ML20064E238
| ML20064E238 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 11/07/1978 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML20064E236 | List: |
| References | |
| NUDOCS 7811150129 | |
| Download: ML20064E238 (71) | |
Text
{{#Wiki_filter:0 e, < g TE10ESSEE VALIKY AUTHORITY 1 DIVISION OF POWER PRODUCTION l i REACTOR BUILDING CONTAIIOGMT INTEGRATED IZAK RATE TEST BROWNS FERRY NUCLEAR PIANT UNIT 2 CONIUCTED JUNE 13-16, 1978 DOCKET NUMBER 50-260 Submitted to The United States Nuclear Regulatory Comuniasion Pursuant To Facility Operating License Number DPR-52 o' 1%\\\G0\M ,
.. s TABI2 OF CONTENTS 1.0 Introduction 2.0 Test turpose and Results A. Test ivrpose B. Test Results 3.0 Conduct of Test 4.0 Measurements and Calculations A. Special Test Equipment D. Sensor Incation C. Computer Based Acquisition and Iata Reduction System 1 50 Data Analysis 5.1 Discussion of Graphical Results 52 Instrumentation Performance
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6.0 Tabulated Test Results 6.1 25-Psig CILRT 6.2 25-Psig Verification
'1hbles and Figures Appendices:
A - Instrumentation Error Analysis B - Su= nary of Types B and C Testing Perfomed on Browns Ferry Unit 2
e- g l.0 Introduction As prescribed in Browns Ferry Nuclear Plant unit 2 technical specification 4.7.A.2, the leakage of air from the boundary foming the reactor building primary containment is limited to 2 percent of containment air mass per day at the calculated peak accident pressure Pa . In conformance with title 10 code of Federal regulations, part 50, Appendix J, Browns Ferry technical specifications require that reactor building integrated leak rate tests be performed as part of the startup and the surveillance programs to demonstrate continuing leak-tight integrity. An inservice reactor building containment integrated leak rate test (CILRT) was successfully completed on Browns Ferry unit 2 by personnel of the Tennessee Valley Authority on June 16, 1978. B is test was conducted in accordance with a plant approved surveillance instruction, BF SI 4.7.A.2, which is on file at the plant site. This surveillance instruction implements the requirements of Browns Ferry unit 2 technical specifications and Appendix J to 10CFR50. The American National Standard for Containment Testing, ANSI N45.4-19721 , and the proposed American Nuclear Society Standard for Containment Testing, N-274 2 , Provided guidance for the procedure implemented by the surveillance instruction. Browns Ferry unit 2 is a boiling-water reactor employing a steel pressure suppression containment and rated 3,293 megawatts thermal. Se Final Safety Analysis Report defines the calculated peak accident pressure Pa to be 49.6 peig. S e reactor building containment is divided into two major compartments--the drywell, enclosing the reactor and the forced recirculation system, and a pressure suppression pool chsaber. These two compartments are connected by blowdown pipes that terminate below the suppression chamber .c e _2 pool level. Vacuum breakers are provided to ensure the suppression chamber is never pressurized with respect to the drywell. For the performance of thic CILRT, these vacuum breakers were mechanically locked open to ensure pressure equalization between the drywell and the suppression chamber. This repo"rt outlines the objectives, principal events, and special equipment used and provides analysis of the test results for the CILRT completed on June 16 on Browns Ferry unit 2. f I _2- >
e e 2.0 Test Purpose and Results A. Test lurpose The objective of the inservice CILRT performed on Browns Ferry Nuclear Plant unit 2 was threefold. The principal objective was to demonstrate the leak-tight integrity of the reactor building containment for return to power operation. For Browns Ferry unit 2, the leak-tight integrity is defined by technical specification 4.7.A.2 and the preoperational CILRT to be that the leakage of air from containment not exceed 0.04437 percentage per hour of containment air mass at a reduced pressure of Pa/2. The second objective of this CILRT was to determine if any degradation of the stnteture forming the containment may have occurred since the performance of the preoperstional CILRT. A pretest inspection of the containment surface was performed to identify the presence of any gross defomities of the structure. The final objective was to evaluate several significant changes of the equipment used to conduct the test. These changes included additional compressed air capacity for containment pressurization and the revision of all test instrumentation to provide for the computer directed automatic acquisition and reduction of test data. Representing a radical departure from previous CILRT's, these changes were implemented by the Tennessee Valley Authority to conclusively detemine if test accuracy could be improved substantially while l reetcing the time required to conduct fttture tests. 1
a f , D. Test Results The leakage rate measured in the 24-hour CILRT was 0.00949 percentage of containment air mass per hour (0.2276 percentage per day) at a . reduced pressure of 25 psig. The observed 95 percent upper confidence limit for this measured leak rate was 0.00994 percentage of containment air mass per hour (0.23856 percentage per day). This measured leak rate represents less than 22 percent of that allowed under technical specification 4.7.A.2. After the completion of the CILRT, a supplemental forced leakage verification test was conducted to check the results of the CILRT. A forced leak of 0.0347 percentase of containment mass per hour (0.8328 percentage per day) was imposed on the containment. The leak ratemeasuredforthe12-1/4-hourverificationtestwas 0.038703 percentage of containment air mass per hour (0 9289 percentage per day). Agreement as prescribed by Appendix J between the CILRT and the verification test was -0.124 La , which is well within the p.250 La required by technical specificetions. A pretest inspection of the containment surfaces revealed no abnormal degradation of the reactor building containment structure. No leakage paths other than those identified as part of the types B and C test progrom were found in the performance of the CILRT or the supplemental ( verification test. Evaluation of the CILRT performed on Browns Ferry unit 2 conclusively demonstrates that accurate results can be obtained while significantly j reducing the time required to conduct the test. The additional compressed air capacity demonstrated that rapid pressurization directly 4 3-reduces the total time required to conduct the test. The computer directed automatic instrumentation provided reliable, ismediate results that accurately measured the containment leak rate with a high level of confidence in far less than 24 hours. Section 5 0, Data Analysis, demonstrates that for any duration of data collection beyond 8 hours, test results were substantially unchanged. Based on the performance of th'e special equipment used for the performance of the Browns Ferry unit 2 CILRT, the Tennessee Valley Authority will, for future CILRT's, consider conducting tests shorter than 24 hours. The guidelines for detezw.ining when to termine.co data collection shall be those outlined in ANS N-274 (draft). I 1 I l
0 0 30 Conduct of Test Prior to the start of the CILRT, local leak rate tests (LLRT) were performed on all potential leaksge paths from the reactor building containment except for the tip purge system which, due to plant design, is not testable. Incal leak rate tests on the containment closures (hatches with resilient seals) and electrical penetrations were conducted in conformance with surveillance instruc'. ion BF SI 4.7.A.2.g-2. Incal leak rate tests on the valves forming the boundary of the primary containment were conducted in conforinance with surveillance instruction EP SI 4.7.A.2.g-3 The single personnel air lock was tested separately in conformance with BF SI 4.7.A.2.g-1. A sunsaary of all LLRT testin6 ' performed since the preopnetional CILRT is included in appendix B of this report. Upon completion of all LLRT's, pressurization of the reactor building containment was begun at 5:46 p.m. on June 13 Pressurization to 25.4 psig was completed at 9:35 p.m. that evening. The failure of the temporary shutoff valve for containment pressurization supply air to completely close delayed the isolation of the air compressors. Upon successful isolation and removal of the supply air line, the containment was
" topped off" to 26.1 psig with air provided by the station-service compressed air system. Stabilization was begun at 5:00 a.m. on June 14.
During pressurization of the containment, test personnel determined that the station-service air supply to the drywell could not be properly vented as required by the surveillance instruction. The supply line was properly vented by plant maintenance personnel at 5:00 p.m. l l 6-
m . 1 The 25-psig CIIRT was officially started at 5:50 p.m. on June 14. For the following 24 hours containment temperature, pressure, moisture content of containment atmosphere, reactor and suppression pool veter level, and ambient conditions were automatically acquired. This data was reduced by a minicomputer to the contaitseent leak rate. Saaples of all measured parameters were acquired every 15 minutes. Upon completion of the CILRT, a supplemental forced leak verification test was performed. Inta from a forced leak and from the containment wasacquiredat15-minuteintervalsfor12-1/4 hours. Agreement, as defined by Appendix J, between the CIIRT and the supplemental verification test was obtained. The test was concluded at 8:00 a.m. on June 16. During containment stabilization the morning of June 14, an apparent change i of the calculated reactor building containment leek rate was noted to coincide with the closing of valve HCV 78-7 Since this valve does not conatitute a psrt of the containment boundary, concern was expressed over the poccibility that a previously unidentified leakage path from containment might exist. Upon the completion of the supplemental verification test, the test director requested plant operations to reopen valve HCV 78-7 to determine if the valve was part of the containment boundary. Inta collection was begun at 8:51 a.m. on June 16 at a frequency of e eight camples per hour. After 2 hours, the leak rate was observed to be unchanced both in trend and magnitude from that measured prior to the reopening of the valve. l Lata acquired when the valve was originally closed was subsequently j rearamined. For this period of stabilization, the containment leak rate l l I
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s . was chcracterized by large swings due to the stabilization of the containment atmosphere. The change of leak rate noted when valve HCV 78-7 was closed was, in fact, of the same magnit% of these swings of stabilization. As demonstrated by data collected after the valve was reopened, the original change noted in leak rate was merely coincidental. At 11:00 a.m. on June 16 the test director concluded that valve HCV 78-7 did not constitute part of the containment boundary. Plant operations was notified to begin depressurization. At approximately 11:00 p.m. on June 16 depressurization was complated. 8-
l o . 4.0 Measurements and Calculations A. Special Test Equipment The test equipment used for the performance of the CILRT on Browns Ferry Nuclear Plant unit 2 was significantly changed from that used in past tests conducted by TVA. Since the last inservice CILRT performed at Browns Ferry, the equipment used for containment leakage mer.surement has been reviewed and significantly modified. As a prime objective for equipment changes, TVA has sought to improve the accuracy of containment leakage measurement while possibly reducing the time required to conduct a CILRT. As a result of this review two major equipment changes, use of additional air capacity and the replacement of the containment leakage measurement system with an automatic system of improved accuracy, were evaluated. I Past inservice and preoperation CILRT's conducted at Browns Ferry used the station-service compressed air system for containment pressurization. Periods of up to several days were required to reach test pressure. For the CILRT performed on Browns Ferry unit 2, portable high-capacity air compressors were used for containment pressurization. Rated at 3,500 SCFM of dry, oil-free air, these - compressors brought the containment to test pressure in less than 4 hours. Test instrumentation used for past CILRT's at Brovns Ferry consisted of a limited number of thermocouples, dewpoint dewcela, and a single pressure transducer for containment parameter measurement. All measurements were made marmally with instruments subject to
o . limitations of repeatability. For the unit 2 CILRT this instrumen-tation was re}. laced with an automatic system allowing for a larger
, number of transducers of igroved accuracy. Table 1 identifies the parameters measured with the new transducer specifications.
Prior to the start of the CILRT, all special test equipment was calibrated by the Tennessee Valley Authority Central Laboratories, traceable to the National Bureau of Standards. After the installation of all special test transducers in the containment, each sensor was checked for functional operation. Upon test completion and depressurization, each sensor was again checked to ensure adherence to the calibration. B. Sensor Incation For the CILRT performed on Browns Ferry unit 2 the temperature and dewpoint transducer locations were selected so as to equalize the volume fraction of containment-free air represented by each measure-ment. No single transducer for temperature measurement represented more than 10 percent of the containment-free air voluna. Table 2 lists the volumetric weighting factor for et.ch temperature and dewpoint transducer. Figures 1-4 identify transducer locations. 110th pressure gauges sampled the containment pressure through pressure transmitter line PT 64-54. i C. Computer Baaed Acquisition and Inta Reduction System Containment parameter meas':rements for the Browns Ferry unit 2 CILRT were made and collected by a microprocessor based data acquisition ! system. This raw data was automatically presented to a portable l l minicomputer system for correction to calibration curves and reduction to containment leak rate. Statistical confidence levels l l
of the calculated results were reported automatically to the test director as the data was acquired. Figure 5 depicts the functional relationship of the acquisition and data analysis system. All calculations performed by the miniconyuter system were in conformance with the procedures outlined in ANS N-274 (draft). Source listings for all camputer progress are on file with the Division of Power Production, Plant Engineering Branch, in Chattanooga, Tennessee. Table 3 identifies the principal function of each computer program, e l
5.0 Data Analysis The previous sections of this report have described the general test conduct, calculation methods, and the special test equipment. In this section the problems that influenced the test results are discussed and used to draw conclusions on the performance of the Browns Ferry unit 2 CILRT. 5.1 Discussion of Graphical Results Figure 6 is a graphical representation of the calculated containment air mass for the CILRT and the subsequent verification test. The graph axes are absolute air mass versus test time. The slope of the least squares fit line to these data is the reported leak rate. In reviewing this graph it is evident that the calculated containment air mass tends to cycle about the least squares fit line. This cyclic variation is most pronounced for the final 12 hours of the CILRT. Analysis of the variance of the calculated air mass indicates a relationship between the measured reactor building containment pressure and the shield building pressure. The mechanism by which the shield btgilding pressure influenced the reactor building containment pressure is difficult to identify. Apparently the connection from the drywell pressure tap to the quartz manometer pressure gauges introduced some sensitivity to external pressure changes. Thisconnectionwasa1/Liech, semi-rigid plastic tube approximately 75 feet in length. Rmall transients introduced through the tubing vall were viewed to produce transients
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in the digital display of measured reactor building pressure. For the small changes measured in containment pressure, these transients effectively added noise to the calculated air mass. Though the transients were self canceling, the data scatter, and hence the confidence limits, were increased. , 5.2 Instrumentation Performance By the techniques outlined in Appendix A, the uncertainty of test results caused by the error introduced by the instrumentation was estimated prior to the CILRT. Based on this analysis the standard deviation of mass observations from a least squares fit, S , should A satisfy the following relationship: 4.86 f SA
- Comparison of S to this calculated range yields a measure of A
instrumentation performance. As S appr a hes the upper limit, A either the instrumentation has grossly failed or a change of leak rate has occurred. Table 4 compares the observed deviation S to various lengths of A data acquisition for the CILRT. In all cases, this deviation is l vithin the bounds defined in relation 1. The effect of the pressure gauge sensitivity to ambient changes clearly is reflected by the increase of S A for the 24-hour results. This increase serves to emphasize the significance of insulating test instrumentatiori from conditions that add to the noise of measurement.
It is noteworthy that the relatively saml1 AS f r the 6-hour data acquisition suggests the most accurate measurement of containment leak rate was made for this period. Since an objective of the Browns Ferry CILRT was evaluating the accurate measurement of leak rate in shorter periods for data collection, this clearly demonstrates that an 8- or 12-hour test would have accurately measured the leak rate. This conclusion is supported by table 5, a comparison of agreement between different lengths of data collection for the CILRT, and the supplemental verification test. As anticipated by the magnitude of AS , agreement is significantly improved for the shorter CILRT. In future CILRT's TVA will seek to demonstrate the reliability of the techniques outlined in this paper for evaluating the test performance. It is important to note that a decision to terininate the CILRT data collection should not be made only on the basis of an arbitrary 3" minimum period or the magnitude of the leak rate but should consider S , the standard deviation of mass, as a key indicator of test success. j 6.0 Tabulated Test Results e I v. v-ww. k a b 6.1 25-Paig CILRT t
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SHEETC2. f TENNESSEE VALLET AUTHORITT
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CONTA!WENT LEAMCE MEASUREMENT TEST SUMART
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HOURS AVERACE CORRECTED TOTAL MSS P-T-P TOTAL TIME MSS SINCE TEMPERATURE PRESSWE OF AIR LEM RATE LEM RATE LEM MTE
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SIMT DEC F. PSIA LM 1 PER HOUS 1 PER HOR 1 PER N0 5 l ........................................................................................................................a
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f.000 83.1398 39.8007 57471.22 f.0000000 0.0000000 f.0000000 ~l i f.258 83.1489 39.8071 57483.46 -0.8851700 -8.0051700 -0.0051528 l j f.5N 83.1452 39.8794 57475.82 f.053tl27 -0.0168270 -0.0168397
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i
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f.758 83.1445 39.8093 574M.83 f.N2&f01 f.flelE3 f.fll839 l.000 83.1462 39.801f 5748.21 f.848322 f.fl9140 f.0260793 1.25f 83.1499 39.8858 57457.78 f.fl69601 f.fl07184 f.8289792 1.5N 83.1368 39.88 4 57473.14 -0.1969011 -0.0022339 f.fl51926 i 1.758 83.1367 39.8837 57401.28 -0.f566027 -f.8100011 f.N34592 2.000 83.1381 39.8792 57471.01 f.f71429 f.0001835 f.N25374 i *
' -0.0005862 j 2.258 83.1247 39.8818 57471.35 0.0441257 -0.0047397 2.5M 83.1487 39.8129 57462.74 f.lfl6799 f.0059024 f.N24034 jl 2.758 83.1581 39.8743 57451.62 f.f773045 f.0124000 f.N71055
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1 3.000 83.1455 39.8780 57%4.25 -0.1810252 f.N20041 f.0063095 3.258 83.1486 39.8779 57447.68 f.1292348 f.f!!6825 f.0093302 3.5N 83.1362 39.8768 57475.41 -0.1930810 -f.0028037 f.0062264 l * -
- 3.758 83.1307 39.87N 57454.47 f.1457422 f.N77728 f.N72359 I
4.000 83.1124 39.8484 57445.72 f.Nf0900 f.0119900 f.0009636 4.258 83.1959 39.8757 57452.00 -0.H37366 f.N7040 f.ff925M , 4.5N 83.1978 39.8600 57454.99 -0.0144959 f.004247 f.0090030 1 4.758 83.lN7 39.8718 57445.59 f.f591587 f.ff93003 f.0096987 5.000 83.08f3 39.8683 57434.81 f.000644 f.0129494 f.filf533 5.258 83.H82 39.8694 57454.77 0.1445703 f.ff54530 f.8102247 5.5N 83.8517 39.8698 57459.68 -0.8341842 f.0034518 f.0091119 4 5.758 83.f360 39.8655 57453.80 0.0480707 f.0052696 f.ff05074
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- l 6.000 83.8535 39.8651 57449.51 f.f290004 f.0062958 f.0083621 6.258 83.8381 39.8615 57447.34 f.fl50947 f.00440 f.0002428 6.5N 83.0135 39.8582 57441.44 f.Hil243 f.ff79722 f.0004126
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6.759 82.9983 39.8578 57442.87 -0.0099559 f.N73004 f.0004104 7.000 82.9889 39.8588 57439.53 f.f232294 f.0070746 f.0005228 7.258 82.9888 39.8578 57439.18 f.ff24402 f.N76894 f.0005450 7.5N 83.H56 39.8626 57447.29 -f.056444 f.0055526 0.0002111 7.758 83.0115 39.8503 57428.45 f.1311519 f.ff96025 f.ff86126 8.000 83.0052 39.8573 57437.93 f.f48680 f.If72395 f.ff05450 8.258 83.0008 39.8538 57436.57 f.8512790 f.0005731 f.0007107 8.5N 82.9951 39.8533 57432.39 f.f!26783 f.N79444 f.N87412 8.758 82.9729 39.85M 57425.57 f.8474739 f.0090767 f.0009496 9.000 82.9605 39.8543 57433.45 -0.f540544 f.N73021 f.0008436 9.258 82.9492 39.8498 57425.83 f.0506272 f.ffua03 f.0089553 9.5N 82.9252 39.8453 57425.41 -0.NZ6121 f.0003909 f.ff98162
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9.758 82.9038 39.8515 57438.31 -0.8899006 f.ff50725 f.0087813 10.000 82.8863 39.8438 57434.27 f.8281558 f.0064292 f.ff04969
- 18.258 82.8685 39.8443 57434.49 -f.N15587 f.f66234 f.0082831
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4 If.5N 82.8753 39.8393 57427.15 f.f511468 f.N73831 f.N82438 10.758 82.8576 39.8393 57438.32 f.f778154 f.N53258 f.N79415 1 !!.fM 82.8378 39.8384 57436.94 f.0096298 f.N54227 f.N76841 11.258 82.8407 39.8341 57395.25 f.2993228 f.f!!7498 f.ff82442
!!.5H 82.8263 39.8361 57436.32 f.2862538 f.H52797 f.N795tl 11.758 82.8126 39.8293 57419.78 f.1152802 f.N76171 f.N79659
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* -4.f45874 12.fN 82.8837 39.8281 57426.47 f.fE4088 f.N78516 w
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SHEET C3. 1 TEleIESSEE VALLEI AUTHORITI , CONTAllfDT LEANACE MEASUREMERIT TEST SUMMRT HOURS AVERACE CORRECTED TOTAL MASS P-T-P TOTAL TIME MASS SINCE TEMPERATURE PRESSURE OF AIR LEAK RATE LEAK RATE LEAK RATE START DEC F. PSIA LBM I PER HOUR I PER HOUR 1 PER H3UR l 1
........................................................................................................................e 12.258 82.7857 39.8333 57404.26 f.1544803 f.ff95106 f.ff80902
!Z.5N 82.7856 39.8291 57414.71 -0.f728341 f.N78653 f.ff81222 12.758 82.7836 39.8298 57422.94 -f.8573141 f.9865884 f.ff80095
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13.fM 82.7835 39.8315 57426.73 -f.0263939 f.085954 f.N78340 13.258 82.8826 39.8348 57413.41 f.9927534 f.N75918 f.N78481 13.5H 82.7961 39.8344 57483.37 f.f699706 f.N87448 f.N79779
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13.758 82.81f2 39.8244 57409.07 -0.8397132 f.N7864 f.ff00!f9 14.8N 82.7988 39.83N 57417.85 -f.8611832 f.ff64328 f.N791N 14.258 82.7961 39.2266 57416.57 f.ff88987 f.0066724 f.N78235 14.5N 82.7883 39.8296 57417.32 f.N52249 f.If6473 f.If77220 14.758 82.7857 39.8214 57484.39 f.0961017 f.ff78835 f.N77692 15.fM 82.7551 39.8263 57418.58 -0.9988888 f.fNif59 f.ff76406
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15.258 82.7528 39.82N 57399.67 f.1317344 f.fM1634 f.N77178 15.5N 82.7442 39.8258 57391.89 f.f54224 f.ff89052 f.N78558 15.758 82.7573 39.8196 57482.79 -0.0759592 f.9875599 f H78570
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16.fN 82.7697 39.8264 57417.83 -f.1848232 f.ff58058 f.N77019 16.258 82.7791 39.8165 57378.92 f.2719918 f.0090833 f.N79172 16.5N 82.7841 39.8198 57377.47 f.8100757 f.ff98868 f.ff811N 16.758 82.7868 39.8198 57384.93 -0.f520126 f.N89634 f.N02278 17.fM 82.7945 39.8207 57386.59 f.fil5175 f.ff86624 f.ff82954 17.258 82.7958 39.8173 57372.55 f.9978575 f.0099538 f.ff84709
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17.5N 82.8H2 39.8186 573W.13 -0.1365516 f.0878634 f.ff84615 17.758 82.8H6 39.8167 57398.66 -0.H5454 f.0871132 f.0083895 18.8N 82.8353 39.8262 57396.35 f.8166612 f.N72372 f.0083311
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18.258 82.8792 39.82f5 57382.52 f.0963686 f.fM4564 f.N83738 18.500 82.9fft 39.8205 57388.52 -f.H17698 f.N77786 f.0083632 18.758 82.9288 3?.8279 57379.11 f.f655357 f.0085474 f.ff84057 19.fN 82.9919 39.8319 57393.38 f.f994282 f.N71289 f.H83438 19.258 83.8521 39.8277 57380.f5 f.0928617 f.N82486 f.H83641 i 19.5H 83.1159 39.8361 57357. 4 f.1574564 f.8101584 f.0985247 l
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19.758 83.1730 39.8413 57359.34 -0.f130758 f.ff98567 f.ff86553 l 2f.fH 83.2399 39.8475 57357.68 f.fil6844 f.H98782 f.H87786 29.259 83.29H 39.8444 57358.48 f.9581521 f.fif3742 f.0089314 28.5ff 83.3316 39.8587 5737f.59 -0.1482H4 f.8085415 f.H89428 28.75J 83.3857 39.8589 57375.78 -f.f342226 f.ff8N30 f.H89172 21.Hf 83.4327 39.8582 57359.07 f.1165435 f.H92923 f.9889804 21.25J 83.4315 39.8689 57357.88 f.00888H f.8892873 f.H98405 21.5H 83.4112 39.8536 57346.43 f.f792715 f.ftef992 f.ff91543 21.158 83.4959 39.8485 57351.63 -0.8362659 f.H95672 f.H922f2 22.fff 83.4113 39.8548 57376.63 -f.1743344 f.8874815 f.H91488 l 22.258 83.4834 39.8474 57363.13 f.f944598 f.H84526 f.H91415 22.5H 83.4890 39.8477 57352.77 f.f722655 f.89916ft f.H91821 22.759 83.4851 39.8521 57348.78 f.f278156 f.ff93645 f.ff92388 23.fH 83.4297 39.85H 57336.15 f.f888842 f.8182181 f.H92115 23.259 83.4605 39.8539 57336.25 -f.fff6548 f.8101812 f.H94165 23.5N 83.5108 39.8648 57352.77 -0.1152458 f.ff877f6 f.ff94183 23.758 83.5733 39.8643 57348.91 0.8269165 f.H89618 f.N94291 24.fH 83.6282 39.8651 57336.36 f.f874867 f.H97778 f.H94889
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j 6.2 25-Psig verification i I 1
l l
- SHEET C. f -
TENNESSEEVALLETAUTHORITT
, CONTAINENT LEAKAGE MEASUREMENT TEST StutART HOURS AVERACE CORRECTED TOTAL MASS P-T-P TOTAL TIME MASS l
SINCE TEMPERATURE PRESSURE OF AIR LEAK RATE LEAK RATE LEAK RATE
,,, START DEC F. PSIA LM 1 PER HOUR I PER HOUR 1 PER N0lft ;
............................................................................................... .....................a f.He 83.6596 39.8618 573 4 .13 f.0000000 0.0000000 f.000000s f.229 83.6636 39.8589 57318.78 f.2889453 f.2N9453 f.2889428 f.479 83.6558 39.8544 57334.10 0.1213873 f.8365271 f.0341398
,,, f.729 83.6594 39.8498 57333.55 f.8177411 f.f3ff827 f.8133964 f.979 83.6658 39.8484 57308.61 f.1748351 f.f668375 f.f423912 1.229 83.6559 39.8416 57318.84 -0.0713783 f.0387288 f.f339183 1.479 83.6482 39.8367 57278.07 f.284484 f.0002452 f.f581587 .
1.729 83.6543 39.8301 57273.82 f.f297341 f.8729361 f.M57471 1.979 83.6592 39.8480 57306.22 -0.2263233 f.8351654 f.H96485 2.229 83.6648 39.8311 57272.69 f.2348532 f.f574548 f.0516854 2.479 83.6734 39.8279 57239.97 -0.1286936 f.f395036 f.f448136 2.729 83.6826 39.8158 57254.95 f.2445054 f.0582625 f.9485954
,, 2.979 83.6972 39.8202 57268.36 -0.8936342 f.H55275 f.f41935 ,,,
3.229 83.7856 39.8168 57261.38 f.849249 f.H58103 f.f447542 3.479 83.7141 39.8154 57254.96 f.f442848 f.H54961 f.H37972
.. 3.729 83.7171 39.8138 57256.14 -0.0002418 f.H28800 f.H28237 ,
3.979 83.7109 39.8N1 57247.82 f.0581538 f.H30858 f.H!l217 4.229 83.6967 39.8092 57247.76 f.0004094 f.f485620 f.f397731 4.479 83.6791 39.7969 57238.45 f.12894N f.f458369 f.f4ff925 4.729 83.6669 39.7937 57234.35 -f.8272198 f.8412198 f.f393625 4.979 83.6688 39.7888 57214.28 f.1402392 f.H61781 f.Hel343
. 5.229 83.6549 39.7815 57211.18 f.0222384 f.H50387 f.94H975 5.479 83.6529 39.7793 5721f.58 f.fM2859 f.H31674 f.8403744 5.729 83.6439 39.7774 57211.48 -f.fE8278 f.Hf9864 f.f398148 5.979 83.6282 39.7747 572f7.57 f.0272841 f.8404187 f.0392586 6.229 83.624f 39.7671 57186.43 f.1478158 f.H47072 f.8397457 6.479 83.6073 39.7588 57179.59 f.9478967 f.8448251 f.8482N1 6.729 83.6f57 39.7685 57181.44 -f.ft29801 f.8426789 f.Hf1750 6.979 83.6859 39.7562 5717f.62 f.f756995 f.H38537 f.Hf3863 7.229 83.6f16 39.7509 57161.f7 f.8648498 f.f446419 f.f407445
. 7.479 83.5993 39.7489 57156.96 f.8287216 f.f44tf69 f.f409544 7.729 83.5948 39.7498 57157.18 f.N15835 f.f426317 f.f408844 7.979 83.5912 39.7455 57154.87 f.f161540 f.8418005 f.84M963 8.229 83.5998 39.7326 57154.36 f.H35267 f.f406374 f.He3515 8.479 83.5886 39.7309 57136.38 f.1258643 f.f431379 f.84H682 8.729 83.5919 39.7282 57131.64 f.f331715 f.f428490 f.f495351 8.979 83.6105 39.7263 57127.94 f.f259274 f.8423751 f.840524 .
9.229 83.6233 39.7233 57124.53 f.0238498 f.f418788 f.f484494 9.479 83.6183 39.7243 57129.56 -f.f352298 f.f398489 f Hff941 9.729 83.6216 39.7882 57111.55 f.1261133 f.HZH56 f.f4ff982 9.979 83.63f3 39.7128 57116.36 ef.8337f57 f.84fl512 f.f398455 1f.229 83.6147 39.7862 57899.25 f.1198758 f.HZ8888 f.f398972 10.479 83.6862 39.7f29 57144.28 -f.f 35242 f.f482466 f.0397019 10.729 83.6828 39.6986 57899.54 f.8331628 f.f4H783 f 8395062 18.979 83.5973 39.7fft 57894.21 f.8373796 f.f4H132 f.f393385
,. 11.229 83.6858 39.6938 57899.88 f.f303585 f.f397951 f 8391653
!!.479 83.6815 39.6885 5789f.61 -f.ff51180 f.f388174 f.8388899 11.729 83.592f 39.6835 57874.5f f.1128688 f.8403851 f.f388389 11.979 83.59f6 39.6332 57f65.97 f.f597638 f.f4f7836 f.f388411
SHEET C. 1 - TEMESSEE VALLET AUTHORITT
. CONTA! MENT LEANAGE MEASUREMENT TEST SWMRT HtC95 AVERAGE CORRECTED 10iAL MASS P T-P TOTAL ilNE MSS TEMERATURE PRESSLflE OF AIR LEM RATE LEM RATE LEM RATE
$1NCE DEC F. PSIA LM 1 PER HOUR I PER HOUR 1 PER N0 5 .
START e 12.Z29 83.5994 39.6770 57068.73 -0.0193053 f.03 0 55 0.8387063 -
................................................--....---------------~-----~--"----~-----'-~~~~---
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Tables and Figures l l l l
TABLE 1 ColiTAIIDENT IRAKAGE HEASURE'EliT SYSTEM SPECIAL TEST Ef.,UIHIEI.'T Manufacturer Measured and Humber Instrument karame ter Mode 1 No. Used Speeification 0 Containment I4eds & Northnrp 29 Range : 0-250 F 0 Model No. 178055 Accuracy : 10.1 0F Temperature Repeatability: 10.02 F Containment Mensor Corporation 2 Range : 0-50 psia; 400,000 counts F.S. Pressure Model No. 10100-001 Accuracy : 20.015% reading Repeatability: 10.0005% reading Containment Foxboro Corporation 6 Accuracy : +1 F dewpoint Lewpoint Model No. 2701 10 Repeatability: 10.50 F dewpoint Acurex Corporation 1 Accuracy : +0.001 F temperature Analog to Digital Autodata Nine 10.0010 F dewpoint il count pressure Converter t'o T Atmospheric Mensor Corporation 1 Range : 0-100 psia; 400,000 counts F.S. Model No. 10100-001 Accuracy : +0.015% reading Pressure
- Repeatability: _IO.0005% reading Atmospheric Leeds & Northrup 1 Range : 0-250 F Temperature Model No. 178055 Accuracy : 10.10 F Suppression Plant Process Transmitter 1 Range : 125 inches of water Chamber Model LT-64-54 Accuracy : 15% F.S.
Water Level Reactor Plant Process Transmitter 1 Range : 0 60 inches of water Water Level Model LT-3-53 Accuracy : 15% F.S. l I l
I l TABLE 2 vowMETRIC WEIGHTIlO GROUPS 4 Volumetric Group Number Weight flumber of Transducers Per Sensor Temperature: I 1 0.0289 II 8 0.0225 III 8 0.0223 IV 4 0.0314 y 1 0.0171 VI 1 0.0278 VII 6 0.0738 Dewpoint: I 1 0.2090 II 1 0.1857 III 1 0.1349 IV 1 0.0278 y 2 o.2213 i
TABIE 3 CONTAINMENT IEAKAGE MEASUREMENT MINICOMPUTER aOUTINE SUM 4ARY Boutine Name Function FORE a. Automatically acquire, store, and correct raw data to calibration curves.
- b. Calculate volumetric weighted containment air mass and leak rate as defined by ANS N-274 (draft).
- c. Print for each sample a summary with average parameters and containmant leak rate.
LIST Provide a sumanary for all samples from test start of average parameters, including calculated containment leak rate. TALLY a. C=Im1mte statistical confidence levels for the measured leak rate from the test start.
- b. Provide a sununary ccanparison of reportable leak rates as defined by ANS N-274 (draft).
BASE a. Allow test director to change the sample considered the test base.
- b. Provide a sununary for each sample leak rate recalculated with a shift in the test base.
l l
l TABIE 4 COI4TAIIDENT LEAKAGE MEASUREMENT CIIRT RESULTS AS A FUNCTION OF TEST IURATION PIP Isak* UCL PTP* Nass Leak UCL Nass CILhT 1Airation Number of Rate Leak Rate Rate Ieak Rate (Hours) Mass Samples UA, % Per Hour % Per Hour % Per Hour % Per Hour 8 33 8.42 0.00527 0.01693 0.00855 0.01036 12 49 9 15 0.00798 0.02318 0.00785 0.00893 24 97 10.76 0.00506 0.01921 0.00949 0.00994
*As defined in ANS N-274 (draft)
-2c-
TABG 5 CONTADDGi2r" GAXAGE MEASURDGENT COMPARISON OF TEST DURATION AND AGREEMENT WITH SUPPLEMENTAL TEST CILRT Durat g Supplemental Duration Agreement 24 12.23 -0.124 La 12 32.23 -0.0865 L, 12 8.23 -0.0496 L, 12 4.23 -0.0627 La 8 4.23 -0.0784 L, l l
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l I ColiPUTCR DASE ACCUISITION AND DATA REDUCTION SYSTEM l MINI COM PUTER SYSTE M A MENSOR DATA ACQUISITION MENSOR UNIT , QUARTZ QUART Z ' MAN OMETER MAN OM ETE R (AUTO DATA NI NE) JL Jk JL JL JL TORUS LEVEL MSING ((G REACTOR LEVEL LT 3-53 LT 64-54 TEST STATION ATMOSPHERIC TEMTdiATURE P RESSURE OUT SIDE CONTAINMENT MULTIPLE X RTIPLEX UNIT A UNIT B JL A l T RANSDUCER SIGNAL I CONDITIONING JL Jk e 29 RTO 6 DEWPOINT TEM PER ATURE T RANS DUCE RS T RANSDUCERS
-32 FIGtJRE G t
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TENNESSEE VALLEY AUTHORITY CONTAINMENT LEAKAGE MEASUREMENT MEASURED MASS PLOT 57800 M A S 57600 S O - o , ,. , y 57400 - a *
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. FIGURE 6
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APPENDIX A INSTRUMENTATION ERROR ANALYSIS Development The mathematical model for the mass of air in containment attributes any change to the independent parameters of containment temperature, pressure, and vapor pressure. By applying the ideal gas law, the basic model is defined: W = 144 x V x (P - Pv) (1) RT Therefore, the derivative of containment air mass is: dW = 144 V dP + c1 Pag + (P - Pv) dT (2) RP T T TZ The normalized or relative change of a mass measurement is simply: E R = ji{ j x 100 (3) Hi If the derivative of each independent variable is set equal to the absolute error of its measurement, equation (3) defines the relative error of the measurement of l the dependent variable. The error for the measurement of an independent variable is a function of the error of the measuring device and the measurement indicator for complex systems. In general, the probable upper bound for the error of an independent variable X can be expressed as: _ - 1/2 dX = (ev )2 + (g ,)2 (5) 4} x __ Since the measurement of containment leak rate is inherently a differential measurement, the application of equation (5) to the expression for the relative error, E R, cannot be made directly. In general, for a differential measurement, the relative error will be influenced by the accuracy and the repeatability , of the measurement. Though it is not possible to solve exactly for ER , the
" actual" relative error will satisfy the following relationship:
EUR 2 E>ELR (6) For a differential measurement, the upper bound will be determined by the limits uf inst ecuracy, while the lower bound will be determined by the limits of repeatability (e.g. , the inherent " noise" in the system). The absolute deviation of a measurement of a dependent variable from its
" actual" value can be expressed as:
SA = En x W (7) 100 Applying (7) to (6) yields: Sg>SA ASL (8) For multiple measurements of a dependent variable, Sg will approach the standard deviation from the mean for the measurement. Using the specifications listed in Table 1, the expected standard deviation of the mass may be estimated. Assume the following conditions: P = 39.696 psia Py = 0.4296 psia T = 539.670R Therefore, W = 56,358.93 lbm, i And, 16.50 lbm 2 Sg 24.86 lbm. l l t j
/ To bound the error of the mass leak rate, SA must be corrected for multiple, nonreplicate sampling. This correction in:
_ _1/2 SA" sax 1 xt95 ItZ - (T.t )/N Z For a 24 hour CILRT sampling at 15 minute intervals, N = 97 samples. Using the one-sided student's t distribution, t95 ~ 1.6609 Therefore, the error of the mass leak rate will satisfy:
& x 100 2 L W
Or 0.00035 percent per hour 2 L ( 1 l i
Definition of Symbols e - Absolute error of the measure of a variable E - Absolute error of the indication of the measure of a variable E R Relative error of a variable L - Absolute error of leak rate, percent of containment air mass per hour
't - Number of replications of a measurement N - Number of independent measurements P - Absolute pressure, poi R - Universal gas constant i
S - Deviation from the mean of a population t - Time of sample
- Student's t distribution for N-1 degrees t95 T - Temperature, degrees Rankine V - Containment air volume, scf I
W - Absolute mass of containment air, lbm Subscripts A - Estimate corrected for replication and sample size L - Lower bound U - Upper bound V - Vapor pressure - -
APPENDIX B SU! NARY OF TYPEG B MID C TESTING PERFORIE.D ON BROWN 3 FERRY NUCLEAR FIANT UNIT 2 t TABE OF CONTLYr3 1.0 Introduction 2.0 Sununary 3.0 Analysis of Lata Tables I i t .lg). I l l
1.0 Introduction Appendix J to 10CFR50 and Browns Ferry technical specifications require that the total leakage from all penetrations subject to types B and C testing be less than 0.60 L .for return to power operations. Technical specification 4.7.A.2.1 requires that the leakage through each main-steam isolation valve be less than 11 5 SCF11, in addition to the total leakage requirement. This appendix presents a summary of all local leak rate testing performed on Browns Ferry unit 2 since the completion of the preoperational CILRT. An analysis and interpretation of conditions contributing to the failure of meeting either the acceptance criteria of technical specifications or Sections III.A.5(b), III.B.3, and III.C.3 of Appendix J are included. 1 2.0 Summary ATior to return to power operations after the Browns Ferry fire and to the cycle 2 CILRT, a series cf local leak rate tests was performed on piping system isolation valves, electrical penetrations, mechanical bellows, and resilient sealed closures that form the boundary of primary containment. This test program was conducted in accordance with plant approved surveillance instructions BF SI 4.7.A.2.g-1, -2, and -3, which are on file at the plant site. Testing completed for the cycle 2 outage conforms with J. E. Gilleland's letter of July 8,1977, to NRC on confonnance to 10CFR50, Appenidx J, and H. J. Green's August 8,1978, memorandum to L. M. Mills on
" Browns Ferry Nuclear Plant Unit 2 - Conversion of Isolation Valve Water Leakage to Air Equivalent."
Tables B-1 and B-2 list all types B and C testing perfonned on Browns Ferry unit 2 prior to return to power operations after the fire. Analysis of the data shows that all four sets of maip-steam line isolations exceeded the maximum allowable leak rate of 115 SCFH, prior to repair. All eight main-steam isolation valves were subsequently repaired with the leakage reduced significantly below 11.5 SCFH. Prior to the return to power, the total leakage of types B and C penetrations was reduced to 97 5387 SCFH, which is significantly less than O.60 L, (707 07 SCFH). Tables B-3 and B-4 list all local leak rate testing perfonned from the return to service to the CILRT. Analysis of the data shows the leakage of four of the eight main-steam isolation valves exceeded 11 5 SCFH, prior to repair. All eight main-steam isolation valves were reduced to less than , 11.5 SCFH prior to the performance of the CILRT. Die total leakage of al'. types B and C penetrations was reduced to 293.o150 SCFH, which is significantly 2-below 0.60 L ,. Leakage of water through submerged valves subject to an inventory restriction of 28.8625 CFH was 1.8356 CFH. The total water leakage through valves constituting isolation for closed-loop seismically qualified extensions of primary containment was 1.7207 CFl!. 4 5 0 9 f I -43 l
J 30 Analysis of Lata Analysis of the data indicates that several of the main-steam isohtion valves exceeded 11.5 3CFH prior to repair. An inspection of the inboard isolation valve seats revealed that the entrapment of rust particles contributed to the excessive leakage. Special testing performed during the March 1978 refueling outage has shown that the test procedure of pressurizing between the inboard and matboard main-steam isolation valves contributed to the excessive leakage. After a preliminary between valve test was perfomed on MSIV lines A and B, a special mechanical plug was installed in place of the inboard M3IV's. A test, prior to any maintenance, was then performed on the outboard M31V's. As indicated in table A-3, the outboard leakage was insignificant in relation to the between valve tests. Ap prently the test pressure tends to lift the inboard valve off the seats, leading to the large leakages measured between the valves. Th is investigating the problem of lifting of the inboard main-steam isolation valves in the performance of type C tests. Alternate test methods for accurately measuring inboard isolation valve leakage are being evaluated. For subsequent testing at Browns Ferry, any to.st between main-steam isolation valves that exceeds the acceptance criteria will be supplemented with a before maintenance outboard isolation valve test. These tests will be reported as part of the type C test program. We believe that testa perfomed on the outboard main-steam isolation valve only present an accurate =casure of the line leakage to be expected in a design basis accident. Though between valve tests are the only i presently practical means of testing the inboard valve, such testing is j excessively conservative. TVA will continue to report between valve tests, supplemented by testa more indicative of valve condition of the outboard only.
r . . 4 Upon completion of the CILRT, final closure testing was performed. These tests were performed on the drywell head, one suppression chamber hatch, the control rod drive removal hatch, and the air lock. The corrected "as lef t" iceAage measured by the types B and C local leak rate test program was 273 7019 SCFH prior to return to power operations. 4 l
-y-
Sheet 1 of 7 TABM B.1 TYPE C TEST
SUMMARY
TEST 1M1 FOR CYCG f Individual Penetration Penetration System Test Leakage Leakage Number Name Remarks Inte (SCFH) (SCFH) X-7A M3IV Line A 1-14/15 Could not pressurize 5/2/75 1-14/15 lolish valve seats 10/3/75 0.0348 0.0348 X-7B EIV Line B 1-26 27 2 75 125.24 1-26 27 Polish valve seats 1 7 75 0 7383 0 7383 X-7C MSIV Line C 1-37/38 5/2/75 31 34 1-37/38 Polish valve seats 10/13/75 2.4029 2.4029 X-7D MSIV Line D 1-51 52 5 75 130.8000 1-51 52 Polish valve seats 1 75 0.4736 0.4736 X-8 Main Steam Drain 1-55/56 3/2/76 0.0 0.0 X-9A Feedwater Line A 3-554 11 75 0.2255 3-558 75 0.4051 0.4051 X-9B Feedwater Line B 3-568 75 o.4541 3-572 11 75 45.1600 3-572 Lap seats 2 76 0.0056 69-579 11 75 0.0 0.4541 X-10 ICIC Steam Supply 71-2/3 8/20/76 0.57/9 0.5779
. _. _ ._ _ _ _ _ _ - . _ _ _ _ _ _ . . _ _ _ . _ _ _ _ _ .~ __ . _ . . - - _ _ _ _ . . _ . . _ . _
Sheet 2 of 7 TABLE B.1 TYPE C TEST SUWJJ1Y TESTING FOR CYCE 1 Individual renetration System Test leakage Leakage Fenetration Itumber Name Remarks l' ate (SCFil) (SCIH) X-11 HPCI Steam Supply 73-213 12/15/75 7.1132 7.n 32 X-12 Shutdown Cooling Suction 12/7 75 0.0 74-661/662 74-47 12 14 75 0.2255 74-48 12 14 75 0.0149 0.2255 X-13A LPCI Injection , 74-53 2/u/7o 0.0074 74-54 2/n/76 0.1262 0.1262 s-T X-13B LPCI Injection 74-67 2/11/76 0.0056 74-68 2/n/76 0.1559 0.1559 X-14 HWCU Suction 69-1 12/16/75 0.0 69-2 12/16/75 0.0056 0.0056 X-16A Core Spray Injection 75-25 12 75 0.0 75-26 12 75 37.5442 75-26 Imp seat 12/ 75 0 5736 0.5735 X-16B Core Spray Injection 75-53 12 75 0.1726 75-54 12 75 3.7251 75-54 Imp seat 1 76 0.8799 0.8799 X-17 Head Spray Injection 74-77/78 2/8/76 0.0631 0.0631
Sheet 3 of 7 TABLS B.1 TYPE C TEST SIMARY mnIU FUR GIulE 1 Individual Penetration Penetration System Test Leakage Leakage Number Na=e Remarks Date (SCFH) (SCFH) X-18 Drywell Sump Discharge 77-2A/2B J2/10/75 0.1355 0.1355 X-19 Drywell Sump Discharge 77-15A/15B 12/10/75 0.0427 0.0427 X-22 Control Air Discharge 32-336 2/ 76 4.4458 32-336 Lap seat 5 76 0.5557 32-2163 2/ 76 2.6675 32-2163 Lap seat 5 76 o.9558 o.9558 5 Containment Purge and 8 X-25 Inerting Supply 84-8A 600 4 76 0.0 84-8 5 76 0.0 0.0 64-17 , 76-24 1 76 38.0113 64-17 19, 76-24 antest 1 76 o.4001 o.4001 X-26 Drywell Ventilation Exhaust 64-31/34/35 Prior to modification: 12/15/75 8.2246 64-31/34/139/160, 1 After modification: 8/20/76 2 3563 2 3563 84-20 X-36 CRD heturn Line 85-573 3/7/76 0.1485 85-576 3/7/76 0.1782 0.1782 X-39A Containment Spray 74-60/61 10/30/75 0.0093 0.0093 X-39B Containment Spray 74-74/75 10/23/75 0.0285 0.0285
Sheet 4 or 7 TABG B.1 TYPE C TEST SUM 4ARY TESTING WR CYCM 1 Individual Fenetration Penetration Syctem Nat leakage Imakage thmber Name Re e k_s, Date (SCFH) (SCFH) X-41 Becirculation Water Quality Sampling 43-13/14 3/4/76 0.0167 0.0167 X-42 Standby Liquid Control Injection 63-525 12/ 75 0.0 63-526 12/ 75 3.4352 63-526 Repair 76 0.0 0.0 X-4aA Containnent Air Monitor I- 76-248 4 76 0.o.
? 76-250 4 76 0.0 0.0 X-46B Containment Air Monitor 76-253 4 4 76 0.0 76-254 4 4 76 0.0 0.0 X-48 Control Air Suction 32-62/63 3/9/76 0 7380 0.7380 X-50A,B Radiation Monitoring System 90-254A/254B/255 12/15/75 0.4312 0.4312 X-Soc Radiation Monitoring System 90-257A/257B 12/15/75 0.2667 o.2667 X-51A Containment Air Monitor 4/14/76 0.0 76-215 0.0 0.0 76-217 4/14/76
Sheet 5 of 7 i TAEG B.1 TYRE C TEST SGC'ARY TESTING FOR CYCLE 1 Individual Fenetration Fenetration System Test Leakage leakage Number Name Remarks rate (SCFH) (SCFd) X-51B Containment Air Monitor 76-229 4/14 76 0.0 76-23o 4/14 76 0.0 0.0 X-205 Torus Vacuum Relief 64- CV 12 13/75 8.0024 8.0024 64-21 cv 12 75 10.0030 10.0030 76-17 /19 - Purge 12 75 5.1126 76-17 /19 - Purge 12 75 0.1200 0.1200 84-8 1 - CAD 5 76 1.7620 1.7620 X-210 Auxiliary Boiler Steam Supply 12-738 2 4 76 0.0144 12-741 2 4 76 0.0056 0.0144 X-211A MdReturntoTorus/ Pump Test 74-57/58 3/7/76 0.4938 o.4938 X-211B IER Return to Torus / Pump Test 74-71/72 3/7/76 0.05o1 0.o501 X-212 RCIC Turbine Exhaust 71-14/580 2/24/76 0.1708 0.1708 X-213B Torus Drain 74-722 Blind Flange 2/ 76 2.1223 74-722 Blind Flange 3 76 0.0 0.0 X-214 H1CI Turbine Exhaust 73-23 603 2/24/7o, 45.M 73<23 603 6/10/76 0.1782 0.1782
Sheet 6 of 7 i TABE B.1 TYPE C TEST SLDNARY i TESTING FUR CYCE 1 Individual Fenet::1Ltion
; Penetration System 7.'est leakage Leakage Number Name Remarks Date (SCMI) (SCFH)
X-220A Containment Air Monitor 76-242 4 4 76 0.0 76-243 4 4 76 0.0 0.0 X220-B Containment Air Ibnitor 76-237 4 4 76 0.o 76-239 4 4 76 0.0 0.0 X-221 RCIC Pump Discharge 71-32/592 2/24/76 0.0065 0.0065 X-222 IIICI Pump Discharge p 73-24/609 2/26/76 0.0074 0.0074 e X-225A Water Quality and Sampling System 43-28A 3 76 0.0 43-28B 3 76 0.0 0.0 X-225B Water Quality and Sampling System 43-29A 3/4/76 0.0028 43-29B 3/4/76 0.0125 0.0125 X-227A Core Spray-Torus IIigh level 75-57/58 3/7/76 0.4938 0.4938 X-229E Containment Air Monitor 76-225 41 76 0.0 76-226 41 76 0.0 0.0 l
. . .. - - . - . . - -_-..- - . - . _ . - - . . _ . ~ _ - , . . . . - - - _ ~ . _ - _ - _ - - . - . - . - - , - . . - . - . .
Sheet 7 of 7 EABIZ 3.1 TYRE C TEST SUELGY , TEST 113G h CYC21 Individual Fenetration Fenetration System Test Imakage Leakage thaber Name Remarks l' ate (SCF3) (SCFH) X-229F Containment Air Monitor 76-220 4 76 o.o 76-222 4 76 0.0 o.o X-231 ventialtion 64-29/3o 12 75 6.2241 64-32/33 12 75 35.8398 64-29/30/32/33,84-19 7 76 13 3373 13.3373 Total 54.4409 k
Sheet 1 of 3 TAEG B.2 TYRE B TEST SUW4ARY TESTING FOR CYCM 1 lellows Irakage, SCFH As Found Imakage. SCFII As Left Leakage atth As Found Late As Imft Late 7A inboard o.0003 2 76 0.0003 2 76 outboard o.0009 2 76 0.0009 2 76 7B inboard 0.0000 2 76 0.0000 2 76 outboard 0.0000 2 76 0.0000 2 76 7C inboard o.0025 2 76 0.0025 2 76 outboard 0.000 2 76 0.0006 2 76 7D inboard o.0006 2 76 0.0006 2 76 outboard 0.0003 2 76 0.0003 2 76 8 inboard 0.0001 2 76 0.0001 2 76 outboard 0.0005 2 76 0.0005 2 76 9A intoard 0.0009 2 76 0.0009 2 76 outboard 0.0000 2 76 0.0000 2 76 98 inboard 0.0006 2 76 0.0006 2 76 outboard 0.0006 2 76 0.0006 2 76 10 inboard 0.0022 2 76 0.0022 2 76 outboard 0.0001 2 76 0.0001 2 76 11 inboard 0.0008 2 76 0.0008 2 76 outboard 0.o006 2 76 0.0006 2 76 12 inboard 0.0021 2 76 0.0021 2 76 outboard o.0031 76 0.0031 2 76 13A inboard 0.0006 2 76 0.0006 2 76 outboard 0.0015 2 76 0.0015 2 76 13B inboard 0.0012 2 76 0.0012 2 76 outboard o.0018 2 76 0.0018 2 76 14 inboard 0.0010 3 76 0.0010 3 76 outboard 0.0007 3 76 0.0007 3 76 16A inboard 0.0007 3 76 0.0007 3 76 outboard 0.0010 3 76 0.0010 3 76 16B inboard 0.0007 3 76 0.0007 3 76 outboard 0.0019 3 76 0.0019 3 76 17 inboard 0.0001 3 76 0.0001 3 76 outboard 0.0003 3 76 0.0003 3 76 i ! Total o.0668 Sheet 2 cf 3 TABI2 B.2 TYPE B TEST SUletARY TESTI!G FOR CYCLE 1 Electrical Leakage, SCFil As Found Leakage. SCFH As h ft Leakage Path As Found Tate As ImM, Date looA EC o.02287 2 76 0.02287 2 76 B BD o.03909 2 76 0.03909 2 76 C BE o.02504 2 76 0.02504 2 76 D BF o.0313o 2 76 0.03130 2 76 E BG o.02191 2 76 0.02191 2 76 FM o.01876 2 76 0.01876 2 76 o DC o.o1811 2 76 0.01811 2 76 101A AB o.01525 2/ 76 o.01525 2/ 76 B AA o.09110 2/ 76 0.09110 2/ 76 C AF o.03615 2 76 0.03615 2 76 D AE o.02984 2 76 0.02984 2 76 102 CA o.03o19 2 76 0.03o19 2 76 103 DG o.04694 2 76 0.04694 2 76 lo4A ED o.02647 2 76 0.02647 2 76 B DB o.0252 2 76 0.0252 2 76 C Bc o.0165 2 76 0.0165 2 76 u CB o.0938 2 76 0.0938 2 76 E EE o.0494 2 76 0.0494 2 76 F EF o.0729 12/ 75 0.0004 76 105B AC o.0346 2/ 76 0.0346 2 76 C AD o.07757 2 76 0.07757 2 76 Dm NA - 0.0002 2 76 lo6A DA o.oS483 2 76 0.05483 2 76 B BA o.07567 2 76 0.07567 2 76 lo7A BA o.01935 2 76 0.01935 2 76 B o.04274 2 76 0.04274 2 76 lo8A EA NA - 0.00022 2 76 B IE o.03949 2 76 0.03949 2 76 109 DD o.03971 2 76 c.03971 2 76 noA EB o.0361 2 76 0.0361 2 76 11oB DF o.0376 2 76 0.0376 2 76 219 FA NA - 0.0014 76 Total 1.o978 f i She:t 3 cf 3 TABM B.2 TYPB B TEST SUM 4ARY TESTING FoM CYCLE 1 Atucilient, Seals Leakage. SCFH As Found Ieakage. SCFH As Left leakage 1ath Ac Found Date As Left Date 1A NA - 0.0249 5 76 la UA - 0.0002 5 76 4 UA - O.0003 6 76 6 0.0003 6/ 76 0.0001 5 76 o.0001 2 76 0.0000 2 76 35A o.0000 2 76 0.0000 2 76 35B o.0000 2 76 0.0000 2 76 35C o.0000 2 76 0.0000 2 76 35u 35E o.0000 2 76 0.0000 2 76 o.0000 2 76 0.0000 2 76 35F o.0000 2 76 0.0000 2 76 35G 47 0.0002 3/ 76 0. m 3 76 200A nA - O A007 8 76 200B HA - 0.0003 3 76 Drywell Head NA - 2.5027 8 76 As oo 0.0084 2 76 0.0001 3 76 450 0.0318 2 76 0.0008 3 76 90 0 0.0101 2 76 0.0058 3 76 135 0 0.2928 2 76 0.0043 3 76 1800 0.6272 2 76 0.0085 3 76 225 0 0 3141 2 76 0.0029 3 76 270 0.0002 2 76 0.0019 3 6 315 0.1268 2 76 0.0050 3 76 eerconnel Air Lock 39.ho40 5/25/76 Tbtal 41 9627
1 TAB 2 B.2 T0fAL IJlAKAGE SID0%RY TESTING FOR CYCM 1 1 Type B Isakage: A. Dellows 0.037.1 f.0FH B. Electrical 1.0978 SCFH C. Resilient deals 41 9627 SCFH Type C I4akage 54.4409 SCFH Total imakage Prior to Return to Power 97 5387 SCFH 3 Operation f f t i I l
~5b~
._. __ .-. =. _ ..
W Sheet 1 of 8 TABLE 3.3 TYPE C TEST SUSC4ARY l TESTI;G FOR CYCLE 2 Individual Penetration Fenetration S/ste= Test Leaka6e LeakaSe , i!unber .';a e Remarks Late (SC7H) (SCFH) X-7A MSIV Line A 1-14 (Inboard) 4/378 1,552.8940 1-15 (outboard) As found 4/378 0.2281 1-14/15 with plus 5/31 78 0. % 68 0.W68 X-7B MSIV Line B 1-26 (Inboard) 3/30/78 778.3469 1-27 (outboard) As found 3/30/78 0.6794 with plug 1-26/27 6/1/78 6.1926 6.1926 X-7C MSIV Line C
& 1-3 38 3/ 0/78 5.5022 1 1-3 38 6 1/78 10 3020 10 3020 X-7D MSIV Line D 1-51/52 3 78 661 9941 1-51 52 4 78 10.0096 1-51 52 78 10 3115 10.3115 X-8 Main Steam Drain 1-55 56 3/ 78 0.0107 1-55 56 Valve aepacked 6 78 0.0000 1-55 56 Air tested 78 0.0000 0.0000 X-9A Feedwater Line A g 3 78 o.W85 3-554/73-45 3-554/73-W 78 0.5881 3/558 78 0.4277 o.5881
sheet 2 or 8 TASG 3.3 nr!E C TEST SCO%3Y TESTrn FOR CYCLE 2 Indi.idual Fenetration Penetration System Test Leaka6e Leakage 1:unber da=e Re arks Cate (scrii) (SCFH) X-9B(y) Feedwater Line B 3-572 gjg .f8 0.7247 3-568/71-40/69-579 4/n 78 58.3200 3-568/71-40/69-579 Lap 71-40 5/1 78 1.8329 ' 3-568/71-39/69-579 y g 2.3760 2 3760 85-576 3elocated 5/ 78 0.0083 ' X-lo RCIC Steam Supply 71-2 3 3/20/78 0.0487 71-2 3 6/3/78 0.0000 0.0000 X-n luCI Steam Supply
. 73-2/3 3/21/78 4.4458 g 73-2/3 6/4/78 0.1760 0.1760 0
Shutdown Cooling Suction X-12(1 78 o.0052
~
74-661/662 74-47 g 7g o,0116 0.0116 74-48 78 0.0107 ~ LPCI Injection X-13A(3) 74-53 3/22/78 0.3707 74-54 3/22/78 0.7128 0.7128 IacI Injection X-13B(3) 74-67 gjgfyg-o,olo7 74-68 gjgf93 o.1319 0.1319 RWCU suction X-14(1) 69-1 4/12/78 0.o428 69-2 4/12/78 0.0416 0.0428
Sheet 3 of 8 TA3E 3.3 TY?E C TEST SU'MdiY TESTIT, WR CYCLE 2 Individual Penetration Penetration System Test Leakage Leakage
!!u=ber Name Re= arks rate (SC75) (SC7H)
Core Spray Injection X-16A(3) 75-25 3 78 0.0000 75-26 3 78 42.7680 75-26 Retest after line 5 78 o.2031 0.2031 replacement Core Spray Injection X-16B(3) 75-53 3 78 0.0143 75-54 3 78 2.5579 75-54 Retest after line 5 78 0.0000 0.0143 replacement i Head Spray Injection y X-17(3) 74-77/78 3/22/78 0.0000 0.0000 Drywell Sump Discharge X-18(1) 77-2A/2B 3/22/78 0.o487 0.0487 Drywell Sump Discharge X-19(1) 77-15A/15B 3/22/78 0.0261 0.0261 X-22 Control Air Discharge 32-336 3 78 o.5758 32-2163 3 78 2.0355 32-2163 Retest after repairs 4 78 o.9184 0 9184 X-25 Containment Purge and Inerting Supply 84-8A 600 3 78 o.7476 84-8 602 78 0.0803 64-17 1 19, 76-24 3 78 6.6227 64-1 1 19, 76-24 78 3.4980 3.4980
Sheet 4 of 8 TA3LF., 3.3 TYi-E C TEST SIM%RY , TESTI;;G FOR CYCi2 2 , Individual Penett% tion
?enetration System Test Leaka6e Leaka6e I umber Name Remarks rate (SCFH) (SCFH)
X-26 Drywell Ventilation Evhanat 64-31 139 140, 84-20 3 78 14.0041 64-31 139 140, 84-20 6 78 0.5718 0.5718 I~ * (1) 55 3/26/78 0.0368 85-576 4/25/78 0.0594
- Co e X-39A[3) I 61 3/20/78 0.1604 0.1604
. Containment Spray X-39a( )
F Mg 5%$8
- E*3u o.23 3 X-41 Recirculation Water Y3 3/24/78 0.0000 43-14 3/24/78 0.0036 0.0036 Standby Liquid X-42(1) Control Injection 63-525 3/23/76 0.0465 63-526 3/24/78 0.0273 0.0273 X-46A Containment Air Monitor 76-248 3 78 1.2296 76-248 3 78 0.0000 76-250 3 78 26.6033 76-250 3 78 0.0000 0.0000 X-46B Containment Air Monitor 76-253 3/23/78 0.6707 76-253 3/25/78 0.0181 0.0181 76-254 3/25/78 o.o
*r.akaae path no longer exists per CRD return line reroute.
a Sheet 5 cf 8 TA2 3 3.3 TY?E C TEST SC:%RY TESTIT, rVR CYCE 2 Individual ie::etration Fenetraticn System Test heaka6e Leaksge au=ber '; ace Re Arks rate (SCFH) (SCFHI X-48 Control Air Suction 32-62/63 3/23/78 0.8157 o.8157 X-SoA, B Radiation Monitorin6 System 90-25hA/254B/255 3/22/78 o.com o.ocoe X-soc Radiation Manitoring System 90-257A/257B 3/22/78 0.0000 0.0000 X-51A Containment Air Monitor
& 76-215 3 3/78 1.2296 'i' 76-215 3 5/78 0.000o 76-217 24 78 40.9396 76-217 -/78 0.0000 0.00 @
X-51B Containment Air Monitor 76-229 3 78 2.2356 76-229 78 0.0000 76-230 3 78 0.0000 o.ocoo X-205 Torus Vacuum Belief 64-20/CV 3 4.5347 64-20/CV 5 78 4.1842 4.1842 64-21/CV 3 78 0.000; 64-21/CV 78 0.0009 0.0000 19 78 0.0000 76-17/18]/19 76-17/18 o.oooo o.0000 89-8B/601 3 0 9434 0 9434 X-210 Auxiliary Boiler Steam
- 2) Supply u-738 3 78 o.0098 12-7tl 3 78 0.0134 0.0134
Sheet 6 of 8 TA3LE 5.3 TYF3 C TIST SintARY TESTIiG KR CYCLE 2 Individual Fenetration Penetration System Test Leakage Isakage I; umber : lame Re= arks Late (SC5H) (SCFH) X-211A RHRReturntoTorus/
- 3) Pump Test 74-57/58 3/20/78 o.3505 0.3505 X-211B(3)
Pump Test 74-71/72 4/ 78 o.3089 i 74-71/72 5/1 78 0.0202 0.0202 RCIC Turbine Exhaust X-212(2) 71-14/580 3/24/78 0.1672 0.1672 8 Torus Drain X-213B(2) h 74-722/BlindFlange 74-722/BlindFlange 3/2478 o.5103 Repair test connection 3/2578 0.2257 0.2257 HPCI Turbine Exhaust X-214(2) 73-23/603 59.4000 73-23/603 3(/22/78 j577g 1.1939 1.1939 X-220A Containment Air Monitor 76-242 3 7g 14,5312 76-242 3 78 0.0000 76-243 78 7.2910 76-243 78 0.0000 0 0000 X-220B Containment Air Monitor 76-237 % 20.4555 76-237 3 0 0000 76-243 3 78 7.2910 76-243 3 78 0.0000 0**
_ . . _ m . _ _ _ _ _ __. _ _. _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . . _ _ -- _._.__.______m._ . _ . Sheet 7 of 8 TA3LE 3 3 TE-E C TEST SU: !A3Y TESTI G r*T)R CYCLE 2 Individual tenetration Fenetration System Test Leaka6e 14aka6e
- eber : lane Re= arks rate (SCFH) (SCFH)
RCIC Iwsp Discharge X-221(2) 71-32/592 0.0049 0.0049 3/24/78 HEC 1 Pump Discharge X-222(2) 73-24/609 3/23/78 0.0059 0.0059 X-225A Water Quality and
- 2) Sampling Syatem 43-28A 3/26/78 0.0046 43-28B 3/26/78 0.0030 0.0046 X-225B Water Quality and
- 2) sampling system
&' 43-29A 3/23/78 0.0000 43-29B 3/23/78 0.0000 0.0000 X-227A Core Spray - Torus
- 2) HiEh Ievel 75-57/LJ 3/21/78 0.1051 0.1051 X-229E Containment Air Monitor 76-225 3 78 12.6824 76-225 3 78 0.0000 76-226 3 78 0.0000 0.0000 X-229F Containment Air Monitor >
76-220 3 78 5.5624 76-220 78 0.0000 76-222 78 0.0000 0.0000
._ _ . - _ _ - ~ . . _ - _ . . . - _ . . . . . - _ _ .
Sheet 8 of 8 TABE B.3 TYFE C TEST St2NA.RY , TESTI:n :1R CYCE 2 Individual Eenetration Fenetration System Test Leakade Isaksge Number Name Remarks rate (SCFH) (SCHI) X-231 Ventilation 64-29/30/32/33,84-19 3/21/78 535.o315 64-29/30/32/33,84-19 6/5/78 16.2511 16.25u , Notes: (1) To be converted to air equivalent leakage ' (2) Water sealed subject to inventory restriction (3) water tested closed seismic I loops of containment , e A. Total of air tested paths - 55.3727 f B. Total of closed systems - 1 7207 C. Total 'of sealed systems subject to inventory requiremerit: - 1.8356 Y a , ' w N s
,Y
+ - - - - , . .
. s TABLE B.3 WATER TECTED LEAXAGE PADIS SUBJECT TO AIR CONVERSION TESTING FoR CYCLE 2 Water - Air Leakage Taalrage . Equivalent Fath Isolation Valves (CFH) (SCFH) X-8 1-55, 1-56 0.0 0.0 x-9A 3-558, 3-554, 73-45, 73- W o.5881 W.oooo X-9B 3-572, 3-568, 71-40, 60-579, 2.3760 133 0000 71-39, 85-576 x-12 74-661, 74-662, 74-47, 74-48 0.0116 2.1250 x-14 69-1, 69-2 0.0428 5 0100 x-18 77-2A, 77-2B o.0487 6.1500 ' x-19 77-15A, 77-15B o.0261 3.2940 x-41 43-13, 43-14 O.0036 0.6150 x-42 63-525, 63-526 0.0465 6.1000 Total 3.1435 200.2940 A l s < l
. s Sheet 1 Cf 3 TABLE B.4 TYPE B TEST
SUMMARY
TESTING FOR CYCLE 2 bellows Leakage, SCFH As Found Imakage, SCFH As Lef. Leakage :sth As Found Eate As Left . ate 7A inboara o.0006 3 78 0.0006 3/2./"8 outboard o.0013 3 78 0.0013 3/ 78 7B inboard o.0013 3 78 0.0013 3 78 outboard o.0003 3 78 0.0003 3 78 0.0013 78 o,0013 3 78 7C inboard 3 outboard 0.0013 3 78 0.0013 3 78 7D inboard 0.0016 3 78 0.0016 3 78 outboard o'.ooo6 3 78 0.0006 3 78 8 inboard o.0006 3/2578 0.0006 3 78 outboard o.0008 3/25 78 0.0008 3 78 o.0027 3' 78 0.0027 3 78 9A inboard 78 outboard 0.0015 3 78 0.0015 3 9B inboard - o.0021 3 78 0.0021 3 78 outbo n d 0.0012 3 78 0.0012 3 78 10 inboard 0.0015 3 78 0.0015 -3 78 outocard o.0015 3 78 0.0015 3 78 11 inboard o.0001 3 78 0.0001 3 78 outboard o.0006 3 78 o.oo(M 3 78 12 inboard 0.0008 3 78 0.0008 3 78 outboard o.0011 3 78 0.0011 3 78 13A inboard 0.0009 3 78 0.0009 3 78 e outboard o.0000 3 78 0.0000 3 78 139 inboard o.0015 3 78 0.0015 3 78 outboard o.0300 78 0.0000 3 78 14 inboard 0.0062 3 78 0.0062 3 78 outboard o.0076 3 78 0.0076 3 78 16A inboard 0.0010 3 78 0.0010 3 78 outboard o.0007 3 78 0.0007 3 78 16B inboard 0.0007 3 78 o.0007 3 outboard 0.0002 3 78 0.0002 3 78 17 inboard o.0004 3 78 0.0004 3 78 outboard o.0000 3 78 0.0000 3 78 Total o.0420 s
Sheet 2 of 3 TE TI!O 2 Electrical Leakage, SCFH As Found Leakage, SCFH As Left 14akage Path As Found Date As Left Date
!= = ::a2 !# ::22 ia
!= = ::2 !3 ::E !#
!= = ::23 ia :23 ia
!= = ::EH ia 8:a! !a 1:l": ::s !# ::En !a l :0! !# 8:0! !#
12A: :Miu !# :Mi*u !# 12": lo4D CB
- 2 o.1512
!3 3 78
- M 0.1512 is 3 78
!s" 5 ::M3% !# :M*J !#
$i$"E" :25 3 d 8:25 id 12 :
106B BA
- 2!
o.0937 3 78
- 2!
0.0937 3 78 107A BA o.0312 3 78 0.0312 3 78 12 m 8:E*2 !# 2:s! !# ! Is": :28 i n 8:22 i # llo F 3 o. 3 219 0.0002 3 78 o.0002 3 78 Total 2.2u97 l ' - F
l e . . Sheet 3 of 3 TABLE B.4 TYPE B TEST SUM 4ARY TESTING FOR CYCIE 2 Basilient Seals Leakage, SCFl! As Found Imakage. SCFH As Inft Date As Inft Date Leakage Fath As Found 1A Equip o.8317 3 78 0.0121 6/ 78 0.0278 6 78 1B Equip 45.8563 3 3 78 0.0002 78 4 OWHA o.co96 78 6 cRD o.1301 3 78 0.0001 o.0000 3 78 0.0000 3 78 35A TIP 0.0000 3 78 35B TIP o.ooo 3 78 o.0002 3 78 0.0002 3 78 35c TIP 0.0000 3 35D TIP o.oooo 3 78 78 0.0000 3 8 35E TIP o.oooo 3 o.oooo 78 0.0000 3 78 35F TIP 0.0000 5 78 35G TIP o.0007 3 78 78 0.0005 3 78 47 POT o.0005 3 3 78 0.0002 6 78 200A Sc o.0499 0.0052 3 78 0.0052 3 78 200B Se 6 78 0.2393 78 Drywell Head 1.7393 3 o.1248 3 78 0.0006 78 Az 00 Shear o.0006 3 22 78 0.0006 3 78 450 Shear 0 o.0006 3 78 0.0006 3/22 78 90 Shear 0.0002 3 78 135 Shear o.0002 3 78 180 Shear o.0001 3 78 0.0001 3 78 225 Shear 0.0378 3 78 0.0001 5 78 2700 Shear o.0126 3 78 0.0002 5/11 78 315 Shear o.0175 3 78 0.0002 4/2778 Personnel Air Inck x-2 0.0 4/16/78 34.7359 6/9/78* 15.4228 6/25/78** Total 15.7110
*Frior to CILkI
** Prior to return to pcVer
-38
o ..
- w TABE B.4 TOEAL LEAXAGE SGSMRY TESTDIG FOR CYC2 2 Type B Leaka6e I. Bellows 0.0420 SCFH II. Electrical 2.2497 SCFH III. Resilient Seals 15.7110 SCFH Type C Imakage I. Air Tested Paths 55.3727 SCFH II. Water Tested Converted to Air 200.294 SCFH Total Leakage Frior to Return to Power 273.6694 SCFH Operation Total of Sealed Systems Subject to 1.8356 CFH Inventory Requirements Total of Closed Seismic I Icops of 1.7207 CFH Containment A
_ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _}}