ML20150E070
| ML20150E070 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/30/1987 |
| From: | Cooper J, Deeman D FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20150D371 | List: |
| References | |
| NUDOCS 8803280103 | |
| Download: ML20150E070 (83) | |
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N RIVER IJNIT 3
<M GENERATING PIANr N CND0Mimr BUIIDING MHGATED IEAK RATE TEr NOVDtBER 1987
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TABLE OF CENITNIS Section Itgg Title 1.0 Syncmais 2.0 InWvticm i 3.0 'Ibst Results and Conclusicms 3.1 Type A Test - 1987 3.2 Type B&C Tests 4.0 General and 'Ibchnical Data 4.1 General Data 4.2 'Ibchnical Data )
5.0 Tvoe A Test - 1987 5.1 Test Information 5.2 Test Prerequisites 5.3 'Ibst Acceptance Criteria ,
5.4 Test Prmarktre l 5.5 Test Performance 6.0 Tvoe A Test Instri% tion 6.1 Sumary of Instruments 6.2 E<hmatic Arrarap===it 6.3 Calibration Checks 6.4 Instrumentaticn I%rformance 6.5 Volume Weighing Factors !
6.6 Systematic Error Analysis 6.7 Supplemental Verification i 7.0 TyDe A Test Results l 7.1 Diemicn of Results i 7.2 Diawicn of Data Analysis 7.3 Statistical Evaluaticn of Results 7.4 Supplesnantal Test Resulta 8.0 Type B&C Test Results 8.1 "As-Found" Analysis 8.2 S= nary of Testa Since the Previous Type A 'Ibst j 9.0 References Appendices Aroendix Title l A Isakage 'Ibst Results that Failed to Meet III.B.3 or III.C.3 l B Schematic Arraum t of i
'Ibst Instrumentation C Paiivwi 'Ibst Data D 'Ibst Data Graphs E Sumary Ocuputer Results F Type B&C 'Ibst Data G Mass Point Analysis H Noventer 9,1987 Aborted IIRT Attempt j
1.0 SYNOPSIS
'Ihe Crystal River Unit No. 3 Nuclear Generating Plant reactor ocntalment billdiry as subjected to an integrated leak rate test during the period of Novs-her 13 to Novanhar 15, 1987. 'Ihe purpose of this test was to demonstrate the acomptability of the biilding leakage rate at an internal pressure of 49.6 psig (Pa). Testing was performed in accordance with the requirements of 10CFR50 Appendix J, ANSI N45.4-1972, Bactitel 'Itpical Report BPIOP-1 aM Crystal River !
Unit 3 Nuclear Generating Plant FISAR.
ANSI N45.4-1972 includes requirements for data reduction and analysis called *rotal Time Analysis". ,
l Utilizing the Total Time method of analysis, the measured leakage rate was found to be 0.097% by wei@lt per day and 0.1164 by weight per day at the upper bound of the 95% confidence interval at the 49.6 psig pressure level.
'Ihe UCL value of 0.1164 by weight per day must be corrected for the "maintenance inprovenant", caused by repairing leakirq valves before the IIRP, and for the *rype C Correcticn Factor", a correction factor I applied for eight ps-Lsuticos that could not be vented for the IIRP.
'Ihe "maintenance improvenant" factor was 0.010% by weight per day and the "Iype C corrective factor" was 0.011% by weight per day. 'Ihis yields a 'Ibtal Tine cx)rrected Isakage value of 0.137% by weight per day. 'Ihis is below the value specified by Appendix J of 0.75I g (0.187% by weight per day).
'Ibe Mass Point method of analysis, allowed by and defined in ANS ,
56.8-1981, resulted in a maamirad leakage rate of 0.083% by weight '
per day at 49.6 psig. 'Ihe leakage rate at the upper bound of the 95%
ocnfidence interval was 0.086% by weight per day. 'Ihe corrected leakage rate at the upper bound of the 95 percent confidence interval is 0.107 percent by weight per day whicts is below the allowable leakage rate of 0.187 percent by weight per day.
'Ihe suwlanental instrumentation verification test at Pa deis-M. rated an agat between maaaned reactor contairunent building integrated leakage rates of 22.4%, whicts is within the 25% requirement of 10CFR50, Appendix J.Section III A.3.b.
- 'Desting was performed by Florida Power corporaden with the technical assistance of United Energy Services Corporation. Prmadural aM calculaticnal methods were witnaaamd by Nuclear Regulatory himion personnel.
2.0 INIX)DUCI'ICH
'Ibe objective of the integrated leak rate test was the establishment of the degree of overall leak ti$hess of the reactor contalment building at the calculated design basis accident pressure of 49.6 psig. 'Ihe allowable leakage is defined by the design basis accident applied in the safety analysis in accordance with site exposure guidelines specified by 10CFR100. For Crystal River Unit 3, the mav4== allowable integrated leak rate at the design basis accident pressure of 49.6 psig (Pa) is 0.25% by weight per day (Ia).
'I% sting was performed in accordance with the procedural requirments as stated in Florida Power Corporation Crystal River Unit 3 Survaillance PIrvwntre, SP-178. 'Ihis petre was awrtwed by the Crystal River Unit 3 Plant Review rhnmittee prior to the ocumencement of the test.
With the excepticn of the makeup valves .amarv iated with per=Lations 333 and 377 all reactor ocntalment isolation valves and per=kations subject to type B and C testiry were tested prior to ocumwvwnant of the integrated leak rate test. 'Ihair etsbined leakage was less than 60 percent of the mavi== allowable leakage rate (la) at 49.6 psig in accordance with 10CFR50, Appendix J.
Isakage rate testing was aevanlished at the praamtm level of 49.6 psig for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 'Iha 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period was followed by a 7.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> supplemental test for a verificatice of test instrumentaticm.
'Ihis zwort includes the informatica required by 10CFR50, Appendix J, V.B.3 'Ihe results of the type A, B & C tests are presented in Section 3.0, the analysis, statistical evaluation and interpretation of the type A test results and the supplemental validation test results are ocntained in Section 7.0, the emnaq analysis of type B&C tests are in Section 8.0, the instrumentation error analysis is contained in Section 6.0 anc! the leakage test results that failed to meet Acceptance Criteria III.B.3 or III.C.3 (of A@endix J) are addraa* in Appeniix A to this report.
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3.0 TSr RESULTS AND CCNCIIJSICHS I 3.1 Type A 'I4st - 1987 l
'Ihe type A test as aimaaafully empleted during Refueling Outage VI in 1987. 'Ihe conclusion that the test was s-fully ocmpleted is haaad cui the maamired test results. 'Ihese results are reported in hhilar format in ,
Table 3.1. l
'Ihe total reported leakage value, mrrected for pre-test !
valve repairs and in-test valve linequs, is 0.137 weight % l per day, niis value is less than the acceptance criteria, !
highest permitted value, of 0.187 weight % per day. A 1 detailed aM==icrt of these results is presented in Section 7.0 of this report.
3.2 Type B and C 'Ibsts l
Type B and C tests have been run periodically since the '
previously run type A test was performed in 1983. With two '
exceptions these tests have all been av,nanafully otmpleted. 'Ihe two excepticris are addraaamd in Appendix A, "Imakage 'Ibst Results that Failed to Meet III.B.3 or III.C.3". ;
Type B and C test prugou were run in 1985, 1986 and 1987.
'Ihey were run in each of these years because the unactarhiled maintenance cutage that nmirred in 1986 extcsdad the fuel cycle so 1crig that the required fw' ,
of testing could not be met if the tests were not performed '
before the next refueliny. Akiitionally, leak rate tests of the Reactor Contairunant Perscx1nel amaaa Hatches were i run on a semi-annual schedule and the Purge Valves (NN-1A l through 1D) were tested before and after several short i forced outages.
'Ihe total type B ard C leakage values are presented chrtriologically in Appendix F to this report.
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TABI.E 3.1 7%st Results Data, Type A 14st - 1987 (all values are reported in weight 4 per day) maamtrud leakage rate 0.097 typer 954 ocnfidence limit (UCL) 0.116 maintenance inprtmunent (MI) 0.010 type C correction factor (T) 0.011 reported total (UCL + MI + G) 0.137
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l 4.0 GENERAL AND TEC3MICAL DA2A
-4.1 GENERAL DAIA Owner: Florida Pcwer Corporaticn Docket No.: 50-302 Iccatim: AR)roxhataly 5 miles north of Crystal River, Florida !
Contairment Reinforced wn.ta structure 0-- M w iption: of cylindrical walls (g-it-1 with a post-tansioning tendan systan in vertical and horizontal directions),
with a flat foundation met (conventiona] reinforcing) and a l shallow dcme roof (prestressed utilizing a threnMay post tensioning tendcn systan). The inside surface is lined with a carbcn steel liner.
4.2 7ECHiICAL DA2A Oritairnent Net Free Volume: 2 x 106 cubic feet Design Pressure: 55 psig Design
'I%cterature: 281*F Calculated Accident Peak Pressure: 49.6 psig Calculated Accident Peak Temperature: 281'F 5.0 TYPE A TEST - 1987 5.1 TEST INEUMATICH The Reactor Contairment Integrated Isakage Rate Test was ,
performed by Florida Power Corporation persconal and by j perscnnel prwided urder cxmtract by United Energy Services .
(UEE) corporation. h w tary, portable w t h . Were
==CM to permanent in-plant systans to pressurize the omtainment. Data was gathered by use of test instruments i taporarily installed for the test.
l Test data was rMM by a ocmputer pregam derveloped by UES. 'Iha raw data was provided to NRC Region II inspectors for their independent reducticn and analysis. The test data reduction and analysis was performed by two techniques, the "1btal Time Method", required by ANSI N45.4
- 1972, and also by the "Mass Point Method", h ibed by ANS 56.8 - 1981 and presented for informaticm only.
'Ihe data results are shown in Table 5.1.
TABIE 5.1 Test Methad: Absolute Data Analysis: Total Time and Mass Point
'1bist Prormni: 64.4 psia Max Allowable Isakage Rate (Ig ): 0.23 wt 4 per day Measured Isakage Rate:
'Ibtal Time 0.097 wt % per day Mass Point 0.083 wt % per day Measumi Isakage Rate at UCL:
'Ibtal Time 0.116 wt % per day Mass Point 0.086 wt % per day Supplanental
'IWist Flow Rate: 0.229 wt % per day Supplanantal Test Maaenul Isak Rate:
Total Time 0.270 wt % per day Mass Point 0.252 wt % per day Supplanental
'Iwst ard Ism ww.t:
?btal Time 22.4%
Mass Point 24%
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l 5.2 TEST acacu1ISITES l l
Prior to h. sin.a==it of reactor contalment buildiry l
pressurization, the following prerequisites were satisfied:
- 1. Prtper operation of all test instrumentation was verified.
- 2. All reactor ocritaiment building isolation valves were l closed using the normal inode of operation. All i associated systaat valves were placed in post-accident positicos.
- 3. Frpiment within the reactor ccritainnent bi41 ding, I subject to damwja, was protected frcan external differential pressures.
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- 4. Porticns of fluid systans, which under post-accident I ocoditions beccme extensicos of the contalment boundary, were drained and vented.
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- 5. Praaans gauges were installed on the following systems to provide a Insans of detection for leakage into these systems:
- a. Purge supply ;
- b. Purge Exhaust '
- c. Main Steam Icop A
- d. Main Steam Incp B
- e. Personnel Access Hatch
- f. Equipnent Hatch Airlock
- g. Personnel Amaaa Hatch Seal
- h. Equipnent Hatch Seals
- 6. With exception of the valves amamiated with paiWwations 333 and 377 all type B and C testirq was ocupleted with a leakage value less than 0.6 Ig.
However, these valves were lined up in their post acx:ident positicm for conduct of the IIRP.
- 7. Cbntainment pressurizaticu systen was in operation.
- 8. Ocotainment recirculaticn fans were in operaticn.
- 9. Potential pressure sources were removed or isolated frce the ccotainment.
- 10. A general inspecticn of the accessible interior and exterior surfaces of the contalment was ocupleted.
5.3 7EGINICAL SPECIFICATICH ACCEPIANCE CRITERIA Acceptance criteria established prior to the test and as specified by 10CFR50, AEpendix J, ANSI N45.4-1972 and the Crystal River Unit 3 Nuclear Generating Plant FSAR, Section 15.4.2.2, Amerdment 49, are as follows:
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- a. 'Ihe measured leakage rate (Lam) at the calculated I design accident preamire of 49.6 psig (Pa) shall {
be less then 75% of the maxiinnn allowable leakage rate (Ia), specified as 0.25% by weight of the J j
buildig atmosphere per day. 'Ihe acx:eptance !
criteria is determined as follows:
Ia = 0.25%/ day 0.75 Ia = 0.187%/ day J
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- b. 'Ihe test instrumentation shall be verified by )
means of a sugplemental test. Agramant between the containnent leaxage maamired during the Type !
A test arri the containnent leakage inaamimi durig the supplanantal test shall be within 25%
of Ia. l i
l 5.4 GENERAL DISCUSSICH ,
I Following the satisfacticn of the prerequisites stated in )
Section 5.2, the reactor containnent ruilding 1 pressurization was initiated at a rate of approximately 3.0 psi per hour. Vaaaal pressure, temperature, and the i anperage required by the ocultainnent recirmlaticn unit fans were monitored hourly. After the containment was stabilized, leak rate testig was initiated at the 49.6 psig pressure level.
During the test the following m'irred at 15 minute intervals (see Appendix C - Pahvwi Iaakage Data):
- 1. Paadings indicated by the two precision pressure gatges were recorded arx1 entered into the caputer.
'Ihe crmputer program ocmerted this rvwling, usig calibraticx1 equaticals, to psia and ocmputed the average.
- 2. Tawlirgs indicated by the 23 RIDS were recorded ard entered into the ocmputer. 'Ihe ocmputer program calculated the weighted average containment building drytaf.b ta:perature by use of a weighirg factor that was assigned to each RID. 'Ihis value wa subsequently ecoverted to degrees Rankine for use in the ideal gas l law equation to calculate ocntairunent buildirg weight l of air. l l
- 3. Paadirgs iniicated by the five dewpoint tarperature sensors were recorded and entered into the ocmynter.
'Ihe ocmputer program converted the rvwiings to ,
dewpoint tarperatures and then calculated the average l ocultainnent dewpoint tenparature by use of a weighim factor assigned to each sensor. 'Ihis weighted average dewpoint tarperav re was then converted to a partial pressure of water vapor.
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'Ihe use of water vapor praamim (Pwy), temperature (T), aM l the total pmtre (P t) is hibed in more detail in Section 7.0. )
1 Data was entered into an IIM AT Portable Otmputer located )
at the leak rate instrumentatical roca. 'Ihe IIRT ocmputer program utilized for the test had been previously checked j with sanple data of known results and certified prior to the test. 'Ihe atmputer preparu then calculated the l following at 15 minute intervals:
- 1. 'Ibtal weight of contalment air.
- 2. Mass point least squares fit leakage rate.
- 3. Mass point 95% upper confidance level leakage rate.
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- 4. Ahma?Ved total time leakage rate.
- 5. Total time mean leakage rate.
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- 6. Total time least squares fit leakage rate.
- 7. Total time 95% upper confidence level leakage rate.
A plot of weighted average attitaiment temperature, contalment total pr-tre, otritaiment average dewpoint taperature, arri weight of air was performed for each 15 minute data set (see Appendix D).
I=ariiately following the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leak test, a superinmaul leakage rate was established for an additional 7.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> test period. During this time, taperature, pressure, and vapor pressure were monitored as rhe'-ibed above.
5.5 TEST PfREGMANCE 5.5.1 Initial Pressurizaticri Praamtrization of the reactor ocritaiment building was started at 2318 on Noverober 7,1987 with a pressurization rate of approximately 3 psi per hour. men ocritalment internal pressure reached 50.4 psig at 1630 on Novenber 8, 1987, praamtrizaticr1 was aantred. By 2100, ta perature stabilization criteria had been met, however the data collected indicated an excessive leakage rate ranging frm 0.4 to 0.5% per day. At 0127 en Novm bar 9, the secondary side of the A OISG was found to be praamirized to 14 psig.
At 0400 a nitrogen source was musiicted to the A OISG and pressurization of the A OISG was initiated. With a N 2 pr= mtre of approximately 45 psig in the A OISG leakage rate data decreased to less than 0.2% per day indicating that the steam generator was the major source of containment leakage.
i Ebliowirg the above aage of events the primary ocntalment was depressurized so work crews could enter to determine the source of leakage into the A OIBG. Upon investigation the upper inspection cover was identified and j oorrected as the major saints of leakage inte the A OISG. '
'Ihis cover had been renoved & ring the autage for l inspection of the steam generator nnd would not have ;
normally been a scurore of leakage trtan the contairunent.
'Iherefore it is omcitr$ed that this does not ocnstitute a ;
failure of the integrated leak rate test. i I
5.5.2 Pressurization and Stabilizaticn IhaMe l Praamtrization of the reactor contalmcit buildiry was restarted at 0106 cm Novmhar 13, 1987. Mien ocmtairmnent I internal pressure reached 50.5 psig at 1648 cn Novenber 13, praamirization was secured. By 2315 cm November 13, taperature stabilizatico criteria had been met. ;
5.5.3 Intearated Leak Rate Testim 1hase At 2330 cn Novsber 13, 1987, 15 mimte frequency test data collecticn was initiated. By 2330 cm November 14, 1987 an acceptable leakage rate at the upper bound of the 95% l ocnfidence interval was obtained. Utilizing the Total Time l method, the measured leakaga rate was 0.097% per day with an anelated 95% ocnfidence interval of 0.019% per day with an anwiated 95% cx:nfi.dence interval of 0.019% by weight per day. 'Ihus the 'Ibtal Time Imakage rete at the tumr 95% confidence level was 0.116% per day.
5.5.4 Sucolamantal Tm1mm Rate 'litst Ibaam Following ocxtpletion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> integrated leak rate test, a leakage rate of 13.9 scfm was 4==4 cn the contalment building through 2 calibrated flow meters at ,
2345 on Novsber 14. Isakage rate data was again collected l at 15 mimte intervals frtan 0015 November 15 until 0800.
With an 4 W leak rate of 0.229% per day a measured emp'alte leakage rate of 0.270% per day was obtained usirg the 'Ibtal Time method. 'Ihis results in a cxantalment buildirg leakage rate agreennent of 22.4% of La with the results of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.
5.5.5 D=anassurizatico Fhase After all required data was obtained and evaluated, ccotairunent building deperizatico to O psig was started. A post test inspection of the contairunent revealed no urusual firriings.
6.0 TYPE A TEST DUIRMENIATICN 6.1 SLMGRY OF D&DDENIS Test instruments arployal are Assr ribed, by systan, in the following s M cms.
6.1.1 T-raturn Indicatincr System CM.=As:
- 1. Resistance '1%uperature Detectors:
Quantity 23 Manufacturer Volumstrics Type 78-S 100 chm platirum Rarrya, 'F 0 to 400 Accuracy, 'F +/- 0.1 Sensitivity, 'F +/- 0.01
- 2. Digital 'limperature Scanner / Printer:
Quantity 1 Marufacturer Fluke Type Model 2280B Acx:uracy, 'F +/- 0.2 Repeatability, 'F +/- 0.1 6.1.2 Dewooint Indicatim System
- 1. Dewoell ElanerfJ:
Quartity 5 ,
Marufacturer Foxboro l Type M: del 2781 !
Range, 'F 0 - 150 dewpoint !
Accuracy, 'F +/- 2 Sensitivity, 'F +/- 0.5
- 2. Digital 'Itmperature Scanner / Printer:
Quantity 1 Manufacturer Fluke Type Rdel 2280B Accuracy, 'F +/- 0.2 Repeatability, 'F +/- 0.1 6.1.3 Pressure tenitorim Systan Precision Prmers Gauges
. Quantity 2 Manufacturer Texas Instruments Type 145-01
l Range, psia 0-100 Aa21 racy, psia +/- 0.010%
of reading plus O.002% fs Sensor sensitivity, +/- 0.0013%fs psia Repeatability, psia +/- 0.001%fs
, 6.1.4 SurolW Test Flow Monitorim Systen Flowmeter e ,
Quantity 2 Manufacturer Brooks Type 1100-08 Range, scfs 0.756-7.56
, Accuracy +/- 1% of full scale 6.2 SGD9&IC ARN
'Ibe arrargs muit of the four measurirq systems stumarized in Secticn 6.1 is depicted in Agpendix B.
Drybulb tarperature sensors were placed throughout the reactor containment veal volume to permit monitoring of internal ta'perature variaticos at 24 locations. Dewoells were placed at six locaticais to permit monitoring of the reactor contairnent partial praaane of water vapor.
6.3 CALIIFATIW GEGS
'Iturperature, dewpoint, and pressure maaanming systens were checked for calibration before the test as reocannnded by ANSI N45.4-1972, Secticn 6.2 and 6.3. 'Ibe results of the calibraticn checks are cn file at Crystal River Nuclear Generating Plant. 'Ibe supplaiental test at 49.6 psig ccnfirmed the instrumentaticn acceptability.
6.4 INETIRLNDTIATICN PEPKFMANCE During the pressurization phase, cne RID ard dewoell exhibited abnormal behavior and were not used for the test. <
'Ihe rwmaining 5 dewoells, 23 RIDS, two precision pressure I gauges, ard flow meter performed satisfactorily thrughcut the performance of the integrated leak rate test and prtwided more than adequate coverage of the contairment.
6.5 VOILNE WEIGHING FACIGE Weighing factors were assigned to se h drybulb tarperature sensor and dewpoint temperature sensor based on the calculated volume of the reactor ocntairment building each sensirs device monitored. Drybulb and dewpoint tatperaturn sensors elevaticn and weighing factors for the test were as follows:
ElevatiaV Tenperature Weighing Feet Ele =nant Factor 100 IR-42-HE .1102 105 IR-20-4E .0367 105 IR-21 'IE .0367 105 IR-22'IE .0367 105 IR-41-HE .0270 108 IR-23 'IE .0135 108 IR-52 'IE .0165 120 IR-44 'IE .0330 140 IR-24 'IE .0587 140 IR-25 'IE .0587 140 IR-26 4E .0587 140 IR-27 'IE .0165 140 IR-53-4E .0135 140 IR-43-H5: .1764 179.5 IR-54 4E .0547 179.5 IR-55-4E .0547 180 IR-29/IE .0547 ,
180 IR-31'IE .0547 186.2 IR-28-4E .0547 200 IR-48-HE .6533 215.5 IR-35-TE .0421 215.5 IR-38 'IE .0421 220 IR-34 'IE .0421 238.7 IR-37-4E .0421 l 243.7 IR-39 'IE .0421 260 IR-30 'IE .0638 l 260 IR-32 'IE .0638 l 6.6 SYSTD9&IC IRFCE ANMELS I l
Systematic error, in this test, is irduced by the operation of the taperature indicating systas, dewpoint irdicating system, ard the praamtm irdicating syste. i Justification of instrumentation selection was mlished, using inanufacturer's sensitivity and repeatability tolerances stated in Section 6.1, by ocmputirg the instrumentatim selectim guide (ISG) fornula.
Ottitairment leakage determined by the Absolute Method requirss accurate inaamittunant of small charges in contairunent pmre with saltable corrections for temperature ard water vapor. Since the Absolute Method utilizes the change in a reading (i.e., praamire and tenparature) to calculate leak rate, trya repeatability, sensitivity, and raadability of the instrument syste is of more concern than the amiracy. To perform the ISG calatilaticri, the sensitivity error of the sensor and the repeatability error of the measurunent system nust be used.
Sensitivity is defined as "the capability of a sensor to msgsd to change." Sensitivity is usually a function of
the systan maamming the sensor output. m en the sensor energy state is raised or lowered an amount equal to the smallest value which the entire systen will prmaaa, a change of irdication will occur. To deterinine sensitivity for IIRT sensors, it is na,ammary to analyze the smallest value of the analog sensor output which will cause a one digit charge in the digital display.
Repeatability la defined as "the capability of the measuresnent systan to reproduce a given rswiing trun a constant Source."
Utilizing the methods, techniques, arri aa==rtions in Appendix G to ANS 56.8-1981, the ISG foruula was ocmputed for the Absolute Method as follows:
- 1. Oxx11tims:
Ig = 0.25%/ day P = 64.3 psia 7 = 540oa dryeuih Tdp = 72 0F dewpoint t = 24 bcurs ;
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- 2. 'Ibtal Absolute Pressure: e p j 1
No. of sensors = 2 I Range = 0 - 100 psia Sensor sensitivity error (E p) = +/- 0.0013% of full scale Meastuuue.rit systen error (ep ) = +/- 0.001% of full scale i ep = +/- [(Ej) 2 + (g p) 2 1/2 3 / [no. of sensors]1/2 ep = +/- (0.0013)2 + (o, col)2)1/2 / [2]1/2 ep = +/- 0.0012 psia
- 3. Water Vapor Pressure: epv No. of sensors = 5 Sensor sensitivity error (Epy) = +/- 0.50F Mca.hswJit systen error (cpy) ,
excitdirg sensor = +/ .10 F At a dewpoint tarperature of 720 F, the equivalent
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water vapor pressure change (as de' ermined frun steam l tables) is 0.013 psia /oF l
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Ep = +/- 0.50 (0.013 psia / F)
Fp = +/- 0.0065 pela e p = +/- 0.1 F0 (0.013 psia / CF) l cp = +/- 0.0013 psia )
ep = +/- (Fp) 2 + (,p)2j1/2/(no. of sensors]V2 ep = +/- (0.0065)E (0.0013)2] 2/(53V2 e p = +/- O. %3 psia
- 4. 'Iwperature: er No. of sencors = 23 sensor sensitivity arror (Fy) = +/- 0.loF = +/- 0. lor Mersurum nt systan errer (ET )r exclucting sensor = +/- 0.loF = +/- 0. loa er = +/- [Fq)2 + (CT )]V2 / (no. of sensors) 1/2 er = +/- [0.01) 2 + (o,1)231/2 / [23) 1/2 ep = +/- 0.210CR
- 5. Instrunent Selecticr:. Guide (ISG):
2400 IsG = +/- [ 2t*P ) + 2(*PV2 + 2 (*T ) 2) 1/2 t p p T 2400 Isc = +/- 2(0.0012)2+ 2(0.003)2+ 2(0.021)2 1/2 24 64.3 64.3 540 ISG = +/- 100(6.96 x 10-10 + 4.35 x 104 + 3.02 x 104) 1/2 ISG = +/- 0.009%/ day
'1he ISG value does not exceed 0.25 Ig (0.0625%/ day) and it is therefore concluded that the instrumentation selected was acceptable for use in determining the reactor l containnent integrated leakage rate.
6.7 I SUPPLDENIAL VERIFICATION In addition to the calibraticn checks described in Section '
6.3, test instrumentation operaticm was verified by a supplemental test s+===nt to the ocmpletim of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leakage rate test. 'Ihis test consisted of inposing a !
known calibrated leakage rate on the reactor containrent ;
building. After the flow rate was established, it was not l
altered for the duration of the test.
During the supplemental test, t.% h leakage rate was:
Ic = Iy' + Io iihere: I Ie = Maa=wed ocuposite leakage rate consisting of the reactor ocntainment building leakage rate plus the i W _ leakage rate 1 Io = T W _ leakage rate 19 '= Isakage rate of the reactor containuertt hiildirq durirq the supplanental test phase
)
Rearranging the above equation, 1
Iv' = Ic - 4
'Ihe reactor containment building leakage during the supplanental test can be caloalated by subtracting the I known superiW leakage rate frun the measured mite ;
leakage rate.
'Ihe reactor containment building leakage rata during the supplemental test (Iy') was then ocupared to the measured reactor containnent building leakage rate during the prwwling 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test (Lam) to determine instrumentation acceptability. Instrumentation is considered acceptable if the difference between the two building leakage rates is within 25% of the maxininn allowable leakage rate (Ig).
7.0 Tvoe A Test Results 7.1 Dimewuilcn of Results
'Ibe Absolute Method of leakage rate detemination was employed during testing at the 49.6 psig prwuaim level.
h IIRT ocmputer code calculates the p a: Dent per day leakago rate using both the total time and mass point methods, h results are calculated for each dcta point, at 15 mimte intervals during the test, h calculation is based on the methods M m = ai below.
'Ihe total time method utilizes the following equation to determine the leakage rate of the reactor otntairmient tuilding:
g, 2400 T1 P2
[1- )
t T2 P1 Nhere:
L =
Ncnwed leak rate in weight percent per day t = Time interval, in hours, between momi::itus T 1,T2 = Average internal ocntairment temperature, CR, at the beginning and the erd of the test interval respectively.
P 1,P2 = Average contalment prwunsm (corrected for water vapor pressure) at the beginning and end of the test interval respectively.
'Ihe mean total tim leakage rate is d? rived frun the above individual total time calculations. h eqtztion for the mean leakage rate is in the form:
i i L = n Whetu:
Li = Individual total time leakage rates n = NLmber of total time leakage rates
'Ihe individual leakage rates are then plotted against time for the duraticn of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test. h IIRT ocmputer code fits the locus of these points to a straight line using a linear least squares fi.t. h equaticn is of the form L = Io + Li t where Li is the sicpe in percent per hour and Io is the initial leakage rato at time zero. 'Ihe least squares parameters are calculated as follows:
Eti2 (Li -
sti eLi 4"
sxx t L cti eLi -
sy gy L1 sxx Mure:
Sxx = N eti2 - (eti)2 The results of the calculations are as follows:
- 1. The measured total time leakage rate for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test was 0.097% by weight per day.
- 2. The 95% confidence limit a= w iated with this leakage rate is 0.019% per day. Thus, tlw leakage rate at the upper bound of the 95%
ocnfidence level hanrnaa:
UCL = 0.097 + 0.019 UCL = 0.116%/ day
- 3. The mean of the measured leakage rates based on the last five hours of the test was 0.078 percent by weight per day.
Additicnal leakage rates must be awlied to the measured leakatyn rate at the u@er 95% confidence level to account for penetration paths not exposed to l the test pmwe and for changes in the net free volume of the containment due to water level changes.
Penetration paths not avpnaa3 to the test pressure and l the corresponding leakage rates baswd on analysis of l mininn pathway local leakage rate testing are as follows:
l I
Mininum Pathway contairment Incal Systen Isolation Valves Isakaae Rate (SCOO Steam MSV-146 7210 Generator Vents and M -114 20 Drains N -128 20 N -132 1201 MSV-130 7560 E -148 237 Liquid N -3/ N -4 1405 Radwante Isak Rate IRV-44 2 Instrumentation h total applicable local leakage rate is 17,655 socm which is equivalent to a leakage rate of 0.011%/ day.
During the test, no makeup water was intzwW in%
the reactor coolant system, however, there was a 1-irds increase in Reactor Building Susp level.
'Iherefore, the volume change a-iated with this change showed a decrease in the net free voluke of 3.16 cubic f,aet. 'Ihis corresponds to an additional leakage rate of 0.00015% per day. 'Ihe additicn of this very small leakage rate hes no significant effect cn the results of the integrated leakage rate test.
'Ihe corrected contairment leakage rate at the upper I 95% ocnfidence level (UCL) for Type C penalties and i charges in net free volume is calculated as follows: !
UCL = In + 95% confidence limit + Type C leakage + changes in net frea volume.
UCL = 0.097%/ day + 0.019%/ day +
0.011%/ day + 0.000%/ day UCL = 0.127%/ day To determine the as-found contaillment leakage rate, an analysis was performed to evaluate any leakage savings frun repairs or maintenance tc, contairment isolation barriers. Isakage savings are realized when ccntainnent isolatico barrier repairs result in a lower minimum pathway leakage than that whlch existed prior to the repairs.
h culy Type C tested penetration t.% t undera nt
, repairs prior to the IIRP was gmuution 347. W as-found mininum pathway leakage for this penetration was through SFF-19, which had a leakage rate of 15,940 o ,
f soca. After replaewunant of SW-19 the mininnn path leakage rate was 189 som, resulting in a savings of 15,751 sota. 'Ihis is equivalent to a leakage rate reductim of 0.010% per day.
'Ihis value, when N to the UCL (corrected) value, gives a leakage value that would have been measured if the IIRT had been the first activity of the Refueling outage.
7.3 S'IATISTICAL EVAIIRTION 7.3.1 General After performing Um lease squares fit, the IIRT ocmputer i code calculates the followirq ststistical parametem: 3
- 1. Limits of the 95% confidence interval for the total time leakage rate (CL) . l
- 2. Limits of the 95% confidence interval for the mass l point leakage rate (CM)*
These statistical parameters are then used to determine that the uma5nwed leakage rate plus the 95 UCL meet the I acceptance critaia. !
7.3.2 Total Tima Confidence l
'Ihe 95% confidence limit for the total time lee.kage rate is '
calculated as follcws:
l
_.2 1/2 CL=t95 Se ( 1 +J, + (t -
t) l n e.(ti - t)2)
Where:
l l
t = 'Ibtal time interval eti t=
n ti = Time interval for each data point n = Nunter of individual total time leakage rates
7.4 SUPPIDENIAL. TEST RESULTS After conclusico of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test at 49.6 psig (Pa ), the flowmter was placed in service and a flow rate of 13.9 scfm was established. 'Ihis flow rate is equivalent to a leakage rate of 0.229% per day. After the flow rate was established it was not altered for the duration of the supplemental test. The measured leakage rate (Ie) during the supplanental test was calculated to be 0.252% per day usirq the Mass Point nethod of analysis and 0.270% per day usirq the Total Time Iathod.
The building leakage 2 ate during the supplanental test is then determined as follows:
Mass Point Total Tima i ty' = Ie Io Iy' = Ie-Io l Iy' = 0.252 - 0.229 Iy' = 0.270 - 0.229 Iy' = 0.023%/ day Iy' = 0.041%/ day ocuparing this leakage rate with the building leakage rate m mred during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test yields the following:
L L Mass Point = am - v8 =
.dE3 .0?Q_ = 0.24 Ig 0.25 i
l l
L L Total Time = am - v' = .097 .041 = 0.224 L 0.25 The blilding leakage rates agree within 24% of I, usirq the Mass Point method and 22.4% using Total Time which are below the acceptance criteria of 25%.
Usity the formulation of ANS 56.8-1981, (Io + Iem - 0.25Ig) $ Ic $ (Io + Iam + 0.25Ig )
(0.229 + 0.097 - 0.0ds) $ Ic $ (0.229 + 0.097 +
0.063) 0.263 $ Ie $ 0.389 Since le was measured to be 0.270%/ day, this value falls within the acceptable range of 0.263% to 0.389% per day.
Therefore, the acoqtability of the test instrumentation is considered to have been verified.
8.0 TYPE B AND C TEST RESUIIIS 8.1 As-Found Analysis
'Ihe Contalment IIRP (Type A Test) was conducted near the mid-point of the cutage scMle. Several Incal I.eak Rate
'Ibsts (Types B & C) were performed prior to the IIRP and one penetration was repaired.
At the eni of the Refuel IV Outage in August 1983, the total type B & C leakage was 86,192.8 som. 'Ihis was the last previous type A test outage. 'Ihe values followi1x3 that ranged frun a low value of 75,450.8 som to a high value of 169.572 som. 'Ihe value at the beginning of Refuel VI was 105,731 som. 'Ihe chronological listing of Type B & C test totals is presented in Section 8.2 to this reoort.
'Ihere was no "trervi" of degradation in the overall ocntalment leakage value. Several specific path leakages churyed over the period. Nnetration 347 leakage had degraded to an "as-left" value of 45,000 som in 1985.
Plans were made at that time to replace the isolation valves at the next refueling cutage. In 1986, during the formd maintenance cutage the leakage was measured at 53,000 socn. However, the replacement valves were not yet available.
In 1987, the penetration path leakage ws measured at 45,000 soca. 'Ihose three data points do not establish a trend, but it can be safely ==ad that the change frca 1986 to 1987 does not reflect an "inprovement".in the valves as ro maintenance was performed. 'Ihe 1986 leakage value may be ancmalous because the penetration isolation valves are manually operated gate valves.
In 1986, the leakage path value for perduaticn 352 was determined by CW-42, which landad 44,000 soca. It was repaired and the "as-left" value was only 20 soca. In 1987, it was found to be leaking 13,500 socn. it was again repaired ard the "as-left" value was only 2 soca. 'Ihe behavior of this valve needs to be closely monitored.
In 1985, penetration 333 was tested and fourd to have a path leakage of 9370 soca. During the outage it was repaired and retested, tue "as-left" value was 4920 soca.
In the 1986 cutage, it was not tested. In January 1987, it was tested and found to have incraama to 13,370 soca.
During Refuel VI it tested and found leaking greater than 300,000 socn. 'Ihis is greater than 0.6 Ig, and it further d % =ced in Appendix A.
8.2 SU!HARY OF TESTS SINCE '1EE PREVICUS TYPE A TEST
'Ihe sumary of results aru presented in Table 8-1.
3 I
4 ThBIE 8-1 )
IEAK RNIE 'IIBF RE!RHS DM3L DME TPCND HOC IIRF DM3L 'IUIRL B & C 08/03/83 SP-179 SP-179 RF-IV As-Ieft Data 86,192.8 08/11/83 Air Iocks SP-181 6070 79,712.8 02/02/84 Air Iccks SP-181 15,680 89,322.8 04/24/84 Purge Valves SP-177 7790 95,720.8 07/13/84 Air Iocks SP-181 5020 85,060.8 11/05/84 Purge Valves SP-177 3784 81,054.8 11/14/84 Purge Valves SP-177 1281.8 78,552.6 l 01-08-85 Air Incks SP-181 1988 75,520.6 !
03/09/85 Purge Valves SP-177 1989 76,227.8 07/24/85 Purge Valves SP-177 1212 75,450.8 08/08/85 Air Incks SP-181 3670 77,132.8 09/09/85 Air Iocks SP-181 6500 79,962.8 09/13/85 IllC SP-179 RF V As-Inft Data 87,830.06 01/03/86 Purge Valves SP-177 2965 89,583.06 l 06/02/86 IIRT SP-179 RCP Outage, As-Found 169,372.
06/02/86 Air Iccks SP-181 19,890 130,762.
06/02/86 IIRT SP-179 RCP Outage, As-Inft 130,762.
06/02/86 Air Iocks SP-181 1645 112,517.
07/01/86 IIRE SP-179 W==nt Sp-181 Data 112,517. l 08/22/86 CAV-431 SP-179 1079.7 112,494.
11/13/86 AHV-1C SP-177 AHV-1C Failed Open ***
11/20/86 Purge Valves SP-177 2077.7 97,921.7 11/20/86 Purge Valves SP-179 Mn=nt SP-177 Data 97,921.7 01/05/87- Ren. 333 SP-179 13370 106,724.
01/05/87 Purge Valves SP-177 2450 106,724.
01/19/87 Air Incks SP-181 17,020 122,099.
07/13/87 Air Iccks SP-181 1474 106,553.
08/24/87 Purge Valves SP-177 1501 105,604.
08/24/87 IIRT SP-179 Wn=nt SP-177 Data 105,604.
08/28/87 Purge Valves SP-177 1628 105,731.
08/28/87 IIRT SP-179 Wn=nt SP-177 Data 105,731.
09/18/87 IIRT SP-179 Begin RF VI ***
10/30/87 Air Iocks SP-179 RF VI "As-Isft" 26,930.1 w w.,-
l l
9.0 REFERDCES
- 1. Crystal River Unit 3 Nuclear Generating Plant Final Safety Analysis Report.
- 2. SP-178, "Containment Isakage Test - Type A, i:r.luding Liner ,
Plant". )
l
- 3. Cbde of Federal Regulations, Title 10, Part 50, Appendix J. l
- 4. ANSO N45.4-1972, Isakage Rate Testing of Cbntalment Structures for Nuclear Reactors, American Nuclear Society (Mard) 16, 1972).
- 5. Steam Tables, American Society of Mechanical ergineers,1967.
- 6. IIRT Ctmptter Cbde, Gilhart/Otanca1 Wealth, Inc.
- 7. ANS-56.8-1981, "Containnent Systen Isakage Testing Requirunents",
American Nuclear D 2,lety.
- 8. Crystal River Unit 3 Nuclear Generating Plant Reactor Otx1tainnent BH1 ding Integrated Isak Rate 'Ihst", Florida Power Corporation, (July, 1983).
- 9. IN-40P-1, "Testirg Criteria for Integrated Isakage Rate Testing of Primary Ox1tainnent Structures for Nuclear Power Plants",
Revision 1, November 1,1972.
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APPENDICES 1 e
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\
I J
I 4
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' II a III.c 1
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m APPENDIX A LEAIQE TUTT RESUIES THAT FATTm 70 NEZr 10CFR50, APPENDIX J, III.B.3 CR III.C.3 l
Between the 1983 IIRT ard the 1987 IIRE, there were two occasicos when the 1 acceptan criteria of 10CER50, Appendix J, III.B.3 or III.C.3 was not met.
The first was cm Novenbar 13, 1986, when valve AHV-1C was found cracked off its seat. The W m,wred during Refuel VI when MN-41 was found with a leakage valve greater than 0.6 Ig.
AHV-1C AHV-1C is a 48 inch butterfly valve located inside the Reactor OxitairEREnt (RB) cn the Contairunent Purge Inlet line. The Purge Inlet is isolated outside the RB by AHV-1D. The test is run by pressurizing between the valves. During the test cn Novmber 13, 1986, the volume would not pressurize. The duct work leading to AlW-1D cutside the test volume was entered and the valve AHV-1D was "butble" checked for evidence of leakage. None was detected. The failure was demonted cn an NCW, Non-Conforming Cperaticos Report by FPC. The volume was retested, after a seven day use of the purge systan, and the acceptance criteria was net.
Valve AHV-1C has had a history of probles with the motor operator placing and keeping the butterfly on its seat. FPC is evaluating this valve presently to determine the best permanent fix for this problen.
MN-41 During Refuel VI in 1987, MN-41 was discovered to be leaking in excess of 300,000 scan, a value greater than 0.6 Ig. This valve provides isolatim cn the Reactor Coolant Istdown Line, inside the Reactor Ocotairunent (RB) . The Istdown Line was aligned per 10CFR50, Apperrlix J, for the Type "A" test (IIRP).
It was not a source of any known leakage during the test. After the IIRT was cccpletal, this penetraticn was Type "C" (IIRF) tested and the failure was discoverod. The valve was repaired, by lapping the seat, and was awafully retested. This failure was also documented en an NC E .
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1 APPENDIX B SOBRTIC ARRANGDENT OF 'IEST INmufENIATICH 1
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APPENDIX B SCHEMATlC ARRANGEMENT OF TEST INSTRUMENTAIION
/ x -
s @ @" /
@ 6%
II W
QUADRANT ORIENTATION
@@ an I III W~ h /7I IV yg I III
" E III II
'O
$E I III h.IV II IV x
x : @ : x II
\III I III IV II
'IT h Iy/
\ /
INST. TAG ELEY. INST. TAG ELEY.
, lHST. TAG ELEY.
LR-20-TE 105'-0" LR-32-TE 260'-0" LR-41-HE 105 '-0 "
LR-21-TE 105 -0 " LR-33-TE 242'-8 " LR-42-HE 100'-0" LR-22-TE 105'-0" LR-34-TE 220'-0" LR-43-HE 140'-0" LR-23-TE 100'-0" LR-35-TE 2 i 5 '-6 " LR-44-HE 120'-0" LR-24-TE 140'-0" lR-37-TE 238'-8" LR-48-HE 200'-0 "
LR-25-TE 140'-0" LR-38-TE 215 '-6 "
LR-26-TE 140'-0" LR-39-TE 242'-8" LR-27-TE 140'-0" LR-52-TE 108'-0" LR-28-TE 186'-2" LR-53-TE 140'-0" LR-29-TE 180'-0" LR-54-TE 179'-6 "
LR-30-TE 260'-0" LR-55-TE 179'-6 " ,
LR-31-TE 180'-0" -
- Not used for test.
1 8
APPENDIX C REDUCED TEST DATA l
I i
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-~- . . - ~. .. - -. . . .
6 REDUCED ILRT TEST DATA i
l DATE TIME PAVG PWV TAVG MASS WEIGHT 11-13-87 2330 64.478 0.5421 84.438 634307.00 2345 64.470 0.5381 84.380 634334.38' 11-14-87 0 64.463 0.5385 84.324 634332.00 15 64.455 0.5422 84.280 634266'.00 30 64.447 0.5375 84.223 634301.31 45 64.440 0.5361 84.170 634301.44 100 64.433 0.5376 84.120 634280.88 115 64.427 0.5359 84.076 634288.81 130 64.421 0.5382 84.032 634253.50 145 64.415 0.5373 83.987 - 634255.56 200 64.408 0.5308 83.946 634297.38 215 64.402 0.5312 83.907 634285.56 230 64.396 0.5347 83.859 634246.38 245 64.391 0.5347 83.821 634236.19 300 64.385 0.5312 83.787 634256.63 315 64.379 0.5337 83.730 634237.50 330 64.375 0.5300 83.708 634256.13 345 64.370 0.5334 83.679 634206.06 400 64.365 0.5283 83.647 634244.69 415 64.360 0.5296 83.601 634240.1?
430 64.355 0.5324 83.586 634180.63 445 64.351 0.5292 83.548 634216.06 500 64.346 0.5245 83.499 634271.31 515 64.342 0.5277 83.481 634215.50 530 64.339 0.5317 83.450 . 634181.94 545 64.334 0.5320 83.404 634182.81 600 64.329 0.5249 83.378 634234.56 615 64.325 0.5222 83.360 634241.56 630 64.321 0.5263 83.332 634198.81 645 64.317 0.5279 83.289, 634194.44 700 64.313 0.5205 83.268 634246.44 715 64.309 0.5230 83.243 634217.19 730 64.305 0.5265 83.213 634177.19
.745 64.301 0.5246 83.190 634103.13 800 ~64.297 0.5199 83.154 634232.25 815 64.294 0.5233 83.158 634158.38 830 64.290 0.5196 83.111 634214.94 845 64.286 0.5221 83.102 634157.00 900 64.282 0.5202 83.083 634157.63 915 64.278 0.5254 83.063 634088.69 930 64.274 0.5192 83.038 634141.25 l 945 64.270 0.5195 83.013 634132.94 1000 64.267 0.5156 82.996 634156.88 )
1015 64.264 0.5225 82.974 634083.50 1030 64.260 0.5208 82.960 634076.88 I
REDUCED ILRT TEST DATA DATE TIME PAVG PWV TAVG MASS WEIGHT 11-14-87 1045 64.r.56 0.5141 82.923 634151.88 1100 64 233 0.5221. 82.904 634059.50 1115 64.249 0.5196 82.906 634042.50 1130 /A.246 0.5195 82.879 634044.88 1145 64.242 0.5153 82.865 634067.25 1200 64.239 0.5186 82.839 634030.31 1215 64.235 0.5182 82.819 634023.13 1230 64.233 0.5147 82.806 634032.81 1245 64.230 0.5168 82.791 634015.44 1300 64.227 0.5138 82.779 634029.44 1315 64.225 0.5195 82.756 633979.75 1330 64.223 0.5154 82.743 634015.75 1345 64.220 0.5125 82.732 634026.63 1400 64.216 0.5156 82.708 633990.19 1415 64.214 0.5154 82.704 633976.38 1430 64.211 0.5129 82.674 634006.63 1445 64.208 0.5171 82.649 633964.56 1500 64.206 0.5165 82.644 633950.56 1515 64.203 0.5142 82.637 633937.19 1530 64.201 0.5135 82.617 633968.31 1545 64.198 0.5137 82.601 633954.69 1600 64.196 0.5098 82.577 ~634002.19 1615 64.194 0.5130 - 82.574 633953.69 1630 64.191 0.5132 82.555 633943.38 1645 64.189 0.5138 82.541 633928.63 1700 64.186 0.5115 82.528 633941.50 <
1715 64.184 0.5115 82.512 633941.25 l
1730 64.182 0.5125 82.504 633915.13 1745 64.180 0.5077 82.471 633962.25 1800 A4.177 0.5102 l 82.469 633934.44 1 1815 64.174 0.5122 82.460 633895.25 '
1830 64.172 0.5115 82.437 633904.06 1845 64.169 0.5112 82.422 633900.13 1900 64.168 0.5107 82.415 633897.38 1915 64.164 0.5112' 82.399 633881.81 1930 64.162 0.5089 82.389 633897.44 l 1945 64.160 0.5106 82.371 633874.81 2000 64.158 0.5076 82.357 633902.13 2015 64.155 0.5102 82.337 633875.31 2030 64.154 0.5104 82.327 633870.06 2045 64.152 0.5088 82.316 633879.25 2100 64.149 0.5090 82.304 633865.94 2115 64.147 0.5092 82.290 633855.25 2130 64.144 0.5078 82.280 633855.25 2145 64.142 0.5091 82.259 633846.81 i
n n- -w-- - e -v . % , ,--
_ .. ._ , _ . . . . - _ . _ . _ _ ~ . . ..
REDUCED ILRT TEST DATA
-DATE TIME -PAVG PWV TAVG MASS WEIGHT 11-14-87 2200 64.140 0.3093 82.248 633337.88 -
2215 64.138 0.5072 82.234 633851.63 2230 64.135 0.5088~ 82.215 633831.25 2245 64.133 0.5062 82.205 633850.19 2300 64.131 0.5072 82.188 633819.~31 2315 64.129 0.5079 82.175 633827.13 2330 64.127 0.5065 82.156. . 633845.25 VERIFICATION TEST DATA i
11-15-87 15 64.119 0.5062 82.125 633799.31 30 64.116 0.5050 82.106 633802.94 45 64.113 0.5053 82.105 633771.13e 100 64.109 0.5031 82.079 633788.75' 115 64.106 0.5059 82.069 633737.75 130 64.103 0.5055 82.067 633714.13 145 64.100 0.5096 82.048 633670.88 200 64.097 0.4998 82.038 633749.31 213 64.093 0.5048 82.028 633671.06 230 64.091 0.5076 82.008 633643.00 245 64.087 0.5042 81.991 633660.81 i 300 64.085 0.5001 81.989 633680.31 '
315 64.080 0.5040 81.979 633607.06 330 64.078 0.5014 01.975 633613.50 l 345 64.074 0.5054 81.951 633565.88 400 64.071 0.5026 81.945 633571.44 415 64.068 0.5047 81.935 633532.63 430 64.065 0.5012 81.918 633557.44 445 64.062 0.5037 81.916 633504.38 500 64.059 0.5039 81.903 633487.56
.515 64.056 0.5006 81.900 433494.44 530 64.054 0.5000 81.877 a$3502.63 545 64.051 0.5039 81.872. 633439.38 600 64.048 G.5030 81.858 633435.13 615 64.044 0.5037 81.850 633401.94 l 630 64.042 0.5037 81.848 633379.38 645 64.039 0.5015 81.826 633401.56 700 64.037 0.5019 81.826 633374.31 715 64.034 0.5033 81.821 633340.13 730 64.031 0.5021 81.808 633332.25 745 64.028 0.5047 81.798' 633293.13 800 64.025 0.5007 81.800 633301.38 i
_ , . , . . . . , ,. m, -_m-.__., _ 4 _ , - _ _ _ . - . _ _ . . , . , . _ . _
c _ _ __, - ,. .. , -
~ _ _ _ _ _
5 APID4 DIX D IEAKNE RATE TEST GRAHE l
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0 24 HOUR TEST i
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I
k X/ DAY MASS POINT.LEAXAGE RATE vs IIME PLOTTED:
11/15/87 0.5 -
09:28:51 7
g'4 _ TEST STARIED:
11/13/87 i 23:30
- 0.3 -
b
\ MkJOR 0.2 INCREMENT 1^
+
45 MINUTES 0,1 f w "vkr4 4 ,,,,,,
a.f
/*b m ,ityg .g m***"### ~ ," m ....,,,.,,,,,,,,,,
iiiiiiiiii! iiiiiiiiiiiiiiiiiiiiTIME 80 2830 i
X/ DAY TOTAL TIME LEAL (AGE RATE vs TIME PLOTTED:
GREATERTHAN24 HOURS 11/15/87 10- 09:28:51 0'8 . TEST STARTED:
11/13/87 23:30 0.6 4 1
z
\ MAJOR i 0.4 INCREMENI
\.\ 45
% MINUTES g'} . "M 4+++++g
'^Y %#emp
"+++&+ : : : : : : : : u : : . ' : : : : ' : : : : : . : : . . . . . .....
+4++++++:: : : : , :: : : : : :: ' : : : :: : : : : : . : . . : : : ! ! ! : ! ! ' : ! :: : . ' . ! ! ! ! !! ! ! ! l ! !
I I I I I I I I I I I I I I I I I I I I I I i I I i ! I I I IIIME
'O 2'30
Thott LBM MASS WEIGHT vs TIME PLOTTED:
11/15/87 09:28:51 634.6 , TEST STARTED:
11/13/87 23:30 634.4 -
Onyi 634.2 - '
,/V\ /g hCMENT
\ 45 fhji,4#
MINUTES 634.0 - .
M' .%+-n* .,g.,
' *YA so.
4 I I I I I I I I I i iiiI I I I I I i I i i ii i i i i ~
i,I'r', TIME
- 2380 2330 i
DEGF AVE RID vs TIME PLOTTED:
11/15/87 85.5 -
09:28:51 g4'7 . IEST STARIED:
+
11/13/87 23:30 84,B -
'N* +
.%,+
, '"s
- MAJ0R 83.2 -
4.,~'++4
' INCREMENT
+ " "++4++ 45
- +++*
- MIHUTES
.y, ****
82.5 -
- m4 ,
, **++.N++H 4
l l l l l l l l l l l l l l l I l l l l l l l II I I I I I I l 2330 2330
~
PSIA AVE PRESSURE vs TIME PLOTTED; 11/15/87 64.6 -
09:28:51 TEST 64'5 '
i STARTED:
. s.g 11/13/87 64.4 ' s, 44
% .,,**++
MAJOR-
' +++4*+#
64.3 4 INCREMENT
++4.'++ 4 45 4 .s* *+
MINUTES
+4++4++*
+4y **
64.2
%.y N+4 94 44+H,
+H+y i i i ,i i i i i i i ii i i i i i i i i i i si i i i ii i i IIME 23'8 2830
l I
l i
i l
l
(
7.75 HOUR VERIFICATION f
l
{
f l
l 1
l l
i I
1 I
I
ThouLBM MASS WEIGHT vs TIME PLOTTED:
11n.5/87 08:10:56 634.g , TEST STARTED:
11/15/87 00:15 633.8 .. , _s
'N A V N - -, -\
MAJOR 633.6 -
- s. ,,.
. INCREMENT
. -\
15
- - # s MIHllIES 633,4- \--+s , . A
~
s.
t
! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! ! l l l l ! ! ! ! !
15 800 t
X/D.'d MASS POINT. LEAKAGE RATE vs TIME PLOTTED:
11n5/87 08:10:56 4 l(\
0'40 './ \i TEST STARTED:
\ 11/15/87 1' 00:15 0.35 -
. \
/ \ MAJOR 0.30 -
/ \' INCREMENT
/{ . ~v + 4 .
- _4..
.- ; .~
LTEs
/i{j 8.25 -
A.,
'+
_+
.s+_ ; ;-+ -
g ,,d ,
\ f -/
\'
i i i i i i i i i i i i i i i i i i i i i i i i i i i IIME 115 800
~
X/ DAY TOTAL TIME LEAKAGE RATE vs TIME PLOTTED:
LESdTHAN24 HOURS 11n5/87 1,2 -
08:10:56 TEST 1'0 _
STARTED:
11/15/87
, 00:15 0.8 -j ,
. MAJOR 0,6 -
. , _ . .N._4 INCREMENT 4-15
' + + + - ++_~_._ . _
MINUTES
/. .
% +-+ #_._
- +_._-+ . : : . .
/I I I I I I I I I I I I I I I I I I I I I_I I I I I I IIME
- .15 800
DEGF AYE RID vs TIME PLOTTED:
11/d/87 82 2 -
08:10:56 P
82'1 ' TEST
~ \_'- STARIED:
"'s 11/15/87
~+,.., 00:15 82.0 -
\_
' . ~_ , _ MAJOR 81.9 -
~~+ .
. INCREMENT 15
_,' ~ .,
MINilIES
- : g
@j,,8 -
~*+-+
15 800
PSIA AVE PRESSURE vs TIME PLOTTED:
11n5/87 08:10:56 t 64.20 -
TEST STARTED:
11/15/87 00:15 64,15 -
D 64,10 -
"++~*+++++' MAJOR IHCREMENT 15
' + +'~+ ' * + _._
MIHUIES
- + + ~4 15 800
o -u- -
-wv, 2 www w-yw ww~ . w ------------
t APPENDIX E O2EUTER N
l 24 HOUR TEST I
l l
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1 I
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j
- TOTAL _ --
TTME ANAt_YSIS ***
t X ODS. LEAKAGE RATE
.25 .414310420663G991
.5 .1891828404657243
.75 .2069399055977554 1 2.151954310524215D-02 1.25 1.683727280322067D-02 1.5 6.5S9965743587263D-02 1.75 3.932300470097516D-02 2 .1012128196593738 2.25 8.649359073320528D-02 2.5 1.456707871740903D-02 2.75 9. 9495324675732350-02 3 7.646139802965912D-02 3.25 8.244006097321232D-02 3.5 5.445763193983044D-02 3.75 7.012377287333722D-02 4 4.812338504856795D-02 4.23 8.986184923073325D-02 4.5 5.239313665674761D-02 4.75 5.322012012612311D-02 5 9.563192586555136D-02 5.25 6.553934116327925D-02 5.5 2.455077316304061D-02 5.75 6.020949531981556D-02 6 7.886559662750314D-02 6.25 7.513126080904075D-02 6.5 4.216594463903879D-02 6.75 3.668045073862795D-02 7 5.847776730015004D-02 7.25 5.874453374393855D-02 7.5 3.035302873844923D-02 7.75 4.334770028678078D-02 8 6.139574370139234D-02 8.25 5.681218027920775D-02 S.5 3.327392312073192D-02 S.75 .0642691135250202 9 3.870365611604597D-02 9.25 6.135659691429977D-02 9.5 5.949302483696751D-02
'r . 7 5 .0347199566431747 10 6.271411162102947D-02 10.25 6.425293253093376D-02 10.5 5.405728367223706D-02 10.75 7.866496483454235D-02 11 7.915582030324497D-02 i
J
... y -- .
11.25 .0521724233428511 11.5 8.143087481778219D-02 ,
11.75 8.517252988677845D-02 12 8. 264925343721696D- 02 12.25 7.405156899014019D-02 12.5 8.375124348304563D-02 12.7S 8.4242006028071240-02 13 7.398140502457445D-02 l 13.25 8.325829725151533D-02 13.5 7.779268468492972D-02 13.75 9.005103207122192D-02 i 14 7.871357470210981D-02 14.25 7.444510722974631D-02 14.5 8.266963951916364D-02 14.75 8.481162933641188D-02 15 7.576772761454631D 15.25 8.496170352635081D-02 15.5 8.700884994276409D-02 15.75 8.403621890466533D-02 16 8.009232910877462D-02 16.25 8.203259013986288D-02 16.5 6.989732674613982D-02 1 16.75 .079809746064627 17 8.0931306319569480-0?
17.25 .0829936895870129.
17.5 7.902437508290814D-02 !
17.75 7.796464665652536D-02 18 8.237336179484078D-02 .
18.25 7.147483206297634D-02 ,
18.5 7.619722379294671D-02 18.75 8.3089103541345470-02 ,
19 8.024090609287426D-02 19.25 7.997274620534328D-02 19.5 7.948104721433762D-02 19.75 8.145638378636865D-02 20 7.748219710644877D-02 20.25 8.075304579993891D-02 ,
20.5 7.472722199187465D-02 20.75 7.G71601682139417D-02 21 .0787248355854721 21.25 7.616278589908933D-02 '
21.5 7.761995961092957D-02 21.75 7.858698684086999D-02 !
22 7.769395289949153D-02 22.25 7.825580081441863D-02 '
I t
6
/
b a
i
_ . . . - . . _ . . - _, _ . . , . , , , . , . m.,, ,_ ..,.. . - ._,.,., , _ _ ,
22.5 7.SS3924448256063D-02
, 22.75 7.373550416369465D-02 23 7.826411857486863D-02 23.25 7.434071941453796D-02 23.5 .078520941718637 23.75 7.644778153945615D-02 24 7.279598049524938D-02 LO = 2.9026999365593SSD-02 % PER DAY L1 = 2.826695499320565D-03 % PER DAY THE 5 HOUR MEAN LEAKAGE RATE = 7.783096E-02 % PER DAY CALCULATED LEAKAGE RATE = 9.686745E-02
< 24 HRS 95% CONFIDENCE LEVEL = .1163038 % PER DAY
< 24 HRS UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = .2131713 % PER DAY (INCLUDES LEAKAGE RATE)
< 24 HRS 95% CONFIDENCE LEVEL = 1.931671E-02 % PER DA
> 24 HR3 UPPER LIMIT OF THE 95% CONFIDENCE LEVEL r= .1161042 % PER DAY (INCLUDES LEAKAGE RATE)
I
, ,_j .ww - w --- w- w~
, a 7.75 HOUR VERIFICATION 1
1 I
i
~_w. ..- . m .
.- .;._ .. 4
- TOTAL -
TIME ' ANALYSIS ***
. )
X OBS. LEAKAGE RATE
.25 . .0549069702565852
.5 .2134745136694871
.75 5.332918375482443D-02 1 .2331179556147034-1'.25 .2580627602053376 1.5 .3242351260833942 >
1.75 .10S1910743969556 '
7 e .2428213425996695 2.25 .2630696027038205 2.5 .209782493255700 2.75 .1638602999502985 3 .2426635639495078 3.25 .216476581661064 3.5 .2525555392954 3.75 .2301043833965988 4 .2524655625908395 4.25 .2155070739274724 4.5 .2481858167051894 4.75 .7485262864239615 5 .2308932766474059 5.25 .213992929234319 !
5.5 .2478128853502575 ,
5.75 .2398372681292123 -
6 .2507891644328686 6.25 .254427540105608 6.5 .2317161529920999 6.75 .2384210713562614-7 .2483999448732645 ;
7.25 .243947555723244 i 7.5 .2555698575327803 7,75 .2432946785501609 LO = .1664448290078045 % PER DAY L1 = 1.339401464204192D-02 % PER DAY THE 5 HOUR MEAN LEAKAGE RAiE = .2366414 % PER DAY CALCULATED LEAKAGE RATE = .2702484
< 24 HRS 95% CONFIDENCE LEVEL = .138067 % PER DAY
< 24 HRS UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = .40G3154 %-PER DAY .)
(INCLUDES LEAKAGE RATE)
> 24 HRS 95'/ CONFIDENCE LEVEL = 3.796046E-02 % PER DAY l
> 24 HRS UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = .3082089 % PER DAY j (INCLUDES LEAKAGE RATE) ,
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APPENDIX F
'IYPE B & C TEETfDG l
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f'~
4 TYPE C TESTS - 1985 NOTE: All leak rate measurements are in scca.
As Found As Left Pen. No. Valve No. Valve Path Valve Path 329 DNV-93 20 20 DHV-91 819 819 278 278 439 CAV-126 78 CAV-1 874 874 CAV-2 3000 3000 CAV-3 46 46 CAV-429 25 25 CAV-431 256 CAV-430 178 178 CAV-432 4556 174 3430 425 CAV-434 20 20 CAV-436 20 20 20 20 CAV-433 20 20 CAV-435 24 24 24 24 440 CAV-4 34 34 34 34 CAV-6 31 31 441 CAV-5 20 20 20 CAV-7 271 271 206 CIV-41 20 20 218 218 207 CIV-40 20 20 20 20 366 CIV-34 20 20 20 20 367 CIV-35 248 248 248 248 117 DWV-162 2610 2610 2610 2610 l DWV-160 496 496 i
333 MUV-40 20 MUV-41 9370 4920 4940 MUV-49 57 377 MUV 260 20 MUV-261 20 MUV-259 20 i MUV-258 186 246 i MUV-253 20 20
. ~
. As Found As Lef t Pen. No. Valve No. Valve Path Valva Path 339 WDV-3 4240 4240 WDV-4 20 20 20 349 WDV-60 20 WDV-61 30 30 30 30 354 WDV-405 818 818 818 818 WDV-406 20 20 374 WDV-94 175,000 20 WDV-62 870 870 315 WSV-3 119 119 33 WSV-4 100 100 100 332 WSV-5 44 44 WSV-6 62 62 62 62 356 WSV-1 61 WSV-2 212,000 64 64 WSV-34 20 20 WSV-35 20 20 20 20 WSV-30 20 20 WSV-31 61 61 61 61 WSV-36 20 20 WSV-39 20 20 20 20 306 WSV-32 20 20 WSV-33 20 10 20 20 WSV-28 20 20 WSV-29 20 20 20 20 WSV-26 20 20 WSV-27 20 20 20 20 376 WSV-41 46 46 WSV-40 46 46 46 46 WSV-42 47 47 47 47 WSV-43 45 45 113 AHV-1C AHV-1D l
357 AHV-1A ,
AHV-1B l 121 LRV-50 41 41 LRV-36 394 435 394 435 ;
, LRV-90 NA 20 l LRV-89 NA 20 40 I
As Found As Left Pen. No. Valve No.. Valve Path Valve Path
.122 BLIND NA 41 41 LRV-88 NA 48 90 LRV-87 NA 42 125 LRV-94 NA 20 LRV-93 NA 20 LRV-92 NA 20 LRV-91 NA 20 80 116 B.F.
LRV-45 20 20 20 20 305 LRV-70 20 20 LRV-72 20 20 20 20 306 LRV-73 20 20 LRV-71 20 20 20 20 202 B.F.
LRV-44 164 164 164 164 ,
123 CFV-20 145 145 145 145 CFV-28 77 77 373 CFV-19 124 124 CFV-25 186 186 186 186 124 CFV-17 1182 1182 1182 1182 CFV-27 782 782 350 CFV-18 1398 1398 1398 1398 CFV-26 86 351 CFV-15 20 CFV-16 20 CFV-29 45 45 352 CFV-11 1634 CFV-12 CFV-42 355 !!GV-62 710 710 710 710 372 NGV-82 32 32 32 32 317 NGV-81 7511 7510 582 582 110 SAV-24 1525 1525 1525 1525 SAV-122 1501 1501 SAV-23 111 IAV-28 1948 1948 1948 1948
As-Found As Left
-Pen. No. Valve No. Valve Path Valve Path 112 IAV-29 871 871 871 871 347 SFV-18 56000 45000 '45000 SFV-19 10000 430 FSV-262 FSV-261 114 114 114 114 316 MSV-114 74 74 14 74 320 MSV-132 453 453 453 453 4
318 MSV-128 20 20 20 20 _
i 314 MSV-146 2000 2000 2000 2000 427 MSV-130 2250 2250 2250 2250
- 428 MSV-148 186 186 186 186 l
i
)
?
TYPE B TESTS - 1985 As Found As Left (secm) (secm)
Equipment Hatch Resilient Seals 5.1 Fuel Transfer Tube Gasket - 3B 28.0 Fuel Transfer Tube Gasket - 3A 26.5 LRV-44 and Blind Flange 163.5 chemical cleaning Pen. Gaskets 119 87.5 Chemical cleaning Pen. Gaskets 120 85.3 Personnel Access Hatches 996 1/7/85 1020 8/2/85 l
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TYPE C TE3TS - 1986 NOTE: All leak rate measurements are in sccm.
As Found As Left Pen. No. Valve No. Valve Path Valve Path 329 DHV-93 4 4 DHV-91 20 20 20 20 439 CAV-126 20 20 CAV-1 20 CAV-2 920 CAV-3 148 148 CAV-429 20 20 CAV-431 43 43 CAV-430 310 310 CAV-432 140 5032 140 1103 425 CAV-434 20 20 CAV-436 20 20 20 20 CAV-433 27 27 27 27 CAV-435 20 20 440 CAV-4 20 20 i CAV-6 81 81 81 81 l 441 CAV-5 20 20 CAV-7 2230 2230 2230 2230 206 CIV-41 997 997 997 997 207 CT,V-40 l 25 25 25 25 '
366 CIV-34 55 55 55 55 ;
367 CIV-35 330 330 330 330 1
l 117 DWV-162 5200 5200 5200 5200 '
DWV-160 350 350 333 MUV-40 MUV-41 l
MUV-49 '
l 377 MUV-260 MUV-261 MUV-259 MUV-258 MUV-253
As Found _
As Left Pen. No,z Valve No. Valve Path Valve Path 339 WDV-3 1280 1280 1365 1365 WDV-4 76 76 349 WDV-60 105 105 105 105 WDV-61 103 103 354 WDV-405 5760 5760 2150 2150 WDV-406 160 160 374 WDV-94 20 20 WDV-62 20 20 20 20 315 WSV-3 3'6 36 36 WSV-4 37 37 37 332 WSV-5 25 25 WSV-6 116 116 116 116 356 WSV-1 20 20 WSV-2 20 20 20 20 WSV-34 20 20 WSV-35 20 20 20 20 WSV-30 197 WSV-31 204 204 204 204 WSV-38 20 20 WSV-39 20 20 20 20 306 WSV-32 33 33 33 33 WSV-33 32 32 WSV-28 26 26 26 26 WSV-29 23 23 WSV-26 20 20 20 20 WSV-27 20 20 l
376 WSV-41 20 20 I WSV-40 23 23 23 23 i WSV-42 20 20 WSV-43 l 20 20 20 20 113 AHV-1C AHV-1D 6250 6250 6250 6250 l 1
357 AHV-1A AHV-1B 10400 10400 10400 10400 121 LRV-50 460 460 460 460 !
LRV-36 114 114 I LRV-90 448 4 4 P, 448 448 >
LRV-89 442 442
As Found As Lef t Pen. No. Valve No. Valve Eath Valve Path 122 BLIND 64 64 64 64 LRV-88 65 65 65 65 LRV-87 62 62 125 LRV-94 13 13 13 13 LRV-93 2 2 LRV-92 9 9 9 9 LRV-91 8 8 116 LRV-45 23 23 LRV-46 854 854 854 854 305 LRV-70 40 40 LRV-72 44 44 44 44 306 LRV-73 120 120 120 120 LRV-71 103 103 202 B.F.
LRV-44 20 20 20 20 123 CFV-20 1190 1190 1190 1190 CFV-28 65 65 373 CFV-19 538 538 538 538 CFV-25 20 20 124 CFV-17 690 690 CFV-27 690 690 690 690 i 350 CFV-18 1198 1198 1198 1198 CFV-26 862 862 351 CFV-15 52 75 52 75 CFV-16 23 23 CFV-29 70 70 352 CFV-11 20 20 40 CTV-12 20 20 CFV-42 44000 44000 20 355 NGV-62 1598 1598 1598 1598 372 NGV-82 72 72 72 72 317 NGV-81 74 74 74 74 110 SAV-24 193 193 SAV-122 SAV-23 1920 1920 1920 1920 111 IAV-28 2580 2580 2580 2580
As Found As Left-Pen. No. Valve No. Valve Path Valve Path 112 IAV-29 93 93 93 93 347 SFV-18 53000 53000 53000 53000 '
SFV-19 8000 8000 430 FSV-262 124 124 124 124 FSV-261 94 94 i 316 MSV-114 20 20 20 20 320 MS7-132 562 562 562 562 318 MSV-128 1839 1839 1839 1839 314 MSV-146 5320 5320 5320 5320 427 MSV-130 2250 2250 831 831 428 MSV-148 1260 1260 694 694 1
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TYPE B TESTS'- 1986 As Found As Left (secm) (secm)
Equipment Hatch Resilient Seals 6.06 Fuel Transfer Tube Gasket - 3B 20 Fuel Transfer Tube Gasket - 3A 20 LRV-44 and Blind Flange 20 Chemical cleaning Pen. Gaskets 119 123 Chemical cleaning Pen. Gaskets 120 26.4 Personnel Access Hatches 19,890 r
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TYPE C TESTS - 1987 i
NOTE: All leak rate measurements are in seca.
As Found As Left Pen. No. Valve No. Valve Path Valve Path 329 DHV-93 20 20 20 DRV-91 546 546 11 439 CAV-126 20 20 CAV-1 275 275 CAV-2 2510 20 CAV-3 620 620 CAV-429 20 20 CAV-431 1028 20 CAV-430 61 61 CAV-432 557 4095 557 996 425 CAV-434 20 20 CAV-436 20 20 20 20 CAV-433 20 20 CAV-435 20 20 20 20 440 CAV-4 277 277 517 517 CAV-6 230 230 441 CAV-5 20 20 CAV-7 422 422 422 422 206 CIV-41 775 775 775 775 207 CIV-40 12 12 12 12 366 CIV-34 2 2 2 2 367 CIV-35 85 85 735 735 117 DWV-162 672 672 672 672 DWV-160 327 327 333 MUV-40 t MUV-41 MUV-49 344 377 MUV-260 MUV-261 MUV-259 MUV-258 MUV-253 150 150
As Found As Lef t Pen. No. Valve No. Valve Path Valve Path 339 WDV-3 2780 2780 2780 2780 WDV-4 1405 1405 349 WDV-60 54 54 WDV-61 59 59 59 59 354 WDV-405 3440 3440 3440 3440 WDV-406 3440 3440 374 WDV-94 77 77 WDV-62 80 80 80 80 315 WSV-3 20 20 WSV-4 20 20 20 20 332 WSV-5 20 20 20 20 WSV-6 20 20 356 WSV-1 20 20 WSV-2 20 20 20 20 WSV-34 20 20 WSV-35 20 20 20 20 WSV-30 20 20 WSV-31 20 20 20 20 WSV-38 20 20 WSV-39 20 20 20 20 306 WSV-32 20 20 WSV-33 20 20 20 20 WSV-28 20 20 WSV-29 20 20 20 20 WSV-26 20 20 !
WSV-27 20 20 20 20 l 376 WSV-41 20 20 l WSV-40 20 20 20 20 WSV-42 20 20 ;
2 WSV-43 20 20 20 20 l 113 AHV-1C 4800 860 AHV-1D 4800 4800 860 860 357 AHV-1A 20 1345 AHV-1B 20 20 1345 1345 121 LRV-50 176 176 LRV-36 322 322 322 322 LRV-90 117 117 117 117 LRV-89 102 102 1
As Found As Left Pen. No. Valve No. 3'alve Path Valve Path 122 LRV-88 30 30 LRV-87 99 99 99 99 125 LRV-94 750 750 LRV-93 750 750 750 750 LRV-92 40 40 40 40 LRV-91 33 33 116 LRV-45 76 20 LRV-46 243 243 243 243 305 LRV-70 2 2 2 LRV-72 2 2 2 306 LRV-73 1120 1120 1120 1120 LRV-71 1093 1093 202 B.F.
LRV-44 2 2 2 2 123 CFV-20 20 20 CFV-28 122 122 122 122 373 CFV-19 140 140 140 CFV-25 20 490 490 124 CFV-17 1152 1152 CFV-27 1248 1248 1248 1248 350 CFV-18 1175 1175 1175 1175 CFV-26 1095 1095 351 CFV-15 20 20 CFV-16 20 20 20 CFV-29 20 20 20 20 20 1
352 CFV-11 20 20 CFV-12 20 20 CFV-42 40 13500 13500 2 355 NGV-62 133 133 133 133 372 NGV-82 44 44 44 44 3 11 NGV-81 !
231 231 231 231 110 SAV-24 124 124 SAV-122 241 241 I
SAV-23 241 241 !
111 IAV-28 79 79 79 79 l
l m _ _ . _ _ _ - _ _ _ _ _ . , . . . _ . . _ , _ _ _ . _ _ _ _ _ - _ . _
-) .
As Found As Lett_
Pen. No. Valve No. Valve Enth Valve P_1th 112 IAV-29 125 125 125 125 347 SFV-38 45000 45000 1805 1805 SFV-19 15940 189 430 FSV-262 400 '400 400 400 FSV-261 61 61 ,
316 MSV-114 20 20 20 20 320 MSV-132 1201 1201 1201 1201 318 MSV-128 20 20 20 20 314 MSV-146 7210 7210 1472 1472 427 MSV-130 7560 7560 291' ~ 291 428 MSV-148 237 237 237 237 I
i
TYPE B TESTS - 1987 As Eburri As Inft (scan) (scan)
Equipnent Hatch Resilient Seals 13.2 2.2 Fuel Transfer
'Ibbe Gasket - 3B 2.0 2.0 Pbel Tramfer
'Ibbe Gasket - 3A 3.4 2.0 IRV-44 and Blind Flarge 2.0 2.0 Q =n W 1 Cleaning Pen. Gaskets 119 73.0 30 Chemical Cleaning Pen. Gaskets 120 29.0 64 Personnel Aomas Hatches 1319 1
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4 Appendix G wt= Ieint Analysis I
/M 4 J --
G-1 The Mass Point method of cceputing leakage rates uses the following ideal gas law equation to calculate the weight of air inside containment for each 15 minute interval:
W = 144 W = KP gp r 'R Where:
W = Mass of air inside containnent, Ibn K = 144 V/R = 5.39831 x 106 1ho *R - in.2 lbf P = Partial pressure of air, psia T = Average internal containment tenperature, 'R V = 2 x 106 ft3 R = 53.35 lbf - ft Ihn 'R The partial pressure of air, P, is calculated as follows:
P = Br - Pwy Khere:
By = Total containment pressure Pw y = Partial pressure of water vapor determined by averaging the five dewpoint tenperatures and converting to partial pressure of water vapor, psia
G-2 The average internal containment temperature, T, is calculated as follows:
T= 1 e Vfi i Ti Where:
Vfi = Volume fraction of the ith sensor Ti = Absolute betwrature of the ith sensor The weight of air is plotted versus time for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test and for the 7.75 hour8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> supalenental test. The IIRr computer code fits the locus of these points to a straight line using a linear least squares fit. The equation of the linear least squares fit line is of the form W = At+B, weight at time zero. The least squares parameters are calo11ated as follows:
A="( cti W)_( i cti) ( W)i Sxx B=( ct i2
) ( cW)_(
i ct i) ( cti W) i Sxx Whem:
Sxx = N (eti2 ) - (et i)2 N = Number of data points Wi = hsured mass of contalment air ti = Time ir.terval The weight pen:ent leakage per day can then be determined frm the followirg equation:
l g . -2400 A l where the negative sign is used since A is a negative slope to express the leakage rate as a positive quantity.
G-3 h ocenen standard deviation (S) is defined by:
S = ( ("i ~ "I ) V2 N-2 Where:
Wi = Nwed mass of air W = Isast squares calculated mass of air The IIRT ccmputer code calculates an upper 95% cxmfidence leakage rate as follows:
UCL = Ian + 2400 t95 (SgB)
This UCL value is then used to determine that the measured leakage rate at the upper 95% confidence limit meets the acceptance criteria.
The 95% confidence limit for the mass point leakage rate is calculated as folk a:
Cg = 2400 t95 (SgB)
Where:
CM = Upper 95% confidence limit t95 = Student's t distribution with N-2 degress of fr
- SA = Standard deviation of the slope of the least squares fit line B = Intercept of the least squares fit line The standard deviation of the slope of the least squares fit line (S A ) is calculated as follows:
" ("}
(N(cti2 ) - (Et i)2]V2 Where:
S = Ctmunon standard deviation of the weighted frcan the least squares fit line N = Number of data points ti = Time interval of the ith data point
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8.0 DISCUSSICN OF RESULTS 8.1 RESUIIIS AT PA 8.1.1 Mass Point Method of Analysis Data obtained during the leak rate test at Pa indicated the following changes (highest to lowest) during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test.
Variable Maxinnn Change Bp 0.351 psia Pwy 0.036 psia T 2.282'F
'Ihis method used in calculating the Mass Point leakage rate is described in Section 7.1.1. 'Ibe results of this calculation is a mass point leakage rate of 0.083%/ day (see Appendix D) .
'Ihe 95% confidence limit aawiated with this leakage rate is 0.003%
per day. 'Ihus, the leakage rate at the upper bound of the 95%
confidence level te---a:
UCL = .083 + .003 UCL = 0.086%/ day
'Ibe total containment leakage rate at the upper 95% confidence level (UCL) is calculated as follows:
UCL = Iem + 95% confidence limit + Type C leakage + changes in net 4 free volume + maintenance inprovement i
I UCL = 0.083%/ day + 0.003%/ day + 0.011%/ day + 0.000%/ day
+0.010%/ day )
UCL = 0.107%/ day
'Ihis value is well below the acceptance criteria leakage rate of 0.1875%/ day (.751g ).
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l c INTEGRATED LEAN RATE TEST RESULTS by GILBERT / COMMONWEALTH TNC.
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- MASS P O I N *T A N A L.Y S I S ***
, TIME OBS. WEIGHT OBS. MIN. CALO.
INTERYAL (LB) (LB) 0 634307 -28.0043656637863
.25 634334.4 4.875833079633039
.5 634332 8.006071823067032
. 75' 634266 -52.48870943351358 1 634301.3 -11.67099069007963 1.25 634301.4 -6.040771946660243 -
1.5 634280.9 -21.09805320324085 1.75 634288.8 -7.655334459806909 2 (v4253.5 -37.46261571638752 2.25 634255.6 -29.89489697295357 '
2.5 634297.4 17.42282177046582 2.75 634285.6 11.11554051388521 3 634246.4 -22.56674074268085 3.25 634236.2 -27.24902199926146 3.5 634256.6 -1.306303255827515 j 3.75 634237.5 -
14.92609451240812 i
4 634256.1 9.204134231011267 4.25 634206.1 -35.35314)w2555479 4.5 634244.7 8.777071717864601 4.75 634240.2 9.732290461298544 5 634180.6 -44.27499079528206 5.25 634216.1 -3.332272051862674 -
5.5 634271.3 57.42294669157127 '
5.75 634215.5 7.11566543499066 6 634181.9 -20.9416158215754 6.25 634182.8 -
14.56139707815601 6.5 634234.6 42.69382166526339 4 6.75 634241.6 55.19904040869733 7 634198.8 17.95425915211672 -
7.25 634194.4 19.08447789555066 l 7.5 634246.4 76.53969663897005 7.75 634217.2 52.84491538238944 l 8 634177.2 18.35013412582339 8.25 634183.1 29.79285286924278 8.5 634232.3 84.42307161267672 8.75 634158.4 16.05329035609611 9 634214.9 78.1210090995155 9.25 634157 25.68872784294945 9.5 634157.6 31.81894658636884 9.75 634088.7 -31.61333467019722
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-., , ,,m-- ,,-r..-- -
x y - . , - . . _ - ~ . , - _ . _ - - , _
10 634141.* 26.45438407322217 10.25 634132.9 23.64710281664156 10.5 634156.9 53.08982156007551 10.75 634093.5 -14.7799596965051 l 11 634076.9 -15.89974095307116 11.25- 634151.9 64.60547779054823 11.5 634059.5 -22.26430346623238 11.75 634042.5 -33.75909472279843 12 634044.9 -25.87886597937904 12.25 634067.3 2.0013527640549 12.5 634030.3 -29.43092849252571 -
12.75 634023.1 ~31.11320974910632 13 634052.8 4.079508994327625 13.25 634015.4 -27.79027226225298 13.5 634029.4 -8.285053518919041 13.75 633979.8 -52.46733477539963 14 634015.8 -10.96211603195026 -
14.25 634026.6 5.418102711453695 j 14.5 633990.2 -25.51417854512692
, 14.75 633976.4 -33.82145980169298 15 634006.6 1.93375894172641 ;
15.25 633964.6 -34.6235223148542 l 15.5 l 633950.6 -43.11830357142026 l 15.75 633957.2 -30.98808482800096 16 633968.3 -14.35786608456692 16.25 633954.7 -22.47764734114753 16.5 634002.2 30.52757140227186 16.75 633953.7 -12.4672098542942 17 633943.4 -17.27449111087481 17.25 633928.6 -26.51927236744096 17.5 633941.5 -8.139053624021472 17.75 633941.3 -2.88353488060209 :
, 18 633915.1 -23.50361613716814 '
18.25 633962.3 29.12660260625125 '
18.5 633934.4 6.819321349685197 18.75 633895.3 -26.86295990689541 19 633904.1 -12.54524116347602 19.25 633900.1 -10.97752242004208 19.5 633897.4 -8.222303676622687 19.75 633881.8 -10.27958493318874 I
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20 633897.4' 2.850633810230647 7 20.25- 633874.8. -14.26914744634996
.20.5 633902.1 18.54857129708398 '
20.75 633875.3 -2.758709959496628 21 633870.1 -2.503491216062685 21.25 633879.3 12.18922752735671 21.5 633865.9 4.381946270776098 l 21.75 633855.3 .8003349857899593 22 633855.3 4.704883757629432 22.25 633846.0 1.772602501063375 22.5 633837.9 -1.659678755517234 22.75 633851.6 17.59553998790216 ;
23 633831.3 2.7257587313361 23.25 633850.2 27.16847747475549 23.5 633819.3 1.798696218189434 23.75 633827.1 15.11641496160883 24 633845.3 38.74663370502822 WO = 634335.0043656633 LB W1 = -22.02087497370082 LB/HR 3 LEAKAGE RATE = 8.331575E-02 % PER DAY UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = 2.633739E-03 '% PER DAY UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = 8.594949E-02 % PER DAY (INCLUDES LEAKAGE RATE) t t
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1 INTEGRATED LEAK RATE TEST RESULTS
, by GILBERT / COMMONWEALTH INC.
CURRENT DATE s 11-15-1987 CURRENT TIME :-08:02 i TIME OF LAST READING : 800
- MASS POINT A N A L_ Y S I G ***
- TIME OBS. WEIGHT OBS. MIN. CALC.
0 633799.3 -15.37961647727954
.25 633802.9 4.8689172470622 !
.5 633771.1 -10.32004902959626
.75 6337S8.5 23.92849469574528 1' 633737.8 -10.44798157991313 1.25 633714.1 -17.44944785557163 1.5 633670.9, -44.07591413124464 1.75 633749.3 50.9851195930969 2.. 633671.1 -10.64134668256136 2.25 633643 -22.05031295822002 2.5 633660.8 12.35572076612152 2.75 633680.3 48.47925449046306 3 633607.1 -8.147211785195395 3.25 633613.5 14.91382193914615 3.5 633565.9 -16.08764433651231 3.75 633571.4 6.098389387829229 4 633532.6 -16.09057688784378 4.25 633557.4 25.34545683649776 4.5 633504.4 -11.0935094391607 4.75 633457.6 -11.28247571481916 5 633494.4 12.21605800952239 5.25 633502.6 37.02709173386393 5.5 63343?.4 -9.599374541794532
! 5.75 633435.1 2.77415918254701 6 633401.9 -13.78980709311145 6.25 l 633379.4 -19.72877336876'991 j 6.5 633401.6 19.08226035557163 i 6.75 633374.3 8.455794079898624 7 I 633340.1 -9.108172195759835 j 7.25 633332.3 .3596384714182932 j 7.5 633293.1 -22.86110474707675 7.75 l 633301.4 2.01242897726479 WO = 633814.6921164773 LB W1 = -66.4941348973607 LB/HR 1
LEAL' AGE RATE = .2517G54 % FER DAY UPPEP LIMIT OF THE 95% CONFIDENCE LEVEL = 1.062496E-02 % PER DAY UPPER LIhIT OF THE 95% CONFIDENCE LEVEL = .2624114 % PER DAY (INCLUDES LEAKAGE RATE)
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APPDiDIX H IKNENBER 9,1987 ABORTED IIRT ATID@r
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BAQGOGO On November 9,1987, during an attatpted Reactor CrJntainnent Integrated Irak Rate Test (IIRP) at Crystal River Unit 3, excessive leakage into the A Main Steam Lines was detected. It was decided to abort the test and make an entry into the Reactor Building to determine the source of the leakage. On Novenber 12, the entry was made and the upper hand hole cxwer on the "A" Ocxm Through Steam Generator (OISG) was found to be miapnaitioned and its sealing gasket was
- damagad. The cover was renoved, the gasket replaced and the cover was reinstalled. On Noveter 13, repressurization of the Reactor Building was begun and the IIRP was <nt,ramafully capleted on November 15.
ANAI2 SIS It is Florida Power Cbrporation's position that the aborted test of November 9 did not constitute a "failed" IIRP. Mispositioning of the hand hole cover can be attributed to outage maintenance activities that mmrred prior to the IIRT attempt. The hand hole cover had been removed early in the refueling outage to facilitate OrSG cleaning activities. It was miapnaitioned during OrSG restoration upon capletion of the cleaning activities. The miapnaitioned cover could not have gone unnoticed during prior or st%wnt plant operations because it would have resulted in an evident feedwater/ steam leak.
ChDSB Mispositicning of the hand hole cover was caused by a difference cm the clearances between the cover stud holes and the gasket seating fit.
Specifically, there is a .125 inch clearance between the studs and stud holes, while the cover gasket seating fit clearance is .020 to .030 inches. This difference in clearan s allowed the cxwer to be installed ani torqued up khile mispositioned.
CWRBCTIVE ACTICN Hand hole cover installation guides have been designed by Florida Power Cbrporation. Use of these guides during installaticn of the hand hole covers will reduce the stud to stud hole clearance and should eliminate problems with mi c: alignment.
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