Text

Reactor Containment Bldg Integrated Leak Rate Test (Preoperational)
	ML20137V669
Person / Time
Site:	Catawba
Issue date:	11/21/1985
From:	Beaver W, Carwile W, Rosalyn Jones; DUKE POWER CO.
To:	;
Shared Package
ML20137V661	List: ML20137V656; ML20137V669;
References
	NUDOCS 8512100053
	Download: ML20137V669 (136)
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DUKE POWER COMPANY

) CATAWBA NUCLEAR STATION UNIT 2

REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST 1

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PSA**A88s8ss$8j44 g

DUKE POWER COMPANT CATAWBA NUCLEAR STATION UNIT 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST (PREOPERATIONAL)

CONDUCTED JUNE 29 - JULY 11, 1985 Prepared By:

AJ N

W.' M.'Carwile Associa En eer Reviewed By:

R.f: Jones V

Test Engineer Reviewed By:

M W. F. Be' aver Performance Engineer Approved By:

. W-J4f. Co(c Superintendent of Technical Services

' TABLE OF CONTENTS Page I.

DEFINITION OF SYMBOLS AND ABREVIATIONS 1

. II.

INTRODUCTION 3

III. TEST PURPOSE 4

IV.

SUMMARY

5 V.

TEST ORGANIZATION 6

VI.

TEST BACKGROUND INFORMATION 7

A'.

Test Method 7

B.

Calculation Technique 7

C.

Test Activity Flow Chart 7

D.

Test Acceptance Criteria and Test Results 7

E.

Results of Type-B & C Leak Rate Tests 13 VII. TEST EQUIPMENT 14 A.

Instrument Specifications 14 B.

Computer Program 15 C.

Instrument Error Analysis 16 VIII. CONCLUSION 18 IX.

ILRT FIGURES 19 X.

RTD LOCATIONS 24 XI.

APPENDICES A.

Derivations and Formulas for Catawba Containment Leak Rate Computations B.

Raw and Processed Data C.

Test Log a

Pag 1 of 26 I.

DEFINITION OF SYMBOLS AND ABBREVIATIONS ILRT Integrated Leak Rate Test E

Repeatability error e

Absolute error I.

Measurement system error

'F Temperature, degrees Fahrenheit FOM Figure of Merit L,

0.20% by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at P,, 14.68 Pstg L

Measured overall integrated containment leakagS rate.

It is <-

0.75 La L

Maximum allowable reduced pressure (7.34 psig) test leak rate.

Determined during the preoperational test and is equal to L*

(L,4,) with L

/L,, 5 0.7 t

3 L

Measured overall integrated containment leakage rate during tm reduced pressure test.

It is 5 0.75 L LR Total observed leak rate during the ILRT.

LR(95%)

95% upper confidence level of observed leak rate of the containment vessel L

Leak rate of all penetrations, valves, flanges which cannot be aux exposed to test pressure.

L Total observed leak rate during the supplemental test c

L The known leakage rate superimposed on the containment during the supplemental test.

LLRT Local leak rate test P

Pressure P,

Design accident. pressure psia absolute pressure psig Gauge pressure a

Page 2 of 26

R Temperature, degrees Rankine SIT Structural integrity test T

Temperature T

Dew point temperature dp t

Time V

Containment' volume, cubic feet i

a

Page 3 of 26 II.

INTRODUCTION The purpose of this report is to provide adequate information so that an objective review of the test can be performed. This will ensure that the test results reflect truly the leakage characteristic of the as-built containment.

In conformance with the Appendix J of 10CFR50 and associated ANSI standards, the absolute method and mass plot techniques, which require monitoring the containment vessel temperature and pressure to determine the change in containment vessel air mass caused by leakage, are used as the framework for selecting test equipment, developing test computer programs and test procedures.

The Catawba Unit 2 Containment System consists of a containment vessel and a separate reactor building enclosing an annulus. The following containment vessel specifications are used as base data for the containment leak rate test.

3

- Containment Net Free Volume 1,216,173 ft (no ice loaded)

- Design pressure 15 PSIG

- Calculated Peak Accident Pressure 14.68 PSIG

- Test Pressure

> 14.68 PSIG for Full Pressure Test

- Test Temperature Ambient 51 Resistance Temperature Detectors, 3 Dewpoint hygrometers and 3 pressure sensors are installed at predetermined locations in the containment vessel to determine the weighted averages of containment vessel temperature, vapor pressure and pressure. The Catawba containment vessel leak rate test utilizes a fully automatic Data Acquisition System. All raw test data is scanned, printed and recorded on Cassette tape automatically to minimize uncontrolled random errors. Assigned engineers of Duke Power Company were responsible for drafting and conducting the test. Two 12-hour shift crews which consisted of one shif t coordinator, one shif t engineer, and two technicians were utilized to maintain 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test activity.

Pressurization for the Catawba Unit 2 ILRT was accomplished by 3 diesel driven portable air compressors / dryers rented from Atlas-Copco. Two compressors were rated at 900 cfm @ 120 psig and one was rated for 1200 cfm @ 120 psig. These compressors supplied air directly to Upper and Lower Containment and to the Ice Condenser through a 40*F dewpoint dryer.

When the test was completed, the containment vessel was depressurized through the containment hydrogen sample and purge system in the annulus and the containment air release and addition system in the Auxiliary Building. The. release rate can be controlled if the air is contaminated.

Section IX, Figures 2 and 3 show the pressurization and depressurization path used in this test.

a

Pega 4 of 26 III. TEST PURPOSE The purpose of the Preoperational Containment Integrated Leak Rate Test is to determine the leak rate of the containment vessel under controlled test conditions; to verify that there were no unidentified openings in the containment vessel due to incomplete construction; and to evaluate the possibility of accurately measuring the containment leak rate in a shorter period of time and/or at a reduced pressure.

The containment vessel was preconditioned to provide test conditions which satisfy the following:

- The vessel is under a calculated accident pressure of 14.68 psig for the Full Pressure Test.

- Air temperature and pressure are stable to avoid biasing the leakage characteristics.

- The containment vessel and all penetrations are lined up as close as possible to the predicted post-accident condition; i.e., those portions of the fluid system that are part of the reactor coolant pressure boundary and are opened directly to the containment atmosphere under pcst-accident conditions and become an extension of the boundary of the containment shall be opened or vented to the containment atmosphere prict to and during the test.

The test utilized highly accurate sensors and an automatic data system to assure the accuracy and quality of the test data.

s Statir tical and error propagation analyses are performed on the test data to ensure that the test results are reliable and accurate.

Y

Pagn 5 of 26 IV.

SUMMARY

The Containuent Vessel Integrated Leak Rate and Structural Integrity Test was initiated on 6/29/85 and completed on 7/9/85.

It was conducted in compliance with the Catawba FSAR and Title 10, Code of Federal l

L Regulations, Part 50, Appendix J, which states that the containment vessel is subject. to a test to assure that an acceptable upper limit of leakage of radioactive material is not exceeded under design accident basis.

l The vessel was initially pressurized up to 16.618 psig (110.8% of design pressure) and held for 10 minutes for the Structural Integrity Test.

Pressure was then reduced to 5 85% of P and held for 2 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to allow T

for outgassing. Pressure was then increased to 2 7.34 psig and the reduced pressure test was begun at 0215 on 7/2/85 after a > 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months temperature stabilization period. After obtaining 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months worth of what appeared to be acceptable results, the data aquisition equipment began to fail. Values were reading correctly on the digital display, but were being randomly changed as they were relayed to the data logger. Due to this problem and the fact that a half pressure test was not required, the half pressure test was aborted and efforts concentrated on repairing the equipment.

Pressure was then increased to 2 14.68 psig and the full pressure ILRT was begun at 0415 on 7/6/85 after a > 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months temperature stabilization period.

Ths data was recorded manually from the digital output display and edited if necessary, on the computer. The test was evaluated as acceptable at 0745 on 7/8/85 using 27.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of test data with the following results:

1 LR = 0.1202962%/ Day LR(95%) = 0.1255774%/ Day The 95% UCL was less than the acceptance criteria of 0.15%/ day.

~

The supplemental verification test began at 0735 on 7/8/85 and was determined acceptable at 1835 on 7/8/85 with an observed leak race of 0.3018148%/ day.

This test was conducted per test procedure TP/2/A/1200/06, Containment Initial Integrated Leak Rate Test and Structural Integrity Test.

Pcg3 6 of 26 V.

TIST ORGANIZATION In order to assure that the test is conducted in a safe and efficient manner, assigned personnel are organized as shown and their responsibility defined.

TEST COORDINATOR l

INSTRUMENT ASSISTANT TEST TEST SUPPORT COORDINATOR COORDINATOR GROUPS I

i SHIFT COORDINATOR DATA COORDINATOR DATA TAKER Test Coordinator: His lead responsibility is to provide overall planning and efficient execution of the test. He is also to provide same support to his 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift.

Assistant Test Coordinator: His lead responsibility is to assume test coordinator responsibilities during his 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months shift.

Instrumentation Coordinator: His responsibility is to provide test equipment maintenance support to Test Coordinator.

Test Support Groups: Their responsibilities are to furnish technical support to Test personnel as required in conducting the ILRT, solving test problems, and minimizing schedule delays.

Shift Coordinator: Assume general responsibility for ILRT execution on a shift basis.

Data Coordinator: His lead responsibility is to process and edit raw data.

Data Taker: Record data accurately at correct intervals.

J

Pags 7 of 26 VI.

TEST BACKGROUND INFORMATION A.

Test Method: The absolute method of leakage rate testing is used for the Catawba test. This requires the determination and calculation of air losses by the containment vessel leakage over a stated period of time by the means of direct pressure, temperature and dewpoint observations during the period of the test.

Sensors are properly located to provide an average value of the containment vessel temperature and pressure. The effect of the partial pressure of water vapor is measured and compensated.

Upon completion of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leak rate test, a test is performed to verify the accuracy of the leak rate test. This requires superimposing a controlled and measurable leak on the containment vessel and the composite leakage of both the containment vessel and the superimposed leak is measured. The difference between the result of the leakage measurement obtained prior to the introduction of the superimposed leak and that of the composite leak determines

- the accuracy of the leak rate test.

The test environment is simulated as close to that of designed accident basis as possible. All portions of the fluid systems that are postulated as opening directly to the containment or outside atmosphere under post-accident conditions are opened or vented during the test except systems required to maintain the plant in safe conditions during the test.

The test pressure is the calculated design basis accident pressure of 14,68 psig for the full pressure test.

B.

Calculation Technique: Mass of the containment vessel air volume is calculated by the Ideal Gas Law for 24 consecutive hours and plotted s

against time. The leak rate is obtained by a linear least square fit to the mass plot graph. The 95% confidence upper limit of the leak rate is calculated by applying the Student T Distribution Test on the leak rate test result. This upper limit is compared with the acceptance criteria to determine the completion of the test. See also Appendix A.

C.

Test Activity Flow Chart: Figure 1, Containment Pressure versus Time provides an overall look of the test activities. This provides information for test planning and test execution.

D.

Test Acceptance Criteria And Test Results 1.a.

Structural Integrity Test Acceptance Criteria:

The Containment Structural Integrity Test is acceptable if a pressure of at least 16.5 psig is maintained for 10 minutes without any apparent changes in appearance of or other abnormal degredation of the containmant vessel surfaces.

I.

Pass 8 of 26 The Reactor Building Structural Integrity Test is acceptable if a visual inspection detects no abnormal degredation or changes in appearance.

1.b.

Structural Integrity Test Results:

No apparent changes in appearance or abnormal degradation of the containment vessel surfaces were detected after a >

10 minute hold at 16.618 psig.

The Reactor Building Inspection detected no abnormal degradation or changes in appearance.

2.a Hot Penetrations Leakage Test Acceptance Criteria:

The hot penetration soap bubble test detects no leakage for those penetrations listed in the test procedure per Tech Spec 4.6.1.2.e.

2.b Hot Penetrations Leakage Test Results:

No leakage was detected for those penetrations listed in the test procedure.

3.a.

Full Pressure Test Acceptance Criteria:

The measured overall integrated containment leakage rate (L,,) is less than or equal to 0.75 L, with the test pressure > 14.68 psig. L,, $ 0.75 L, where L, = 0.20 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months @ P, (14.68 psig) L, 5 0.15%/ Day.

Also, L,,= LR(95%) + L,,

where LR(95%) = 95% Upper Confidence Level of observed leak rate of the Containment Vessel and L

= Leak rate of all penetrations, valves, flanges which cannot be exposed to test pressure due to system operation.

The difference ! stween the supplemental verification test and the total observed leak rate is within 0.25 L,:

(L ~ b ) - LR

$ 0.25 L, c

o Where L = Total observed leak rate during supplemental test e

L, = The known leakage rate superimposed on the cortainment during the supplemental test

f Pigs 9 of 26 The quantity of air bled from containment during the supplemental test must be equivalent to 75 to 125% of the leakage rate L,.

0.75 L, f L, $ 1.25 L, 3.b Full Pressure Test Results:

24-Hour Test Result (0415, 7/6/85 to 0744, 7/7/85)

LR = 0.1202962 %/ Day LR(95%) = 0.1255774 %/ Day The following penetration were not exposed to test pressure due to system alignment required by ILRT. They were Type C tested and the leakage added to L, Penetration #

System Reason M204 VQ Flowpath for turbine flowmeter during imposed leak rate test.

M346 VY Relief valve for containment connected to this penetration.

CNIP-2 MIS MI ILRT Pressure sensing line.

CNIP-2MI6 MI ILRT Pressure sensing line.

CNIP-2MI7 MI ILRT Pressure sensing line.

The following penetrations were not exposed to test pressure due to an exemption from venting and draining in Supplement 3 to the Catawba SER. These penetrations contain a " reverse" check valve for overpressurization protection and process containment isolation valves receiving seal injection water. Therefore the reverse check valve is Type C tested and the results added to L,,,,

Penetration.g System M256 (2NV90 only)

NV' M230 (2RN485 only)

RN M308 (2RN430 only)

RN M221 (2WL868 only)

WL M345 (2WL806 only)

WL M359 (2WLA22 only)

WL M374 (2WL321 only)

WL

Pcga 10 of 26 The following penetrations were not exposed to test pressure due to following reasons:

Penetration #

System Reason CNIP-2NS10 NS Pressure transmitter 2NSPT5260 was an exception to turnover and was not installed prior to ILRT. The transmitter was Type C tested after ILRT and the results added to L, M240 RN This penetration has the outside isolation valve supplied by NW.

The l

inside check unit is type C tested.

i However, it was noticed to ne leaking excessivly prior to l

beginning the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leak rate test and so the penetration was isolated.

Maintenance was performed on 2RN438 and valve internals were rebuilt /

replaced. A Type C test was performed on 2RN438 and results were added to L aux M321 (2KC279 only)

KC Exempted from venting and draining since both containment isolation valves receive seal injection water. A reverse check valve bypasses this inside containment isolation valve. This check valve is Type C tested and results added i

t o L,,

The NRC was notified that this penetration would be exempted from venting and draining for Type A testing per letter from H. B. Tucker to Harold R. Denton, dated July 30, 1985, File No.: CN-801.01.

Upper Air Lock IAE Pressurization fixture was installed Emerg. Air Peneration on penetration to allow entry into containment during inspections.

Type B test results were added to baux

Pzga 11 of 26 Leakage

%/ Day Leakage

~

P'enetration System (scem) x 2.1476x10 ' scem

= _%/ Day M308 RN 1

x 2.1476x10

= 2.1476x10 '

~

M221 WL 1

x 2.1476x10 '

= 2.1476x10

~

M345 WL 1.8 x 2.1476x10 '

= 3.8657x10 '

M359 WL 1.6 x 2.1476x10

= 3.4362x10

M374 WL 49.4 x 2.1476xio"*

= 1.0609x10

M240 RN 13 x 2.1476x10

= 2.7919x10

M321 KC 1

x 2.1476x10

= 2.1476x10

CNIP-2NS10 NS 1.8 X 2.1476x10

= 3.8657x10

-8

-8 Upper Air Lock IAE 3.16 x 2.1476x10

= 6.7864x10 Emerg. Air Penetration

~

Total L, 3.3279 x 10 '%/ Day

=

Therefore, L,

= LR(95%) ' L,

= 0.1255774%/ Day + 3.3279x10 1 %/ Day

=

0.1255807

%/ Day Which is within Acceptable Criteria of < 0.15%/ Day

P:gs 12 of 26 Supplemental Verification Test Results:

L = 0.3018148%/ Day c

L, = 0.200003%/ Day LR = 0.1202962%/ Day

\\ (L o) -

5 0.25 L,

~

c

{(0.3018148-0.20003)'-0.1202962'$0.050%/ Day 0.0185 5 0.050%/ Day which is within Acceptance Criteria

+,

0.75 L, $ L, 5 1.25 L, 0.75 (0.20) $ 0.200003 $ 1.25 (0.20) 0.15%/ Day $ 0.200003%/ Day 5 0.25%/ Day Which is within Acceptance Criteria.

Prg3 13 of 26 E.

RESULTS OF TYPE B AhT) C LEAK RATE TESTS Test Final Conservative Test Results PT/2/A/4200/01C, Isolation 2006.6 scem 4.3411x10 %/ Day Valve Leak Rate Test

=

PT/2/A/4200/41A, Containment 3395.8 scem 7.293x10 %/ Day Purge Isolation Valve Leak Rate Test

=

PT/2/A/4200/41B, VQ Penetration 80.0 scem 1.7181x10 %/ Day Leak Rate Test

=

PT/2/A/4200/01D, Fuel Transfer 1.0

'secm 2.1476x10 %/ Day Tube Leak Rate Test

=

TP/2/A/1200/18, Upper Cont.

1683 scem 3.6144x10 %/ Day Personnel Lock Leak Rate Test

=

TP/2/A/1200/19, Lower Cont.

1861 sccm Personnel Lock Leak Rate Test

,=

3.997x10 %/ Day PT/2/A/4200/01H, Equipment Hatch 14.5 sccm 3.1140x10 %/ Day Leak Rate Test

=

PT/2/A/4200/01B, Electrical 271.4 sccm 5.8286x10 %/ Day Penetration Leak Rate Test

=

PT/2/A/4200/01P, NF Penetration 4.2 sccm 9.020x10 %/ Day Leak Rate Test

=

PT/2/A/4200/01R, M301 Penetration 2.8 seem 6.013280x10 %/ Day Leak Rate Test

=

Pega 14 of 26 VII. TEST EQUIPMENT The ILRT instrumentation system is designed to accurately record test pa rameters. The system consists of a central data acquisition system with a remote scanner / multiplexer unit and individual temperature, pressure, and dewpoint sensors. All RTD's are wired to the remote scanner / multiplexer unit located inside containment. The signals are then multiplexed and sent to the central data acquisition facility.

All-other sensors are wired directly to the data acquisition facility located outside contalument in a test van.

A.

Instrument Specifications Precision Pressure Gauges are Ruska Model 6000-801-40 PSIA gauges.

Range:

0 to 40 PSIA Repeatability - 24 Hr: i.0008 PSI:

90 Day: i.0016 PSI Accuracy:

(.008% Full Scale +.012% Reading) or better, traceable to NBS Output:

Direct digital output plus BCD parallel signal for recording.

The Dewpoint Temperature Analyzers are General Eastern system 1200 AP sensors with Model 700 aspirators.

Range:

-40 to +120*F Dewpoint Repeatability -i.05'F Accuracy: 1.4*F dewpoint, traceable to NBS Output:

Direct digital readout plus 0-50 mV signal recording The Resistance Temperature Detectors are Leeds & Northup Catalog Number 178055 Range:

-100 to +250'F Accuracy:

!.40*F over 32 to 100*F h

Element:

Copper Resistance:

10 ohms at 77'F Sectiot IX, Figure 5 shows placement of RTD's while Section X gives their general locations.

The Turbine Flowmeter is a Flow Technology Model FTC-8C5.0-GJS Flocapsule with Model PRI-402A Flow Rate Monitor.

Range:

0.5 to 5 ACFM Repeatability - i.25% FS Accuracy: 10.2%, Traceable to NBS.

1.0125 ACFM i

Page 15 of 26 Output:

Visual display plus 0-5 VDC signal for recording The' Data Acquisition Facility is a Leeds and Northup Catalog Number 70072-409-4999-6-000000-0600-00-001-301-099 Digital Data Surveillance Facility with the following features:

- Numation Numeric Display

- Scanner / Programmer

- Digital Printer

- Digital Clock

- Cassette Tape Recorder Section IX, Figure 4 shows the test instrumentation set-up.

B.

Computer Program To provide on-line data analysis, a computer program is developed using formulas and methods specified in Appendix A.

The Leak Rate Test Program (LRT) reads instrument readings from a magnetic tape cassette taken from the data recorder on the Digital Data Surveillance Facility (DDSF). The raw data from the tape is calibrated using quadratic curve fits. This calibrated data is then checked for validity. Using the mass plot analysis method, the calibrated vertfled data is processed to yield a normalized weight which is the ratio of the mass of air in the containment at the present time to that which was initially present when the test began.

Linear regression and confidence interval calculations are then performed to determine whether the results have coveraged sufficiently to yield an accurate indication of the actual containment leak rate.

Using the terminal procedures detailed in the user documentation, the test administrator can run the program from any teletype-compatible terminal device having magnetic tape cassette capability. The program is designed for interactive processing so that at each step the user will be queried as to how he wishes the work to be accomplished.

Instrument parameters and readings can be entered into the computer system either automatically from cassette or manually from the terminal keyboard.

If any errors are detected in the' data, then the user will have the option of correcting the specific error on the computer instead of re-entering all of the data.

All data stored in the computer is protected by a password selected at the beginning of the test'and must be specified each time the program is run to gain access to the data. This provides some measure of protection against inadvertent intrusion during the conduct of the test. At the conclusion of the test all of the stored data, from raw instrument readings through intermediate results to the final results, will be copied to an archival storage medium to satisfy long-term retention requirements of regulatory agencies. The archives can be placed on active storage at any time to verify calculations or generate reports.

Pegs 16 of 26 C.

Instrument Error Analysis (Equations used in the section can be found in ANS N274, Draft Revision 3, November 15, 1978)

Symbols:

FOM = Instrument Figure of Merit (%/ day) t

= Test duration (hrs)

P

= Test pressure (PSIA) (use 14.68 psig for Full Pressure Test, 7.34 psig for Reduced Pressure Test)

P

= Vapor pressure at test time (PSIA) y T

= Cont. weighted average absolute test temp. (*F) (Assume 76.63*F)

= Error associated with measurement of change e

E

= Sensor error (Sensitivity)

I

= Measurement system error excluding sensor 1.

Pressure:

No. of sensors = 3 Range 0 - 40 PSIA Sensor Error (E ) = 1 0.008%FS = 0.0032 PSIA p

Measurement, system repeatability error (Ip) = 10.002%FS = 0.0008 PSIA

((E )8 + (I )8 ]E p

p e =i

= 10.0019044 PSIA P

(3) 2.

Vapor Pressure:

No. of sensors = 3 Range -40*F to 120*F Sensor Error E = 10.40*F or i.001268 PSIA

Measurement System Error (I) = 10.05'F or 1.0001585 PSIA *

[(.001268)8 + (.0001585)8]I

/

(3)E

= i.0007378 PSIA e

=

pj

At dewpoint of 36*F, the rate of vapor pressure change per l'F is.00317 PSIA /*F

Page 17 of 26 L

3.

Temperature No. of Sensor = 52*

Sensor Error =

0.40'F or i 0.40'R Measurement System Error = i.15'F or i.15'R I

[(.4'R)* +(

.15'R)8]

(52)E i.0592420*R e =i

=

T

Although only 51 were used during the test due to one RTD giving an open signal.

4 FOM (Figure of Merit) 2 +2e)

FOM = i 2400

[2ep h + 2 [e T

py kp j

(p T /._

t

=i 2400 2.0019044h8 + 2 0007378h8 +2 0592420 8 1/2 24 29.376 I

29.376 I

536.3 1

4

= i.0184585% per day for Full Pressure Test (Note that value is < 0.25L, = 0.05)

These FOM values indicate that test instrument repeatability is adequate to provide a precision measurement of maximum allowable leak rate for both Full and Reduced Pressure Leakage Tests.

Random errors on test results were analyzed under 95% confidence analysis and incorporated into the test results for acceptance verification.

The test also underwent the required accuracy test at the end of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ILRT and met the Acceptance Criteria (See test results).

Page 18 of 26 VIII. CONCLUSION With all conservative factors built in the test results analysis, the following conclusions were made on the Catawba Unit 2 ILRT:

1.

Catawba Unit 2 Containment Vessel is capable of safely containing fission products under designed accident conditions.

2.

With a properly controlled test environment, test acceptance could be attained much earlier than the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months minimum required time for a 24-hour test.

C 3.

No unidentified opening in the Catawba Unit 2 Containment vessel exists due to incomplete construction.

-~._.

t Page 19 of 26 IX.

ILRT FIGURES 1.

Containment Pressure vs Time 2.

RTD Locations and Pressurization /Depressurization Paths i

3.

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4.

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8 o

TRD

/.

u 7

eee r) r

/1 -

sdc t ui s

02-

)

5 c d i, J;

ll',

ee dd-0 l

0 PT' r o ll, e

s A ),

7 sb$,FB ERTC

'}-

/1 uo ue

'q eeo f

)i 02 rr lg up sm T

L_

6 et li iatp n

p i l

0 P

mr - e rR e

t 0

I 7

.ee nDAee l

sp t at d A

sr t t

/1 ue aeF I

02 rs mu l4}

i 7

es Ap l l-P u

c t l Tr q i l

Ii r

I ei unP t

e!

0 sz ig r

-ljd.

s!

0 t i s

e lj _

u!

s n

iTs g

t osi

'}_8 7

r

/1 F

o r

i elI i u 02 o

n e

l, El I

t 8

'r 00 7

'I

l'

jg l[

e e lk ltN I i

/1

'it DB 02

o a

9 l

pg,

C i

ri en ~

Vm s

ep

s Trl 0

u eie + "

l 0

r sft 8

i t ie

7 z

cd

/1 l

i a

n t

1 2 g,

i j L_

0 o

n

p Pcgm 21 of 26 FIGURE 2 RTD Locations and Pressurization /Depressurization Paths

~-

A A

a u

n:._.

m n

g g N' @

STM STM

?

'3 L

'r g_i i

i x

. ~..

1 s

9,

~

g

$_5_g..

n

s n

v@

- (,, j,1 @v c

e : rm.m.

--a r% %ps.s, s.ws.mw.

a St; 9 :.- -

Yu v

e

$ @-4 v-.. -

v-.

a

=

,r g.

_m.

-s

k k

Page 22 of,

I la I

la I

13 5

N1

Nd

F9 = d l3 l

\\

e e

d Od I 55

()1 O 2 t

en a en a en n JI J1 J1 IIII!il5 iiiiii,i; a

a a

n >13 i 1111 l

"I "I

SI "I

1111:1 J

I

y: :i ll

1

~,......

x_ z

t y

a 3

3 4

E ou a

i :;l

I

ll f

l i

'T*h Ese N

8

,I

,3r r

~TT

=

h$ig 7 T

{

kl steh I

strii i 1:tv "I

i "I

St:t:

ll l ll f 1:: 3;

!. I fi I

"I I

i i

r1 i !i

!go

j ': 7,l:i u&i lll7;i,,iA;gI"i j

i i

y i

i

e i

j, i

~

u if il I

. l.

it il il i

1 1

i 1

1 i

l

)

}

i Turbine Flow

-2 l

I Flow M.

Display i

RTD's a

Display.

J l

Dewpoint l

Sensor heatron Pressure 1

diock Sensor f

~ ~

Computer i

1 i

f b

Printer I

Magnetic Tape 2

I Reader I

t

[

Magnetic Tape Intercoupler i

CONTATIRE5ft VESSEL Cassete Unit 2

E i

f ILR T van i

i M

FIGURE 4 l

Test Instrumentation System i

i

Page 24 of 26 X.

RTD LOCATIONS LOWER CONTAINMENT (CONTAINMENT VOLUME FRACTION = 0.26121 RTD #

GENERAL LOCATION COMPARTMENT VOLUME FRACTION 1

Wall mounted in incore inst, area 0.0528 2

S.G. D lower support structure el. 570' O.0530 3

S.G. A lower support structure el. 570' O.0530 4

S.G. B lower support structure el. 570' O.0530 5

S.G. C lower support structure el. 570' O.0530 6

Wall mounted in tunnel area 0.0327 7

Wall mounted in tunnel area 0.0327 8

Wall mounted in tunnel area 0.0327 9

Wall mounted in tunnel area 0.0327 10 On top of S.G. 2D 0.0530 11 On top of S.G. 2C 0.0530 12 On top of S.G. 2B 0.0530 i

13 On top of S.G. 2A 0.0530 14 On top of NC Pump 2D 0.0530 15 On top of NC Pump 2A 0.0530 16 On top of NC Pump 2B 0.0530 17 On top of NC Pump 2C 0.0530 18 In Accumulator Room 2D 0.0120 19 In Accumulator Room 2C 0.0101 20 In Accumulator Room 2B 0.0116 21 In Accumulator Room 2A 0.0116

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

-.,_r-.

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

Paga 25 of 26 RTD #

GENERAL LOCATION CONTAINMENT VOLUME FRACTION 25 Column mounted in incore 0.0533 l

instrumentation area 26 Column mounted near lower 0.0419 containment vent 27 Column mounted near lower 0.0399 containment vent UPPER CONTAINMENT (CONTAINMENT VOLUME FRACTION = 0.57'34) l RTD #

GENERAL LOCATION COMPARTMENT VOLUME FRACTION 28 On concrete housing for S.G. 2D 0.0590 l

29 On concrete housing for S.G. 2A 0.0590 30 On concrete housing for S.G. 2B 0.0590 l

31 On concrete housing for S.G. 2C 0.0590 i

32 On wall between S.G. 2A & 2D 0.1150 i

33 On wall between S.G. 2B & 2C 0.1150 34 On wall below crane track el. 665' O.1100 35

.On wall below crane track el. 665' O.1100 36 On cont. spray piping 31'6" of 0.0950 center el. 707' 37 On cont. spray piping 31'6" of 0.0950 center el. 707' 22 Wall mounted in room with air 0.0200 return fans 23 Mounted on ladder support in 0.0590 reactor cavity 24 Mounted on ladder support in 0.0450 reactor internals storage area i

b a

Paga 26 of 26 ICE CONDENSER (CONTAINMENT VOLUME FRACTION = 0.1654)

RTD #

, GENERAL LOCATION COMPARTMENT VOLUME FRACTION 38-43 Evenly spaced around the upper 0.0538 Each plenum area el. 669' 44-47 Evenly spaced around the upper 0.0539 Each plenum area 48-49 Evenly spaced around the lower 0.0882 Each plenum area el. 600' 50 Lower plenum area el. 600' O.1385 52 Lower plenum area el. 600' O.1384

7..

I h

t 4

il i

r APPENDICES I

1 d

I I

J

'?i 4

f 9

J -

l f

o

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

'""'Te

-a

,m, e-,._

=

i i

i.

l.

L i

APPENDIX A DERIVATIONS AND FORMULAS FOR CATAWBA CONTAINMENT LEAK RATE COMPUTATIONS This appendix presents derivations of formulas used to develop the Catawba leak.

rate. computer program.

J i

.e-.

4,

,-m_e...

,,,,,.4

._,___n,--.

Page 1 of 8 DEFINITION OF SYMBOLS P =

Absolute pressure in the Containment Vessel (PSFA)

T =

Weighted average absolute temperature of the Containment Vessel air compartment (*R) th W..=

Normalized mass of containment vessel air at i data point (dimension less)

P =

Partial pressure of water vapor (PSFA)

V time (min) th t =

Vk= Assigned volume fraction of k sensor (Fraction of volume) th i

Tk= Recorded temperature of k sensor (*R)

W. = Estimated value of W. in the least square fit calculation bl=

Slope of the least square fit line (fraction / min.)

LR(95%) = 95% confidence value of LR LR = Measured containment leakage rate (%/ day) y intercept of the least square fit line (dimensionless) a =

S$= the variance of Wg Sa = the variance of b b

SUBSCRIPTS upper containment compartment u =

L =

lower containment compartment I =

Ice Condenser compartment v =

vapor 1 =

data point at start of test th i = i data point (i = 1 to N)

N =

Final data point of a given set th k = k sensor

-MASS PLOT CALCULATION AND STATISTICAL TREATMENT OF LEAK RATE DATA Normalized Containment Vessel Air Mass The air mass of the Containment Vessel is calculated using ideal gas law compensated for partial water vapor pressure. Air mass of 3 compartments (lower, upper, Ice) ~are determined separately and combined to yield the whole Containment Vessel to simplify the calculation. Normalization of W is g

th applied by taking the ratio of the i value and that of the initial value.

,y.,

Pegs 2 of 8 l

The values 0.5734, 0.2612, 0.1654 are the assigned volume fraction for upper containmant, lower containment and Ice Condenser The average temperature T at each compartmsnt is calculated as the sum of the

-volume weighted recorded temperatures.

1 I -P )

[P-P)i h-P )i P

0.5734 v

+ 0.2612 i v i + 0.1654-v

(

y u

L I

[P-P

[P-P h-P

+

1 0.5734 v

t

+ 0.2612 '

v

+ 0.1654 v

(Tj (T

(T J

u L

I TV T = Ikk k=

1 to 21, 25 to 27 for lower containment k=

22 to 24, 28 to 37 for upper containment k=

39 to 52 for ice condenser See Section X for volume fraction of each sensor.

Leakage Rate of the Containment Vessel The graph of W versus time is least square fitted to yield an estimated g

straight line. The rate of the containment vessel air mass loss (or the

( ~'

gontainment vessel leak rate) is the slope b of the least square fitted line

-W:

g A

W = btg+a g

The value of a and b can be determined by taking the first partial derivation

- W )" with respect to a and b of the sum of square of deviation Q (Q = I (Wg g

and minimize them:

4 A

W

)8 W = bt 6

I (Wg g

g g+a 63 a

=0 6a 6a W

-W =W

- bt

-a g

g g

g

Page 3 of 8 W )2

.6 I (W i

i

= 2 I (W. - bt. - a) = 0 6a I (W - bt - a) = 0 g

g Na + bItg = IWg (1) 3 a

6 I (W.-

- W.

)2 WI = bt. + a 1

1 l

g=

= 0 A

ob 6b W - W. = W. - bt.

a i

1 1

1 6

I (W

- W

)2 1

g

- = 2 I-t.* (WI

- bt. - a) = 0 6b I-t (W - bt - a) = 0 (2) g g g

2 = It.W.

(3) alti + bIti 1 1 with (1) an'd.(3), a and b can be solved by matrix:

Na + (It ) b'= IW (1) g 1

.Ita) b = It W (3)

(It ) a t (

g gg N

IWg It It W nit W - (IWg ) (Itg)

(4) g g g g g N

It.

nit." - (It.)Z 12 1

1 It.

It 1

1 m

Page 4 of.8 Iw It g

g It W It 2 IW It 2 It It W o=

i' i i

=

i i i i i (5)

N It nit 3 - (It.)*

It.

Ik.2 i

1 1

1 LR = -b 144000% per day.

(*unless otherwise specified, all summation will be from i = 1 to i = N It is important to emphasize here that the slope b or leak rate is formulated en the following assumptions:

- the deviation of W. from the true value are distributed according to the gas distribution function 1

- only the W contains random error, not the t g

g

Page 5 of 8 The Confidence Limit of the Slope of the Least Square Line As indicated in the error analysis, the random error is a major contribution which deviates the test result from the true value. Due to the random characteristics of this error, only statistical treatment can possibly evaluate the error effect on the test result.

In order to choose a proper statistical treatment, it is important to identify the characteristics of the observed data.

In the previous derivation, it is found that LR is the outcome of the calculation from the observed temperature and pressure in the Containment Vessel using the ideal gas law and curve fitting method.

It is now obvious that the observed data is a continuous measurement which is completely different from the discrete measurement. The latter requires discrete statistical treatment (X2 chi SQUARE), while the former requires continuous statistical treatment (The t test).

The t test provides information which indicates how much the calculated leak rate deviated from the true value and at what probability.

In other words:

L(TRUE) = LR i " Deviation" (percent of probability)

For t test method " deviation" is defined as:

Deviation = t Sb

- t is a tabulated value which corresponds to the number of Data sets taken and the required probability (in this case 95% is chosen on popular basis).

-S is the standard deviation of the variance of the containment air weight.

b Equation (4) indicates that b = f (W ) and by definition of variance:

g I6bh2 S 2=yI(6W.1 S 2 (5) b 1<

w where S 2 is the variance of W :

y 1

a - bt )2 (W

S,2 =

i i

(6)

Pags 6 of 8 The (N-2) is chosen here instead of N because the least square line W is g

restricted by value of b and a.

The freedom to evaluate the variance of W is 1

reduced by 2 even though N data is recorded.

[NItW-(IWi)

(It)\\

6 L

ii i I 2

nit

- (It )8 8b

=

i i

6W 6W g

g e

let c = nit 8 (It )"

g g

(nit W -(IW)(It))

6 i i i

i C

6b

=

6W 6W f

g nit W - (IW ) (It )

1 6

ii i

i

= c 6W Nt - It

=

g c

6b 8

= 1 Nt It (7) 3 6W C

i i

g Substitute (7) to (5)

S*

8 It

)*

S

=

w I (Nt F

b c

i i

S*

2 8

v' I (N t

- 2Nt It + (It

)")

=

c' i

i i

i S8

- 2 nit Itb + ~ N(It

)*)

i

=

w

-(N*Et 8 7

i i

3

-.en---

- =. -. -

y

.9-

--c-

-~..---,e y-h+

or.

Pega 7 of 8 r

l.-

S2.

2 (N 7t 2 - N(It )2)

=

w7 i

i (8) nit.2 - (It.)2 to (8):

Substitute c =

1 1

2 S

= NS w b

c

=S2 e

w/??

nit 2. It 2 e

=

i i

= It 2 - It 2 N

N i

i N

S 2 2

3w

=

It 2 b

It.;

i N

The identity provides:

(It.)2 1

I(t - t)2 = It.2 _

= It 2. E yt, i

1 i

N S2 32.

32 S 2=

w

=

w

=

(9) b It 2-It 2 y(t _t)2 It 2_t yt i

i i

N I

l

.J

Pags 8 of 8 Summarization:

The following are the essential equations used in developing ILRT computer program:

0.5734[(P-P 0.2612[(P-P

+0.1654[(P-P

+

v

[

v/

i y

5 T

\\T /L LT I

W

=

i 0.5734(P-P))1 1

1 0.2612[(P-P )\\ + 0.1654 [(P-P I

+

v I

v l

l v

l

(

T JL

( T / I (T su T = IT V kk W = btg+a g

l nit W (Ng ) (It )

g 1 g

b=

nit *

(It )*

g g

IWg (Itg ")

(Itg ) (Itg y W) a=

nit * - (Itg)*

g LR = -b LR(95*.) = LR i tS b t va!ue corresponds to f = N-2 and 0.975 I(W - a - btg) 8 S

=

W N-2 8

S i

S

=

w b

It 8 -EIt g

g l

l

_m

9 APPENDIX B RAW AND PROCESSED DATA

a 1

INITIALIZATION DATA

____3

\\

e F a

-- ;;7 w o,..,_

l

,w.

~...,w--

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t...,

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h C

L

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ily e

4:

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h k

5 3

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b

<d E

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I

?

5 1

g 4

5 t.

?

t-

'E b.

R' 5.

I(

lr 3(r.

E

$W h

j

=

g

)

l t

g I

4

(.

ya.*

5

)

M dt.s

_,- = =.-@.

(j g.t u. -

.a e;. =_,.

4, eWGho'WEstiet.,SIWteWftee* _ i N

P

.gr ft gy=P _ Pure g

(

I tame.e o.me 9 -- ___

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_ 88W95 W

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funcu L,

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A e futss.t op a,

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t e t 'I 9 ?

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=

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p 4

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.... C-m : ^- -- = = = = ; _- = = =

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g

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r. 4

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g.sr- -

_ e -- -

-g eg.

gg e.D eust i _.

, IM 9.St

@.tff -46 D4 M6.,es=e ^ ^ 9Pe mgem@b.

_ _-. = _.

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,e

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.3

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e at

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==

..--_==- =-

............ =..==

,.m....

i

.. -...-.... c i

7.

=.

.c.

- e..,,.

7.. -...

=

e;

=.

t

n..',

=,r - _--- Z.

_ z.- -.

=-

.Ds.

n ---

-. -. - _ _- satsst -. =. = _ = =.:.

De

^_ _ - -

22 J.- e

=arbWt o. ddal::::

,. :: _ o~_

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= = = =.

2.W.W

.=.

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=

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e

.==.<,.=.=c

c. :.:....

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= :.

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l e

w......... u.. $.... _..,,............g

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4

p k.

a.

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

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c..c....C... C.. e...c.S.C.,.9. 8..e.o.,..c..,o..

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C

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=

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er 4

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x-w g.

v.

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y 8

f

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t'h a

k t-T 9

.k

[

h.

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i C.*

i r;

k

~-

L A

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(*:

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7 N

k

?

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a u-

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s m

e u r,o orte :

we.e.ne., :- -_.- Oe S.ew a l i.o.

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B O Oe SOOO OO OO S1IO 85 Oee9046696et 81 *

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e i :_-_ = - 2eini>o A

b.

P.

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e peseSDO4'*fWm6eS$hS] >O l.

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i a

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~

{

evenWune.c +-- _.

M 4

1 ej r;

2

,n.

.a Z

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h 1

j

--. -**: : :.: : i t.:_:

U, : : =-: e a a 2. 2 : La :s t.2 : : : *: 2: 28888*2 4

--w,-.---mm-._

ww-.

-,----------r-

m a

s-s

-a

4 L.-

s---

A

-A--

I l

FULL PRESSURE TEST CALIBRATED DATA i

--- - - -~ ---, - ~,,,

I

%r e.s.sessea.m

-aee L6.e.e-en ee.ne*

e. -

s

_ J a

'.mia i.on s.ar s

~

~...~....v.. s..

...v....v... v.,. o.. ;. a.., o... o.. n g

i 9

m i

R 1

.i

.q s

y g

3 y

y t,

i

/

g

/

s

}

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g-c.

a

,s e

g C

s.

5 a

a 3:

n 8

i e

a

(

[.

(

l e

1 1

c'*

i;

~

g t

a y

a e

e u

t 2

4

,1 j

t EEE. =.. '3*

===.EE.

M*:E =E=_i E.=..E.,.,S.=5:.88

[

t=.

4

~.

[

g.

'"*3 l

k 3

W g

I g

5 C

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MASS PLOT ANALYSIS (MIH, 088, MAX)
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NORMALIZED AIR MASS 1
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{ :i '
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.s ICE CONDENSER TEMPERATURE.
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APPENDIX C TEST LOG
Page 1 of 2
SUMMARY
OF MAJOR ACTIVITIES DURING ILRT Date/ Time Comments May 9, 1985 Design Engineering completed pre-ILRT inspections.
June 8, 1985 Began valve alignments for ILRT.
June 21, 1985 Completed set up of rental compressors.
June 26, 1985 Ran and checked out rental compressors. Checked out 0.K.
June 27, 1985 Began venting of Mechanical Penetration bellows to the annulus.
June 29, 1985/1400 Began pressurization of Containment for Structural Integrity Test.
June 29, 1985/2130 Entered Containment for visual inspection.
June 30, 1985/0100 Reached SIT pressure of 16.618 psig, Started 10 minute hold period.
l June 30, 1985/0330 Personnel entered Containment to perform Post SIT inspection.
June 30, 1985/0815 Personnel exited Containment after performing Post SIT inspection.
June 30, 1985/2030 Reached.85P. Began 24-hour outgassing period.
T July 1, 1985/2045 Began repressurization to P
T July 1, 1985/2200 Began 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months hold period for temperature stabilization.
July 2, 1985/0215 Began Reduced Pressure Test.
July 4, 1985/2000 Decided to abort Reduced Pressure Test due to unacceptable readings and problems with data acquisition equipment.
July 4, 1985/2330 Began pressurizing to Pa.
Due to problems with data acquisition equipment, readings were taken manually to verify correctness.
July 5, 1985/2345 Began 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months hold period for temperature stabilization.
July 6, 1985/0415 Began Full Pressure Test.
Page of 2 D-te/ Time Comments July 1, 1985/0715 Satisfactorily completed Full Pressure Test. Allowed General Office Personnel to work on data acquisition equipment.
July 8, 1985/0735 Data acquisition equipment now working better -
continued to take manual readings and started the Supplemental Verification Test.
July 8, 1985/1835 Completed Supplemental Verification Test.
l July 8, 1985/2100 Began depressurization of containment after checking results of ILRT.
July 9, 1985/0715 Completed depressurization of Containment.
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