ML20082F503

Reactor Containment Bldg Integrated Leak Rate Test, Final Rept

ML20082F503
Person / Time
Site:	Waterford
Issue date:	06/30/1991
From:	BCP TECHNICAL SERVICES, INC.
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NUDOCS 9108150043
Download: ML20082F503 (40)

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O 5

ENTERGY OPERATIONS, INC.

WATERFORD STEAM ELECTRIC STATION t UNIT 3

- REACTOR CONTAINMENT BUILDING O INTEGRATED LEAK RATE TEST FINAL REPORT i

Prepared By:

BCP Technical Services, Inc, June,1991 I

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DCP Technical S::rvices, Inc.

Entergy Operations,Inc. Waterford 3 SES Reactor Containment BuildinD ILRT Final Report O

TABLE OF CONTENTS SECTION TITLE PAGE 1.0 Summary 3 2.0 Doncription of Containment 4 3.0 Proceduro and Methodology 5 3.1 Containment Preparation 5 3.2 Pressurization G 3.3 Test Monsutomonts, Instrumentation 7 and Air Mass Calculation 3.4 LeakoDo Rato Calculations 0 4.0 Chronolo0y and Events 9 5.0 Test Results 10 5.1 Total Time Leakago Rate 10 ,

5.2 Mass Point Leakago Rate 12 5.3 Shielding Building Examination 13 6.0 References 13 Tables and F10uros 14 27 Appendix I Local Leaka00 Rate Test Results 28 39

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BCP Technical Services, lnc.

Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment Buildina ILRT Final Report O

1.0

SUMMARY

The second parlodic integrated leakago rato test (ILRT) on Waterford SES Unit 3 containment was sucessfully completed on May 12,1991. All acceptanco critoria specified in the test proceduto (Ref.1) were satisfied. Test results and acceptanco critoria are listed below.

Paramotor Results Acceptanco Limits (s) 95% upper confidence lim't (UCL) on total timo leako0a rato (including additions) 0.0731 wt%/ day <0.375 wt%/ day Total timo leaka00 rate trend extrapolated to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.0G72 <0.375 Mean of the measured leaka00 rates over the final 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 0.0G94 <0,500 Verification leaka00 rate 0.5443 0.4G11 0.7111 As found 95% UCL (test result plus minimum pathway improvements) 0.0858 <0.375 Containment pressurization started at 7:38 a.m. on May 10,1991 and was stopped at G:54 p.m. on the same day when containment pressure had reached 46 -

psig. Followin0 an extended temperature stabilization potiod, (Sco Section 4.0, Chronolo0y and Events), the start of the ol0ht (8) hour (minimum) test period was declared at 5:30 p.m. on May 11. The test onded at 1:30 a.m. on May 12 and the verification leaka00 was imposed. The verification test was started at 2:45 a.m.,

following a mandatory one hour stabilization period, and onded at 0:45 a.m.

Containment pressure stayed betwoon 40 and 44 psig throu0hout the stabilization, test and verification phases.

The ILRT was conducted in accordance with a controlled proceduro (Hof.1) which incorporated the requirements of the FSAR (Rof. 2), the Technical Specification (Ref. 3), Appendix J to 10CFR50 (Ref. 4) and BN-TOP-1 (Ref. 5). ANSI /ANS 50.8 (Ref. G) was used for informational Guidance on cortain aspects of the test. Valves on pipin0 systems penetrating containment were ali0ned as specified in Ref. 2, 3

BCP Technical Services, Inc.

Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment Building iLRT final Report with the exception of those on shutdown coolin0 and fire protection lines. Fire protection was lef t in service to satisfy Fire Protection Pro 0 ram (UNT - 005 -013) requirements and a penalty was taken on minimum pathway leaka0e through the penetrations.

A structural examination of the exterior and interior surfaces of the corstainment vessel was performed in conjuction with the ILRT as required by Ref. 3. No evidence of degradation was found.

2.0 DESCRIPTION

OF CONTAINMENT The containment vessel completely encloses the entire reactor coolant system to ensure no leakage of radioactive materials to the environrnent in the unlikely avent of a loss of coolant accident.

The containment system incorporates a free standin0 containment vessel surrounded by a low leakage reinforced concrete shield building. A four foot annular air space is provided between the outer wall of the conteinment vessel and

(] the inner wall of the shield building to allow filtration of any containment vessel leaka0e during accident conditions to minimize off site doses.

The free-standing containment vesselis a two inch thick circular cylinder, 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 vesselis fabricated of ASME-SA 516 Grade 70 fully killeo pressure vessel quality steel plate. The not free volume of the containment is 2,677,000 cubic feet.

The containment vessel structure includes one personnel airlock, one emor0ency escape airlock, one fuel transfer tube, one equipment maintenance hatch, and one seal-welded construction hatch. All process piping and electrical 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.

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BCP Technical Services, Inc.

Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment Buildin0 ILRT Final Report O

The containment vesselis desl0ned and constructed in accordance with the requirements for class MC vessels contained in Section 111, Subsection NE of the ASME Code,1971 Edition including Summer 1971 Addenda and Code cases 1431,1454-1 and 1517, as approved by the USNRC Ro0ulatory Guides 1.84 and 1.85. The containment vesselis code stamped in accordance with Paragraph NE-8000 of Section lli of the ASME Boiler and Pressure Vessel Code. The containment vessel and all penetrations are desl0 ned to limit leakage to less than 0.5 percent by weight of the containment air mass per day at a design pressure of 44 psig. The calculated peak accident pressure for the design basis accident at Waterford SES Unit No. 3 is 44 psig at 263 degrees Fahrenheit.

3.0 PROCEDURE AND METHODOLOGY The leakage rate test was conducted by alignin0 containment systems in the specified post. accident configuration, pressurizin0 the containment to the design basis accident pressure of 44 ( + 3, -0) psig, measurino containment atmospheric conditions, and calculatin0 the out leaka00 of the air usin0 the atmospheric condition data. These activ!tles are described in detail in the followin0 paragraphs.

O 3.1 Containment Preparation Systems penetrating containment were aligned in the specified post-accident configuration except that systems required to maintain the plant in a safe condition were aligned to perform the safety function. Systems postulated to rupture as a result of the accident were vented inside and outside of containment (with the exceptions noted above). Isolation valves were closed. The reactor coolant system was vented to containment atmosphere throu0h the pressurizer. The safety injection tanks were vented to ensure that slow in or out leakage would not occur. The reacter drain tank and pressurizer relief tanks were vented for the same reason as well as to provido protection a0ainst external pressure. Sources of compressed gasses within the containment (fire extinguishers accumulators, etc.) were removed, vented or fitted with pressure pages to determine gas loss. A complete listing of valve lineups, temporuY Dage installations, and items removed from containment is included in Ref.1.

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BCP Technical Services, Inc.

Enter 0y Operations,Inc. Waterford 3 SES Reactor Containment Building ILRT Fine' Report items unable to withstand ILRT pressuro Aro removed from the containment. Those are identified in Ref.1. The breakers foodinD many equipment ltoms were racked (or locked) out to protect the containment against major water injections as well as to provent events which could invalidato leakage rato test results. A complete listing of breaker lineups is contained in Ref.1, Prior to pressurization, the insido and outsido surfaces of the conta!nment woro examined for evidence of structural datorioration which ml 0ht limit pressure retaining capacity.

All fans and containment li0hting were shut off prior to pressurization. This was done to eliminato point sources of heat which could offect the responso of the temperature measurin0i nstruments. Instrumentation was installed prior to containment closure.

A containment temperature / humidity survey was dono prior to final instrument placement to verify that si 0nificant temperature Oradients existed only in the sortical direction and that water vapor is un:formly dispersed throu0hout the containment. RTD and RHD locations woro specified on the basis of those assumed conditions. Wet and dry bulb temperatures woro O measured at soveral azimuths on the 4, 21, 40, and 95 foot levels, and at D both ends and the middle of the polar crano Ol rder catwalk.

Dry bulb tornporature was found to vary significantly only with clovation as assumed. Water vapor pressure as determined from wot and drybulb temperatures was found to be essentially constant throu0h out the containment, which confirmed the assumption of a uniform dispersion of water vapor. Survey numerical results are included in the offical test copy of Ref 1.

Local (type B and C)leaka00 rato tests woro completed prior to the start of the integrated leaka00 rate test. Results of alllocal tests performed since the first periodic ILRT are included in the Appendix.

3.2 Pressurization The containment was pressurized at a rate of about 4 psl/ hour usin0 oil froo compressors with an aggregato capacity of 13,550 SCFM. The dischar00 air was passed throu0h two trains of af tercoolor/ moisture separator units and refrigerated air dryers. Plant chilled water was used for cooling.

Pressurization air was dried to minimize the probability of moisture condensation in containment during the ILRT. Pressurization was stopped at 6

BCP Technical Services, Inc. I EntorDy Operations, Inc. Waterford 3 SES Reactor Containment Dulldin0 ILRT Final Report ,

O 40 psl 0. This allowed an adequate margin (2 psi) for pressure decay due to coolin0 of the air which had boon heated well above the equilibrium temperaturo during pressurization.

3.3 Test Measurements, Instrumentation and Air Mass Calculation  :

The containment atmosphoto condition data required to calculato leakaDe rate woro provided by two (2) vibrating cylinder mannmotors, forty (40) resistance temperaturo detectors (RTD) and ten (10) resistance humidity detectors (RHD). The performanco characteristics of those devices are listed in Table 2.1. The vibratin0 cylindor manomotors were connected to the containment atmosphere through a penetration dedicated to the leaka00 rate tost. Tho RTD's and RHD's woro hung at well dispersed clovations and azimuths within the containment. Tablo 2.2 identifies the locations of thoso devices.

Wiring from the RTD's and RHD's was connected throu0h containment O eiectricei nemoiretio" to comeitiomi"O e'ectro"ics iocetoo i" the retictor auxiliary buildin0. The vluratin0 cylinder manomotors were connected to the conditionin0 electonics via 20 ma current locps. Output from the conditionin0 electronics was connected to a multiplexor which was, in turn, wired to the plant computer. The temperature, relative humidity (R.H.) and pressuro data, in do0 roes Fahronhoit, % R.H. and psia units respectively, woro output by the piant computer to the ILRT computer (an IBM PC/ System 2), at fiftcon (15) minuto intervals via a serialinterface.

Water vapor pressure is datormined from temperaturo and R.H. data. Each RHD was installed adjacent to an RTD. The BCP Technical Services, Inc.,

ILRT program contains an algorithm to calculate the saturation pressure correspondin0 to the temperature indicated by the RTD. Partial pressure of the water vapor at the RHD/RTD location is datormined as the product of saturation pressure and R.H. The program than calculates volume weighted mean temperature and vapor pressure usin0 the wol0hting factors listed in Tablo 2.2. The mass of the air within the containment is computed usin0 equation (1) which is a formulation of the ideal gas law.

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BCP Technical Services, Inc.

Entergy Operations, Inc. Waterford 3 SES ,

Reactor Containment Building ILRT Final Report M = (P P,) V/RT (1)

Whero:

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

P = Absolute pressure of the alr/ water vapor mixture, Ib/sq. f t.

P, = Absoluto pressure of the water vapor, Ib/sq. ft.

V = Containment free air volume, cu. ft.

R = Gas constant for air, Ibf ft/lbm degroo R.

T = Volume weighted mean containment temperature, degree R.

Water vapor pressure is subtracted from total pressure in an effort to ensure that air mass and, consequently, leakage rate are not affected by evaporation or condensation.

The magnitude of the leakage induced during the verification test was measured using a float type flowmeter throttled at the output. The O characteristics of this device are listed in Table 2.1.

All instrumentation was 'aboratory calibrated prior to the test. Following installation of the RTD's and RHD's, in situ performance was checked to verify end to end system calibration. RTD performance was checked by inserting the sensing elements in an ice '" und verifying that the plant computer displayed a temperature within s (1) degroo Fahrenheit of the bath temperaturo. RHD performance was checked using a psychometer.

Dowpoint temperatures were calculated for the psychometer wet and drybulb readings and for the RTD and RHD readings displayed by the plant computer. The two dowpoint ternperatures woro verified to be within five (5) degrees Fahrenheit of each other.

Containment gage pressure was measured with a conventional dial type pressure gage. The performance characteristics of this gage are listed in Tablo 2.1 l

LO 8 er > -,---+-.-,w- -- -  % w -4.y y ..v-- >swwm--v--+- - ,, 7- e-g.e-rez. y-rw

DCP Technical Services, Inc.

Entor0y Operations, Inc. Waterford 3 SES Reactor Containment BuildinD ILRT Final Report 3.4 Leaka00 Rato Calculations l Leaka00 rbto was calculated usin0 both the total timo and the mass point methods. The mass point method, as described in Ref. O, defines leaka00 rato as the stopo of a tiial 0ht line fittod to air mass vs. timo data sets, by the method ot ! cast squaros. The total time method, as described in Ref. 5, is based on the promiso the leakago rato varios linearly with timo, and definos the loah 00 rato as the ordinato of the leaka00 rato versus timo at the end of the to it. The leaka00 rato versus timo line is fitted by the method of least squares to measured leaka00 rate /timo data sets. Monsured leaka00 rato for any timo, t,is the initial air mass (at t,) less the air mass at t, divided by (tet,).

Tho 95% upper confidence limit (UCL) on the calculated leakago rate must be loss than the acceptanco limit (0.375% mass loss por day). The UCL is always Orcator than the calculated lookage rato and increases with the scatter of the air mass data away from a strai0 ht line trend with timo. Tho 95% UCL is offectively described by the followin0 statomont, if the leaka00 rato test is performed a very lar00 number of timos under identical conditions,95% of the calculated leaka00 rates (no two of which will be exactly the samo) will be less than the 95% UCL*.

The test procedure requires the total time calculation. Results of the mass point calculation tre reported to provido additionalinformation.

• The derivation of total timo UCL in Ref. 5 introduces added conservatism into the calculation. What is referred to as a 95% UCL in that document does,in fact, provided a much higher (than 95%)

level of confidenco.

4.0 CHRONOLOGY AND EVENTS Containment preparation includin0 instrument installation and valvo lineups woro completed by 5:50 a.m. on May 10,1991. Prior to the start of pressurization RTD 29 was declared inoperablo due to cablin0 problems. RTD 29's volume fraction was equally distributed to the two (2) vertically adjacent RT9's 27 and 30.

Pressurization was started at 7:38 a.m., following final containment closure and

, si0n off of proceduro proroquisites. Pressurization was stopped at G:54 p.m. on the same day when pressure had reached 46 PSIG.

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DCP Technical Services, Inc.

Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Report O

During the temperature stabilation period, preliminary leakage rate calculations indicated excessive leakage of approximately 2.9 wt%/ day. The major portion of the leakage was observed at the refueling water storage pool access hatch. Air was leaking through thu Safety injection Sump Recirculation line valves SI G02 A and D. These valves are not classified as containment isolation valves and are not required to be vented for the ILRT por FSAR Table G.2 32. Initial hand tightening of the valves reduced the leakage to approximately 0.G wt%/ day. No other sl0nificant leakage paths were identified. At 4:00 p.m. on May 11, additional hand tightening of SI 602 0 reduced the leakage to approximately 0.0G wt%/ day.

The ci0ht (8) hour (minumun4) 'est period started at 5:30 p.m. on May 11 af ter verifyin0 that the temperature stabilization criteria (Ref. 5) had been satisfied durin0 the proceeding four (4) hour period. The test ended at 1:30 a.m. on May

12. Verification flow was established just prior to 1:45 a.m. The four (4) hour verification test was started at 2:45 a.m., following a mandatory one hour stabilization period (Ref 5), and ended at 6:45 a.m.

Containtnent depressurization started 8:17 a.m. The depressurization rate was maintained below G PSl/ hour to satisfy Ref.1 requirements. The containment was opened when zero pressure was reached at 0:15 p.m. on May 12, 5.0 TEST RESULTS The el0ht (8) hour (minimum) leaka0e rate test was started at 5:30 p.m. on May 11,1991. Temperature stabilization criteria were satisfied prior to the test as

.hown on Table 4.1. Temperature decay is illustrated graphically in Fi0 ure 4.1.

Containment pressure at the start of the test was 44.2 PSIG. All original test data is filed with the of ficial test copy of Ref.1.

5.1 Total Time Leakage Rate Containment leaka0e rate was quite small. The computed 95% UCL on the total time leaka00 rate was 0.0718 wt%/ day which is less than one fif th of the procedure acceptance limit of 0.375 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 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. Pressure and temperature decay during the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test are shown graphically on Figures 4.2 and 4.3 respectively. Air mass change is shown graphically on Figure 4.4, which is discussed later in Section 5.2.

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BCP Technicti Services, Inc, Entergy Operations, Inc. Waterford 3 SES Reactor Containment DulldinD ILRT Final Report O

The fire protection penotrations (60 and G1), thu ILRT pressurization lino penetration (03) and ILRT pressure senso lino penetration (65) woro not aligned in the speciflod post accident confl0uration durin0 the ILRT. The minimum pathway leaka00 throu0h those penotrations must be added to the total timo UCL to compensato for the nonconservativo valvo lineups. Those minimum pathway leaka00s are listed below. '

PENETRATION Looka00, SCCM GO 1G20 61 351 G3 710 G5 20 Total 2701 SCCM = 0.0013 wt%/ day Addir'g the total minimum pathway leaka00 to the calculated total timo 05%

UCL of 0.0718 wt%/ day yloids the adjusted total timo 95% UCL of 0.0731 wt %/ day.

Chan0cs in the accumulator pressures were too small to af fect leaknDo rato in the least sl0nificant figuro. Pressures are recorded in the official test copy of Ref.1. RCS level dropped only sli0 htly, but no correction for fallin0 ovel l is allowed. Sump and tank levels did not chan00.

Followin0 the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test, a 38 SCFM (equal to La = 0.5 wt%/ day) leak was imposed on the containment through a flowmotor followin0 a one hour stabilization period. The now leakago rate was determined for a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> test duration. The calculated total timo leaka00 rato of 0.5443 wt%/ day fell '

within the acceptanco limits of 0.4611 and 0.7111 wt%/ day as shown on Table 4.3. Successful completion of the verification test demonstratos the validity of the leaka00 rato computational methods The acceptance critorion for the verification test is stated as:

L,, + L. .2 5 L, .s;. L, .s;. L,, 4 _ L, + . 2 5 L, where:

L,, is the total timo leaka00 rato calculated for the 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> test = 0.0672 L,is the imposed leaka00 rata = 0.5189 O ,,

13CP Technical Services, Inc.

Entergy Operations, Inc. Waterford 3 SES Reactor Containment Dullding ILRT Final Report

'L,is the maximum allowablo Leakago rato = 0.500 L,is the rato calculated during the verification test it must be shown that the results of the leakapo rato tost would have bacri acceptable had the test boon performed prior to any topalts being modo during the localleakago rato testing program. This is shown by addin0 minimum pathway leaka00 improvements to the total timo 95% UCL. Total minimum pathway improvements sum to 20,324.5 SCCM which is equivalent to 0.0127 wt%/ day. Adding this to the total timo 95% UCL of 0.0731 wt%/ day (includes additions for penetrations 60,01,03 and 65) results in a theoretical as found (bofore repairs)leaka00 rate of 0.0858 '

wt%/ day. This is well below even the as left acceptanco limit of 0.375 wt%/ day. Localleaka00 rate test results aro includod in the Appendix.

• The leaka00 rato prior to a return to power must be loss than .75 La.

This allows 0.25 La for increases in leaka00 rato durin0 the operation cycles betwoon leakago rate tests.

C 5.2 Mass Point Leahaue Pate Mass point calculations generally provido a more realistic estimato of true leaka00 rate than do total timo calculations (total time, as defined in Raf. 5, is always applied to a test with a duration under twenty four (24) hours sinco the 95% UCL is a very conservativo upper bound on leakago rato).

Mass point results are listed below for information.

Mass Point calculated loakage rate = 0.0009 wt%/ day Mass Point 95% UCL = 0.0079 wt%/ day Mass Point verification upper limit = 0.7108 wt%/ day Mass Point verification calculated rato = 0.54G8 wt%/ day Mass Point verification lower limit = 0.4008 wt%/ day Completo mass point data is contained in Tables 4.4 and 4.5 Fl0ure 4.4 is a plot of air mass versus timo. The plot includes the line fitted to the mass data and a lino v"hich represents a leakago rato of 0.375 l

wt%/ day (0.75 La). The slope of the lino fitted to the mass data is tho l

calculated leaka00 rato. Figure 4.5 is a plot of air mass versus timo during the verification test. The plot includes the lino fitted to the mass data and lines representing the upper and lower acceptance limits on calculated O

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DCP Technical Services, Inc.

Entergy Operations,Inc. Waterford 3 SES Reactor Containment Dullding ILRT Final Hoport vorification leakago rato, in both figuros, the plotted air massos show very little di"crgenco about the fitted lino.

5.3 Shicid BuildinD Examination Referenco 3 requires that the exterior and interior surfaces of the shield building bo exarnined in conjunction with the ILRT to datortnino structural condition. The examination was performed prior to pressurtration No evidence of abnormal deterioration was found.

G.0 REFERENCES

1. Surveilla. co Proceduto PE-005 001, Containmont Integrated Leak Rato Tost, Revision 3,

2. Final Safety Analysis Report, Soction G.2.6 and 3.8.2.7.

Y

3. Technical Specifications, Soction 4.G.1.2 alb/c/f, 4.6.1.0 and 4.0.6.3. N

' O 4. Codo of Federal Regulations Titio 10. Past 50, Appondix J, Primary Reactor Containtnent Leakago Testing for Wator Cooled Power Roactors.

5. Dochtel Topical Report, BN TOP 1, Testing Critoria For Integrated -

Loakago Rato Testing of Primary Containment Structures for Nuclear Power Plants, Revision 1, November,1972.

G. ANSl/ANS SG.8 - 1981, Containment System Leakago Testing Requirements 7, (Referenco cited in Appendix J) ANSI N45.4 - 1972, Lankage Rato Testing Of Containment Structures for Nuclear Reactors.

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Enter 0y Operations, Inc. Wateiford 3 SES Reactor Containment BullJinD ILRT Final Report e

TABLES AND FIGURES O

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DCP Technical Services, Inc.

Enter 0y Operations, Inc. Watorford 3 SES m Reactor Containment Building lLRT Final Report b

TABLE 2.1

,t TEST INSTRUMENTAllON PERFORMANCE CHARACTERISTICS Precision Manomotor Make and Model: Volumetrics PPM 1000 Rango: 0-100 PSIA Absoluto Accuracy: 0.015% tcWjoy 4 .005% F.S.

Resolution: 0.0001 PSlit Resistance Temperaturo Detector 6 Make and Model: Burns WPPOG141/2-3 A Rango: Calibrated from 32 deproos Fahrenheit to 120 dc0rees Fahrenhelt-Absolute Accuracy: 0.1 degrees Fahrenheit Resolution: 0,01 de0rees Fahrenheit O

V Rosistance Humidity Detector Make and Model: PhysChem Research Model B Rango: 0-100% relative humidity Absolute Accuracy: 2% R.H.

Rosolution: 0.01 % R.H.

Flow Motor Make and Model: Brooks Model 111010K3B1 A l Range: 8 - 75 SCFM Absolute Accuracy: 1 % F.S.

l Pressuro Gage Make and Modol: Heise Model CM Ran00: 0100 PSIG l Absolute Accuracy: 1 % F.S.

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BCP Technical Services, Inc. l Enter 0y Operations, Inc. Waterford 3 SES  :

Reactor Containment BuildinD ILRT Final Report O

t TABLE 2.2 (1) (2) (3)

RTD/(RHD) El.,Ft. Rad. Ft. AZ, do0ree Volumo Fraction 1 195.0 7.5 20 .0271 2 176.5 23.0 140 .0281 I 3 170,0 28.5 260 .0273 4 158.5 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 128.5 49.5 340 .0288 O 12/(7) 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 .01'80 21 123.5 49.5 20 .0288 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 .0426 28/(10) 93.5 49.5 260 .0284 29 83.5 49.5 300 .0000 (5) 30 78.5 49.5 340 .0423 31 30 (4) 48.0 10 .0241 32 58.5 52.5 30 .0236 O 16

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DCP Technical Services, Inc.

Enter 0y Operations,Inc. Waterford 3 SES Reactor Containment Dullding ILRT Final Report TABLE 2.2 Continued (1) (2) (3)

RTD/(RHD) El. Ft. Rad. Ft. AZ, deurce Volume Fraction 33/(4) 53.5 49.5 70 .0236 34 33.5 57.5 110 .0201 35 G3.5 49.5 140 .0266 3G 43.5 64.0 200 .0201 37/(8) 3.5 G1.5 20 .0148 38 -1.5 49.5 70 .0129 39 -G.1 49.5 100 .0154 40/(9) 27.5 49.5 170 .0201 Ov Notes:

1. Reference elevations: Lowest level (-) 11 f t.; Sprin0 line ( + ) 138 f t.:

Top hemisphere (+) 208 f t.

2. Containment radius = 70 f t.

3. Containment free air volume = 2,677,000 cu. f t. All RHD's have volume fractions of 0.1.

4. RTD hun 0i n refueling cavity.

5. RTD 29 was inoperable. Its original volurne fraction of .0284 waa equally distributed between RTD's 27 and 30.

G. As lastalled elevations, radius, and azinluths aro + /. 3 ft., +/ 5 ft.

and + /- 5 degrees, respectively, l

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BCP Tech"ical Services, Inc. i Enter 0y Operctions, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Report '

TABLF 4.1 WATERFORD 3 - 1991 ILRT TEMPERATURE STABILIZATION REPORT Start Time = 1330 511

• = stabilization criterion satisfied AN31 BN TOP 1 data clapsed temperaturo dT1 dT4 dT1-dT4 dT or d(dT) set timo, hr T, dog F avo dT avgdT avg avg (1 hr) (4 hr) (2 hr) (2 hr) 1 0.00 77.267 2 0.25 77.253 3 0.50 77.243 4 0.75 77.233 5 1.00 77.218 -0.049 6 1.25 77.209 -0.044 7 1,50 77.200 -0.043 8 1.75 77.188 0.045 O' 9 2.00 77.181 -0.038 0.043' O.013' 10 2.25 77.174 0.035 0.039' O.007' 11 2.50 77.165 0.035 -0.039' O.002' 12 2.75 77.165 0.023 0.034' O.028' 13 3.00 77.161 -0.019 -0.028' O.011' 14 3.25 77.160 -0.014 0.025* 0.016*

15 3.50 77.155- 0.009 -0.022' O.015' 16 3.75 77.154 -0.011 -0.017' O.011*

17 4,00 77.151 0.010 -0.029 0.019' -0.015' O.007' O 18

BCP Technical Services, Inc.

Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment BuildinD ILRT Final Report TABLE 4.2 WATERFORD 3 - 1991 ILRT TOTAL TIME LEAKAGE RATE REPORT data timo date elapsed dry air measured leakago uct set time mass rato rate rate thrs) (Ibm) (%/ day) (%/ day) (%/ day) 17 1730 511 0.00 788408.89 0.0000 0.0000 0.0000 18 1745 511 0.25 788403.07 0 0708 0.0708 0.0708 19 1800 511 0.50 788396.59 s.0749 0.0749 0.0749 20 1815 511 0.75 788391.56 0.0703 0.0718 0.1059 21 1830 511 1.00 788387.13 0.0002 0.0678 0.0841 22 1845 511 1.25 788381.11 0.0676 0.0670 0.0775 23 1900 511 1.50 788372.84 0.0732 0.0695 0.0814 24 1315 511 1.75 788366.63 0.0735 0.0712 0.0818 ,

25 1930 511 2.00 788361.70 0.0718 - 0.0715 0.0807 26 1945 511 2.25 788357.99 0.0689 0.0706 0.0700 27 2000 511 2.50 788352.83 0.0683 0.0697 0.0775 28 2015 511 2.75 788342.60 0.0734 0.0708 0.0784 -

29 2030 511 3.00 788339.01 0.0709 0.0708 0.0779 O 30 2045 511 3.25 788330.47 0.0734 0.0715 0.0784 31 2100 511 3.50 788323.53 0.0742 0.0723 0.0789 32 2115 511 3.75 788320.46 0.0718 0.0723 0.0786 33 2130 511 4.00 788317.66 0.0694 0.0717 0.0780 34 2145 511 4.25 788310.68 0.0703 0.0715 0.0775 35 2200 511 4.50 788306.43 0.0693 0.0711 0.0770 36 2215 511 4.75 788304.19 0.0671 0.0703 0.0763 37 22?0 511 5.00' 788297.31 0.0679 0.0698 0.0757 38 2245 511 5.25 788290.11 0.0689 0.0696 0.0753 39 2300 511 5.50 788286.27 0.0679 0.0692 0.0748 40 2315 511 5.75 788281.23 0.0676 0.0689 0.0743 41 2330 511 6.00 788274.58 0.0681 0.0686 0.0739 42 2345 511 6.25 788270.90 0.0672 0.0683 0.0735 43 0 512 6.50 788266.36 0.0667 0.0679 0.0730 44 15 512 6.75 788258.78 0.0677 0.0678 0.0727 45 30 512 7.00 788251.21 0.0686 0.0677 0.0726 46 45 512 7.25 788249.22 0.0670 0.0675 0.0723 47 100 512 7.50 788239.49 0.0688 0.0675 0.0722 48 115 512 7.75 788241.12 0.0659 0.0672 0.0718 49 130' 512 8.00 788228.78 0.0685 0.0672 0.0718-Allowable leakage rate, La = 0.5000 %/ day 75% La - 0.3750 %/ day Total time leakage rate = 0.0672 %/ day

• Total time UCL = 0.0718 %/ day 19 i

- - , , - , - ,--r . y- , .,n-w 4,-., --.--e_.-, . i-,,-,,_.----_-_ ~ + . r

l DCP Technical Services, Inc. i Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment BuildinD LRT I Final Report  !

O  ;

l TABLE 4.3 l WATERFORD 3 1991 ILRT TOTAL TIME LEAKAGE RATE REPORT  :

VERIFICATION data tirno date clapsed dry air measured leakat,e set timo mass rato tato (hrs) (Ibm) (%/ day) (%/ day) <

54 245 512 0.00 788025.00 0.0000 0.0000 55 300 512 0.25 75/977.23 0.5937 0.5937

' 50: 315 512 0.50 787935.21 0.5528 0.5528 57 330 512 0.75 787890.43 0.5504 0.5440 58 345 -$12 1.00 -787830.98 0.5750 0.5590 59 400 512 1.25 787797.38 0.5509 0.5557 60 415 512 1.50 787752.91 0.5544 0.5520 1 61 430 512 1.75 787709.80 0,5502 0.5491 02 445 512 2.00 787J04.01 0.5503 0.5471 03 500 512 2.25 787015.00 0.5502 0.5481 64 515 512 2.50 787570.88 0.5544 0.5483 4 2.75 787525.38 0.5544 0.5480  ;

05 530 512 60 545 512 3.00 787483.53 0.5557 0.5477 l 67 000 b12 3.25 787442.59 0.5407 0.5400  :

68 015 512 3.50 787393.88 0.5500 0.5400 -

CD- 630 512 3.75 787350.19 0.5488 0.5451 70 045 512 4,00 787307.34 0.5472 0.5443 Upper limit on leakage rate = 0.7111 %/ day lotal timo leakago rate

• 0.5443 %/ day Lower limit on leakage rate - 0.4011 %/ day s

I 8

C 20 I-

,. d + s w a _

--.w

BCP Technical Services, Inc.

Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Report (q

c)

TABLE 4.4 WATERFORD 3 - 1991 ILRT MASS POINT LEAKAGE RATE REPORT data tirno dato elapsco dry air leakage uti set timo tuass rate rate (hrs) (Ibtn) (%/ day) (%/ day) 17 1730 511 0.00 788400,69 0.0000 0.0000 18 1745 511 0.25 788403.07 0.0708 0.0700 19 1800 511 0.50 788390.59 0.0749 0.0952 20 1815 b11 0.75 788301.50 0.0712 0.0782 21 1830 511 1.00 780387.13 0.0670 0.0735 22 1845 511 1.25 788381.11 0.0007 0.0700 23 1900 511 1.50 788372.84 0.0702 0.0751 24 1915 511 1.75 788300.63 0.0722 0.0703 2b 1930 511 2.00 788301.70 0.0723 0.0754 20 1945 511 2.25 788357.99 0.0708 0.0737 27 2000 511 2.50 788352.83 0.0097 0.0723 28 2015 511 2.75 788342.00 0.0711 0.0738 29 2030 511 3.00 780's39.01 0.0711 0.0733

(,)

30 2045 511 3.25 788330.47 0.0720 0.0741 31 2100 bil 3.50 788323.53 0.0729 0.0750 32 2115 511 3.75 788320.40 0.0728 0.0745 33 2130 511 / 00 780317.00 0.0719 0.0737 34 2145 511 4.25 788310.68 0.0715 0.0731 3b 2200 511 4.b0 788300.43 0.0709 0.0725 36 2215 511 4.75 788304.19 0.0099 0.0710 37 2230 C.11 5.00 788297.31 0.0093 0.0710 38 2245 511 b.25 788290.11 0.0000 0.0706 39 2300 511 5,50 788280.27 0.0080 0.0701 40 2315 511 5.75 788281.23 0.0682 0.009G 41 2330 511 0.00 786274.r,8 0.0080 0.0093 42 2345 511 0.25 788270.90 0.0677 0.0689 43 0 512 G.50 788206.30 0.0673 0.0685 l 44 15 512 0.75 788258.78 0.0072 0.0083 i

45 30 512 7,00 788251.21 0.0673 0.0683 40 45 512 7.25 768249.22 0.0071 0.0081 47 100 512 7.50 788239.49 0.0672 0.0061

48 115 51? 7.75 788241.12 0.0S08 0.0678

! 49 130 512 8.00 788228.78 0.0009 0.0679 Allowable leaka0'; rato, La = 0.5000 %/ day 75% La - 0.3750 %/ day Mass point leakage rato u 0.0009 %/ day Mass point UCL ~ 0.0679 %/ day 21

I BCP Technical Services, Inc.  ;

Enter 0y Operations, Inc. Waterford 3 SES Reactor Containment BuildinD LRT I Final Report l

TABLE 4.5 l

WATERFORD 3 1991 ILRT MASS POINT LEAKAGE RATE REPORT VERIFICATION f data timo date elapsed dry air leakage set time mass rato (hes) (Ibm) (%/ day) 54 245 512 0.00 783{/ %.90 0.0000 787977.23 l 55 300 512 0.25 0.5937 50 315 512 0.50 787935.21 0.b528 57 330 512 0.75 787EU.43 0.5405.

58 345 512 1.00 787830.98 0.5002 59 400 512 1.25 787797.38 0.5598 i 60 415 512 1.50 787752.91 0.5550 01 430 512 1.75 787709.80 0.5513 02 445 512 2.00 787004.01 0.5493 03 500 512 2.2b 787015.00 0.5512 04 515 512 2.50 787570.86 0.5517 530 512 2.75 787525.38 0.5520 A 05.

545 512 3.00 787483.53 0.5509

~V 00 07 000 512 3.25 787442.59 0.5480 08 015 512 3.50 787393.88 0.5483 09 030 512 3.75 787350,19 0.6477 70 045 512 4.00 787307 34 0.5408 Upper limit on leakage rate - 0.7108 %/dsy Mass point leakage rata = 0.5408 %/ day Lower limit on leakage rate = 0.4008 %/ day L

22

f~} Q .c .

ifB'8-

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FIGURE 4.1 TEMPERATURE STABILIZATION

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58.910 E s E-

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1730 IIME 130 ,

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FIGURE:4.2 IEST PRESSURE vs TIME-6 b

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77.100 i , , , , i i i 1730 IIME 130 511 DATE 512 FIGURE 4.3 IEST TEMPERATURE vs IIME i

i

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-, < g 98 ii 14ATERFORD 3 - 1991 ILRT AE5 788500 ((m e.

a_2a-G $

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787000 e 1730 IIME 130 511 DATE 512 FIGURE 4.4 AIR MASS vs. TIME

() O U (v3

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245 IIME 645 512 .DATE 512 FIGURE 4.5 UERIFICATION AIR MASS vs. TIME-

BCP Technic:1 Ssrvices, Inc.

Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Report O

APPENDIX l LOCAL LEAK RATE TEST RESULTS O

E ry 28

Entergy operations, Inc. Waterford 3 SES.

Reactor Containment 8uilding ILRT__ Final Report Appendix 1 TYPE 8 LOCAL LEAK RATE TEST

SUMMARY

ELECT. AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCH) (YYMMDD) (SCCM) (YYMMDDJ 101 NA 3.0 891001 3.0 891001 0.43 910325 0.43 9'0325 102 NA 5.5 891001 5.5 1 12.8 910325 12.8 J 104 NA 7.3 891001 7.3 891001 e 0.15 910323 0.15 910323 106 NA 5.5 -891001 5.5 891001 0.22 910323 0.22 910323 107 NA 0 891004 0 891004 0.96 910329 0.96 910329 108 NA_ _7.3 891001 7.3 891001 0 910323 0 910323 109 NA 3.6 891001 3.6 891001 l

1.0 910325 1.0 910325 110 NA: 1.8 890926 1.8 890926 0 910323 0 910323 111 NA 3.1 890928 3.1 890928' O.12 910328 0.12 910328 112 NA 2.9 890928 2.9 890928 l.84 -910328 1.84 910328 113 NA 2.1 890928 2.1 890928 0.22 910329 0.22 910329 l ..

! 114 NA 0 890926 0 890926 l 0 910319 0 910319 l' 115 NA 0 890926 0 890926 0 910319 0 910319 g 116 NA 0 890926 0 890926 l 0 910319 0 910319 117 NA 1.9 890926 1.9 890926 1.2

_O 1.2 910323 910323 29

, . . = _ _ - . - - - . - . - . . - .. -- . . - - - - - . _ _ _ -

. , . . _ , - . ~ . . - . - - ~ - - - - - . ~ - ~ . . ~ . . . - . - ~ . . . ~ ~ - - - - . - . . . .

() Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Report Appendix I-TYPE 8 LOCAL LEAK RATE TEST

SUMMARY

- ELECT. AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 118 NA 3.8 891001 3.8 891001 0.04 910325 0.04 910325 119 NA 0 890926 0 890926 0.1 910319 0.1 910319 120 NA 0 890925 0 890925 0.1 910320 0.1 910320 121 NA 1.9 890929 1.9 890929 4.5 910326 4.5 910326 122 NA 2.0 890927 2.0 890927 1.6 910321 1.6 910321 123 NA 3.6 890926 3.6 890926

0.11 910322 0.11 910322 I-124 NA 2.0 890928 2.0 890928 0.36 910327 0.36 910327 125 NA 0 890927 0 890927 0.34 910321 0.34 910321 126 NA 2.0 890928 2.0 890928 0 910329 0 910329 127 NA 2.3 890928 2.3 890928 0 910327 0 910327 128 NA 0 890925 0 890925 0 910320 0 910320 l

129 NA 0.3 890925 0.3 890925 0 910320 0 910320 130 NA 0 890927 0 890927 l

0 910321 0 910321 131 NA 4.1 890926 4.1 890926 0.11 910322 0.11 910322 132 890926 890926 0 NA 4.1 0 910322 4.1 0 910322 30 i

,,re. . . . - - , y ~ --.w.,r. y -.-.( --. , -

- . . . ~ - . . - - - . . - . - . - . ~ _ - . .

Entergy' Operations, Inc. Waterford 3 SES

-Reactor Containment Building ILRT Final Report Appendix I TYPE B LOCAL LEAK P. ATE TEST

SUMMARY

ELECT. AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 133 NA 0 890928 0 890928 0.06 910327 0.06 9103 134- NA 5.5 891001 5.5- 891001 0 910326 0 910326 135 NA 0.3 890925 0.3 890925 0.1 910320 0.1 910320 136 NA 1.5 890925 1.5 890925 0 910320 0 910320 1

137-- NA 2.3 890929 2.3 890929 0.38 910326 0.38 910326

_138_ NA _2.4 891002 2.4 891002 O 910323 0 910323 139 NA 2.3 890929 2.3 890929 0 910326 0 910326 140 NA 2.3 890927 2.3 890927 0.7 -910321 10.7 910321 141 NA 2.3 890928 2.3 890928 0.12 910328 0.12. 910328 142- NA 0 890927 0 890927-0 910321 0 910321 143 NA 0 890928 0 890928 0.12 910327 0.12 910327 144 JNA 3.6 890928 3.6 890928 3.91 910328 3.91 910328 145 NA 0.3 890925 0.3 890925 0.05 910320 0.05 910320 146 NA 0 890926 0 890926 0 910319 0 910319 147 NA 2.4 890929 2.4 890929 l

O

• O 910325 0 910325 31

. ..-.__...-__...--..m.-_-.- . - - - _ . _ _ _ - . .. ._ .-____m.- m.. m __ .

O Entergy Operations, Inc. Waterford 3 SES

~ Reactor Containment Building ILRT Final-Report Appendix I TYPE B LOCAL LEAK RAT 2 TEST

SUMMARY

AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 148 NA 2.3 890929 2.3 890929 0.05 - 910326 0.05 910326 149 NA 2.3 890928 2.3 890928 0 910328 0 910328 151 NA 0 890927 0 890927 0 910320 0 910320 0

0 32

. -. . _ - - . . . . - - . . . - . . . - - . - ~ - - . . - . . . - . - . ,~ . - . . ..,.:...-- .

.1 O,

~

Entergy Operations, inc. Waterford 3 SES Reactor containment Building ILRT Final Report Appendix I TYPE B LOCAL LEAK RI.TE TEST

SUMMARY

AS FOUND DI.TE AS LEFT DATE PEN NO. BELLOW (SCCM) (YYMMDD) (SCCM) (YYMMDD)_

1 MS-1 20 891002 20 891002 533 910321 533 910321 2 MS-2 41 891010 41 891010 62 910409 62 910409 3 FW-1 40 893011 40 891011 49 -910409 40 910409 ,

4 FW-2 28.8 891010 28.8 891010 l 40 910409 40 910409 l l

25 FUEL XFER 20 891102 20 891102 TUBE 473 910326 473 910326 32- SI-602A 0 891003 0 891003 795 910318 795 910318 1 33- SI-6028 0 891003 0 891003 24 910318 24 910318 43 BM 0 891003 0 891003 38 910318 38- 910318 l'

l~

'1 33 1

.- . . . . . . . _ _ . _ _ _ _ _ _ . _ . , _ . . . - . - _ . . _ _ . _ , __- . . _ _ _ ._ .m. . _ _

Entergy Operations, Inc. Waterford 3 SES l ' h' N-s - ' Reactor Containment Building ILRT Final-Report Appandix I TYPE D LOCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE AS LEFT DATE pESCRIPTION (SCCM) (YYMMDD) (SCCM) (YYMMDD)

.?UEL XFER TUBE BLIND 86 891103 86 891103 g FLANGE "O" RING 20 910501 20 910501 l

MAINTENANCE HATCH 4 880521 4 880521 GASKET INNERSPACE O 881028 0 881028 2.5 881106 78 881114 3 891111 3 891111 2.53 900201 2.53 900201 4.3 901013 4.3 901013 8.7 910316 8.7 910316 20 910509 20 910509 l PERSONNEL AIR LOCK 35,150 880521 35,150 880521 9600 881029 9600 881029 13,605 890419 13,605 890419 28,000 890717 28,000 890717 0 890811 0 890811 0 900420 0 900420  !

. 1054 900920 1054 900920 4030 910307 4030 910307 7720 910506 7720 910506 ESCAPE AIR LOCK 0 880513 0 880513 2600 881028 2600 881028 512 890418 512 890418 0 891109 0 891109 60 900418 60 -900418 920 900921 920 900921 1001 910308 1001 910308 460 910503 460 910503 34

- . . . _ - . _ _ . _ . , . _ . . _ . _ _ _ . . _ - - . . . - - - _ . . _ . _ . . _ _ _ . _ . = _ . . . . _ ._._ ______

.t Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT-Final Report Appendix'I-TYPE C LOCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE AS LEFT DATE PEN NO.. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 7 PMU-151- 15.5 8909?5 15.5 890925 40 910319 40 910319 PMU-152 6.5 890925 6.5 890925 2- 2. 910318 2.2 910318 8- SA-908 20 891030 20 891030 1100 910326 35 910426 SA-909 3060 891030 1460 891107 1100 910326 1100 910326 9 IA-910 20 891029 20 891029 125 910424 125 910424 IA-909 740 891029 740 891029 811 910424 706 910424 10 CAP-103/ 17,000 880518 17,000 880518 CAP-104 16,500 880825 16,500 880825 11,100 8d1027 11,100 881027

\ 355,000 890127 48,000 890128 94,600 890512 18,700 890513 20,300 890921 20,300 890921 221,600 - 891101 16,000 891104 18,880 891107 18,880 891107-13,600 900129 13,600 900129 15,190 900501 15,190 900501 4180 901009 .4180 901009 16,730 910108 16,730 910108 12,470 910425 12,470 910425 11- CAP-203/ 400 880518 400 880518 CAP-204- 1500 880825 1500 880825-1300 881027 1300 881027 1100 890127 1100 890127 375 890512 375 891512 500 890715 500 890715

>400,000 891102 506 891107 1000 900131 1000 900131-717 900501 717 900501 92.8 900816 92.8 900816 523 901009 523 900109 1208 900110 1208 910110 685 910501 685 910501 O

35

..._.__.___....__._._._.___.__._._.-__._.-._-__....m. .

h

) Entergy Operations, Inc. Waterford 3 SES Reactor Containment-Building ILRT Final Report tppendix I TYPE C LOCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 12 CVR-101 170 891004 170 891004 666 910329 666 910329 12 CVR-102 70 891004 70 891004 82 910329 82 910329 13 CVR-201 10,800 890927 2120- 891108 2280 910320 2120 910504 CVR-202 7900 890927 .270 891106 207 910320 25 910504 14 NG-157 142 890927 142 890927 2770 910320 155 9106.20 NG-158 28 890927 28 890927 2250 910320 170 910420 23 CC-641 171,700 891007 350 891101 478 910325 478 910325

' #~

l

/ CC-644 300,000 891007 4560 891031 j- 5070 910325 20 910420

'24 CC-710 11,500 891007 55 891104 20 910328 20 910328 CC-713 810 891007- 810 891007 256 910328 256- 910228 26 CVC-103 180 891005 180 891005 21.5 900130 21.5 900130-653 910323 653 910323 CVC-109 2600 881030 2600 881030 1272 891005 1272 891005 18,560 910323 2210 910429

-28 PSL-105 20 891002 20 891002 L -

20 910320 20 910320 PSL-107 20 891002 20 891002 20 910320 20 910320 29 PSL-203 267 890928 20 891017 10,020 910320 21 910423 PSL-204 13,210 890928 20 891017 L 27,500 910320 20 910502 l=

30 PSL-303 54,100 890929 25 891021 0 13,270 910323 72 910424 l 36 l

l i- _ __ ._ _ _ __, __ ~ . _ _ _, _ -

Entergy Operations, Inc. Waterford 3 SES

~\se Reactor Containment Su11 ding Ti.RT Final Report

' Appendix I TYPE C LwCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE AS LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 30 PSL-304 243,700 890929 2030 891021 27.5 900323 27.5 910323 31 GWM-104 4200 890928 3680 891107 917 910321 290 910426 GWM-105 3800 890928 3630 891107 901 910321 170 91042G 42 SP-105 20 890930 20 890930 20 910420 20 910420 SP-106 20 890930 2s 890930 20 910420 T.0 910420 43 BM-109 20 891003 20 891003 60.2 910329 60.2 910329 B11-110 20 891003 20 891003 20 910329 20 910329 44 RC-606 20 890930 20 890930 20 910321 20 910321 CVC-401 20 890930 20 890930 20 910321 20 910321 45 CAR-101B- 100 891004 100 891004 20 910327 -20 910327 CAR-102B 20 891004 20 891004 20 910327- 20 910327 46 CAR-101A 20 891004 20 891004 20 910327 20 910327 CAR-102A 20 891004 20 891004 20- 910327 20 910327

.47 CAR-200B/ 850 890928 685 891103 CAR-201B/ 13,000 910326 560 910416 CAR-202B 48 CAR-201A/ 100 890928 112.5 891109 CAR-202A 150 910327 155 910416 49A ARM-109 12 890925 12 890925 85 910321 85 910321

[

l ARM-110 12 890925 12 890925 l

85 910321 85 910321 37

Entergy Operations, Inc. Waterford 3 SES Reactor Containment Building ILRT Final Peport Appendix I TYPE C LOCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE \S LEFT DATE PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD1 498 ARM-103 9 890925 9 890925 84 910321 84 910321 ARM-104 92 890925 92 890925 233 910329 233 910329 51 FS-405 1150 891105 1150 891105 _

2950 910430 100.5 910506 FS-406 880 891105 880 891105 990 910430 990 910430 59 S1-343 180 891002 180 891002

~ 20 910429 20 910429 SI-344 0 891002 0 891002 20 910429 20 910429 60 FP-601A 2400 890929 4240 891108 2055 910422 2055 910422 FP-602A 262,000 890929 750 891108 O 3070 910422 1620 910426 61 FP-601B 40 890930 40 890930 635,440 910319 4059 910412 FP-602B 250,000 890930 175 891108 4600 910319 351 910412 62 FS-415 173,000 891106 20 891106 35 910327 35 910327 FS-416 173,000 891106 20 891106 45 910327 45 910327 63 LRT-109/ 890 891106 890 891106 BLIND FLANGE 20 910317 1420 910513 65A LRT-201 17 890923 17 890923 20 910318 20 910513 LRT-202 17 890923 17 390923 20 910318 20 910513 65B LRT-203 11 890923 11 890923 20 910318 20 910318 LRT-204 11 890923 11 890923 20 910318 20 910318

( 66A HRA-109A 0 890927 0 89092i 38

\

Entergy Operations, Inc. Waterford-3 SEs O- Reactor Containment Building ILRT Final Report-

. Appendix 1 TYPE C LOCAL LEAK RATE TEST

SUMMARY

AS FOUND DATE AS LEFT DATE

- PEN NO. VALVE NO. (SCCM) (YYMMDD) (SCCM) (YYMMDD) 66A HRA-109A 25 910323 25 910323 '

HRA-110A 0 890927 0 890927 '

19.5 910323 19.5 910323 66B HRA-126A 20 890927 20 890927 245 910325 245 910325 HRA-128A 31 890927 31 890927 630,697 910325 850 910415 67A ~ HRA-1098 7.5 890927 7.5 890927 1100' 910323 1100 910323 HRA-110B 7 890927 7 890927 1100 910323 1100 910323

.678 HkA-126B 20 890927 20 890927 4.8 910323 d.8 910323 HRA-128B 21,400 890927 20 891018 1100 910323 1100 910323 71 CMU-244 ' 4 .1 891009 0.2 891105 199 910415 199 910415 CMU-245 20 891009 20 891009 8350 910415 8350 910415 U

39 l

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