ML20073S786

Reactor Containment Bldg Unit 1 Preoperational Integrated Leak Test,1983

ML20073S786
Person / Time
Site:	Comanche Peak
Issue date:	12/31/1983
From:	TEXAS UTILITIES SERVICES, INC.
To:
Shared Package
ML20073S780	List: ML20073S786 TXX-3664, Forwards Reactor Containment Bldg Unit 1 Preoperational Integrated Leak Rate Test,1983. Electrical Penetrations Leaked Excessively During Testing.Further Testing to Determine Cause of Leakage in Progress
References
NUDOCS 8305100135
Download: ML20073S786 (33)

Text

-

COMANCHE PEAK STEAM ELECTRIC STATION o

REACTOR CONTAINMENT BUILDI!!G UNIT ONE PREOPERATIONAL INTEGRATED LEAK RATE TEST 1983 DOCKET NUMBER 50-445 TEXAS UTILITIES GENERATING COMPANY h

0305100135 030506 PDR ADOCK 05000445 R,

PDR

ILRT Test Summary 1.0 Introduction 1.1 General Data:

The Comanche Peak Steam Electric Station (CPSES) Unit 1 preoperational Containment Integrated Leakage Rate Test was conducted during the period from January 18, 1983 to February 2, 1983.

Both a reduced pressure and a peak pressure test were conducted in accordance with 10CFR50, Appendix J, Reactor Containment Leakage Testing for Water Cooled Power Reactors.

1.2 Technical Data:

The containment building at CPSES is a reinforced concrete structure with a carbon steel liner.

The structure contains a net free volume of 2,919,893 cubic feet. The design pressure is 50 psig and the calculated peak accident pressure is 48.1 psig. The design temperature is 120'F and the calculated peak accident temperature is 280*F.

The Technical Specification limit for the containment leakage (La) is 0.1 percent by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at pressure Pa (48.1 psig).

2.0 Test Summary The Comanche Peak Steam Electric Station Unit One preoperational containment Integrated Leak Rate Test (ILRT) was conducted concurrently with the Structural Integrity Test (SIT) as shown on Figure 1.

Immediately prior to closing the containment building for the SIT /ILRT test, a pre-test containment survey was conducted to ensure the building was properly prepared for the tests.

No deficiencies were found during this inspection. The containment was pressurized for the SIT in five (5) increments to a peak pressure of 57.5 psig.

The containment was subsequently depressurized to 12.5 psig to allow personnel entry to check for leakage on the steam generators.

A number of instrument valves were found to be leaking and were reclosed to better seat the valves and stop the leakage.

After completing the entry, the containment was pressurized to Pt (24.05 psig) for the reduced pressure test.

Both reduced pressure and full pressure tests were conducted to meet 10CFR50, Appendix J requirements. A temperature stabilization period of approximately five hours preceded the reduced pressure leakage measurement.

Leakage data was taken for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> at Pt to ensure sufficient data was contained for a reliable test indication. The resultant leakage rate Lem was 0.02026%/ day and the upper confidence limit (UCL) was 0.02559%/ day.

At the end of the reduced pressure test, a verification test was performed by superimposing a known leak of Lt for approximately eight hours.

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The containment pressure was next increased to Pa (48.1 psig) for the peak pressure ILRT. A temperature stabilization period of five hours was allowed prior to taking leakage data. The leakage measurement was started but was terminated after about nina hours when it became apparent the leakage rate was excessive. The containment was again depressurized to 12.5 psig to allow entry.

A number of valves, packings, and fittings on the steam generators were found to be leaking and were tightened.

The containment was repressurized to Pa to start another leakage measurement.

Another five hour temperature stabilization preceded the leakage measurement and the test was once again terminated af ter about 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br /> due to an excessive leakage rate. The containment was completely depressurized this time to allow more time for leak repairs. All four steam generators were thoroughly checked and various leaks repaired on instrument lines on the generators. Also, the ventilation penetrations were local tested to ensure that leakage through them was not the problem.

After about sixteen hours at atmospheric pressure, all checks and repairs were completed and the containment once again pressurized to Pa.

This time a six hour temperature stabilization period preceded the leakage measurement. The leakage data was taken for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> and the resultant leakage rate Lam was 0.05579%/ day and the UCL was 0.05936%/ day. Then the verification test was started by super-imposing a known leakage of La.

The verification test was delayed about three hours due to a computer software error which incorrectly limited the superimposed leak. This error was found and corrected and the verification test completed after six hours. Jhe containment was then depressurized to 5 psig for a Hydrogen Purge System preoperational test and then to atmospheric pressure to complete the ILRT.

After complete depressurization of containment, a post-test survey was conducted to check for any possible damage or abnormal conditions.

No deficiencies were found during this inspection.

During the reduced pressure test, an electrical penetration was observed to be leaking excessively and its vent path was isolated.

This penetration was left isolated during the peak pressure test also.

Additionally, two more electrical penetrations were found leaking during the peak pressure test and their vent paths isolated. After the ILRT, the penetrations were pre-repair local leak tested.

Penetrations E-49 and E-68 showed a minimal leakage rate, while penetration E-62 was 118 SCCM.

Penetration E-62 was repaired and the post-repair leakage was less than 2 SCCM, which is acceptable.

Penetrations E-49 and E-68 low leakage rates indica:e a uni-directional leakage path since the local leak rate test is conducted in the opposite direction of the ILRT.

These two penetrations have high voltage power cables in them whereas the other penetration, E-62, which was repaired, has smaller control cables in it.

A determination of the leakage mechanism in these two penetrations has as yet not been determined.

Further testing is forth coming and the results and necessary repairs will be a supplement to this report.

No other penetrations, electrical or mechanical, required isolation during the conduct of the ILRT.

2

3.0 Plant Conditions During the ILRT, the plant was maintained in a mode similar to that which would be expected during a periodic ILRT. To simulate post accident conditions, all systems that would not be expected to be fluid filled post accident were drained and vented to the containment atmosphere.

The containment recirculation cooling units were in service to support ILRT testing and their corresponding penetrations were not drained or vented. The local leakage rate values for these two penetrations are additions to the measured UCL.

The reactor coolant system (RCS) was filled to a level of 35 percent in the pressurizer and the RCS was vented to containment through the pressurizer power operated relief valves.

One train of the residual heat removal (RHR) system was in recirculation to the RCS to simulate core cooling and to provide letdown for the reactor coolant pump seal injection system which was in service.

During the entire test, the containment recirculation fans, whose blade pitch had been reset for the denser air, were in operation to provide containment atmosphere mixing. This resulted in a very small variation between temperature and dewpoint readings throughout the containment.

To prevent the introduction of temperature variances during the ILRT, the chillers for the cooling water to the containment recirculation fans were secured.

All pressurized tanks, i.e. accumulators were depressurized and vented during the ILRT. Also, all compressed gas sources were removed from the containment, including fire extinguishers.

The electrical penetrations, which normally have 60 psig nitrogen gas applied between their seals, were depressurized to ensure no leakage of the nitrogen into the containment building. Each penetration was vented to atmosphere to provide a leakage path should the seals in the penetration assembly leak.

As an added precaution against possible fires, all equipment in the containment building not needed for the test was de-energized from outside the containment building. Also, all lighting in containment was turned off during the test.

4.0 Pressurization System The containment was pressurized through an ILRT dedicated penetration, MIII-30.

This is a twelve inch penetration through which the containment was both l

pressurized and depressurized.

See Figure 2 for an illustration of the l

pressurization system.

!1.

A fleet of air compressors was used to supply the pressurization air.

The air l

compressors were arranged in two banks, each of which connected to a coalescing filter for hydrocarbon removal.

These were connected to a pair of air dryers which conditioned the incoming air to maintain a 40*F dewpoint. The two dryers l

were connected to a common desister and then through an eight inch line to l

penetration MIII-30. Also attached to this eight inch line is a blowdown silencer for use when depressurizing the containment.

Inside the containment, a flow diverter was attached to the penetration to prevent the high velocity air flow from impinging on any equipment.

3 i

r 5.0 Instrumentation System The instrumentation system for ILRT was based around a mini-computer controlled data acquisition system (DAS), see Figure 3.

The DAS is capable of reading all sensors rapidly, storing the information and then outputting to the mini-computer for conversions and calculations on the data.

A system of 13 deweells and 42 resistance thermometer devices (RTD) was installed throughout the containment as shown on Figures 4 through 8.

These locations were selected to provide thorough coverage of the containment in order to provide an accurate representation of wet bulb and dry bulb temperatures.

Each sensor was assigned a volume fraction and the containment average wet bulb and dry bulb temperatures were then computed. Just prior to closing the containment building for the ILRT, a temperature survey was conducted. This survey verified that the location of the temperature sensors was correct for each of the assigned volume fractions.

Connected to containment penetration MV-7 were two precision quartz pressure gauges to provide the containment total pressure. The total pressure less the vapor pressure, with temperature corrections, provides a corrected containment pressure.

Also connected to the DAS were an RTD, a dewcell and a barometer for monitoring the atmospheric conditions outside the containment building.

Two mass flowmeters were connected to the DAS to provide an indication of the-superimposed leakage during the flow verification test, see Figure 9.

There were no instrument failures during the ILRT.

6.0 Instrument Selection Guide The guidelines of ANSI /ANS-56.8-1981, Containment System Leakage Testing Requirements, were used to select the instruments for the ILRT.

In addition, the formula from the Instrumentation Selection Guide (ISG) was used during the ILRT to ensure that the data acquisition system accuracy was sufficient to provide reliable test results.

This formula utilizes the systematic error of each sensor to determine an overall value for the system. At the start and end of each test, the ISG value was acceptable if it did not exceed 0.25 La.

7.0 Calculation of Leakage Rate 7.1 Leakage Rate Test:

l The method chosen for leakage rate calculation was the Absolute Method as recommended by both ANSI N45.4-1972 and ANSI /ANS-56.8-1981. This t

calculational technique was applied to the " mass-plot method" to determine l

the containment leakage rate.

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4

In the mass-plot method the' air mass inside containment is determined absolutely, utilizing the ideal gas law, at each time point and a least squares analysis is used to estimate the leakage rate.

For each time point (ti), the corresponding mass of contained air (Wi) is determined directly from the ideal gas law:

Wi = 144V (Pi - Pvi)

R T1 V - Containment free air volume R - Gas constant for air P - Containment total absolute pressure Pv - Containment water vapor partial pressure T - Containment mean absolute temperature The linear least squares fit of the total number (n) of mass points is given by:

Wi = Ati + B Where the slope (A) and intercept (B) are given by:

n (EW t ) - (EW ;) (Et,)

i g n(It2 ) _ (gg ;)2

(

and E

(IW ) (Et ; ) - (It W ) (Et )

g g g y

n(Et [) - (It )2 g

The leakage rate is then expressed as the ratio of the rate of change of mass and the mass in containment at time ti=0; s

Lam = (-2400) (A/B) %/ day A = Mass rate of change B = Initial contained mass

- 2400 Converts to %/ day The Upper Confidence Limit (UCL) is established such that there is only a five percent probability that the actual leakage rate exceeds the UCL value. This value is approximated by:

UCL = Lam + 2400 t.95 SA/B t.95 = 95th percentile of Student's t distribution SA = Estimate of the standard deviation of A i

5

7.2 Supplemental Test:

The supplement test was conducted by superimposing a known leak onto the existing leak. The known leak (Lo) was in the range of Lt or La as appropriate. The supplemental test is acceptable provided that the composite leakage (Lc) is within 0.25Lt or !0.25La of the sum of the measured leakage Ltm or Lam and the superimposed leakage Lo.

8.0 Data Analysis The results of both the reduced pressure and peak pressure ILRT's are tabulated in Appendix A and B respectively.

During the test, data was taken at fifteen minute intervals to provide sufficient data for a good confidence level.

8.1 Reduced Pressure Test:

After pressurization to 24.05 + 1.0 - 0.0 psig a temperature stabilization period was started which lasted approximately five hours. The containment atmosphere was considered to be stable when the last hourly average temperature was less than 10.5*F different from the average temperature over the last four hours.

The ILRT measurement was begun and lasted for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

The reduced pressure test resulted in a measured leakage rate (Ltm) of 0.02026%/ day with an upper confidence limit (UCL) of 0.02559%/ day. Adding the penalty leakages, Appendix D, does not alter the UCL since the penalty leakages are so small. The UCL of 0.02559%/ day is less than the allowable leakage 0.0272%/ day (0.75Lt).

Lt was determined by the formula from 10CFR50, Appendix J:

Lt = La (Ltm/ Lam)

Lt = 0.1%/ day (0.02026/0.05579)

Lt = 0.036315%/ day The reduced pressure test is therefore acceptable since the UCL is less than 75 percent of the allowable reduced pressure leakage (Lt).

l A verification test was subsequently performed by superimposing a leakage rate (Lo) of approximately Lt.

The resulting to was 0.06864%/ day with a composite leakage (Lc) of 0.09482%/ day.

The acceptance criteria for the composite leakage (Lc) is:

1 Lc = (Lo + Ltm) ! 0.25Lt %/ day Lc = (0.06864 + 0.02026) ! 0.25 (0.036315) %/ day Lc = 0.08890 0.0091%/ day or l

0.07982 6 Lc 6 0.09798 6

The verification test is therefore acceptable since the composite leakage Lc (0.09482%/ day) is within the required values, and this then provides confidence that the data acquisition system is functioning properly.

8.2 Peak Pressure Test:

The containment was pressurized to 48.1 + 1.4 - 0.0 psig for the peak pressure test.

The first test was terminated early due to excessive steam system boundary leakage.

The containment was again pressurized and during the conduct of the second peak pressure test it was noted that there were large variations in containment air mass occurring. Upon examining the raw data, it was observed that humidity element (HE) number 10 was varying several degrees. These changes were occurring at the same times as the large air mass changes. Upon checking the volume fraction assignments, it was noted that HE-10 was assigned 56.8 percent of the total containment volume.

This large volume fraction was causing the large air mass changes to occur in accordance with HE-10 changes. The volume fraction was reassigned such that four other groups received a portion of the volume fraction leaving HE-10 with a m:te representative volume. The computer program was updated to reflect these changes and no further problems were observed.

See Appendix C for the volume fractions.

The second peak test was also terminated early due to an excessive leak rate. After complete depressurization for repairs, the containment was again repressurized to peak test pressure and the temperature stabilization period begun. The containment atmosphere was considered to be stable after approximately eight hours. The extra time for stabilization was allowed to ensure a good mixing of the containment atmosphere because of the prior depressurization to zero'psig.

The average temperature change at this time was less than 0.l*F.

The peak pressure leakage rate measurements lasted for approximately 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> resulting in a measured leakage rate (Lam) of 0.05579%/ day and a UCL of 0.05936%/ day. The allowable leakage rate (La) is 0.075%/ day so the leakage rate is acceptable. The penalty leakage, Appendix D, has not been added to the UCL pending the results of the post-repair leakage rate for the three electrical penetration.= which were isolated during the conduct of testing.

However, the test results appear acceptable since the difference between La and UCL is 0.01564%/ day which is greater than 3.8E06 SCCM.

This is far more leakage than would be added since each electrical penetration is allowed only about 2 SCCM leakage.

7

b PAGE.

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PAGL. 326 1-CP-PT-75-02 PEAK PRESSURE (40 i PSIG)

INTEGRATED LEAK WALE ILUT

()

O NLAL TINEeL3,01i2Y 05 0Yi07 COMPUILD bA1A

()

• • • • • • • • • o******** TINC ******************** **** PREGSURE **** $$$ TLMPENA1URE ** * *

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DA1A LLAPSLD DONATION INURVAL IuTAL VAPUN DNY Luth WCT DuLb WLICui NAIC UCL IbG 8%

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F 1

01.20.04 53,56 000 000 H 000 0.00 63.457 0.2412 72.215 50.323 Y36615.

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f% 3 PACE. 327 1-CP-PT-75-02. PEAK P2 ESSURE (40.1 PSIC)-

()

' INTEGRATED LEAK R ATE TEST l.

REAL TINCiO3 01:29 05iO9 07 EuMPuiED DATA 6

P j

ses***ssess**ese** TIME ********************

s*** PRESSUWE **** *** TEMPERAiuME **~' * * *

• LE AK AGE AND Ek ROH P Ak AME T EN S * * * *

1. 5 l

MIN.

AIR LEAKAGE

' r DAIA ELAPSED DURATION INTERVAL TOTAL VAPOR DRY BULB WET bulb ~ WEIGHT RATE UCL ISC "i

SLT REAL (HRS)

(HRS)

(MIN)

. (PSIA)

(PSIA)

(DL'C f)

(DEC f)

(LbH)

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! r 40 01:20:16:39.07 011.750 u.000 15.00' ' 63.451 0.2359 72.302

'57.704 ' 936370

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63.457 0.2409 72.43v ^

50.200' 936225

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.00439

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54 01:20 1u 09 06 013.250 H 000 15.00 63.459 0.2330 72.506 57.362 936254.

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57 01:20 10 54 06 014.000 0.000 15.00 63.463 0.2369 72,507.

57.020 50 01:20 1Y:09:07 014.250 0.000 15.00 63.463 0.2320 72.500 57.332 _ YJ6256

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60 01 2G:19:39i06 014.750 U.000 15.00 63.463 0.2295 72.510 56.Y42 936346.

.07514

.001U5

.00977 61 01:20 19:54 07 015.000 0.000 15.00 _

63.465 0,2370 _

72.550 57.0J1 VJ6tv5.

.07562

.00212

.00961 62 01:20 20:09:07 015.250 a.n00 t$.00 63.46Y 0.232u 72.599 57.33Y V36243.

.07519

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63 01 20i20:24 06 015 500 0.000 15.00 63.469 0 233Y 72.5Y4 57.464 V36237.

.07477

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64 01 20 20 39 06 015 750 u.000 15.00 63.46v 0.2296 72.5HL 56.957 V36314.

.07315

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65 01:20 20 54 06 016.000 0.000 15.00 63.469 0.2351 72.500 57.612 VJ6242.

.07260 07H54

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.07145 07731

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.07096

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.07425

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.067v5

.07331

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72 01.20 22 39 07 017.750 0.000 15.00 63.477 0.2360 72.666 57.713 V361Y7.

.06773

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73 09.20 22 54 06 OtH.000 0,000 15.0a 63.475 0.2344 72.653 57.527 936214.

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.06523

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06241 066Y7

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'57.402 936101.

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PAGE: 52 1-CP-PT-75-02 PEAK PRESSURE (40.1 PSIG)

VERIFICATION LEAKACE TEST

.]*

m H L'AL TIMEiU3 01:29613:39 05 COMPHIED DATA

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3 u

"%4 seasses***** IInE ****s***ss*****

• • • ICHPERATURE ** **** PRESCUNE $$$$

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DAIA ELAPGED INIERVAL DN Y 14UL Es WET ftOLit IUTAL VAPOR LO (LueLAtt-0.25LA)

LC (LutLAMt0.25LA) w SLI REAL

( H'( S )

(MitO (DLC F)

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(PSIA)

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(% / DAY)

(% / DAY)

(% DAY)

(% / DAY)

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t 01 29 07:23:57 0.000 0.000 73.005 57.162 63.505 0.2313

.0Y613

.126V2 (=

0.00000 (=

.176V2 2

01:2Y:07:39 05

.250 15 000 73.009 57.369 63.505 0.2331

.0Y617

.126V5 (a 0.00000 (=

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=

3 01 29 07:54 05

.500 15.000 73.006 57.311 63.505 0.2326

. 0Vf,20

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.10305 (=

.17679 3'

4 01 29:00 09406

.750 15.000 73.012 57.455 63.505 0.2330

.0Y620

.12697 (=

.00327 (=

.t?6YV v

01 29.0H 24605 1.000 15.000 73.025 56.02Y 63.505 0. 220fa

.99622

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.01112 (=

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=

6 08 29.0H:39 05 1.250 15,000 73.051 57.431 63.507 0.2336

.09623.

.12702 (=

.0v464 (=

.17702 y

7 01:29 00 54 05 1.500 15.000 73.040 57.010 63.505 0.23u1

.09622

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.07674 (=

.17701

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01 29 09.09 05 1.750 15.000 73.042 57.043 63.5u5 0.2304

.0Y623

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.06900 (=

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01 0V 09 24i06 2.000 15 000 73.066 57.165 6.5.507 0.2314

.09625

.12704 (=

.07922 (=

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4 10 01 29 09.39 06 2.250 15,000 7.(.0HS 57.999 63.507 0.2304

.99624

.12703 ( =

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.09625

.12703 (=

.12v17 (=

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12 01 29 10 0Y 05 2.750 15.000 73.000 57.V16 63.507 0.2377

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.12704 (=

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5 13 01:29 10:24 05 3.000 15.000 73.100 57.424 63.507 0.2335

.09627

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.15525 (=

.17706 M8 *1, w

14 01 2Y 10:39 06 3.250 15 000 73.127 57.574 63.50Y 0.2340

.0Y627

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.16245 (=

.17706 M.

15 01:29610 54:05 3.500 15.000 73.140 50.205 63.509 0.2402

.0Y627

.12706 (=

.18921 (=

.17706 M.a 16 01 29 11 09:05 3.750 15 000 73.115 57.073 63.509 0.2374

.0Y625

.12704 (=

.18331 (=

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.09626

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.16635 (=

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tu 01 2Y.tt:39:06 4.250 15.000 73.130 57.745 63.50V 0.2363

.99627

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.16191 (=

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.09623

.12706 (=

.36050 (=

.17706

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21 Ot 2Vil2 24 05 5.000 15.000 73.103 57.5v0 63.511 0.2350

.09630

.12709 (=

.16419 (=

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22 Ot 2Yi12 39 06 5.250 15.000 73.106 57.506 63.511 0.2349

.07630

.12709 (=

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.09632

.12713 (=

.15933 (=

.17710

_,s 24 01.29:13 09 05 5.750 15.000 73.214 57.419 63.511 0.2335

.09633

.12712 (=

.15574 (=

.17712 25 Ut.?Yi13 24:06 6.000 15.000 73,216 57.211 63.511 0.2310

.09634

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REDISTRIBtlTED Vi>Lutil DNAClluNS VOI 11 6 bC l l uteS VOLut1C FNACilON fur IE 1 13653

=

Vol Ohi I N AC l lute I ON ll 1 =

33653 VOLUME FNACTION F OR TE 2 25704

=

VIH llNE f H ACIiUN i UN 10 2 = 257U4 l VOLUNE FRACIlON IOR 1E 3 37390

=

VOs util I R Af f lHN F UR IL 3 =

37390

,' VOL11NE I NACflON FOR TE 4 =

3UYS3 vill unt I N AC l lON f ON II; 4 = juvs3 VOLUNC FRACTION FOR TE 5 43202

=

V8 ti lettf I lmf i lOl3 I ON IL 5 43202 VOLUME INACTION FOR TE 6 15456

=

VOltihi I N ACl lON 1 OM IL 6 = 154 %

VOLut1C fMACTION IOR TE 7 36456

=

36456 VOLuhE INACilON ION TE 8 vot uht i kM lloff I UR II: 7 =

45Y19

=

Vul litti 19 ACl lHN I ON 10 11 = 4SV19 VOL UME FW AC TION + 0N lE 9 1Y403

=

= 19403 VOLUME I N ACT ION f OR 10 10 Vol tini I H Ari lDrl I ON IL Y

= 16000 Vul HN4 iRACilllN IUR IL in = l e>U G O VOLUt1E FNAcil0N FOR TE 11 28325

=

Vol Ont i U AC I IUti i DH IL 11 = 20325 VOLut1C FRACTION 1OM l E 12

= 19403 VIH unt tRACilllN lON IL 12

• 1Y403 VOLut1E FNACTION IUR IE 13 1Y403

=

Vol Uni INAC11DN IOlt 10 13 = 1V403 bOLut'.E l'NACilON iOR TE 14

24105 VOLut1E F W AC T IUte f uM TE 15 24105 Vol unt i t! At:110t8 I ON 88 14

19402

=

VIH ilN! T Whf I l ON l OR IE 15 tV402 VOLut1E I NACTION # 0R IE 16 =

a 15603 VIH Uttt iRACllON TOR IL 66 =

1%ll3

. VOLUME FNACTIUf4 iUR lE 10 VOLUME & WACTION F OR TE.17 42005

=

Vol Ont iRACIION iUN IL 17 + 42005

= 40103 vol Hite IN At: Illite D ON li' its 40103 VOLunE fitACTION FOR TE 19

=

H0500 y

=

VOl utir I R Ariluta l ON IL 1Y

= 041$00 VOLut1E F N ACT ION F OR fE 20 55.193

=

VsH ttnf IMACilON 04Hf IL Jh

%3Y3 VOLUME fkACIIOteION 1E 21

= 50052 Voi tini IRAriliitt ION li 21 51:052 VOLUME INACTION IUR TE 22

=

g 40103

=

Vul ilML IRAClioteIOR IL 2a 4Ht03 VOLut1C FWACilON 6 0R TE 23

=

110011 VOI Ottt I M AC ! l Oli i Ol* IL 23

110011 VOLUME FRAC 110N FOR 1E 24 19403 T

=

Vul sInt iPAtlION IllW 11 24 tv403 h

1Y403 VOLut1E FRACilON FDM IE 25 u

g

=

Up! Unt lin.ClIDH I04 IL ;"

SY403 VOLut1E FNACilON fOR TE 26

=

16000 t3

=

Vul tlnt IPACllON t ilN 11 26 = l t.0 0 0 VOLut1E FRACIION DUR IE 27 = ' 1Y403 H

YUt Unl i k..I'l litst i UN IL 27 =

,1 Y 4 0.5 VOLuf1E F N AC f lON f 0R IE 20 207249

=

Vol Uni i PACI tilN I ON [E 281 20724Y VOLUME FRACIION FUN IE 29 =

=

211Y05 n

Vot ont IPArilot4 IttN li 1* Y 211YG5 VOLut1C FRACIl0N FOR TE 30

=

211YO5

=

g VOI tiht ( Fat:llott I H4 IL 30 21190$

VOLut1E F NACilON F OR TE 31

=

206606

=

f VO! Ont F R AC i l uti S OR IC 31 4

206606 VOLUML f NACTION FOR TE 32 = 170076 VHe utti. l eACIIOta I UR IC 32 17U076 VOLUNE FRACilON IOR 1E 33 = 17H076

=

volHMC INACllON IGN Il 33 17H076 VOLut1E INACiluN fou IE 34

' 170076 s.

=

uu! Hnt I P AC l l HN I ON IL 34 170076 VOLift1E FNAC TION FOR TE 35

=

170076

=

VOl linr I RACllON S UN It 35 1',11076 VOLUME INACTION FOR TE 36 = 91891

=

4 Vill Oril IRACllON ItlH IL 36 = Y1U91 VOLUME INACllON FOR 1E 3u = 73465 VOLUME INACllON f0W lE 37 a ' 7.5465 s

Vol tine I N AClllHe I ON lE 37 V.14 %

=

vol UML f M ACl itita f uN I E 311 73465 VOLUt1C fRACilON FON IE 39

=

= 1416Y Vol linF iNAUlluta iUH IL 3Y = 1416Y VOLUt1E INAC110N fOR lE 40 _= 1416Y VIH ilnl I N AC i l t iti I HR In 40 4

1416Y V10Y1 i VOLUNE INACilON FOR 1E 41 ~= YsH91 VOIOnt I N Ar l l pli I ON ll 41 VOLUt1C I N ACT !UN f uW IE 42

=

73465

=

' 734 t,5 VOLUME FNACilON SUN DE 1 Vl41 tint I C AC l l ure f uN IL 42 =

g

13653 Vill iH11 i pal:llute I ON I/L 1 13653 63102 VOLUt1E iRACTION FUN DE 2

=

631U2 Vill llhi INACilOtalON DC 2 VOLUrtE THAC110N fun DE 3

=

U2155 O2155

=

VOI Ont I R ACi tuti S UN let 3

=

VOLUhE tHACTION SUN DE 4 =

g 20325 l

Vol Otti: IRACilllN FUN DL 4 201325 VOLut1C I NACTION ION DC 5

=

82375

=

Voi t ti l' I N ACl lOli t uR DE 5 U2.575

- VOLut1E i NACilute i UN DE 6

=

06575

=

Vtli 4thC i RAC I ION i UN OL 6 = 0 % 75 VULUME FNACilON fOR DE 7 = v170s j

VOI IINL f H ArilON l ON DL 7 V1701 VOLut1E INACilON F UM DE O

=

647070

=

t VulHitr lHACllON ION Dl: 0 =

31 % 61 VOLUME FRACTION IUR DE Y

15456 VoI Hnl i t' ACl lleti l uk DE Y

15456 y

VOLUt1C FRACilON l'OR DE 10 331507

=

VOi Util 0FACllON ION OL 10 =

1.657S43t'*6 VOLUME FNACTION FON DE 11 643795

=

Vol latir i H AC 110:4 i ON DS: 1i = 312206 l VOLUNE F R AC T ION F OR DE 13 VOLut1E FHACIIUN TOR DE 12 406304

=

Voti1ME IRACilON IUR Dt' 12 747YS N1 = 42, NPV= 13 NP= 1

=

y 427715

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VD Util INACllON FOR Dl' 1.5

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Y6006 NI= 42 Hl* V 2 13 tJP = 1 e

s, 2

^-

i APPENEIX D PENALTY LEAKAGE LIST Pentration Service Type C Leakage (SCCM)

MV-12 Chilled Water Supply 80 to Containment Coolers MV-13 Chilled Water Return 500 from Containment Coolers MIII-30 ILRT Pressurization 20 Pipe Penetration MV-7 ILRT Pressure Sensing 10 Penetration I

E-49 Electrical i

k E-62 Electrical 2

E-68 Electrical

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