave, J = 3 TI J i=1 N y where TI,J = the absolute temperature of the Ith RTD in the Jth subvolume NJ = number of RTD's in the Jth subvolume now,[(V) is calculated f rom f (T) = NVOL I BT [(Tave,j) 8 Tave, j
.- J=1 ~
where BY = VFJ BTave, J [(Tave, J) = RTD accuracy (Nj)2 therefore, NVOL [(T) = I (VFj) RTD accuracy j=1 (Hj)
- 2. Calculation of [('P")
d(P) = [(P)2T + 8(Py)2 i where PT = total absolute primary containment pressure Py = partial pressure of water vapor in the primary containment substituting [(P) = PPC accuracy T II of PPG's)i 2239 270 [(pV) NVOL I (VFj) (Dewcell accuracy) J-1 (ny)g
-3 6-
where PPG = precision pressure gage NJ = number of dewcells in the Jth subvolume therefore, - -
- NVOL
$(P)= (PPG accuracy) 2 + (E (VFJ)(dewcell accuracy))2 i
( of PPG's)t_ J=1 (Nj)2 _ _7 _ 3 The above analysis was performed twice; once for system accuracy and once for system repeatability. The following chart shows the various sensor errors as determi -ed by pretest ralibration. RTD Sensor Zone 1-10 PPG DEWCELL Accuracy t o . 38' F +0.015 PSIA 22. 7C F Repeatability 20.013'F +0.001 PSIA 10.0092'F Using the above quantities, the system error due to instrument accuracy was found to be 10.14902 weight %/ day. Similarly, the system error due to Instrument repeatability was 0.00175 weight
%/ day. A total system error of 20.14903 weight %/ day was deter-mined by the following Identity.
(L) = $(L) accuracy + [(L)2 repeatability, I 2239 271
0 APPENDIX 8 TYPE A TEST GRAPHS 2239 272
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APPENDlX C TYPE B AND C TEST RESULTS 2239 275 O
~
LOCAL LEAK RATE TESTS PERFORMED DURING TiiE UtilT 2 REFUELil1G OUTAGE OF 1979 TYPE OF PENETRATION: MKl'tf STPAM'~SOLATi0tl l VALVES TESTED.AT.25 PSIG. INITIAL INITIAL TitRU FINAL FillAL TilRU TEST PENETRATION LEAK RATE LEAKAGE LEAK RATE LEAKAGE I flUMBER ' NUMBER' VOLUME'BEING' TESTED ^ WT t/ DAY VT t/ DAY 'WT t/0AY' WT t/ DAY 1 X-105A 203-1A* r 203-2A .00441/2.16 .00110/0.8i4 ---
.00110/0.54 2 X-105A 203-1A E 203-2A .00551/2.70 --- --- ---
3 X-105B 203-IB* & 203-2B .00582/2.85 .00582/2.85 ---
.00582/2.85 4 x-1058 203-1B & 203-2B .01340/6.56 --- --- ---
5 X-105C 203-1C* s 203-2C .00729/3.57 .00223/1.09 ---
.00221/1.09 6 X-105C 203-1C c 203-2C 00952/4.66 --- --- ---
7 X-1050 203-1D* c 203-2D .00290/1.42 .00102/0.50 ---
.00102/0.50 8 x-105D 203-ID & 203-2D ,
.00392/1.92 -- - : --- ---
TOTAL TliRU LEAKAGE FOR PAGE . 2239 276 Indicates waterhead present on one side of valve 42 -
p .- LOCAL LEAK RATE TESTS PERFORMED DURING THE UNIT 2 REFUELING OUTAGE OF 1979 .
. . TYPE OF PENETRATION: TSOL'ATION VALVES' INITIAL INITIAL THRU FINI.L FINAL TNRU TEST PENETRATION -LEAK RATE LEAKACE -
. LEAK RATE LEAKAGE NUMBER' NUMBER' ' VOLUME'BEING' TESTED'
'vr t/ DAY' 'VT t/ DAY 'WT t/0AY 'tG' t/ DAY 9 X-147 205-2-4 & Blind Flanqe .00504 .00504 ---
.00504 10 X-147 205-2-7 & Blind Flange .03241 --- --- ---
11 X-106 220-1 & 220-2 .00051 .00027 ---
.00027 12 X-122 220-44 & 220-45 .00008 .00004 ---
.00004 13 X-107A 220-57A* & 220-58A .04280 --- --- ---
14 X-107A 220-57AA & 220-62A .03243 .03243 ---
.03243 15 X-107B 220-57B* & 220-58B .04297 --- --- ---
16 X-107B 220-57B* & 220-628 .
.02291 .02291- ---* .002291 17 X-1098 301-95 & 301-99* .01027 --- --- ---
18 X-109B 301-98 & 301-99* .00825 .00825 ---
.00825 19 (-111A, 1118 1001-1Aa, IB*, 2A, 2B & 2C 0 0 ---
0 20 X-138 1101-1* & 1101-15 .00257 .00257 ---
.00257 21 X-138 1101-1* & 1101-16 .00347 --- --- --- -
22 X-113 1201-1, 2 & 3 .01707 .01707 ---
.01707 -
23 X-108A 1301-1 & 1301-2 .00208 .00104 -
.00104 24 X-109A 1301-3 & 1301-4* .00225 .00225 ---
.00225 25 X-108A, 109A 1301-17 & 1301-20 .00006 .00004 ---
.00004 26 X-310A 1402-4A, 8A*, 25A & 36A* .01174 .01174 ---
.01174
' ~
27 X-149A 1402-24A & 1432-25A .01632 --- --- ---
~
28 X-310B 1402-4B, 8B*, 258 6 36B* .00235 .00235 --- ---
~'
29 X-149B 1402-24B c.1402-25B 0 --- ---
~
2239 277.. TOTAL TilRU LEAKAGE FOR PAGE 0.1060.0 O.10600 indicates waterhead present on one side of valve j.
~
, .s .
0 LOCAL LEAK RATE TESTS PEl 70RMED DURit1G TiiE UtilT 2 REFUELillG OUTAGE OF 1979 .s
. TYPE OF PEllETRA'l0ti: 'ISOLATlott VALVES-
lillTI AL INITIAL THRU FillAL FillAL THRU TEST PEllETRATl0t1 -
-LEAK RATE LEAVJ\GE LEAK RATE LEAKAGE P1 UMBER tlUMBER' ' VOLUME ' B E l tlG ' TEST ED ' 'WT t/ DAY' VT t/ DAY ' 'WT t/ DAY 'WT t/ DAY 30 X-311A 1501-18A & 1501-19A
' .00415 .00208 - - - -
.00208 31 X-3118 1501-18B & 1501-198 .00929 .00466 ---
.00466 32 X-310A 1501-20A & 1501-38A .00415 .00208 ---
.00208 33 X-310B 1501-20B & 1501-388 -
.00578 .00290 ---
.00290 34 X-116A 1501-22A, 26A* & 1001-5A .00278 --- --- ---
35 X-116A 1501-25A 5 1501-26A* .00265 '.00265 ---
.00265 36 X-116B 1501-22B, 26BA & 1001-5B .00133 .00133 ---
.00133 37 X-1168 1501-258 s 1501-:'6B* i .03343 - - - --- ---
l 38 X-145 1501-27A & 1501-28A .02573 .01287 *
.02218 .01109 I 39 X-150A 1501-278 c 1501-288 .01048 .00525 ---
.00527
_,- 40 X-304 1601-20A & 1601-31A 0 n --- n 41 X-304 1601-208 s 1601-318 .00104 .00053 ---
.00053 42 T-126, 304 1601-21, 22, 55 6 56 .00274 .00137 ---
00137 - 43 <-125, 318 1601-23, 24, 60, 61, 62 s 63 3.39006 3.39006 .03941 .01971 .. 44 x-126, 304 1601-57, 58 & 59 .00006 .00004 --- 00004 45 X-118 2001-5 ; 2001-6 .00210 .00106 ---
.00106 46 X-117 2001-105 s 2001-106 .00325' .00163 .00404 .00202 47 X-128 2101-4 r. 73ni-5 .00476 00_239 .00504 .00253 48 X-312 2301-34 c 2301 .03339 '.01670 ---
.01670
~
49 --- 2301-35 s 230-36 - 0 0 --- 0 50 X-317 2301-45 c 2301-74 .01728 .00864 ---
,.00864 2239 278 TOTAL rnau tEuAGE r0R race 3.45624 .08466 -
Aindicates Orhead present on one side of valve -4 4 - Q -
I I: l
.d (f I r - ., LOCAL LEAK RATE TESTS PERFORMED DURING THE UtilT 2 REFUELil1G ~0UTAGE OF 1979 [
l
. . t
.. . TYPE OF pet 1ETRATl0tt: ' ISOLATION VA'VES' !
- I ItilTI AL ItilTI AL THRU FINAL FiflAL Ti!RU TEST PENETRATION -
-LEAK RATE LEAKAGE . LEAK RATE LEAKAGE NUMBER' NUMBER' ' VOLUME *BEING' TESTED' 'WT */ DAY VT 2/0AY * 'WT t/ DAY WT t/ DAY 51 X-202v 2499-1A E 2499-2A .00014 .00008 ---
.00008 52 X-204B 2499-10 s 2499-28 .00061 .00031 ---
.00031 53 X-316A 2499-3A & 2499-4A *
.00006 .00004 ---
.00004 54 x-316B 2499-3B & 2499-4B .00022 .00012 ---
00012 55 X-202V 2599-2A & 2599-23A .03563 .00018 --- _00018
~
56 X-204B 2599-2B & 2599-23B .00086 .00043 ---
.00043 57 x-316A 2599-3A c 2599-24A .00102 .00051 ---
.00051 58 X-3168 2599-3B & 2599-248 .
.00006 .00004 ---
_n00n4 59 x-125, 318 2599-4A & 2599-5A .00053 .00027 ---
.00027 60 X-125, 318 2599-4B c 2599-5B .00006 .00004 ---
.00004 61 X-139D 4720 & 4721 .00008 .00004 ---
.00004 62 X-121 4722 & Check Valve .00696 .00349 ---
.00349 63 X-309A 8501-1 A & End of Line .00082 --- --- --- -
64 X-309A 8501-1B & End of Line .00041 .00041 --- onn6t - 65 X-204 8501-3A c 8501-38 .00327 .00163 ---
.00163 66 x-143 8501-5A & End of Line .00010 --- --- ---
67 X-143 8501-58 & End of Line .00002 .00002 ---
.00002 68 X - 14 3 9205A & End of Line. nnnty . 0 0 01 '> ---
nnn_ty 69 X-143 92058 6 End of Line .00841 --- --- --- 70 X-143 9206A & End of Line .00823 .00823 ---
.00823 71 X-143 92068 & End of Line
- 2239 279 TOTAL TilRU LEAKAGE FOR PAGE
- 45. .01598 .01598 -
Indicates Orhead present on one side of valve ' s
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'j LOCAL LEAK RATE TESTS PERFORMED DURING Tile UNIT 2 REFUELING OUTAGE OF 1979 TYPE OF pet 1ETRAT10N: 'DRYWELL' RFl.l 05/S' SE ALS '
ItllTI AL lillTI AL TilRU F illAL FillAL THRU TEST PEllETRAT10N . LEAK RATE LEAKAGE . LEAK RATE LEAKAGE I NUMBER' l1 UMBER' 'WT t/ DAY Vr 2/ DAY ' 'WT */ DAY'* WT */ DAY
' VOLUME'BEIflG~ TESTED (
106 X-109B iso. Cond. Condensate Return 4 0 0 --- 0 107 X-149A core Spray .00486 .00243 ---
.00243 108 X-149B Core Sprav .00133 .00067 ---
.00067 109 X-144 CRD Return .00186 .00094 ---
.00094 110 X-105A Hain Steam Line \
111 X-1058 Main Steam Line 112 X-105C Main Steam Line 113 X-105D Main Steam Line .* 114 X-106 Hain Steam Drain 115 X-107A Feedwater ! 116 X-1078 Feedwater - 117 X-111A Shutdown Coolinn .00088 .00045 ---
.00045 118 X-1118 Shutdown Coolino l 119 X-115A HPCI Steam Line 120 X-116A LPCI Injection 121 X-116B LPCI I n_i n c r i nn 122 X-123 RBCCW Inlet 123 X-124 RBCCW Outlet I 124 X-126 Vent to Drvwell 9
}}}g } TOTAL TilRU LEAKAGE FOR PAGE
.00449 .00449 .
Indicates /jrheadpresentononesideofvalve
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\t I l{ '
r
.A .e, LOCAL LEAK RATE ' TESTS PERFORMED DURiflG THE UtilT 2 REFUELillG '0VTAGE OF 1979 t'[
l ~
. TYPE OF PEllETRATI0ti: *DRYWELL' BELLOWS'5E'ALS '
Itil TI AL ltilTl AL .THRU FINAL FlilAL THRU TEST PEllETRATION LEAK RATE LEAKAGE LEAK RATE LEAKAGE tlUMBER' ilUMBER'
' VOLUME *BEING TESTED' '
'WT t/ DAY VT t/ DAY 'WT 2/ DAY"' VT t/ DAY 125 X-108A- Iso. Cond. Steam Line k .
126 X-113 Cleanno 127 X-125 Vent frcm Drveell 0 0 --- 0 128 X-130 Standby Liquid Control l 129 x-147 Reactor Head Spray ')
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l . 2239 283 TOTAL TilRU LEAKAGE FOR PAGE O.. 0 : Aindicates / rhead present on one side of valve 49-
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, LOCAL LEAK RATE TESTS PERFORMED DURING THE UNIT 2 REFUELING'0VTAGE OF 1979 -
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. TYPE OF PENETRATION: ' DOUBLY CASKFTFDSFhts .-
INITIAL INITIAL THRU FINAL FINAL THRU TEST PENETRATION LEAK RATE . LEAKAGE LEAK RATE LEAKAGE l l NUMBER ~ NUMBER' ' VOLUME'liElHG TESTE0' 'WT t/0AY VT t/0AY 'WT t/0AY" 'WT t/ DAY 150 X-301F Torus Vacuum Breaker 1601-33A .00071 .00037
.00037 151 X-301F Torus Vacuum Breaker 1601-338 .00047 .00025 ---
.00025 152 X-301E Torus Vacuum Breaker 1601-33C .00751 .00376 ---
.00376 153 X-301E Torus Vacuum Breaker 1601-33D .00149 .00076 ---
.00076 154 X-301D Torus Vacuum Breaker 1601-33E .18163 .00014 .00068; .00011 155 X-3010 Torus vacuum Breaker 1601-11F .00118 .00059 ---
.00059 156 X-306A East Torus Access Hatch .00002 .00002 0 0 157 X-3068 West Torus Access Hatch 5 00002 .00002 0 0
. 158 X-313A East Torus Drain .00012 .00006 ---
.00006 l 159 X-3138 West Torus Drain .00016 .00008 ---
.00008
_,. 160 Shear Lug Hatch 0 0 --- 0 161 Shear Lug Hatch 0 0 --- 0 162 Shear Lug Hatch 0 0 --- n - 163 Shear Luo Hatch 0 0 --- 0 .- 164 Shear Luo Hatch 0 0 --- 0 . 165 Shear Luq Hatch 0 0 --- 0 166 Shear Lug Hatch 0 0 --- 0 167 Shear Ing H,tch .01540 0 --- 0 TOTAL TilRU LEAKAGE FOR PAGE
.00605 .00619 Aindicates V erhead present on one side of valve Li ,
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