ML20151Y724

Reactor Containment Integrated Leak Rate Test,Final Rept

ML20151Y724
Person / Time
Site:	Waterford
Issue date:	05/31/1988
From:	WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML20151Y704	List: ML20151Y724 W3P88-1283, Forwards Waterford Steam Electric Station Unit 3,Reactor Containment Integrated Leak Rate Test,Final Rept, in Accordance W/Requirements of 10CFR50,App J
References
NUDOCS 8808290013
Download: ML20151Y724 (62)

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3 Waterford 3 ILRT Report I

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E WATERFORD STEAM ELECTRIC STATION UNIT 3 I REACTOR CONTAINMENT INTEGP.ATED LEAK RATE TEST FINAL REPORT I

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i Prepared By:

Westinghouse Electric Corporation May, 1988 I

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W3 SES Reactor Containment ILRT Final Report l l

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l TABLE OF CONTENTS E l I

SECTION TITLE PAGE I 1.0 Sumary and Description of Containment Pages 1 and 2 l 2.0 2.1 Procedure and Methodology Containment Preparation Pages 3-6 Page 3 and 4 2.2 Pressurization Page 4 2.3 Test Measurements, Instrumentation and Pages 4 and 5 Air Mass Calculation 2.4 Leakage Rate Calculations Page 6 3.0 Chronology and Events Page 7 3.1 Chronology Fage 7 3.2 Events Page 7 4.0 Test Results Pages 8 - 12 4.1 Total Time Leakage Rate Pages 8 and 9 4.2 Mass Point Leakage Rate Page 10 4.3 Results Analysis Pages 10 - 12 l 4.4 5.0 Shield Building Examination References Page Page 12 13 6.0 Tables and Figures Pages 14 - 36 Appendix Local Leakage Rate Test Results Pages 37 - 59 I

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I W3 SES Reactor Containment ILRT Final Report Page 1 I 1.0

SUMMARY

AND DESCRIPTION OF C0FAINMENT

SUMMARY

The first periodic integrated leakage rate test (ILRT) on the Waterford SES Unit 3 containment was successfully compi>ted on May 23, 1988. All acceptance criteria s ecified in the test procedure (Ref. 1) were satisfied. Test results an acceptance criteria are listed below.

Parameter Result Acceptancelimit(s) 95% upper confidence limit (UCL) on total time leakage rate (including additions) 0.116 wt%/ day <0.375wt%/ day Total time leakage rate trend extrapolated to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> <0.051 <0.375 Mean of the measured leakage rates over the final 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> <0.16 <0.500 Verification leakage rate 0.534 0.440-0.690 As found 95% UCL (test result plus minimum pathway improvements) 0.123 <0.375 Containment pressurization started at about 2:10 a.m. on May 22, 1988 and was stop)ed at about 1:50 p.m. on the same day when containment pressure had i reacied 46 psig. Containment atmosphere mean temperature met the stability criteriawithinthefour(4)hourmandatorystabilizationoeriodandthe start of the eight (8) hour (minimum) test period was dec1tred at 6:00 p.m.

B The test was ended at 2:15 a.m. on May 23 and the verification leakage was imposed. The verification test was started at 3:45 a.m., following a mandatory one hour stabilization period, and ended at 8:00 a.m. Containment I pressure stayed between 46 and 44 psig throughout the stabilization, test and verification phases.

TheILRTwasconductedinaccordancewithacontrolledprocedure(Ref.1)

I which incorporated the requirements of the FSAR (Ref. 2), the Technical Specifications (Ref. 3), Appendix J to 10CFR50 (Ref. 4) and BN-TOP-1 (Ref, 5). ANSI /ANS 56.8 (Ref. 6) was used for informational guidance on certain I aspects of the test. Valves on piping systems penetrating contaminant sere aligned as specified in Ref. 2, with the exception of those on the shutdown cooling and fire protection lines. Fire protection was left in service to satisfy Ref. 3 requirements and a penalty was taken on minimum pathway I leakages through the penetrations.

A structural examination of the exterior and interior surfaces of the E containment vessel was performed in conjunction with the ILRT as required by IF Ref. 3.

i W3 SES Reactor Containment ILRT Final Report Page 2 Sumary (cont)

I No evidence of degradation was found. However, the examination did reveal six I-Beam construction supports in the annulus that extended radially from the shield building to the containment vessel with no clearance between the beams and the vessel. An engineering evaluation was performed which concluded that the structural integrity of the containment vessel was not impaired by the presence of the construction supports (Ref. 8). The beams were removed prior to performance of the ILRT.

I DESCRIPTION OF CONTAINNENT The containment vessel cornpletely encloses the entire reactor and reactor coolant system to ensure no leakage of radioactive materials to the environment in the uniikely event of a loss of coolant accident.

The containment system incorporates a freestanding containment vessel surrounced by a low leakage reinforced concrete shield building. A four foot l annular air space is provided between the outer wall of the containment vessel l and the inner wall of the shield building to allow filtration of any containment vessel leakage during accident conditions to minimize off-site I doses.

The freestanding containment vessel is a two inch thick circular cylinder, I with a one inch thick hemispherical dome and two inch thick ellipsoidal bottom. The overall vessel dimensions are: 140 foot diameter by 240.5 foot high. The vessel wall thickness is increased to a minimum of four inches adjacent to all penetrations and openings. The vessel is fabricated of I ASME-SA 516 Grade 70 fully killed pressure vessel quality steel plate. The net free volume of the containment vessel is 2.677 x 10 to the sixth cubic feet.

The containment vessel structure includes one personnel airlock, one emergency escape airlock, one fuel transfer tube one equipment maintenance hatch, and one seal-welded construction hatch. Allprocesspipingandelectrical I penetrations are welded directly to the containment vessel nozzles, with the exception of the main steam, main feedwater, and fuel transfer tube penetrations. These penetrations are provided with testable expansion bellows to allow for thermal growth or building differential motion.

The containment vessel is designed and constructed in accordance with the requirements for class MC vessels contained in Section III, Subsection NE of the ASME Code, 1971 Edition including Summer 1971 Addenda and Code cases 1431, t

i 1454-1 and 1517, as approved by USNRC Regulatory Guides 1.84 and 1.85. The containment vessel is code stamped in accordance with Paragraph NE-8000 of 3 Section III of the ASME Boiler and Pressure Vessel Code. The containment g vessel and all )enetrations are designed to limit leakage to less than 0.5 per:ent by weigit of the contained air mass per day at the design pressure of 44 psig. The calculated peak accident pressure for the desi n basis accident at Waterford SES Unit No. 3 is 44 psig at 263 degrees Fahren eit.

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W3 SES Reactor Containment ILRT Final Report Page 3 2.0 PRkCEDURE AND NETH000 LOGY The leakage rate test was conducted by aligning containment systems in

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specified post-accident configurations pressurizing the containment to the design basis accident pressure of 44 ( 3, -0) ps g, measuring containment atmospheric conditions, and calculating the out eakage of air using the atmospheric condition data. These activities are described in detail in the following paragraphs.

2.1 Containment PreDaration Systems penetrating containment were aligned in the specified post-accident configurations except that systems required to maintain the plant in a safe condition were aligned as required to perform the safety functions. Systems postulated to rupture as a result of the accidentwereventedinsideandoutsideofcontainment(withthe exceptionsnotedabove), Isolation valves were closed. The reactor coolant system was vented to containment atmosphere through the pressurizer. The safety injection tanks were vented to ensure that slow

( in or out leakage would not occur. The reactor drain tank and L pressurizer relief tanks were vented for the same reason as well as to provide protection against external pressure. Sources of compressed gasseswithinthecontainment(fireextinguishers, accumulators,etc.)

were removed, vented or fitted with pressure gages to determine gas loss. A complete listing of valve lineups, temporary gage installations, and items removed from containment is included in Ref. 1. ,

ItemsunabletowithstandILRT$ressurewereremovedfromthe containment. These are identif ed in Ref. 1. The breakers feeding many quipment items were racked (or locked) out to protect the F conta nment against major water injections as well as to prevent events I which could invalidate leakage rate test results. A complete listing of breaker lineups is contained in Ref. 1. Prior to pressurization, the inside and outside surfaces of the containment were examined for i evidence of structural deterioration which might limit pressure retaining capacity.

All fans and containment lighting were shut off prior to pressurization. This was done to eliminate point sources of heat which could affect the response of the temperature measuring instruments.

Instrumentation was installed prior to containment closure.

A containment temperature / humidity survey was done prior to final instrument placement to verify that significant temperature gradients exist only in the vertical direction and that water vapor is uniformly dispersed throughout the containment atmasphere. RTO and RHD locations were specified on the basis of these assumed conditions. Wet and dry bulb temperatures were measured at several azimuths on the -4, 21, 46, and 95 foot levels, at both ends and the middle of the polar crane girder catwalk, and at various elevations on the stairs and ramp leading from elevation 46 to elevation 200. l l

I W3 SES Reactor Containment ILRT Final Report Page 4 il 2.1 ContainmentPreparation(cont)

Dry bulb temperature was found to vary significantly only with elevation as assumed. Water vapor pressure as determined from wet and drybulb

. temperatures was found to be essentially constant throughout the I containment which confirmed the assumption of a uniform dispersion of water vapor. Survey numerical results are included in the official test copy of Ref. 1.

rior to the Local start of(ty!eBandC)leaka!eratetestswerecomleted he integrated le kage rate test. Resu ts of 11 local tests performed since the preoperational ILRT are included in the Appendix.

I 2.2 Pressurization The containment was )ressurized at a rate of about 4 psi / hour using oil free compressors wit 1 an aggregate capacity of 13,800 SCFM. The discharge air was passed through two trains of aftercooler/ moisture E separator units and refrigerated air dryers. Plant chilled water was E used for cooling. Pressurizing air was dried to minimize the probability of moisture condensation in containment during the ILRT.

Pressurization was stopped at 46 psig. This allowed an adequate margin (2 psi) for pressure decay due to cooling of the air which had been heated well above the equilibrium temperature during pressurization.

2.3 Test Measurements. Instrumentation and Air Mass Calculation The containment atmospheric condition data required to calculate leakage I rate were provided by one (1) quartz bourdon tube manometer *, forty (40) resistance temperature detectors (RTD) and ten (10) resistance humidity detectors (RHD). The performance characteristics of these devices are listed in Table 2.1. The quartz bourdon tube manometer was connected to I the containment atmos)here through a penetration dedicated to the leakage rate test. T1e RTD's and RHD's were hung at well dispersed elevations and azimuths within the containment. Table 2.2 identifies the locations of these devices.

Wiring from the RTD's and RHD's was connected through containment g electrical penetrations to conditioning electronics located in the auxiliary building. Output from the conditioning electronics was 5 connected to a multiplexer which was, in turn, wired to the plant computer. The temperature and relative humidity (R.H.) data, in degrees I Fahrenheit and % R.H. units were output by the plant computer to a printer. Precision manometer readings were manually recorded. Time, pressure,(temperature, and2)R.H. data(15) were manually entered into the ILRT computer an IBM PC/ System at fifteen minute intervals.

• A second unit provided backup data.

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W3 SES Reactor Containment ILRT Final Report Page 5

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2.3 TestMeasurements.InstrumentationandAirMassCalculation(cont)

The ILRT computer program converts manometer readings to true pressure using the manometer calibration table. Water vapor pressure is determined from temperature and R.H. data. Each RHD was installed adjacent to an RTD. The program contains an algorithm to calculate the saturation pressure corresponding to the temperature indicated by the RTD. Partial pressure of the water vapor at the RHD/RTD location is determined as the product of saturation pressure and R.H. The program then calculates volume weighted mean temperature and vapor pressure using the weighting factors listed in Table 2.2. The mass of the air within the containment is computed using equation (1) which is a formulation of the ideal gas law.

M = (P - Pv) V/RT (1)

Where:

M= Total mass of dry air in the containment, lbm.

P= Absolute pressure of the air / water vapor mixture, lb/sq. ft.

Pv = Absolute pressure of the water vapor, lb/sq. ft.

V cu. ft.

R = Containment

= freeair, Gas constant for air volume,/lbm lbf-ft - degree R.

T = volume weighted mean containment temperature, degree R.

Water va)or pressure is subtracted from total pressure in an effort to ensure tlat air mass and, consequently, leakage rate are not affected '

by evaporation / condensation.

L The magnitude of the leakage induced during the verification test was The measuredusingafloattgeflowmeterthrottledattheoutlet.

characteristics of this vice are listed in Table 2.1.

Allinstrumentationwaslaboratorycalibratedpriortothetest.

Following installation of the RTD s and RHD's, in situ performance E was checked to verify end to end system calibration. RTD performance was checked by inserting the sensing elements in an ice bath and verifyingthattheplantcomouterdisplayedatemperaturewithinone(1) degree Fahrenheit of the bath temperature. RHD performance was checked using a psychrometer. Dewpoint temperatures were calculated for the i

psychrometer wet and drybulb readings and for the drybulb reading and the R.H. displayed by ths plant com The two dewpoint temperatures were verified to be within five (5)puter. degrees Fahrenheit of each other.

i Containment gage )ressure was measured with a conventional dial type pressure ga e. T1e performance characteristics of this gage are listed in Table 2. .

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W3 SES Reactor Containment ILRT Final Report Page 6 l

2.4 Leakaae Rate Calculations Leakage rate was calculated using both the total time and the mass point methods. The mass point method, as described in Ref. 6, defines leakage '

rate as the slope of a straight line fitted to air mass / time data sets by the method of least squares. The total time method, as described in Ref. 5, is based on the premise that leakage rate varies linearly with time, and defines the leakage rate as the ordinate of the leakage rate versus time line at the end of the test. The leakage rate versus time line is fitted by the method of least squares to measured leakage rate / time data sets. Measured leakage rate for any time, ti, is the initialairmass(atto)lesstheairmassattidividedby(ti-to).

The 95% upper confidence limit (UCL) on the calculated leakage rate must be less than the acceptance limit (0.375% mass loss per day). The UCL is always greater than the calculated leakage rate and increases with the scatter of the air mass data away from a straight line trend with time. The 95% UCL is effectively described by the following statement.

If the leakage rate test is performed a very large number of times under identical conditions, 95% of the calculated leakage rates (no two of whichwillbeexactlythesame)willbelessthanthe95%UCL*.

The test procedure requires the total time calculation. Results of the mass point calculation are reported to provide additional information.

The derivation of total time UCL in Ref. 5 introduces addad conservatism into the calculation. What is referred to as a 95% UCL in that document does, in fact, provide a much higher (than 95%) level of confidence.

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3.0 CHRONOLOGY AND EVENTS

,l 5 3.1 Chronoloav Containment preparations including instrument installation and valve I lineups were completed by twelve midnight on May 21, 1988.

Pressurization was started at about 2:10 a.m. on May 22 following final containment closure and sign off of procedure prerequisites.

E Pressurization was stopped at about 1:50 p.m. on the same day when W pressure had reached 46 PSIG.

I Theeight(8) a mandatory hour (Ref. (minimum))testperiodstartedat6:00p.m.following

5) four (4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> temperature stabilization period.

The test was ended at 2:15 a.m. on May 23. The additional fifteen minutes of test time resulted from a delay in obtaining air samples 3 needed for anclysis prior to venting verification flow to the auxiliary y building. Verification flow was established just prior to 2:45 a.m.

The verification test was started at 3:45 a.m., following a mandatory (Ref. 5) one hour stabilization period, and ended at 8:00 a.m. The I fourandaquarter(4.25)hourdurationsatisfiedtheRef.5 requirement that the length of the verification test be one half that of the leakage rate test.

Containment depressurization started shortly after completion of the verification test. The depressurization rate was maintained below 6 PSI / hour to satisfy Ref.1 re uirements. The containment was opened when zero pressure was reache late on May 23.

3.2 Events No significant events occurred during the ILRT. During the eight and a quarter (8.25) hour test the data for temperature sensor number 35 was noted to be erratic. This sensor was assigned a zero volume fraction I- and its previously assigned fraction (0.236) was allocated equally to vertically adjacent sensors 16 and 32. Also, during the 8.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test, R.H. sensors 1, 3, and 5 were noted to indicate erratic or excessive I vapor pressure changes. The volume fractions for these sensors were set to zero and the remaining R.H. sensors assigned equal volume fractions (3 0 0.1428 and 4 0 0.1429). R.H. sensors 6 and 10 were removed from 3 the verification calculation during the verification test due to erratic 3 indications. Remaining sensors 2, 4, and 7 - 9 were assigned volume fractions of 0.2 for the verification test.

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Page 8 4.0 TEST RESULTS The eight (8) hour (minimum) leaka e rate test was started at 1800 hours0.0208 days <br />0.5 hours <br />0.00298 weeks <br />6.849e-4 months <br /> on May 22, 1988, approximately four ( ) hours and ten (10) minutes after stopping pressurization. Temperature stabi ization criteria were satisfied prior to the test start as shown on Table 4.1. Containment pressure at the start of the test was 45.2 PSIG as shown on Table 4.1. Temperature decay is illustrated graphically in Figure 4.1. All original test data is filed with the official test copy of Ref. 1.

4.1 Total Time Leakaae Rate Containment leakage rate was quite small The computed 95% UCL on the total time leakage rate was 0.116 wt%/ day which is less than one third of the )rocedure acceptance limit of 0.375 wt%/ day as shown on Table 4.2. T1e total time calculated value was 0.051 wt%/ day (Table 4.2) and showed a decreasing trend. All total time measured rates were below 0.375 wt%/ day. Therefore, all total time acceptance criteria were met.

Test duration was 8.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. Pressure and temperate decay during the 8.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test are shown graphically on Figures 4.2 and 4.3. Air mass change is shown graphically on Figure 4.4, which is discussed in Section 4.2.

Thefireprotectionpenetrations(60and61)andtheILRTpressuresense line penetration (65) were not aligned in the s)ecified post-accident configuration during the ILRT. The minimum pat 1way leakage through these penetrations must be added to the total time UCL to compensate for the nonconservative lineups. These minimum pathway leakages are listed below.

PEN Leakage, SCCM 60 0 61 210 65 0 Total 210 SCCM = .0001 wt%/ day The total minimum pathway leakage is too small to change the computed total time 95% UCL of 0.116 wt%/ day in the least significant figure.

Changes in accumulator pressures were too small to affect leakage rate in the least significant figure. Pressures are recorded in the official

( test copy of Ref. 1. RCS level dropped slightly, but no correction for falling levels is allowed. Sump and tank levels did not change.

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l W3 SES Reactor Containment ILRT Final Report 1 Page 9 5 4.1 TotalTimeLeakaaeRate(cont)

Followingthe8.25hourtest,a38SCFM(ehualtoLa=0.5wt%/

leak was imposed on the containment throug a flowmeter following day) a one hour stabilization period. The new leakage rate was determined for a I 4.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test duration. The calculated total time leakage rate of 0.520 wt%/ day fell within the acceptance limits of 0.430 and 0.680 wt%/ day as shown on Table 4.3. Successful completion of this I verification test demonstrates the validity of the leakage rate computational methods. The acceptance criterion for the verification test is stated as:

Ltt + Lo .25 La 5 Lc 5 Ltt + Lo + .25 La where: Ltt is the total time leakage rate calculated for the 8.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test = .051 Lo is the imposed leak = 0.504 La is the maximum allowable leakage rate * = 0.500 Lc is the rate calculated during the verification test it must be shown that the results of the leaka e rate test would have

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beenacceptablehadthetestbeenperformedprkortoanyrepairsbeing made during the local leakage rate testing program. This is shown by adding minimum pathway leakage improvements to the total time 95% UCL.

I Total minimum pathway improvements sum to 14,400 SCCM which is equivalent to 0.007 wt%/ day. Adding this to the total time 95% UCL of 0.116 results in a theoretical as found (before repairs) leakage rate of 0.123 wt%/ day. This is well below even the as left acceptance limit of 0.375 wt%/ day. Local leakage rate test results are included in the Appendix.

I The leakage rate prior to a return to power must be less than .75 La.

This allows 0.25 La for increases in leakage rate during the operating

, cycle between leakage rate tests.

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W3 SES Reactor Containment ILRT Final Report Page 10 4.2 Mass Point Leakaae Rate Mass point calculations generally provide a more realistic estimate of true leaicage rate than do total time calculations (total time, as defined in Ref. 5, is always a) plied to a test with a duration under twenty four (24) hours since t1e 95% UCL is a very conservative upper bound on leakage rate). Mass point results are listed below for information.

Mass Point calculated leakage rate = 0.061 wt%/ day Mass Point 95% UCL = 0.070 wt%/ day Mass Pointverification Mass Point verificationcalculated upper limit rate= =0.690 0.540wt%/

wt% day / day Mass Point verification lower limit = 0.440 wt%/ day Complete mass point data is contained in Tables 4.4 and 4.5.

Figure 4.4 is a )1ot of air mass versus time. The plot includes the line fitted to tie mass data and a line which represents a leakage rate 0.75La). The slope of the line fitted to the mass of data0.375 is thewt%/

calcuday (lated leakage Figure rate. 4.5 is a plot of air mass versus time during the verification test. The plot includes the line fitted to the mass data and lines representing the upper and lower acceptance limits on calculated verification leakage rate. In both figures the plotted air masses show very little divergence about the fittedline. However, in Figure 4.5, the divergence is much less during the last 6.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> of the test than during the first two hours.

This is discussed further in the following section.

4.3 Results Analysis Since the true containment leakage rate is quite small, the calculated

- value is significantly influenced by any minor differences between actual and indicated changes in containment atmospheric conditions.

' Changes in total pressure and temperature are generally determined quite accurately since the devices used to measure these quantities H incorporate very basic physical principles. The smooth changes in l pressure and volume weighted mean temperature

• over the entire time at pressure as shown in Figures 4.6 and 4.7, support the conclusion that changes in these variables are adequately determined. The

, instrumentation used to determine the partial pressure of water vapor

! incorporates somewhat more complex physical principles and generally provides data which exhibits some unexpected characteristics.

RTD number 35 exhibited erratic behavior and was eliminated from leakage rate calculations. The volume fraction assigned to RTD 35 was distributed equally to RTD's 32 and 16, which are at elevations adjacent to that of 35.

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4.3 ResultsAnalysis(cont) l l

Figures 4.8 through 4.10 show changes in volume weighted mean vapor pressure over the entire time at pressure. The plot in Figure 4.8 is based on equal volume fractions assigned to all R.H. sensor locations.

The plot exhibits large and unexpected changes in vapor pressure. In fact, since the containment was dry at the start of pressurization, and since no R.H. sensor ever indicated more than 91% R.H., no evaporation or condensation is expected. Therefore, calculated mean vapor pressure should be proportional to total pressure after some period of stabilization.

During the 8.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test, R.H. sensors 1, 3, and 5 indicated excessively large or erratic changes in vapor pressure. The volume fractions for these sensors were set to zero and leakage rate was calculated with the remaining sensors equally weighted. Figure 4.9 is a plot of vapor pressure with R.H. sensors 2, 4, and 6 - 10 equally weighted. The variation in vapor ressure over the test eriod is reasonable except for the instabil ty between 1800 and 20 0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

During the verification test, R.H. sensors 6 and 10 indicated sudden l large increases in vapor pressure. The volume fractions for these sensors were set to zero and the verification calculations were done I using a volume fraction of 0.2 for each of the remaining sensors (2, 4, and 7 - 9). Figure 4.10 plots vapor pressure calculated using these volume fractions. The fractional change in vapor pressure over the final twelve (12) hours of the plot is essentially the same as the fractional change in total pressure, as expected.

l Based on the above discussion, it may be concluded that true leakage I

I rate is better approximated by calculations based on total )ressure unless there is evidence of evaporation or condensation witiin the containment. Tables 4.6 and 4.7 list the mass point 8.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> test and I

l verification results for total pressure calculations. These compare to the corrected pressure calculations as noted below.

Mass Point Parameter Calculation Result

= Total Pressure Corrected Pressure Leakage Rate .035 wt%/ day .061 wt%/ day 95% UCL .039 wt%/ day .069 wt%/ day I Difference .004 wt%/ day .008 ut%/ day Verification Upper Limit .664 wt%/ day .690 wt%/ day Verification Rate .524 wt%/ day .540 wt%/ day Verification Lower Limit .414 wt%/ day

.a40 wt%/

l Deviation From Midpoint .015 ut%/ day .025 wt%/ dayday) 5 W

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I W3 SES Reactor Containment ILRT Final Report Page 12 B 4.3 ResultsAnalysis(cont)

The total betweenca$ressureresultshavebetterstatisticsinthatdeviation culated rate and UCL is smaller and deviation between verification rate and midpoint (between upper and lower limits) is i smaller. These points are illustrated graphically in Figures 4.11 and 4.12. The air mass data in Figure 4.11 deviates less from the fitted line than does that in Figure 4.4 (corrected pressure calculations). Differences in the verification test plots, Figures 4.5 I and 4.12, are less noticeable.

Table 4.8 is a total time report for the total pressure calculation.

I The corrected pressure calculation gives a much higher estimate of the 95% UCL as restated below.

Total Time 95% UCL Total Pressure Corrected Pressure

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0.067 wt%/ day 0.116 wt%/ day Therefore, leakage rates reported in the summary and in Section 4.1 are concluded to be very conserv6tive estimates of the true values.

.I 4.4 Shield Buildina Examination Reference 3 requires that the exterior and interior surfaces of the shield building be examined in conjunction with the ILRT to determine structural condition. The examination was performed prior to I pressurization. No evidence of deterioration was found.

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W3 SES Reactor Containment ILRT Final Report Page 13

5.0 REFERENCES

1. Surveillance Procedure PE-5-001, Containment Integrated Leakage Rate Test, Revision 1.

2. Final Safety Analysis Report, Sections 6.2.6 and 3.8.2.7.

3. Technical Specifications, Sections 4.6.1.2 a/b/c, 4.6.1.6 and 4.6.6.3.

4. Code of Federal Regulations, Title 10, Part 50, Appendix J, Primary Reactor Containment Leakage Testing For Water-Cooled Power Reactors. j

5. Bechtel Topical Report, BN-TOP 1, Testing Criteria For Integrated Leakage Rate Testing of Primary Containment Structures For Nuclear Power Plants, Revision 1, November, 1972.

6. ANSI /ANS 56.3 - 1981, Containment System Leakage Testing Requirements.

7. (ReferencecitedinAppendixJ)ANSIN45.4-1972, Leakage Rate Testing Of Containment Structures For Nuclear Reactors.

8. PEIR #70996, Evaluation of Construction I-Beam Supports in Annulus.

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W3 SES Reactor Containment ILRT Final Report Table 2.1 Page 14 TABLE 2.1 TEST INSTRUMENTATION PERFORMANCE CHARACTERISTICS Precision Manometer Make and Model: Mensor Quartz Manometer Range: 0-100 PSIA Tracking Error: .004 PSI over test range Resistance Temperature Detector Make and Model: Burns WPP0G1-5 1/2-3-A B Range: Calibrated from 32 degrees Fahrenheit to 120 degrees Fahrenheit Tracking Error: 0.01 degrees Fahrenheit over test range Resistance Humidity Detector Make and Model: PhysChem Research Model B Range: 0-100% relative humidity Tracking Error: 2.1% R.H.

Flow Meter Make and Model: Brooks Model 1110-10K381A I Range: 8 - 75 SCFM Absolute Accuracy: 1% F.S.

Pressure Gaae Make and Model: Heise Model CM Range: 0-100 PSIG I- Abse'ute Accuracy: 0.1 PSI I

I I

B B

W3 SES Reactor Containment ILRT Final Report Table 2.2 Page 15 TABLE 2.2 (1) (2) (3)

RT0/(RHD) El..Ft. Rad. Ft. AZ, dearee V.F.

1 195.0 7.5 20 .0271 2 176.5 23.0 140 .0281 3 170.0 28.5 260 .0272 4 1 58.5 38.0 20 .0263 5/(1) 184.5 16.0 60 .0289 6 153.5 42.5 100 .0274 7 148.5 46.5 140 .0281 8/(2) 164.0 33.5 180 .0298 9 138.5 49.5 220 .0288 10 133.5 49.5 260 .0288 11/(3) 143.5 49.5 300 .0286 12/(7) 128.5 49.5 340 .0288 13 38.5 59.0 230 .0201 14/(6) 73.5 49.5 260 .0278 15 48.5 49.5 300 .0227 16 68.5 49.5 340 .0274 17 23.5 63.5 210 .0201 18 18.5 52.5 230 .0201 .

19 13.5 52.0 290 .0201 20 8.5 49.5 320 .0180 21 123.5 49.5 20 .0284 22 118.5 49.5 60 .0284 23 113.5 49.5 100 .0284 24 103.5 49.5 140 .0284 25/(5) 108.5 49.5 180 .0284 26 98.5 49.5 180 .0284 27 88.5 49.5 220 .0284 28/(10) 93.5 49.5 260 .0284 29 83.5 49.5 300 .0284 30 78.5 49.5 340 .0284 31 30(4) 48.0 10 .0241 32 58.5 52.5 30 .0236 33/(4) 53.5 49.5 70 .0236 34 33.5 57.5 110 .0201 35 63.5 49.5 140 .0236 36 43.5 64.0 200 .0201 37/(8) 3.5 61.5 20 .0148 38 -1.5 49.5 70 .0129 39 -6.1 49.5 100 .0154 40/(9) 27.5 49.5 170 .0201 m

• i

s W3 SES Reactor Containment ILRT Final Report -

Table 2.2 Page 16 Table 2.2(cont)

Notes: 1. Reference elevations: Lowest '.evel (-) 11 f t. ;

Springline(+)138ft.;Tophemisphere(+)208ft.

2. Containment radius = 70 ft.

3. Containment free air volume = 2,677,000.00 cu. ft. All RHD's have volume fractions of 0.1. See Section 4.3 for redistributions g

required by instrument malfunctions.

4. RTO hung in refueling cavity.

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5. As installed elevations, radii, and azimuths are +/-3 ft, +/-5 ft, and +/- 5 degrees, respectively.

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Page 17 TABLE 4.1 WATERFORD 3/1988 ILRT ST4E41LIZ ATION DATA

SUMMARY

REPORT data time date t ern perat ure pressure vapor dry air set de0 F psia pressure mass psia lbm 1 1351 522 96.0128 60.5250 O.5309 780113.7 2 1400 522 95.5269 60.4389 O.5260 779739.O 3 1415 522 94.5313 60.3447 0.5124 780089.5 4 1430 522 93.8458 60.2788 0.4973 780393.1 5 1445 522 93.3334 60.2292 0.4993 780441.8 .E 6 1500 522 92,9218 60.1976 0.5004 780464.9 7 1515 522 S2.5751 60.1522 0.5035 780450.9 8 1530 522 92.2881 60.1218 O.5028 780468.1 9 1545 522 91.9941 60.0944 0.5001 780560.4 10 1000 522 91.8034 60.0691 O.5029 780462.4 11 1615 522 91.5712 60.0458 O.5030 780484.4 W

12' 1630 522 91.3850 60.0225 O.5044 780423.8 13 1645 522 91.1664 60.0043 O.5056 780478.9 1*

14 1700 522 91.0300 59.9850 O.5040 7",0440.5 k-15 1715 522 90.8512 59.9678 O.5053 730450, 8 ~?-

16 1730 522 90.7202 59.9506 O.5039 730429.5 17 1745 522 90.5*55 59.9344 0.5011 780487.4 18 1800 522 90.4089 59.9192 O.5032 780467.1 Tempers are change 1600 - 1700 = . 77 degrees Fahrenheit / hour Temperature change 1700 - 1800 = .62 degrees Fahrenheit / hour Average rate of change = (.62 + .77)/2 = .695 degrees Fahrenheit / hour

< 1.0 degrees Fahrenheit / hour Second dif ference = .77 .62 = .15 degrees Fahrenheit / hour' < .5 degrees F/ hour' , .

4:

Page 18 TMLE 4.2 WATERFORD 3/1988 ILRT TEST AT 46 PSIG TOTAL TIME LEAKAGE RATE REPORT data time date elapsed dry air measured leakage uc1 set time mass rate rate rate -

(hrs) (Ibm) (%/ day) (%/ day) (%/ day) 1 1800 522 0.00 781491.4 0.0000 0.0000 0.0000 2 1815 522 0.25 781477.4 0.1715 0.1715 0.1715 3 1830 522 0.50 781435.2 0.3453 0.3453 0.3453 4 1845 SE2 0.75 781447.6 0.1793 0.2359 1.8053 5 1900 522 1.00 781423.2 0.2095 0.2186 0.7500 6 1915 522 1.25 781400.6 0.2231 0.2192 0.5450 7 1930 522 1.50 781395.4 0.1965 0.2058 0.4489 8 1945 522 1.75 781401.8 0.1572 0.1800 0.3822 9 2000 522 2.00 781355.6 0.2085 0.1857 0.3620 10 2015 522 2.25 781346.6 0.1976 0.1G56 0.3419 11 2030 522 2.50 781334.6 0.1926 0.1841 0.3251 12 2045 522 2.75 781354.2 0.1533 0.1706 0.3009 13 2100 522 3.00 781336.7 0.1584 0.1624 0.2831 14 2115 522 3.25 781329.9 0.1526 0.1549 0.2676 15 2130 522 3.50 781338.4 0.1342 0.1445 0.2508 16 2145 522 3.75 781340.4 0.1236 0.1340 0.2349 17 2200 522 4.00 781338.3 0.1176 0.1244 0.2205 18 2215 522 4.25 781324.4 0.1206 0,1175 0.2093 19 2230 522 4.50 781322.1 0.1155 0.1110 0.1991 20 2245 522 4.75 781320.4 0.1105 0.1048 0.1895 21 2300 522 5.00 781327.2 0.1009 0.0980 0.1797 22 2315 522 5.25 781320.1 0.1002 0.0923 0.1713 23 2330 522 5.50 781330.3 0.0900 0.0859 0.1624 24 2345 522 5.75 781316.3 0.0935 0.0811 0.1556 25 0 523 6.00 781315.2 0.0902 0.0765 0.1493 26 15 523 6.25 781315.2 0.0866 0.0722 0.1434 27 30 523 6.50 781310.6 0.0854 0.0683 0.1382 3

28 45 523 6.75 781318.6 0.0786 0.0641 0.1326 29 100 523 7.00 781302.6 0.0828 0.0611 0.1287 _

30 115 523 7.25 781296.6 0.0825 0.0585 0.1255 31 130 523 7.50 781293.4 0.0811 0.0560 0.1225 Jn-p(iA g .: .

32 145 523 7.75 781E69.4 0.0880 0.0548 0.1214 33 200 523 8.00 781296.6 0.0748 0.0522 0.1182 (d' .y[.;

34 215 523 8.25 781278.4 0.0793 0.0505 0.1163 fjf t

v '": ,

Allowable leakage rate, La = 0.5000  %/ day rjf' .

75% Le = 0.3750  %/ day 3/YF j Total time leakage rate = 0.0505  %/ day f ff Total time UCL = 0.1163  %/ day s(ly(JG 3.,

mm#

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I Page 19 TABLE 4.3 fI WATERFORD 3/1988 ILRT VERIFICATION TOTAL TIME LEAKAGE RATE REPORT VERIFICATIDN data time date elapsed dry air measured leakage set time mass rate rate (hrs) (1bm) (%/ day) (%/ day)

I 5 345 523 0.00 781084.3 0.0000 0.000 6 400 523 0.25 781029.3 0.6757 0.676 7 415 523 0.50 780986.3 0.6023 0.602 8 430 523 0.75 780974.8 0.4483 0.462 9 445 523 1.00 780931.9 0.4683 0.432 10 500 523 1.25 780870.1 0.5264 0.458 11 515 523 1.50 780854.6 0.4704 0.444 I 12 13 14 530 545 600 523 523 523 1.75 2.00 2.25 780804.9 780751.4 780700.2 0.4906 0.5114 0.5245 0.447 0.458 0.472 15 61E 523 2.50 780653.6 0.5293 0.483 16 630 523 2.75 780624,4 0.5138 0.486 I 17 645 523 3.00 780571.8 0.5249 0.492 18 700 523 3.25 780515.8 0.5374 0.501 19 715 523 3.50 780473.6 0.5361 0.507 5

• 20 730 523 3.75 780428.1 0.5376 0.512 P1 745 523 4.00 780384.8 0.5373 0.516 1:0: 800 523 4.25 780340.8 0.5375 O.520 Upper limit on leakage rate = 0.6795 %/ day Total time leakage rate = 0.5196 %/ day Lower limit on leakage rate = 0.4295 %/dky I

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Page 20 TABLE 4.4 L-WATERFORD 3/1988 ILRT TEST AT 46 PSIG .

MASS POINT LEAKAGE RATE REPORT i; o j data time date elapsed dry air leakage uc1 , 4 s set time mass rate rate ,,

(hrs) (1bm) (%/ day) (%/ day) .'

1 1800 522 0.00 781491.4 0.0000 0.0000 - .

2 1815 522 0.25 781477.4 0.1715 0.1715 3 1830 522 0.50 781435.2 0.3453 1.2039 4 1845 522 0.75 781447.6 0.2132 0.473S 5 1900 522 1.00 781423.2 0.2042 0.3251  ?.t 6 1915 522 1.25 781400.6 0.2121 0.2845 t:  :

7 1930 522 1.50 781395.4 0.1990 0.2497 - tg 8 1945 522 1.75 781401.8 0.1704 0.2190  ;- T 9 2000 522 2.00 781355.6 0.1836 0.2229 g' 10 2015 522 2.25 781346.6 0.1863 0.2172 11 2030 522 2.50 781334.6 0.1860 0.2109 L 781354.2 0.1694 12 2045 522 2.75 0.1963 13 2100 522 3.00 781336.7 0.1609 0.1851 14 2115 522 3.25 781329.9 0.1533 0.1753 1C 2130 522 3.50 781338.4 0.1420 0.1642 L' 16 2145 522 3.75 701340.4 0.1307 0.1531 -

17 220) 522 4.00 781338.3 0.1209 0.1429 ~. =

18 22i.1 522 4.25 781324.4 0.1149 0.1353 <  ;

19 2230 522 4.50 781322.1 0.1092 0.1283 -;_._

h y 20 2245 522 4.75 781320.4 0.1038 0.1218 4 21 2300 522 5.00 781327.2 0.0974 0.1148 -

22 2315 522 5.25 781320.1 0.0925 0.1090 23 2330 522 5.50 781330.3 0.0864 0.1026 24 2345 522 5.75 781316.3 0.0825 0.0978 0 SP3 781315.2 0.0789 0.0934 -

25 6.00 --

l 26 15 's23 6.25 781315.2 0.0753 0.0892

. 27 30 523 6.50 781310.6 0.0724 0.0855 l 28 45 523 6.75 781318.6 0.0687 0.0814 ..

29 100 523 7.00 781302.6 0.0667 0.0786 30 115 523 7.25 781296.6 0.0651 0.0763 31 130 523 7.50 781293.4 0.0636 0.0742 32 145 523 7.75 781269.4 0.0637 0.0736 n~ E 33 200 523 8.00 781296.6 0.0616 0.0712 -

34 215 5P3 8.25 781270.4 0.0607 0.0697 .

Allowable leakkge rate, La = 0.5000 %/ day 75% La = 0.3750 %/ day -

Mass point leakage rate = 0.0607 %/ day .- .--

Mass point UCL = 0.0697 %/ day f q 1

Page 21 TABLE 4.5 WATERFORD 3/1988 ILRY VERIFICATION MASS POINT LEAKAGE RATE REPORT VERIFICATION data time date elapsed dry air leakage set time mass rate (hes) (1ba) (%/ day) 5 345 523 0.00 781084.3 0.0000 6 400 523 0.25 781029.3 0.6757 7 415 523 0.50 780986.3 0.6023 8 430 523 0.75 780974.8 0.4563 5 445 523 1.00 780931.9 0.4415 10 500 523 1.25 780870.1 0.4826 11 515 523 1.50 780854.6 0.4660 12 530 523 1.75 780804.9 0.4712 13 545 523 2.00 780751.4 0.4861 14 600 523 2.25 780700.2 0.bO14 15 615 523 2.50 780653.6 0.5131 16 630 523 2.75 780624.4 0.5138 17 645 523 3.00 780571.8 0.5186 18 700 523 3.25 780515.8 0.52s5 19 715 523 3. Ts0 78C'473. 6 0.5314 20 730 521 3.75 78(o28.1 0.5353 21 745 523 4.30 780384.8 0.5380 22 800 523 4.25 780340.8 0.5399 Upper limit on leakage rate = 0.6897 %/ day Mass point leakage rate a- 0.5399 %/ day Lower limit on leakage rate = 0.4397 %/ day L

i'r' 3

8 I Page 22 TABLE 4.6 WATERFORD 3/1988 ILRT TOTAL PRESSURE C46 7 MASS POINT LEAKAGE RATE REPORT I data set time date elapsed time (hrs) dry air mass (Ibm) leakage rate

(%/ day) uc1 rate

(%/ day) 17 1800 522 0.00 787077.5 0.0000 0.0000 18 1815 522 0.25 787063.6 0.1690 0.1690 19 1830 522

'I 0. 5C 787051.0 0.1615 0.1983 20 1845 522 0. 7! 787046.3 0.1295 0.1842 23 1900 522 1.00 787045.9 0.0983 0.1477 22 1915 522 1.25 7B'035. 4 0.0936 0.1234 I 23 24 25 1930 1945 2000 522 522 522 1.50 1.75 2.00 787038.3 787036.6 787020.4 0.0780 0.0669 0.0704 0.1050 0.0899 0.0882 I 26 27 28 2015 2030 2045 522 522 522 2.25 2.50 2.75 787021.6 787017.4 787033.7 0.0675 0.0652 0.05;7 0.0818 0.07G9 0.0691 29 2100 522 3.00 787021.9 0.0437 0.0633 I 30 31 32 2115 2130 2145 522 522 522 3.25 3.50 3.75 787004.6 787007.6 787025.5 0.05!9 0.05;O

0. 044 5 0.0636 0.0611 0.0555 I 33 34 35 2200 2215 2230 522 522 522 4.00 4.25 4.50 787006.6 786994.8 786991.6 0.0407 0.0449 0.0457 0.0534 0.0536 0.0534 36 522 787013.5 I 2245 4.75 0.0417 0.0497 37 2300 522 5.00 786996.6 0.0410 0.0482 38 2315 522 5.25 786998.4 0.0396 0.0463 39 2330 522 5.50 787004.9 0.0373 0.0439 I 40 41 42 2345 0

15 522 523 523 5.75 6.00 6.25 786987.1 786992.5 787013.3 0.0374 0.0364 0.0332 0.0433 0.04?O 0.0392 I 43 44 45 30 45 100 523 523 523 6.50 6.75 7.00 786996.6 786987.9 786976.1 0.0320 0.0316 0.0321 0.0377 0.0369 0.0370 g 46 115 523 7.25 786963.2 0.0332 0.0330 Ig 47 130 523 7.50 786967.1 0.0337 0.0382 48 145 523 7.75 786944.9 0.0354 0.0399 49 200 523 8.00 786975.9 0.0347 0.0390 50 215 523 8.25 786955.9 0.0351 0.0391 Allowable leakage rate, La = 0.5000  %/ day 75% La 0.3750  %/ day I

=

Mass point leaka3a rate = 0.0351  %/ day Mass point UCL = 0.0391  %/ day I

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I Page 23 TABLE 4.7 WATERFORD 3/1988 ILRT TOTAL PRESSURE CALC MASS POINT LEAKAGE RATE REPORT .

VERIFICATION data time date elapsed dry air leakage I set 55 345 523 time (hrs.)

0.00 mass (1bm) 786713.3 rate

(%/ day) 0.0000 I 56 57 58 400 415 430 523 523 523 0.25 0.50 0.75 786657.7 786616.6 786605.1 0.6787 0.5903 0.4464 445 523 I 59 1.00 786557.1 0.4453 60 500 523 1.25 786497.6 034851 61 515 523 1.50 786479.6 0.4709 62 530 523 1.75 786431.1 0.4751 63 545 523 2.00 786381.9 0.4854 64 600 523 2.25 786325.9 0.5014 65 615 523 2.50 786282.1 0.5117 I 66 67 68 630 645 700 523 523 523 2.75 3.00 3.25 786251.3 786200.5 786152.0 0.5124 0.5163 0.5210 69 715 523 3.50 786127.6 0.5184 I 70 71 730 745 523 523 3.75 4.00 786078.4-786016.9 0.5185 0.3231 72 800 523 4.25 785984.9 0.5240 Jpper limit on leakage rate = 0.6641 %/ day Masis ptAnt leakage rate = 0.5240 %/ day Lower 11.i.t on leakage rate = 0.4141 %/ day I

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Page 2A TABLE 4.8 WATERFORD 3/1988 ILRT TOTAL PRESSURE CALC TOTAL TIME LEAKAGE RATE REPORT data time date elapsed dry air measured leakage uc1 set time mass rete rate rate (hrs) (1bm) (%/ day) (%/ day) (%/ day) 17 1800 522 0.00 787077.5 0.0000 0.0000 0.0000 18 1815 522 0.25 787063.6 0.1690 0.1690 0.1690 19 1830 522 0.50 787051.0 0.1615 0.1615 0.1615 20 1845 522 0.75 787046.3 0.1267 0.1313 0.2575 21 1900 522 1.00 787045.9 0.0964 0.1005 0.1518 22 1915 522 1.25 787035.4 0.1027 0.0918 0.1429 23 1930 522 1.50 787038.3 0.0796 0.0760 0.1150 24 1945 522 1.75 787036.6 0.0714 0.0638 0.0987 25 2000 522 2.00 787020.4 0.0871 0.0635 0.1110 26 2015 522 2.25 787021.6 0.0757 0.0595 0.1067 27 2030 522 2.50 787017.4 0.0733 0.0564 0.1033 28 2045 522 2.75 787033.7 0.0486 0.0467 0.0896 29 2100 522 3.00 787021.9 0.0565 0.0421 0.0842 30 2115 522 3.25 787004.6 0.0684 0.0423 0.0879 31 2130 522 3.50 787007.6 0.0609 0.0407 0.0867 32 2145 522 3.75 787025.5 0.0423 0.0352 0.0791 33 2200 522 4.00 787006.6 0.0541 0.0;37 0.0779 34 2215 522 4.25 786994.8 0.0594 0.0338 0.0795 35 2230 522 4.50 786991.6 0.0582 0.0337 0.0804 36 2245 522 4.75 787013.5 0.0411 0.0305 0.0759 37 2300 522 5.00 786996.6 0.0493 0.0295 0.0748 38 2315 522 5.25 786998.4 0.0459 0.0281 0.0731 S.3-E f7f-L 39 2330 522 5.50 787004.9 0.0403 0.0261 0.0703 [

40 2345 522 5.75 786987.1 0.0479 0.0257 0.0702 ~

g c-41 0 523 6.00 786992.5 0.0432 0.0247 0.0690 s 42 15 523 6.25 787013.3 0.0313 0.0221 0.0654 S'. ~

4.7 30 523 6.50 786996.6 0.0379 0.0208 0.0639 - L' 44 45 523 6.75 786987.9 0.0405 0.0202 0.0633 T- $)I. .

45 100 523 7.00 786976.1 0.0442 0.0202 0.0637 =..,,~g 46 115 523 7.25 786963.2 0.0481 0.0207 0.0650 (/ #' f ;.

47 130 523 7.50 786967.1 0.0449 0.0209 0.0655 -%2 TH 48 145 523 7.75 786944.9 0.0522 0.0219 0.0675 iI -T 49 200 523 8.00 786975.9 0.0387 0.0213 0.0666 [ .' ' U \

50 215 523 8.25 786955.9 0.0450 0.0215 0.0670 3: 9-A11owabit leakage rate, La = 0.5000  %/ day 7 7.;;} l . .

75% La = 0.3750  %/ day -,-

Total time leakaDe rate = 0.0215  %/ day /;

Total time UCL = 0.0670  %/ day y;-J. j'

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W3 SES Reactor Containment ILRT Final Report Appendix

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{ l APPENDIX l LOCAL LEAKAGE RATE TEST RESULTS L

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W3 CE5 ROOcter Crntoinacnt ILRT Finc1 R:p3rt Type C Tect P go 37 TYPE C LOCAL LEAX RATE TECT

SUMMARY

r LEAXAGE (acca) DATE PEN WO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 7 PMU-151 0 0 840420 0 0 861201 0 0 880405

. 7 PMU-152 0 0 840420 3,000 0 861231 100 100 880405 8 SA-908 0 0 840425 160 160 660314 0 0 870105 150 150 880415 8 SA-909 60 60 840425 135 135 860314 160 160 870105 370 370 870415 9 1A-909 7,000 0 840509 2,200 990 860321 700 700 870107 1,500 1,070- 880517 9 1A-910 >20,000 >20,000 840426 11,000 30 840927

>20,000 10 860319

>50,000 0 870113 0 0 880509 10 CAP-103 2,500 2,500 840515 0FF SCALE 15,200 850117 +

>21,000 9,510 850514

W3 CES C cct:r C;ntoinOcnt ILRT Finoi R:p3rt Type C T Ot Pago 38 TYPE C LOCAL LEAX RATE TEOT

SUMMARY

LEAMAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 10 CAP-103 11,500 11,500 450816 5,900 5,900 d51213 6,600 6,600 860312 3,200 3,200 860710

>65,000 10,000 870120 18,000 18,000 870414 18,000 18,000 870527 70,000 10,900 870904 10,400 10,800 871211 11,600 11,600 880321 12,400 12,400 840322 17,000 17,000 880518 10 CAP-104 2,500 2,500 440515 OFF SCALE lb,200 050117

>21,000 9,510 850514 11,500 11,500 850816 5,900 5,900 853213 w

6,600 6,600 860312 3,200 3,200 860710

>b5,000 10,000 870120 18,000 18,000 870414 16,000 18,000 870527 70,000 10,900 870904 10,800 30,800 8701211 11,600 11,600 880321 L 12,400 22,400 880322 M

C3 SES R00stcr C ntOinncnt ILRT Final R port Type C Tcct P2g3 39 TYPE C LOCOL LEAK NATE TEST SUMMANY LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LMFT (YYMMDD) 10 CAP-104 17,000 17,000 880518 11 CAP-203 0FF SCALE 2,700 840526 0FF SCALE 21,000 850115 7,900 7,900 &but14 10,600 10,600 85081b 1

2,000 2,000 851214 2,600 2,600 460314 7,000 7,000 #60711 j l

640 640 87011e 520 520 870414 650 650 870527 650 650 870904 1,000 1,000 871211 3,300 3,300 880320 400 400 880318 11 CAP-204 0FF SCALE 2,700 84052L i

0FF SCALE 21,000 830115 7,900 7,900 8bo514 10,600 10,600 850816 2,000 2,000 851214 2,600 2,600 860314 7,000 7,000 860714 640 640 87011e 520 520 870414 650 650 870527 b50 650 870904

W3 SEO ROccter Contoin:cnt ILRT Finol Report l

Typo C Toot POgo 40 TYPE C LOCAL LEAK RATE TEST

SUMMARY

LEAXAGE (accm) DATE PEN NO. J ftLVE NO.

. As FQ MD AS LEFT (YYMMbus 11 CAP-2f.d 1,000 1,000 871211 3,300 3,300 8e0320 400 400 880413 12 CVR-101 OFF SCALE 150 8405v7 920 920 861206 2,050 2.050 860413 12 CVR-102 130 130 840413 7 60, 'JOO 56U 870106 2,000 2,000 880413 13 CVR-201 OFF SCALE 2,100 840507 7,000 3,900 8701C9 5,100 2,100 88051b 13 CVR-202 00 60 840413 560 560 86120s 1,900 1,900 870109 ,

g 120 0 860514 Ig 0 840425 14 NG+157 0 305 lob 840605 2,000 10 860317 95 95 861205 300 300 880407 870 400 680416 400 110 880419 14 NG-158 OFF SCALE 11b 840b07 2,600 225 860317 40 40 ebizub E

lQ W3 SES Rosetor Containment ILRT Final Report

g Typo C Tcat Pogo 41 TYPE C LOCAL LEAK RATE TEST

SUMMARY

5 LEAKAGE (secm) DATE PEN NO. V,6LVE NO. AS FOUND AS LEFT (YYMMDD) 14 WG-158 120 120 880407 23 CC-641 200 200 870113 l5 120 120 880427 23 CC-644 1,300 1,300 870113 665,449 120 880428 24 OC-710 4,200 4,200 870116 18,600 2,000 880502 24 CC-713 0 0 870116 0 0 880429 26 CVC-103 OFF SCALE >20,000 840425 OFF SCALE 3,200 840515 1,500 1,500 840518 10 10 d40618 0 0 861219 2,400 2,400 880413 26 CVC-109 40 40 840425 1,500 110 870110 269,011 15,000 8eO51e 28 PSL-105 0 0 840416 O O 870108

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28 PSL-107 OFF SCALE O 840b09 0 0 870108 O O 880407 O O 880504

W3 SES Roactor Containment ILRT Final Report Typo C Tost Page 42 TYPE C LOCAL LEAK RATE TEST

SUMMARY

LEAKAGE iseca) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMUD) 29 PSL-203 10 10 840417 145 145 861218 45 45 870108 42,000 30 880421 29 PSL-204 0 0 840417 410 0 870106 O O 880407 30 PSL-303 45 45 840417 0 0 861223 29,200 40 88042S 30 PSL-304 50 50 840417 6,900 105 870105 2,800 50 880425 31 CWM-104 100 100 840510 0 0 861210

• 860 330 880422 F 31 GWM-105 100 100 840510 0 0 861210 l C 0 880408 42 SP-105 0 0 840406

- 0 0 861210 170 170 880409 42 SP-106 0 0 640406 O O 861210 120 120 880409 43 BM-109 35 35 840427

W3 SES Reactor Contair mont ILRT Final Report Type C Toot Pago 43 TYPE C LOCAL LEAK RATE TEST SUMMANY LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDU) 43 BM-109 O O 861215 0 0 880412 43 BM-110 40 40 840427 0 0 861215 0 0 880412 L

44 RC-606 O O 840412 O O 861211 170 0 880506 44 CVC-401 0 0 840412 0 0 861211 l

O O 880430 l

O O 880505 45 CAR-101B 275 275 840409 0 0 861209 250 250 880412 5 45 CAR-102 O O 840409

/ 0 0 861209 160 160 880412 P

46 CAR-101A 180 180 840410 0 0 861209 H 300 300 880412

/ 46 CAR-102A O O 840409 25 25 861209 160 160 680412 47 CAR-2OOB 120 120 880423 120 120 860516 a

W3 SES Roccter Casitointent ILRT Finoi R2 port Typa C Tcct Pcga GC TYPE C LOCAL LEAK RATE TEST

SUMMARY

{

j LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMup) 47 CAR-201B 140 140 840410 68,000 0 870116 580 0 880413 120 120 880423 120 120 880516 47 CAR-202B 140 140 840410 68,000 0 870116 580,500 120 880516 48 CAR-201A 130 130 640410 22,000 1,000 870106 1,300 100 870113 10,000 0 880423 48 CAR-202A 130 130 840410 22,000 1,000 870106 1,300 100 870113 l

" 10,000 0 880423 F 49A ARM-109 10 10 840404 5

0 0 861211 0 0 880406 49A ARM-lio 10 10 840404 h 0 0 861211 0 0 880406 40B ARM-103 20 20 840404 OFF SCALE O 861211 0 0 880406 49B ARM-104 OFF SCALE 120 840524

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W3 SES Roactor Containment ILRT Final koport Type C Toot

) Pogo 45 TYPE C LOCAL LEAK RATE TEST

SUMMARY

LEAMAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 49B ARM-104 40 40 850114 80 80 861206 1,400 120 880416 51 FS-405 0 0 e40504 0 0 870114 0 0 880514 51 FS-406 14,000 0 840514 55 55 870114 f

O O 880504 59 SI-343 20 20 840423 O O 861215 0 0 880409 59 SI-344 O O 840423 O O 861215 280 280 880409 l

60 FP-601A CFF SCALE 145 840529 0 0 861202 139,000 12,100 880408 12,100 0 880421 60 PACKING 4,200 120 680421 60 FP-602A 0 0 840512 2,100 2,100 861218 1,200 1,200 870117 1,900 O 880421 61 FP-601B 2,500 2,500 840512 6,100 0 840531

W3 SES Roactor Containment ILRT Final Report Type C Toot Page 46 TYPE C LOCAL LEAK RATE TEST NUMMARY LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD)

G1 FP-601B 180 180 861212 380 380 880406 PACKING 4,200 O 880416 61 FP-602B OFF SCALE 1,700 840529 300 300 861212 3,700 300 870118 3,500 210 88C416 62 FS-415 0 0 e40420 0 0 870114 0 0 880514 h

62 FS-416 O O 840420 0 0 870114 O O 880514 63 LRT-109 0 0 840330 J O O 870115 660 660 8705',7 600 600 880523 63 BLIND FLAN O O 840330 0 0 870115 660 660 880517 600 600 860523 65A LRT-201 10 10 840403 0 0 861124 O O 880404 0 0 880523

- 6 0.', LRT-202 10 10 840403 a

W3 SES R ctor Cantoinacnt ILRT Finc1 Report Typo C Toot Pcgo 07 TYPE C LOCAL LEAK RATE TEST

SUMMARY

LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 65A LRT-202 O O 861129 0 0 880404 O O 880523 65B LRT-203 2 2 840403 0 0 861124 0 0 880404 65B LRT-204 5 5 840403 0 0 861129 0 0 880404 66A HRA-109A 10 10 840405 O O 861205 O O 880502 66A HRA-110A 10 10 84040S O O 861205 0 0 880502 66B HRA-126A 10 10 840405 10 10 860311 0 0 861205 O O 880421 66B HRA-128A 400 10 840524

>20,000 18,000 860314 18,000 2,300 860315 2,300 985 860315 985 870 860317  ;

870 10 860417 I 27 27 861205 y

s

W3 SES Roactor Containment ILRT Final Roport Typo C Toot Page 48 TYPE C LOCAL LEAK RATE TEST

SUMMARY

LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 66B HRA-128A 60 60 880421 67A HRA-109B O O e40404 O O 861205 0 0 880504 67A HRA-110B O O 840404 0 0 661205 0 0 880504 67B HRA-126B 15 15 840331 10 10 860311 O O 861205 O O 880428 l 67B HRA-128B OFF SCALE 150 840525 2,600 1,500 860315 1,500 210 86031*-

180 0 861231 i

80 80 880426 71 CMU-244 O O 840504 0 0 661202 O O 880411 71 CMU-245 O O 840504 110 110 861203 O O 880411

]

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W3 SES Reactor Containment ILRT Final Roport Typo B Toot Pago 49 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (""MMDD) 101 0.01 0.01 840424

.00 .00 860314

.07 .07 861207

.01 .01 880412 102 .00 .00 840424 5.70 5.70 860314 J 9.84 9.84 861208 5.90 5.90 880411 f

104 .00 .00 840424 e

.00 .00 860314

.11 .11 861207

.10 .10 880412 106 .00 .00 840424

.00 .00 860314

.11 .11 861207 l

.10 .10 880412 107 .00 .00 840424 -

l L

.00 .00 860311

.00 .00 861209

.10 .10 880412 108 .00 .00 840424

.00 .00 860315 - .

.00 .00 861209

.10 .10 880412 109 .05 .05 840423  ;

.07 .07 860314 ,

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L W3 SEG ROOctor Cantoinment ILRT Finol Rcpert Typo.B Toot Pcgn 50 . TYPE B LOCAL LEAK RATE TEST

SUMMARY

t ELECT LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 109 .30 .30 861206

.JO .30 880411 110 .01 .01 G40330

.00 .00 e60309

.12 .12 861204

.20 .20 880407 111 .06 .06 840414

.32 .32 860310

.14 .14 861205

.10 .10 880408 112 .03 .03 840416

.32 .32 860310

.13 .13 861205

.10 .10 880408 113 .03 .03 840413 l

.08 .08 860310

.14 .14 861205

.10 .10 880407 114 .05 .05 840328 l

.22 .22 860306

.07 .07 861202

.30 .30 880405 115 .00 .00 840327

.17 .17 860306

.06 .06 861202

.10 .10 880405

W3 SES Reactor Containment ILRT Final Roport Typo B Tont pago 51 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAKAGE (sces) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 116 .00 .00 840327

.17 .17 860306

.07 .07 861202

.30 .30 880405 117 .03 .03 840330

.00 .00 860310

.13 .13 861204

.20 .20 880401 118 .02 .02 840423

.07 .07 860314

.32 .32 861206 I .30 .30 880411 L

119 .08 .08 840328

.09 .09 850112

.22 .22 860306

.12 .12 861201

.10 .10 880405 a

120 .15 .15 840328

.23 .23 860308

- .22 .22 861202 l

h .10 .10 880405 121 .05 .05 840416 2.90 2.90 860312 3.88 3.88 861106 1.20 1.20 880408 L 122 .02 .02 840404 s

W3 CES ROcetor Cantoinacnt ILRT Finol R:psrt Typ3 B Tect POg3 52 TYPE B LOCAL LEAK RATE TEST SUMdAhV ELECT LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT ~<YYMMDD)_ )

l 122 .42 .42 860309 i l

.45 .45 861204

.30 .30 880407 123 .02 .02 840405

.00 .00 860309

.45 .45 861204

.20 .20 880407 124 .04 .04 840411

.13 .13 860311

.04 .04 860313

.58 .58 861204

.40 .40 880408 125 .02 .02 840410

.06 .06 860308

.13 .13 861204

.10 .10 880406 126 .00 .00 840414 L

.08 .08 860310

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! .13 .13 861205 s

.10 .10 880407 127 .03 .03 840411

.05 .05 860311

.58 .58 861205

.40 .40 880408 128 .05 .05 840329 L .23 .23 860308 r

W3 SES Roactor Containment ILRT Final Report Typo B Toot Page 53 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAKAGE (seca) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 128 .14 14 861202

.10 .10 88040b 129 .20 .20 840328

.23 .23 C60308

.21 .21 861202

.10 .10 880405 130 .00 .00 840411

.06 .06 860308

.00 .00 861204

.30 .30 880407 131 .04 .04 840404

.42 .42 860309

.49 .49 861204

.20 .20 880407 132 .03 .03 840405

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.20 .20 880407 l 133 .04 .04 840412

.05 .05 860311

.29 .29 861205

.10 .10 880408 l

134 .00 .00 840423 2.40 2.40 860313 4.33 4.33 861206 1.10 1.20 880411 I

W3 CED Rc:ctcr Cantoinment ILRT Finci R pSrt Typo B Toct Pego 50 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 135 .09 .09 840329

.16 .16 860307

.15 .15 861202

.10 .10 880405 136 .02 .02 840328

.23 .23 860308

.22 .22 861202

.10 .10 880405 137 .21 .21 840416

.00 .00 860312

.29 .29 861205 I .10 .10 880408 L

138 .13 .13 840330 I .00 .00 860309

.15 .15 861204

.30 .30 880407 139 .02 .02 840417 1

.00 .00 860312

.07 .07 861206

.20 .20 880411 140 .08 .08 840404

.42 .42 860309

.00 .00 861204

.30 .30 880407 141 .01 .01 840413 P

.08 .08 860310 L

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[ W3 CES Raceter Contcinucnt ILRT Finci ROport Typo B Tcet P0ga 55 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAMAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 141 .15 .15 861205

.20 .20 880407 142 .04 .04 840411

.06 .06 860308

.15 .15 861204

.20 .20 880406 143 .03 .03 840412

.05 .05 860311

.30 .30 861205

.10 .10 880408 144 .24 .24 840416

.32 .32 860310

.59 .59 861205

.40 .40 880408 145 .08 .08 840329

.16 .16 860303

.15 .15 861202

.10 .10 880405 r 840327 146 .00 .00

(

.17 .17 860306

.08 .08 861201

.10 .10 880405 147 .01 .01 840417

.00 .00 860312

.08 .08 861206 e

y .20 .20 880411 I

l

W3 SES R2ceter Cantoinocnt ILRT Fin 01 Raport Typo B Tcct Pago SS TYPE B LOCAL LEAK RATE TEST

SUMMARY

[ ELECT LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 148 .03 .03 840417

.07 .07 860314

.07 .07 861756

.20 .20 880411 149 .03 .C3 840416

.32 .32 860310

.14 .14 861205

.10 .10 880408 151 .02 .02 840410

.06 .06 860308

.14 .14 861204

.20 .20 880406 EQUIPTMENT HATCH 620.00 620.00 840530 g .00 .00 8b0111 10.00 10.00 850120 g

l

" 100.00 100.00 850228

- 10.00 10.00 850619 L

10.00 10.00 850907 2.65 2.65 851007 100.00 100.00 851214

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t

~ 10.00 10.00 860320

- 10.00 10.00 860325 L 17.00 17.00 860716 13.00 13.00 860718 10.00 10.00 870119 F

3.00 3.00 870131

g W3 SES R0cetor Containcont ILRT Final Rcport f

g Typo B Tcat TYPE B LOCAL LEAK RATE TEST

SUMMARY

l Pego 57

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ELECT LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) l EQUIPTMENT HATCH 1.80 1.80 870927 4.50 4.50 871005 1.80 1.80 880402 4 4 880521 PERSONNEL LOCK 2,000 2,000 840802 5,200 5,200 850130 5,800 5,800 850621 6,300 6,300 851123 10,200 10,200 860522 38,549 38,549 861019 LO,200 10,200 870118 i 8,100 8,100 870630 14,000 14,000 871106 19,800 19,800 880401 I ESCAPE LOCK 100 100 840803 100 100 850215 100 100 850708 760 760 851222 14 14 860622 1,950 1,930 870109 2,200 2,200 870627 660 660 871103 25 ,uEL TRA S TeeE ,LAmee 25 25 .5e111 g

10 10 860118 O O 880519 i BELLOWS NEXT TO LINER O O 840606 I

W3 SES Rocctor Containaant ILRT Finci Report Typo B Tant Pago 58 TYPE B LOCAL LEAK RATE TEST

SUMMARY

[ ELECT LEAKAGE (acem) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 1 BELLOWS NEXT TO LINER O O 861221 1,100 1,100 880415

[

i BELLOWS NEXT TO SHIELD WALL O O 840606 O O 861222 O O 880415 2 BELLOWS NEXT TO LINER O O 840606 0 0 861220 0 0 880415 2 BELLOWS NEXT TO SHIELD WALL 0 0 840606 O O 861220 g

0 0 880415 3 BELLOWS NEXT TO LINER O O 840606 O O 861221 O O 880415 3 BELLOWS NEXT TO SHIELD WALL 0 0 840606 0 0 861221 0 0 880415 F

L 4 EELLOWS NEXT TO LINER O O 840606 O O 861220 0 0 880415 L 4 BELLOWS NEXT TO SHIELD WALL 0 0 840606 0 0 861220 0 0 880415 25 BELLOWS O O 840419 0 0 870127 O O 880514 F

1

W3 SES Reactor Containsont ILRT Final Report Typo B Toot Page 59 TYPE B LOCAL LEAK RATE TEST

SUMMARY

ELECT LEAKAGE (accm) DATE PEN NO. VALVE NO. AS FOUND AS LEFT (YYMMDD) 32 PIPE GUARD ASSY O O 840418 0 0 861217 O O 880409 43 PIPE GUARD ASSY O O 840420 0 0 661217 0 0 880409 I

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