ML20030A429
| ML20030A429 | |
| Person / Time | |
|---|---|
| Site: | Big Rock Point File:Consumers Energy icon.png |
| Issue date: | 04/29/1974 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML20030A428 | List: |
| References | |
| NUDOCS 8101090498 | |
| Download: ML20030A429 (20) | |
Text
{{#Wiki_filter:d SPECIAL REPORT NO 17 Reactor Containment Building Integrated Leak Rate Test April 24-29, 1974 Introduction In fulfillment of the requirements of the Big Rock Point Plant Technical Specifications, Section 3 7, the biannual Containment Integrated Leak Rate Test was conducted on April 24-29, 1974. This was the seventh reduced pressure test of the series dating from June 1962. A summary of the past test results is provided in Table I of this report. On February 1k, 1973, Appendix J to 10 CFR 50 entitled " Reactor Containment Leakage Testing for Water-Cooled Power Reactors" was published in the Federal Register. Every effort has been made to conduct the test in compliance with the requirements of this document and of ANSI Standard Uk5.k-1972 entitled " Leak Rate Testing of Containment Structures for Nuclear Power Reactors," dated March 16, 1972. All points of exception l are noted in this report. The following are also included in this report: a. A description of the test procedure including data-taking and calculational methods. b. Discussion of the test results. c. Results of the component leak rate test conducted from October 1972 to April 1974. d. Instrumentation error analysis. e. Analysis of the total allowed leakage rate. f. Plots of raw data taken throughout the test. Test Procedure The 197h Big Rock Point Plant Containment Leak Rate Test employed the Reference Vescel Method as described in ANSI Nk5.4-1972. The reference vessel system is the same as has been used for previous tests and consists of eight interconnected chambers, each proportional to the volume of air space in which it is located. For a schematic diagram of the reference system and test instruments, see Figures 1, 2 and 3 j One change from previous tests is the relocation of the large chamber formerly located east of the steam drum enclosure access door and identified as the " Personnel Lock Reference Chamber." It has been '. '.3 U h V.L&LO96h
2 relocated to a pocition just above the top of the blowout panel near the center of the north wall of the steam drum enclosure and has been relabeled the " Blowout Panel Reference Chamber." The change is documented in the plant records as Facility Change C-2h6. Upon review of the data from this test, it is recommended that this change be permanent. The reference vessel system was initially pressurized with dry air from_the plant instrument air system to N 13 psig. The vapor pressure of the reference system was measured to be 0.0663" Hg. Measurements taken before and after the containment leak rate test show essentially zero reference system leakage. The containment building was initially pressurized with air to a differential of approximately 8" H O above the reference system. Thus, 2 any reference system leakage would result in a conservative containment leak rate indication. The containment was pressurized in 12 hours with two 600 cfm diesel compressors, each equipped with an aftercooler. Two high volume filters were incorporated for oil vapor separation. Temper-atures recorded downstream of the compressors were as follows: Cooling Water Into Aftercoolera 37 F Cooling Water Out of Aftercoolers 72 F Air Into Aftercoolers 175 F Air Out of Aftercoolers 75 F Following a h-hour stabilization period, data was taken every hour. Later, in order to improve statistics, the frequency of data taking was increased to every half hour. The data taken throughout the leak rate test included measurements of containment temperature, containment vapor pressure, barometric pressure, containment pressure, reference system pressure and differential pressure. The,various measurements are displayed in Figures 4, 5 and 6. See Appendix A for a description of the instrumen-tation employed for data gathering. The four thermocouples and four dew-cell elements for measuring temperature and vapor pressure were located in the vicinity of the four major reference chambers. The readings from each were weighted according to the relative volumes of the chambers to determine the average containment temperature and vapor pressure. The recirculating fan units in the containment building were on throughout the test to provide mixing of air. Doors and hatches inside the building were opened to insure pressure equalization and circulation of air. The heating and cooling units remained out of service as in the 1972 leak rate test. Aluminum covers were installed over the spent fuel pool to keep evaporation to a minimum. I The calculation of percent leakage was performed by two methods for each set of data according to the formula: P -P (P -P $ Leakage = p,p P -P (P -P2) y y 2 y y y y 2 1{ .j
. _.-. ~. t 3 . where (P - P ) = The differential pressure between the containment and i reference. system, inches of Hg. P = Pressure of containment building, inches of Hga. 4 P = Vapor pressure of the containment building air, y j inches of Hga. P = Vapor pressure of the reference system air, inches t of Hga. } T = Containment temperature, F. { 1 = Start of test period. 2 = End of test period. l The value of percent leakage was corrected to obtain percent per day leakage rate by the factor: 4 i 2h Total # of Hours Between 1 and 2 The actual measured leakage rate was determined from a linear least squares fit to the leakage rate data. 1 Method 1: Point to Point Method The percent leakage is determined for each hou throughout the The factor to convert to leakage rate (%/ day) is.5h-The linear test. l _ least squares fit in the arithmetic average of the indivibu. ally calculated hourly leakage rates. - Method 2: Total Time Method The total percent leakage is calculated at each data point based on the data at the start of the test. - The factor to convert to leakage 2h ! "I " Total # of Hours From Start of Test
- 1 Following the hold test, a controlled leak off was superimposed
) upon the as-found leakage in an effort to verify the results of the hold. j test. Calculations were identical to those performed during the hold test. The as-found leakage is then: "b-bc 4 where: La = As-found leakage. 4 4 = Total measured leakage. T LC " Superimposed controlled leakage. (1)L. Wang Lau,' " Data Analysis During Containment Leak Rate Test," Power i Engineering. February 1974. i t ~. 7-.-9-ny v c- - + -, - y =-- .-,---.,.e- .,,y y ---w ,s,,-
l y i Discussion of Test Results The 1974 Containment Leak Rate Test was performed in three parts. The initial hold test was conducted for 36 hours during which a leak was discovered that exceeded the Technical Specifications allowed leakage rate. Following measurement and repair of this leak, a second hold test was per-formed for a period of 29 hours. Upon the successful completion of this test, a controlled leakage was superimposed. This phase was successfully completed after an additional 2h hours whereupon the containment building was depressurized. Atmospheric conditions were nonstable throughout the test. The wind speed varied from calm to 15 mph. Temperature ranged from 32 F to j 75*F and cycled diurnally. d j Initial Hold Test i I The first hold test was conducted over a period of 36 hours. j Results are as follows: Measured Technical Specifications 4 Method Leakage Rate Allowed Leakar,= Rate Point to Point (avg least squares fit to 13 concurrent 24-hour periods). 0.309 %/ Day 0.175 %/ Day Point to Point (least squares l fit to calculations for data taken 2h hours apart). 0.307 5/ Day 0.175 %/ Day Upon invesitgation for the sou?rce of the high measured leakage rate, it was discovered that the 2h-inch butterfly valve on the supply ventilation line into the containment building was leaking at the contain-ment side flange. This valve had been installed during the shutdown prior to conducting the leak rate test. An estimate of the leakage rate was made by collimating the airflow through a one-inch diameter (ID) pipe and measuring the velocity profile across the pipe. The leakage rate through the flange was estimated to be 0.292 %/ day. (See Appendix D for analysis.) Hence, essentially all of the leakage measured during the first hold test was through the supply vent butterfly valve containment side flange. Bolts were tightened around the flange and the leakage stopped. { The* containment pressure was increased to approximately 8 inches of H O 2 , above the reference system and conditions were allowed to stabilize for four hours prior to initiation of the second hold test. o Second Hold Test The second hold test was conducted for 29 hours after completion of the stabilization period. Data was taken every half hour throughout i this test. Results of the data analysis follow: 4 -_m m.
i 5 Rev 9/23/7h i Measured Technical Specifications Method Leakage Rate Allowed Leakage Rate Point to Point (avg of 10 24-hour periods). 0.037 %/ Day 0.175 %/ Day Total Time (least squares fit to 36 hours - 58 data sets). 0.075 %/ Day 0.175 %/ Day The data from the Total Time Method was subject to the instru-mentation error analysis outlined in Appendix B. To the 95% confidence limit, this analysis yielded an instrumentation error of 0.0h7%/ day. Hence, to the 95% confidence limit, the maximum measured leakage rate is 0.123%/ day, less than 0.131%/ day, the Acceptance Criteiia specified in 10 CFR 50 Appendix J of 75% of the Technical Specifications allowed leakage rate. Supplemental Test At the end of the second hold test, a controlled leakage of 3 1.15 ft / min (approximately equal to the Technical Specifications allowed leakage rate) was superimposed for 2h hours on the as-found leakage. The leakage was measured by an integrated gas meter calibrated to 10.2%. Since the test lasted for only 2h hours, an analytical technique was used that was appropriate for the absolute method (fit least square line to total leakage and determined slope of line to determine leakage rate, refer to Figure 9). i The results of data analysis follow (see Appendix E): Measured Leakage Rate Through Method Leakage Rate Gas Meter Total Leakage (least squares fit to 2h hours 48 data sets). 0.197 %/ Day 0.177 %/ Day The difference between the measured leakage rate of 0.197%/ day and the results of the point-to-point leakage rate of 0.037%/ day for the hold test is 0.16%/ day. Since the 0.16%/ day lakage rate is within 9% of the allowed leakage rate, the Acceptance Criteria of 25% in 10 CFR 50 Appendix J has been met. i Variance From Specifications of 10 CFR 50 Appendix J Listed below are three specifications in the Federal code with which the 197h Big Rock Po %t Containment Leak Rate Test did not comply due to plant design and construction occurring approximately 12 years prior to the develo1 ment of 10 CFR 50 Appendix J. 1. Paragraph 11.G.1. " Type B Tests" ( Local leak tests of components at Big Rock Point do not include testing of the electrical penetrations. The design of the electrical t
4 ? l 6 Rev 9/23/Th l l penetrations is such that component testing is impossible. The present containment testing schedule is five times in a 10-year period versus three times in a 10-year period required by 10 CFR 50 Appendix J. Any L plan to replace the electrical penetrations to permit component testing is uneconomical when the unit downtime for penetration replacement is compared to the downtime associated with six additional containment leak rate tests over the next 30 years. 2. Paragraph III.A.d. " Systems Vented During the Containment Leak Rate Test" i The clean-up system resin sluice isolation valves were not vented to containment pressure during the 197h Containment Leak Rate Test. Such action would entail removing the clean-up system fran service and draining the demin tank. Since the component leak test of these valves at 20 psig has always been successful and since the valves are open only a few hours each year under hot primary conditions, it is not deemed essential that III.A.d. be complied with in this ce.se. 3. Paragraph III.D.2. " Type B' Retest Schedule" The containment air locks at Big Rock Point are leak tested every six months rather than after every opening. The containment building is designed to permit personnel access during power operation. The person-nel lock is operated many times each day and the equipment lock is often in service several times each week or more. The requirement of leak test-ing these after each opening is totally impractical. Conclusl3n The results of the 197h Contain' ent Leak Rate Test depended m greatly on atmospheric conditions. The same has been true for all past tests and should be expected throughout the life of the plant. However, the relocation of one reference chamber has had a positive effect as the data now more closely represents the conditions of the overall contain-ment. The atmospheric variations are clearly displayed by the point-to-point calculational method which shows wide scatter of data from hour to hour (see Figure 7). Although the reference vessel method analysis was successful for the hold test, a least square fit analysis of calculated leak rates was inadequate for the controlled leak-off test (Figure 8). Results of the " Total Leakage" calculation method (Figure 9), on the other hand, show much less scatter and for this reason are reporte3 as the measured leakage rate. -9 _m-. .-y
Appendix A Equipment _and Instrementati m EquiIment Air Ccapressors (2) teroi Ocupany Aftercoolers (2) Righ Volume Filtere (2) (See Figure 2) Instrumentation _Barom-ter: Measures strospheric pressure Meriam Instrtment Company Type W Model - 31EG10 Measurement accuracy smallest scale division - 0.01" Hg Mercury Coltan: Msaeures containment building precourc Herism Instrument Company Type W !!odel - 30EB25 Measurczent accurney smallest scale divisics - 0.1" Hg _Irelined Mercury itsnetnster: Measures reference system pressura Merina Instrunent Conpany Type W Model - 30EB23 Measurment accuracy rnallest scale division - 0.0h" Hg Differential Macometer: Meriam Instrument Company Ir.clir.e Water Mancaster Type W Model - 40HE35 Measuraront accuracy smallest scale divisics - 0.00073" H6 _Tramocouples: Chrmel-Alumel 0 Read by General Electric 312 Computer Ro. 1h Wire Weightsd average accuracy of four used to measure contair.acat temperature - 0.23 F 3por Preseure Msasurements: The foxboro Campany Electronic Type Deveell Element read by General Electrie 312 Computer Weighted average accuracy of four used to measure containment vapor p essure - 0.C08" Hg Gas Meter: American #1694923 Capacity: 1T5 ft3/hr - Temperature ecupensated Accuracy - 0.2% P00R ORIGINAL. A-ot-Air Meter for Velocity Profile Measurement Model 60
Appendix B Ina,trument Error Analysis Analysis of error introduced by instruments used during the Containment Leak Rate Test was accomplished using the standard propagation of error relation: 2 ' D m' I 2 SQRT da db e = . 'baj bb a 6 i i s i s f where e, is the error in function n (Las to instrumentation limitations m is a function of a, b,... m = f(a,b,...) a,b,... are measured quantities Oa,6b,... are the error limits of the quantities a, b, etc. Error A.salysis of the Leak Rate Equation For the Reference Vessel Method, Ti .pf_(p _ pf) a 100 -Pyj- (P -Pr) p 2 2 y v (P -P ) V2 y y for ey incremental timo period. From the propagettion of error forr:la, for any iceremental time, 3 7 i,, +2}A(P-Pr{2 [P,-Pr_(p_pr)2 1U om=1 Scat 72 y p,, _p Y- (P - P ) (AP) Y + 2 mpy )2 + 2 1# 7y - Py y l Pb + P, - P d y Y . (gp)2,(Ap)2[. Py-PY - (P - P ) y +2 Pb+P -P a y
- Where, Ve.lue Symbol _
Doncription T Sphere Turrperr.tv.re (Avg) 521.1 R OT Sphere Temperature Error Limit i 0.231 R Barce.etric Pressure (Avg) 29.bh" Eg Pb Paranetric Pressure Error Linit 0.01" Us APb P, Sphere Prescuz1r (Avg) 27.0b" Hg 6 P, Sphere Pressure Error Limit i 0.04001" Hg Py Sphere Vapor Pressure (Avg) 0 3438" I's 6P Sphere Vapor Pressure Error Limit 0.0061" lig y ~ Pl10R ORIGINAL
bprendit B (Contd) 10. Symbol Description Ve.lue Pr Reference System Vapor Pressure (constant) 0.0663" Hg y 6P Beference System Vapor Pressure Error Limit t 0.0061" Iit; y (P - Pr) Differential Pressure (Avg) 0 52h3" IL; 6 (P - Pr) Differential Pressure Error Limit t 0.0007367" H6 P Pb + P. 56.48" F4 Therefore, 1 0.0289 for any incremental time. 6 LR = For the 29-br hold test, 24 1 0.0239 $/ day (.0289 x /29). 6 LR = For 95% confidence limit. 1 0.OkT $/ day (.0239 x 196). 6 LR = e / POOR ORIGINAI
Appendix C Pemissible Lenk Rate Calculation _of Extrapolated leak Rate @ 26.52" Hg (~13poigl Average Reference System Pressure and _0 _61.h0F, Average Containment Temperature From the Big Rock Point Plant Technical Specifications, Section 3.7(c), Pt - l' pa Lt = k .Pe - 1, pt
- where,
% Leakage rate at air test pressure Lt = % Icakage rate at extrapolsted pressure Le = Extrapolated pressure, atmospheres, absolute Pe = Test pressure, atmospheres, absolute Pt = Viscosity of air-steam mixture at temperature and pressure of DBA pa = Viscosity of air at test teoperature and precsure Ut = 9.44" Hg-1 901 ATM (abs) '5" Pt = = 3 7 0 psig + 14.7 psig 2.837 (abe) Pe = = 14.7 psig 0 5 %/dey In = 171.6 micropoise pa = 181.6 micropoise pt u (1.901)2,7" f171.6 (0 5) Lt = (2.837)z - 1 181.6 3 0.175 %/ day (Technical Specificaticus allowed) Lg = (0.75) (0.175) (0 75)(Lt) = 0.131 %/ day (10CFR50 Appendix J) = P00R ORIGINAL
Appendix D Imahage Rate Through Bupply Vent Valve Flange 1 inch Inside diameter of collinator pipe = Area of Collimator 0.00545 ft = 390 ft/ min Velocity profile measurement = 2 = 2.13 ft / min (leakage rate) 3 390 x.00542 ft g Assume instrumentation efficiency = 90%, 2) 3 Leakage Rate = 1 91 ft / min 3 = 2760 ft / day 3 Volumo of contnisment = 940,000 ft =) Leakage rate through vent = 0.293%,* day valve flange 1 (2) Velocity var measured at centerline of collizator pipe. 'Ib obtain avera6e linear velocity, miltiply velocity measured at center by 0.90. P00R ORIGINAL
(- Rev.9/23/Th (- -Appendix E - Determination of Superimposed' Leakage Rate 0.175 5/ day Technical Cpecifications allowed leakage rate @ test = pressure (from Appendix E). 3 9ho,000 ft Free volume of containment building. = 3 940,000 x 0.00175 1645 ft / day = 3 1.1h2 ft / min. = 3 3 f -Superimposed leakage rate was initially set at 1.15h ft / min (1 ft leakage in 52 seconds). 4 h 9 e 1 i J .I ( i
k Rev 9/23/74 4 Appendix F Analysis of Leakage Rate: Corrected for Supply Vent Valve Repair Leak rate through. vent valve (before repair) = 187 lb/ day. - Leak' rate through vent. valve (after repair).= 11 lb/ day. Difference - 176 lb/ day . = 0.107 %/ day (@ 20 psig). Leakage rate measured from containment leak rate' test = 0.037 %/ day (@ 13 psig). Both values must be extrapolated to design pressure of 27 psig. IPe - II g g, t 2,y pa p t L b For differential before and after vent valve repair: 2 27 + 14.7 ) 181.6' 14.7 Le = (.107)' ) 171.6; 2 1 20 + 1h.7 -1 4 14.7 i Le = 0.175 %/ day (@ design pressure of 27 psig). For containment leak rate test: 27 + 1h.7 17 i 1 1.6' Le - (.037)I '26.52 + 29.hh i2 171.6; g i 29.44 Le - 0.106 %/ day (@ design pressure'of 27 psig). 4 i SUM = 0.281 %/ day. d 4 1 .m --y ~
i 1 Appendix G Component Leak Rate Test - October 1972 to April 197h Table II lists the results of the Component Leak Rate Tests conducted since the April 1972 Containment Leak Rate Test. The tests were conducted at 6-month intervals in accordance with the requirements of the Technical Specifica-tions, Section 3.T. The maximum leakage rate allowed by the Technical Specifica-tions (410 lbs/ day @ 20 psig test pressure) was met by each test, although the Acceptance Criteria of 10 CFR 50 Appendix J (60% of the Technical Specifica-tions allowed leakage rate) was not met by the April 1973 test. It should be noted that the major contributor to the total component leakage is the supply ventilation valves. The supply (and exhaust) vent lines are built with two valves external to the containment building in series to pro-vide double isolation. A butterfly valve is closest to the containment structure with a swing valve farther away. The component test is conducted by pressurizing between the butterfly valve and swing valve. During the 1972 Containment Leak Rate Test, it was discovered that the supply vent butterfly valve leaked through; thus, the swing valve was pressurizing the piping between the valves to the containment test pressure. For this reason, a new butterfly valve was purchased following the 1972 Containment Leak Rate Test. The new valve arrived at the plant site following the April 1973 refueling outege. Since both the April 1973 and October 1973 Component Leak Rate Tests met the Technical Specifications Acceptance Criteria, the valve replacement was delayed until the March 1974 refueling outage. Prior'to the valve replacement in April 1974, an as-found component leak rate test was performed on the supply vent valves with a resulting leakage rate from the supply vent valves of 187 lbs/ day @ 20 psig test pressure. Following replacement of the butterfly valve and prior to conducting the containment leak rate test, a second component leak rate test of the supply vent valves yielded a leak rate of 11 lbs/ day at 20 psig test pressure. The difference in leakage rates before and after the replacement of the valve - 176 lbs/ day - was added to the measured containment leakage rate (see Appendix F for analysis). The total as-found measured leakage rate, extrapolated to design pressure of 27 psig is then 0.389 0.047 %/ day, within the Technical Specifications limits of 0.5%/ day (at design pressure) but greater than the 10 CFR 50 Appendix J Acceptance Criteria of 0.375%/ day. m
Rev 9/23/7h As reported in the previous section, a leak was discovered at the . ( flange of the new butterfly vent valve which exceeded the Technical Specifications allowed leakage rate. It was Lapossible to detect this leak through local leak testing because the local leak test method is to pressurize between the swing-and butterfly valve and the leaking flange was on the sphere side of the butter-fly valve seat. However, because the new valve was installed only a few days prior to conducting the leak rate test and no other maintenance had been per-formed on the supply vent valves since the 1972 Containment Leak Rate Test, it is reasonable to assume that the leak was not present prior to the valve replace-ment. An investigation is presently under way to improve the component leak test method to detect similar leaks in the future. Data taken during the Containment Leak Rate Test revealed that the but-terfly valve on the containment exhaust vent line was leaking through so that the swing valve was supporting the test pressure. However, the component tests show that the leakage has not progressed to the severity of that on the supply vent line prior to installation of the new butterfly valve. Present plans call for rebuilding of the butterfly valve removed from the supply line and it is recom-mended that this valve be installed in the exhaust vent line prior to the 1976 Containment Leak Rate Test. The eleven containment isolation valves (main steam, main steam drain, reactor and fuel pit drain (2), clean-up resin sluice (3), clean sump (2) and dirty sump (2)) have been tested with water during each re?aeling outage at a minimum pressure of 20 psig. The Technical Specifications limiting leakage through each of these valves to drops /second has' been met at each test. \\ ( G-2 d
t Rev 9/23/74 Table I Stammary of leak Rate Tests - Big Rock Point Plc.nt Containment Test Date Pressure Measured Leak Rate Allowed Lead Rate 1/61(" 27 psig 0.036 %/ day 0 5 %/ day 6/62 10 psig 0.021 %/ day 0.121 %/dcy h/6k 10 paig 0.037 1 0.034 0.321 %/ day h/66 10 psig 0.077 A 0.025%/ day 0.121 5/ day 7/68 10 psig 0.061 0.0175/ day 0.121 %/ day 3/70 10 peig 0.084 1 0.030%/ day 0.121 %/ day h/72 12 psig 0.028 1 0.Or25/ day 0.149 %/ day h/74 13 peig 0.037 + 0.086%/ day (cH d) 0.131 %/dey " Included pneumatic overload test at 33 75 psig. (b)In accordance with 10CFR50 Appendix J, thic nu:nber equals 75% of the T2chnical Specifications allowed leak rate extrapolated to the test pressure.
- Leak rate measured after repairs.
(d)One-sided 95% confidence interval estimate - upper limit is equal to average leakage rate plus 1.56 (standard deviation). P00R ORIGINAL
i Tablo II Summary of Component Leak Rate Tests - Big Rock Point Plant Containmen_t Test Date Component Pressure Measured Imeh Rate Allowe5 Lc 2 RcM l 10/72 Escape Iock 5 psig 17 7 lbs/24 hrs *I Personnel Lock 20 psig 5.0 lbs/24 bra Equipment Lock 20 psig 26.k Ibs/24 hrs Sapply Vent Valve 20 psig 101.5/77.8 lbs/24 hrs Exhaust Vent Valve 20 paig 15.2 lbs/24 hre TOTAL 165 7/1k2.1 lbs/24 hre 2k6 lbs/24 hre h/73 Escape Lock 5 psig 9.9 lbs/24 hrs
- Personnel Lock 20 peig 8.5 lbs/24 hrs Equipment Iock 20 psig 32 9 lbs/24 hrs Supply Vent Valve 20 psic 225.0 lbs/24 hre Erhanet Vent Valve 20 psig 15 5 lbs/24 hrs sd)
TOTAL 291.8 lbs/2h hra 2h6 lbs12h Fra 10/73 Escape Inck 5 psig ~ 0 lbc//4 brs("} Personnel Lock 20 psig 4.8 lbo/2h hrs Eq,:1pnent Lock 20 psig 27.T lba/24 hrs Supply Vent Valve 20 psig 131.7 2ba/2h tra E;:haust Vent Valve 20 psig 21.1 its/24 tre } TOTAL 185 3 lbs/2h hrs 246 lbs/24 Prs h/74 Escape Loch 5 psis- ~ 0 lbc/2h hrs ("} Personnel Iock 20 psig 4.8 lbs/24 b n Equipment Lock 20 paig 18.8 lbs/24 hra Supply Vent Valve 20 poig 187.1/11.3 lbs/2h hrs Exhenst Vent Valve 20 peff,, 29 1 lbs/2h hrs I 239.8/64.0 lbs/24 hrs *) 246 lbs/24 hrs (0) '!OTAL Calculation extrapolated to 20 peig. Naasured leak rate following valve packing adjustment. Measured leak rate following installation of nott butterfly valve. In accordance with 10CFR50 Appendix J, this number equals 60% of the Technseal. Specifications eJ. loved leak rate. P00R ORIGINAL
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