ML20214L066

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Reactor Containment Bldg Integrated Leakage Rate Test for Braidwood Unit 1,Preoperation Test on 860521-29
ML20214L066
Person / Time
Site: Braidwood Constellation icon.png
Issue date: 08/19/1986
From:
COMMONWEALTH EDISON CO.
To:
Shared Package
ML20214L065 List:
References
NUDOCS 8608250076
Download: ML20214L066 (43)
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Text

T Attachment 1 Reactor Containment Building Integrated Leakage Rate Test for Braidwood Unit 1 Pre-Operational Test May 21 - May 29, 1986 i

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TABLE OF CONTENTS Pate 1.0 Abstract 3 2.0 Summary of Type A, B & C Test Results 4 3.0 Test Preparations 6 4.0 Test Methodology 10 5.0 Summary of Events 12 6.0 Type A Test Data 15 6.1 Reduced Pressure Test 6.2 Full Pressure Test 6.3 Full Pressure Supplemental Test 7.0 Type A Test Plots 22 7.1 Reduced Pressure Test 7.2 Full Pressure Test 7.3 Full Pressure Supplemental Test 8.0 Interpretation of Test Results 32 8.1 Reduced Pressure Test 8.2 Full Pressure Test 8.3 Full Pressure Supplemental Test 9.0 Type B & C Test Results 33 10.0 Attachments 36

1.0 ABSTRACT This report provides the details of the Braidwood Unit One Preoperational Containment Integrated Leakage Rate Test (ILRT) performed May 21 through May 29, 1986. The test was performed in accordance with Appendix J to 10CFR50, ANSI N45.4-1972, and the Byron /Braidwood Final Safety Analysis Report.

This report contains information on the following items associated with the Braidwood Unit One Containment Leakage Rate Program:

1. Type B & C Local Leakage Rate Testing
2. ILRT/ SIT Plant Equipment Lineup
3. Reduced Pressure ILRT
4. Full Pressure ILRT
5. Supplemental Verification Test Item 1 took place from January to May 1986. In addition some retesting was done in June and July of 1986. A brief discussion of the Local Leakage Rate Test Methodology and a summary of the leakage rates can be found in section 9. Item 2 was performed from May 12 to May 21, 1986. Item 3 started on May 21 and Item 5 concluded on May 29, 1986.

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2.0

SUMMARY

OF TYPE A, B. & C TEST RESULTS 2.1 Test Acceptance Criteria for the Type A Test.

2.1.1 Acceptance Criterion #1 stated: "For the Full Pressure ILRT, verify the overall Integrated Leak

' Rate, which is equal to the 95% Upper Confidence Limit of L ,added to the required local leakage rate additions, is less than 0.75 L,."

The 95% Upper confidence limit was determined to be .0333%/ Day or 2.57 SCFM. The local leakage rate additions are as follows:

Penetration No. Reason Valve No. Leakane (SCCM) 82 No way to vent ISD002A 716 1 20 83 No way to vent 1SD002B 3712 80 No way to vent ISD002C 400 1 20 81 No way to vent ISD002D 43 1 2 88 No way to vent 1SD002E 6 2 89 No way to vent 1SD002F 512 90 No way to vent 1SD002G 100 1 2 91 No way to vent ISD002H 412 52 EQ Hatch Pressurized IPR 033B 6i2 52 EQ Hatch Pressurized IPR 002G 41 1 2

  • 4 Pressurization Line CPP Line 34 1 2 13 Pressure Sensing Line IVQOl6 412 13 Induced Leak Line IVQO17 412
  • 93 Not Vented Recire Sump B Bellows 149 22 TOTAL 1574 1 29** SCCM
  • Tested subsequent to the test
    • ERROR TOTAL CALCULATED by the square root of the sum of the squares of the individual errors.

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1574 1 29 SCCM x 1 CF = .055 i .001 SCFM 28317 CC The total local leakage rate addition is .056 SCFM

(.00072%/ Day). The overall Integrated Leak Rate is .034%/ Day (2.626 SCFM) which is less than the acceptance criterion of

.75 La (.075%/ Day) or 5.79 SCFM.

2.1.2 Acceptance Criterion #2 stated, "For the Full Pressure ILRT Supplemental Test, verify the measured composite leakage Le is within 0.25 Laof the sum of the superimposed leakage to and the previously measured leakage Lam-(Lo+ Lam - 0.25L a ) i Le 1 (Lo+Lam

+ 0.25 L.); where the superimposed leakage rate Loshall be between 75% and 125% of aL ." The superimposed leakage Lo was 7.665 SCFM which was 99.3% of La . The previously measured leakage 1,, eas 2.25 SCFM. 0.25 La is equal to 1.93 SCFM, yielding an acceptance criteria range of 7.98 SCFM to 11.84 SCFM. The measured composite leakage L ewas 8.56 SCFM which was within the acceptance criteria range.

2.2 Test Acceptance Criteria for the Type B & C Tests 2.2.1 Acceptance Criterion #1 stated: "The combined leakage rate, including the measurement error, for all penetrations and valves subject to Type B and C tests shall be less than 0.60 La at a minimum pressure of P (44.4 psig)." The tests +

were performed by local pressurization using air or nitrogen and measuring the amount of air or nitrogen it takes to keep the system at approximately 46 psig. 0.60 La = 277.77 scfh and the measured leakage was 38.43 scfh i 0.62 scfh.

! 2.2.2 Acceptance Criterion #2 stated: "The Equipment Door Air Lock shall each have a leakage rate of less than or equal to 0.05 La at a minimum pressure of Pa (44.4 psig)." This was met by pressurizing the airlocks with air and measuring the amount of air required to keep the Airlock at approximately 46 psig. The Integral Personnel Airlock pressurization test had a measured leakage rate of 3.09 sefh. The Emergency Airlock pressurization test had a measured leakage rate of 4.30 scfh. This is less than the allowable of 23.15 scfh (.05 La).

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I 2.2.3 Acceptance Criterion #3 stated: "Normel Containment Purge (VQ) Penetrations P-95 and P-97, consisting of containment isolation valves (1VQOO2A&B, IVQOO7) and (1VQ001A&B, IVQOO6) respectively, shall have a measured leakage rate less than 0.05 La at a minimum pressure of Pa-(44.4 psig)." This was met by pressurizing the area between the valves (1VQ001A & B or IVQ002A & B) and measuring the amount of air required to keep the area at approximately 46 psig. The measured leakage rate for IVQ001A & B was 2.25 scfh. The measured leakage rate for IVQ002A&B was 2.99 scfh. The allowable leakage rate for each is 23.15 scfh.

2.2.4 Acceptance Criterion #4 stated: "Miniflow Containment Purge (VQ) Penetrations P-94 and P-96, consisting of containment isolation valves (1VQ005A, B & C, IVQOO3, IVQ009) and (1VQ004A &

B, IVQOO8) respectively, shall each have a measured leakage rate less than 0.01 La at a minimum pressure of Pa (44.4 psig)." This was met by pressurizing the area between the isolation valves and measuring the leakage. The measured leakage for IVQ005A, B & C and IVQOO3 was 0.17 scfh. The measured leakage for IVQOO4 A

& B was 0.15 scfh. The allowable leakage rate for each penetration is 4.63 sefh.

2.2.5 Acceptance Criterion #5 stated, "Each Personnel Lock Door Gasket Interspace shall have a measured leakage rate less than 1.94 scfh at a minimum pressure of 10 psig." This was met by pressurizing the interspace to approximately 10 i

psig and measuring the leakage. The measured leakage Equipment Hatch door gasket interspaces were .013 scfh and .008 sefh. The measured leakage Emergency Hatch door gasket interspaces were .008 scfh each.

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3.0 TEST PREPARATIONS 3.1 Type A Test Procedure The Unit 1 Preoperational Containment ILRT was performed in accordance with test procedure BwPT PC-11, revision 1 and revision 16 of the Braid 4 cod Startup Manual. BwPT PC-11 was written to comply with Appendix J of 10CFR50 and ANSI N45.4-1972, although much of the methodology used was taken from ANSI 56.8-1981. During execution of the test procedure 12 test change requests were issued, the majority of which were of a minor aature.

3.2 Type A Test Instrumentation Setup Containment air mass data was taken utilizing a Volumetrics Data Acquisition System (DAS). Twenty five RTDs for temperature measurement and ten lithium chloride dewcells for determining vapor pressure were located in containment as shown in Attachment 10.1. A multiplexer scanner (n0X) located inside containment scanned the sensor outputs and transmitted the reading through a permanent electrical penetration to the DAS console located in the Auxiliary Building. Containment absolute pressure was monitored with two quartz bourdon tube pressure gauges located in the DAS and connected to containment by a short run of poly-flo tubing.

Additional instrumentation used included an ambient pressure transducer, ambient temperature RTD and a rotameter used to measure the superimposed leakage of the supplemental verification test.

Attachment 10.2 contains specifications for the aforementioned equipment including values for accuracy, repeatability, sensitivity and resolution for the RTDs, deweells, and pressure sensors. The quality and quantity of the sensors chosen were such that the Instrument Selection Guide (ISG), as defined by ANSI 56.8-1981, would still be less than 0.25 La for a test duration less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> assuming failure of several RTDs or deweells and one pressure sensor.

Attachment 10.3 depicts the general arrangement of the Integrated Leakage Rate Monitoring System relative to the containment wall.

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

3.3 Type A Test Data Processing Leakage rate data was acquired by the DAS every 15 minutes. This included Time, Julian Date, RTD temperatures, Dew Cell temperatures and absolute pressure sensor readings. The data was sent electronically to the Prime Computer through two telephone modems in a RS232 format as shown in Attachment 10.4. The Prime Computer placed the incoming data into a permanent file from which it drew one data set at a time to compute the leakage-rate. From the Prime Competer User Terminal the data was reviewed for completeness and accuracy and then entered into the leakage rate program. Leakage rates, raw data and calculation summaries could be printed as desired for review and later permanent storage. The multicolor plotting of leakage rates and other. data on both hard copy (HP Plotter) and the RANTEK 6211 CRT was available to facilitate trending parameters such as containment leakage rate, dry air pressure, vapor pressure and containment average temperature.

A bench mark calculation was performed prior to the test to prove the validity of the Prime Computer ILRT code.

The results of a sample data set entered in the computer were compared with hand calculations with an acceptable correlation.

3.4 Type A Test Subvolume Determination The containment was divided into 5 discrete subvolumes.

Subvolume demarkation and size are indicated on Attachment 10.1. Subvolume 4 is defined as the annulus between the outermost containment wall and the Missile Barrier below the 426' level. Subvolume 5 is the volume inside the Missile Barrier below the 426' level, not including the reactor cavity.

Two dew cell sensors were distributed to each subvolume so that loss of any one sensor would not leave a subvolume uncovered. RTD sensors were placed so that each sensor had a weighting factor of 3-5% and loss of any one sensor would not result in an RTD weighting factor of greater than 10% for any single sensor.

Containment temperature surveys were performed prior to the test to justify the location of the sensors. At the request of the NRC inspector the survey was repeated for subvolumes 4 and 5 at the ceaclusion of the test and 4%

hours later. The post test surveys showed a maximum temperature variation of 3.2*F over one subvolume thus validating the sensor locations.

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3.5 ILRT/ SIT Plant Equipment Lineup The valve and equipment lineups are detailed and specific, i.e. component by component with individual signoffs. This ensured containment integrity conditions as close as possible to those which would exist after a design basis Loss of Coolant Accident (LOCA). It also assured penetrations were properly drained and vented.

Out of Service cards were hung to preclude misalignment during the test.

3.6 Structural Integrity Test The Structural Integrity Test (SIT) of Unit 1 containment preceded the Integrated Leakage Rate Tests. It utilized the valve and equipment lineup of the'ILRT procedure to isolate the containment and protect equipment within exposed to pressure. During the SIT the containment was pressurized to greater than 57.5 psig or 115% of its design pressure of 50 psis. A post-SIT / pre-ILRT inspection of accessible interior and exterior containment surfaces indicated no significant deterioration of the containment structure.

3.7 Type A Test Pressurization One 7000 SCFM and three 1800 SCFM electrical " oil free" air compressors with air coolers and dryers were used to pressurize containment. The compressors were situated on the east side of the Fuel Handling Building.

Pressurization was accomplished through a six inch header pipe which penetrates containment at penetration P-4.

(See attachment 10.5 for a general arrangement).

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. l 4.0 Test Methodology 1 4.1 Reduced Pressure ILRT During this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, pressure, temperature, and humidity data were taken to determine the statistically averaged containment leakage rate Ltm (weight percent /24 hours). The test was conducted at a nominal pressure of Pt (24 psig) above the required minimum of 22.2 psig (0.5 P a). Reactor Containment Fan Coolers were operated during this test.

4.2 Full Pressure ILRT During this 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, pressure, temperature, and humidity data were taken to determine the statistically averaged containment leakage rate Lam (weight percent /24 hours). The test was conducted at a nominal pressure of 46 psig above the required minimum of P a (44.4 psis) the Design Basis Accident containment pressure. Reactor Containment Fan Coolers were not run during this test. The purpose of this test was to determine a 95% Upper Confidence Limit value of L ,for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period.

4.3 Temperature Stabilization Periods Prior to start of each ILRT a Temperature Stabilization Period of a minimum duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> was employed.

The criterion for temperature stabilization was as follows: The latest rate of change of the weighted average containment air temperature averaged over the last hour does not deviate by more than 0.5 *F/hr from the average rate of change of the weighted average containment air temperature averaged over the last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

4.4 Supplemental Verification Test Following the Full Pressure ILRT, a deliberate leak of known magnitude was superimposed on the existing containment leakage through a calibrated flowmeter. The superimposed leak was maintained between 0.75 La and 1.25 La (5.79 and 9.64 SCFM).

The duration of the test was defined as a minimem of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and 10 sets of data. The acceptance criterion for the test was follows: The statistically averaged Composite Leakage Eate e(L ) is within 0.25 La (1.90 SCFM) of the sum of the statistically averaged Full Pressure ILRT leakage rate (Lam) and the average flowmeter induced leakage rate (L o).

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4.5 Method of Leakate Rate Determination The leakage rate is assumed to be constant during the testing period, ideally yielding a straight-line plot with a negative slope. However, sampling techniques and test conditions are not perfect; consequently, the measured values will deviate from the ideal straight-line situation.

A Least Squares Fit Statistical Analysis was performed to determine a regression line for mass versus time after each set of data was acquired. The slope of this regression line was designated to be the statistically averaged leakage rate (Lam) for the Full Pressure ILRT.

Associated with the statistically averaged leak rate was the 95% upper confidence limit leakage rate (Lucla)-

The calculation of this upper limit was based upon the standard deviations from the regression line and the one-sided T Distribution function. An expanded discussion of the Least Squares Fit Statistical techniques used can be found in Attachment 10.6.

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i 5.0

SUMMARY

OF EVENTS 5/12/86 1000 Began lineups on WM and FW systems.

1530 Lined up OG system.

5/13/86 0730 Began lineup for RY system.

0830 Ceco Insurance Administrator notified of start dates for SIT and ILRT.

5/14/86 0815 Began lineup of RE system.

5/15/86 0730 Began lineups on CV SI,RH,RC,PR,MS,CC,FC, and WO systems.

0845 Lineup up the VP fans.

1115 Granted PCD a temporary lift on the RE systems for a hydro.

Valve lineup will be reperformed.

5/16/86 0730 Continued valve lineups for the CV SI and WO systems. Began lineups on the PW.PW.FP and RE (relineup) systems.

5/19/86 0715 Began lineups on th RF and PS systems.

1300 Took SI Accumulator instrument tap vent valves out of service open for a vent.

1800 Began NT lineup for the electrical penetrations.

5/21/86 0715 Began lineups on the IA and SD systems.

1100 Closed up the Equipment and Emergency hatches.

1115 Released control of containment to the SIT engineer.

5/22/86 1912 SIT peak pressure, 57.5 psig reached.

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5/24/86 0227 SIT depressurization completed.

0930 SIT equipment relaxation complete, containment access authorized and post SIT / pre ILRT inspection initiated.

1200 Containment inspection complete. No signs of structural deterioration.

1215 Entered ILRT procedure at step 9.1.1 after verifying prerequisites and briefing shift personnel. Support systems CC and SK will not be required to be operational for ILRT. WM is being fed and bled to the CC side of the RHR heat exchanger to control temperature.

1302 Started pressurization.

1735 pressure approximately 15.1 psig. RCFC fans A-D started on low speed.

2058 Began temperature stabilization.

2113 Received scrambled data.

2148 Restarted temperature stabilization.

5/25/86 0148 Completed temperature stabilization and began reduced pressure test.

0905 Leak identified on the lower shaft seal on the inside face of the personnel lock in elevation 426. After troubleshooting, it was decided to close the outer equipment hatch personnel lock door, equalize the pressure around the inner door and open the inner door.

1115 Test connection valve 1CV064 was found to be leaking excessively. Since this test connection was not being used as a vent, it was taped and capped.

1840 Reset the base dataset to #49 which occurred after the mass settled from the personnel lock door switch.

5/26/86 0715 RTD #16 declared inoperable and removed from scan. Data was replotted from the base dataset without #16.

0948 Terminated reduced pressure test with an upper confidence leak rate of .0393%/ day.

0955 Began repressurization of containment.

1020 RCFC fan C tripped on high amps.

1024 RCFC fan B tripped on high amps.

1140 RCFC fan D tripped on high amps.

1150 RCFC fan A tripped manually.

1330 Thermal mass flowmeter declared inoperable. A rotameter will be used for the induced leak test.

1800 Peak pressure reached and temperature stabilization started.

2300 Temperature stabilization completed and LOCA pressure test started.

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5/27/86 0700 Reactor vessel level below the expected range of 1-21%. RHR pump A motor amps remained steady. This dropping of level was noticed during the SIT but level returned to 6% during depressurization.

2300 Completed LOCA test.

2310 Began induced leakage with flow set at 7.72 scfm.

5/28/86 0011 Began induced leakage test.

0556 Completed induced leakage test.

0750 Began depressurization.

0800 Opened IPR 033C and D to aid in depressurization.

1430 Reached VP-12 test pressure of 25 psig and stopped depressurization.

5/29/86 1827 VP-12 test complete.

1830 Began depressurization again.

2100 Lifted outage on OG system to aid in depressurization.

5/30/86 0525 Containment depressurization complete. Restored PR and OG systems.

0615 Entered containment for final inspection and post test containment temperature survey requested by NRC Inspector F. Maura. No containment damage was noted. Maximum temperature variation in subvolume 4 was 1.2 deg F.

1100 Second post test temperature survey requested by F. Maura performed. Maximum temperature variation in subvolume 4 was 1.3 des F.

1400 Exited ILRT procedure.

1500 Began ILRT restoration procedure.

6/13/86 1200 Completed restoration portion of the ILRT procedure, i

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6.0 Type A Test Data 15 1379m(073186)

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LATA TAPE T19E TEST CONT AVE C041 AVE TOTAL SET CuRATION ORY AIE TtMP (a) 04Y AI4 PRES LEtt RATE (34Y MM M1 SS) (HOURS) (dig R) (PSIA) (% / OAV) 10 1+5 00:12:06 0.00000300E*00 0.54019055E+03 0.59226271E+02 11 0.00000000E+03 the 00:17:00 0.53476094E-01 0.54013710E+03 0.59524189E+02 0.00000000E+00 12 146 00:22:06 0.1es50391E+00 0.54013sB9E+03 C.59324531E+02 13

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_ q _ ___ . _ . . _ . . .

I I l l i O.2000E-01

_. ._. __. _ _ f

' I 0.0000 L., - __ ._ _____ .__. . .. . _ _ _ . _ . _ _ _ _ _ _ _ . . _ . . _ _ __ _ _ . _ _ _ _ _ _ . . . _ ,

Descrip_ tion Units Symb o'll Base Dataset Time

. CALCULATED LEAK RATC  % PER DAY 3 148 00: 12:06

[ 9 5 % _U P P E R_ C_0 N F I D E N C E __L I M I T _ . . . .,_. _  % P_ER_D_AY 6

BRAIDWOOD UNIT 1 INTEGRATED LEAK RATE TEST BRAIDWOOD UNIT 1 INTEGRATED'LEAKRATE TEST Verification Test CONTAINMENT ORY AIR TEMPERATURE vs TIME Base Dataset # 10 Plot Starting Dataset # 10 Plot Ending Dataset # 79 Aelative Time (Hours) . . .

9 99 0 'iH 1.15 1.73 2.30 .2.8d 3.45 4.03 4.60 5.18 n./4 gg gg so 95 89 51 90 46 -

\/ \ ,

s\

8 so 36 4

. T 80 a y-N *N h Ho di , ,

40 22 s*% _

'N% o, ,

d9.17 80 13

~Destrtotion Units Symbol ' Base Dataset Time ORY AIR TEMPERATURE DEG F 0 146 00.12;06

4 6

/

5 4

t 8

1 +

e 5 m i

9 6 7 ,

T 0 1 t 2

  1. 0 e 1 6 s t  : a 0 .

4 t 0 e a s  : D a

8 t

a " e s

4 1

D 3

  • a g 0
  • B n 4 T i E

E d

  • l T n o E b E ) -

nO T t S5 y A

R o r4 m S T l e K P u A S o '-

E E H L

D E

T E

0 1

(

e8 2

T A T # m8 . s R A i 2' t A G T i I E R t n S T K e U P N s e I A a v 1

T E

L t

D a i0 t3 -~

N -

I E a2 --

N U

D Mg l s E I n e a D T Ti R

O A t O sr h W

D R va 3 I G t 1 A E ES .

E R 1

S T Ut .

N So _

I Sl 1

EP R 5 P 1 0

T tT1 I sN 1

, E N eE f M#

R U  % U .-

N nS -

nI t o S DoAe e t E S

t R OiTt N v<

O 0 / , n P aOt i W cCa L D t D -

u A I f L  %- s T A iAe rT s 0 e O D I ReOa 0 [I BVTB 9 I

9 / 5 4 9 /

1 n

i 4

1 2

1 1

1 0  ; 3 0 1

0 9 ) 9 0 0 g 9 9 9 9, 6 6 6 6 6 E t 6 e 6 2

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

P 8.0 INTERPRETATION OF TEST RESULTS 8.1 Reduced Pressure Test t

The statistically averaged containment leakage rate Ltm (weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) was 0.0363%/ day after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 96 datasets. The 95% upper confidence limit of the containment leakage rate Lucir was 0.0393%/ day.

The plot of leakage versus time shows a relatively steady-line with a slight decreasing trend over the last 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> of the test. The plot is unsteady the first three hours due to the statistical uncertainty of fewer j datasets. Plots of containment average pressure and temperature versus time display a steadily increasing

trend throughout the test due to the constant heat input of the Reactor Containment Fan Coolers.

8.2 Full Pressure Test The statistically averaged containment leakage rate Lam (weight percent per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) was 0.0292%/ day after 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and 96 datasets. The 95% upper confidence limit of j the containment leakage rate, Lucia was 0.0333%/ day.

{ With no Reactor Containment Fan Coolers producing heat,

the containment building cooled during the test resulting
in a' downward trend of the containment average pressure and temperature plots. The plot of containment leakage was well below the allowable limit and at the termination l of the test, still decreasing.

i 8.3 Supplemental Verification Test The statistically averaged composite leakage rate Le i was .111%/ day after 5.75 hours8.680556e-4 days <br />0.0208 hours <br />1.240079e-4 weeks <br />2.85375e-5 months <br /> and 69 datasets. This was within .25 of L, of the sum of the statistically averaged Full Pressure leakage rate and the average flowmeter induced leakage rate as discussed in Section

2.1.2.

I 4

l l

i iI 32 1379m(080586)

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c -

9.0 TYPE B & C TEST RESULTS 9.1 Local Leak Rate Methodology Type B & C tests were conducted in accordance with Appendix J to 10CFR50 and ANSI N45.4-1972. The test volumes were pressurized and regulated with air or nitrogen to nominally 46 psig. The test volume leak rate was determined by measuring the flowrate necessary to maintain the test volume at 46 psig after a suitable stabilization period.

9.2 Leakane Rate Summary:

TYPE PENETRATION (P) LEAKAGE RATE (SCCM)

B Zone 1 Electrical penetrations 69 i 2 B Zone 2 Electrical penetrations 3612 B Zone 3 Electrical penetrations 32 1 2 B line 4 Electrical penetrations 9912 B Fusi Transfer Tube Flange 4i2 B Equipment Door Personnel Lock 1463 1 20 B Blind Flange #1 on Equip. door 412 B Blind Flange #2 on Equip. door 412 B Equip. Door Double casket 11 1 2 B Emergency Personnel Lock 2038 1 200 B Blind Flange #1 on Emers, door 812 B Blind Flange #2 on Emers. door 412 B P-4 Cnmt pressurization line - 412 Blind Flanges C P-97 Cnmt Normal Purge (1) 1064 1 20 C P-95 Cnmt Normal Purge (1) 1410 1 20 C P-96 Cnat Miniflow Purge (1) 74 i 2 C P-94 Cnmt Miniflow Purge (1) 79 i 2 C P-13 Inst. Isolation Valves (1) 412 C P-I3 Inst. Isolation Valves (2) 412 C P-70 Pressurizer Stm Sample 4t2 C P-70 Pressurizer Liq Sample 412 C P-70 Reactor Coolant Sample 412 C P-70 Accumulator Tank Sample 412 C P-12 Hydrogen Monitoring (SUC) 207 t 20 C P-12 Hydrogen Monitoring (Ret) 172 1 2 C P-31 Hydrogen Monitoring (SUC) 259 i 20 C P-31 Hydrogen Monitoring (Ret) 191 1 2 C P-41 Chemical and Volume Control 22 1 2 Letdown Line C P-11 Reactor Coolant Drain Tank 1712 (RCDT) Pump disch.

C P-65 RCDT to Auto Cas Analyzer 412 C P-65 Waste cas from RCDT 412 C P-27 Pressurizer Relief Tanks 156 1 2 (PRT) to Auto Cas Analyzer f'

33 1379m(073186)

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TYPE PENETRATION (P) LEAKAGE RATE (SCFH)

C P-27 PRT Nitrogen Supply 483 1 20 C P-28 CV Seal Water Ret. 247 1 20 C P-24 CC Seal Water Ret. 5312 C P-44 Primary Water to PRT 6512 C I-5 Pressurizer pressure indicator 412 C P-21 Component Cooling Ret. 295 20 C P-25 Reactor Coolant Pump Seal 3212 Water Supply C P-32 Refueling Cavity Return Header 412 C P-57 Refueling Cavity to Refueling 412 Water Pump C P-1 Cnmt Spray Supply 642 1 20 C P-16 Cnmt Spray Supply 13112 C P-39 Instrument Air Supply 124 1 2 C P-56 Service Air Supply 48 i 2 C P-30 Demin Water Supply 153 1 2 C P-47 Reactor Blds Floor Drains 5712 C P-13 Hydrogen Recombiner Ret. 28 i 2 C P-13 Hydrogen Recombiner Suc. 118 i 2 C P-69 Hydrogen Recombiner Ret. 1012 C P-23 Hydrogen Recombiner Suc. 3012 C P-52 Process Rad. Air Sample Suc. 412 C P-52 Process Rad. Air Sample Ret. 105 1 2 C Process Rad - Equip. Door Suc. 6i2 C Process Rad - Equip. Door Ret. 4112 C Process Rad - Emerg Door Suc. 29 i 2 C Process Rad - Emerg Door Ret 184 1 2 C P-5 Cnmt Chilled Water Ret 2140 1 200 C P-8 Cnmt Chilled Water Ret 1150 20 C P-55 Nitrogen Supply 19 i 2 C P-55 Accumulator fill line 4i2 C P-82 Stm Generator 1A Blowdown 716 1 20 C P-83 Stm Generator 1A Blowdown 37 1 2 C P-80 Stm Generator ID Blowdown 400 1 20 C P-81 Stm Generator ID Blowdown 43 1 2 C P-88 Stm Generator 1B Blowdown 6i2 C P-89 Stm Generator 1B Blowdown 512 C P-90 Stm Generator 1C Blowdown 10012 C i'-91 Stm Generator 1C Blowdown 412 C P-4 Cnmt pressurization line test 412 Conn.

C P-6 Cnmt Chilled Water Supply 1665 1 20 C P-10 Cnmt Chilled Water Supply 1410 1 20 B Fuel Transfer Tube Sleeve Bellcws 84 + 2 TOTAL 18139 293*

= 38.43 i .62 SCFH

  • Summation of error done by:

Error Total = (E 1

+E 2

+ ***)

34 1379m(080586)

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ATTACHMENT 10.1 Subvolume Calculations and Sensor Placement 4 Dt. Des .90* aperf s%'

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l 35 l 1379m(073186)

A l .

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10.0 ATTACHMENTS 10.2 ILRMS Specifications

1. Drybulb Twenty-Five Channel Temperature System The drybulb temperature sensors shall conform to the following:

Number of sensors: 25 Configuration: 3 wire Type of sensor: Resistance Temperature Detector (RTD)

Element: Platinum Resistance: 100 OHMS 9 32 'F The drybulb temperature system readouts, including sensors, shall conform to the following:

Accuracy: 60* - 120*F Range 1 0.1*F 0* - 150*F Range i 0.25'F Repeatability: 1 0.01*F Sensitivity: 1 0.01*F Resolution: 0.01*F

2. Dewpoint Ten Channel Temperature System The dew point temperature sensors shall conform to the following Number of Sensors: 10 configuration: 5 wire Type of sensor: Lithium Chloride Special: Nylon sock cover for element Range: 32' to 120*F The dewpoint temperature system readouts, including sensors, shall conform to the following:

Accuracy: 45' to 90*F Range i 1.5'F Repeatability: 1 0.50*F Sensitivity: 1 0.1*F Resolution: 0.Ol*F

3. Pressure Two Channel System The pressure sensors shall conform to the following:

Number of sensors: 2 Type of sensors: Quartz Bourdon tube Range: 0 to 100 PSIA Manufacturer: Mensor Corp.

36 1379m(073186)

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/~

l The pressure system readouts, including sensors, shall conform to the following:

Accuracy: i .01% of reading i .002% of full scale i 5 microns of abs. press.

Repeatability: i .001% of full scale Sensitivity: i .001 PSIA Resolution: .001% of full scale

4. Vacuum System for Zero Pressure Reading Verification Check Vacuum pump: Two stage Free air displacement: 50 liters / min Power required: 110 VAC 60 HZ Vacuum gauges: Two thermocouple type gauges Hardware: Two channels and connection for transfer standard
5. Verification Flow System Number of sensors: 1 Type of sensors: Rotameter Range: 0.8 to 10.2 SCFM Accuracy: 1 1% F.S.
6. Ambient Pressure Number of sensors: 1 Type of sensors: Strain gauge Range: 12 to 17 PSIA Accuracy: i .1% F.S.

Repeatability: i .1% F.S.

Stability: i .15% 6 Months

7. Ambient Temperature Number of sensors: 1 The specifications are identical to that of the other 25 RTDs of item 1.
8. Time The built-in clock shall maintain real time by Julian date, hours minutes and seconds on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time basis.

Accuracy: i 1 minute /24 hrs.

Resolution: 1.0 second 37 1379m(080586)

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9. Data Acquisition System A/D Conversion Dual slope integration V F, constant scan rate Display: 5 + Digit, Polarity. .

Decimal & Legend Sampling Rate: 10 Channels /Second Common Mode Rejection: DC-140db, 1000 OHN Unbalance .

AC-140db at 50-60 Hz Normal Mode Rejection: 80db Input Impedance: 1,000 MEG 0HMS/ Volt Ambient Temp. Range: 32-125'F Zero Offset: Recalibrate before each reading automatically Full Scale Temp. i 5 PPM /*C or 0.005%/*C Accuracy: i .005% F.S., 1 005% of Reading at 25'c with i 10%

A.C. Power variation.

l 38 1379m(073186)

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ATTACHNENT 10.3 .

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' # I*

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lDises 9Yl ll i certo'l J l DOAL EU MULTI-f1 EXER l A -100 A5 ggigge l f 3 w.ee I _ -

To Peat CoraPUT88 SCANNE R RS - 2 M I/o ly (Affochene.A 10.4 s'6ast l y 3 10 i peWPot Wp'y g l l scuae cm,ns,y, INPt/T3 g,,

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, Co +omt 60ttorne tJoss.

l INTEGRATED LEAK RATE MONITORING SYSTEN 39 1379m(073186)

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ATTACHMENT 10.4 PRIME COMPUTER EQUIPMENT CONFIGURATION DATA

. STORAGE OF 4 PLOTTER LEAKRATE DATA SETS VOLUMETRICS PRIME PR R DAS MODEM hard MODEM for COMPUTER (Attach) wire SPOOL FILM 10.3 i

USER TERMINAL WYSE. DECWRITER OR RANTEK 6211 i

I 40 1379m(073186)

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ATTACHNENT 10.5 .

CONTAINMENT PRESSURIZATION FLOWPATH OI4C.W

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41 1379m(073186)

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10.0 ATTACHMENTS 10.6 Least Squares Fit Statistical Technique In order to comply with the calculation techniques of ANSI N45.4-1972 and 10CFR50, Appendix J, it was necessary l to perform a least squares fit of the ILRT data. The method for "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured data. The criterion for the best fitting line to a set of data points is that the sum of the squares of the deviations of the observed points from the line must be a minimum. When this criterion is met, a unique best fitting line is obtained based on all of the data i points. The value of the leak rate based on the regression is called the statistically averaged leak rate.

Based on this statistical process, the calculated statistical leak rate is obtained from the equation.

W = At + B l Where W = contained dry air mass at time t B = calculated contained dry air mass at time t=0

~

A = calculated leak rate t = test duration Contained Dry B Air Mass (lbs) slope =A 0

Test Duration (hrs)

The values of the constants A and B such that the regression line is best fitting to the ILRT data are:

E = {N2(ti )(W i )} - {([t i)({Wi )} = (((t -t)(W i -W)}

i

{N{(ti 2)-({t)2} i 1(ti-t)2 B = lWi - Alti = ({ti 2)(lwi)-({t)({wi t) i i N N[(t )2-({t i)2 i

l By definition, leakage out of the primary containment is considered positive leakage; therefore, the statistically averaged leak rate in weight percent per day is given by Lg = -2400 (A)/(B) (weight %/ day) 42 1 1379m(080586) i A

10.6 (continued)

In order to calculate the 95% confidence limits of the statistically averaged leak rate, the standard deviation of the least squares slope and the T-Distribution function are used as follows:

'a= 1 7

NI(Wi)2 _ (ygi)2 -

i -A2 '1/2

[ (N-2) ( NE(ti)2 - (Eti)2 ,

UCL = L3+0 (TE)(2400)

B Where TE = 1.645 + 1.5068 + 1.7136 (N-2) (N-2)Z N = number of data sets ti = test duration at the ilh data set Wi = contained dry air mass at the i$h data set a = standard deviation of least squares slope TE = value of the single-sided T-Distribution function with 2 degrees of freedom (conservative numerical values of computerized program)

La = statistically averaged leak rate in %/ day UCL = 95% upper confidence lir.it WBASE = contained dry air mass at time t=0 l

43 1379m(080586)

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