ML20054B521

Primary Reactor Containment Integrated Leakage Rate Test, Final Rept

ML20054B521
Person / Time
Site:	Grand Gulf
Issue date:	04/14/1982
From:	BECHTEL GROUP, INC.
To:
Shared Package
ML20054B503	List: AECM-82-140, Forwards Primary Reactor Containment Structural Integrity Test & Primary Reactor Containment Integrated Leakage Rate Test, Final Repts.Fsar Section 3.8 Will Be Revised to Include Results of Containment Structural Integrity Test ML20054B505 ML20054B521
References
NUDOCS 8204160572
Download: ML20054B521 (50)

Text

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MISSISSIPPI POWER AND LIGHT CO.

GRAND GULF NUCLEAR STATION j

UNIT 1 DOCKET NO. 50-416 1

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PRIMARY REACTOR CONTAINMENT INTEGRATED LEAKAGE RATE TEST REPORT l

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Submitted To j

The United States Nuclear Regulatory Commission

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Pursuant To Facility Operating License 1

O 8204160572 820414 PDR ADOCK 05000416 A

PDR

TABLE OF CONTENTS Page No.

I I.

INTRODUCTION 1-1 II.

TEST SYNOPSIS 2-1 III. TEST DATA

SUMMARY

3-1 IV.

ANALYSIS AND INTERPRETATION 4-1 V.

COMPUTER REPORT AND DATA PRINTOUT 5-1 i

APPENDIXES A.

Bechtel ILRT Computer Program A-1 B.

ILRT Stabilization Data B-1 1

l C.

ILRT Summary Data C-1 D.

ILRT Calculations Mass Point Analysis D-1 Total Time Analysis D-2 Trend Report Analysis D-3 l

E.

ILRT Plots Temperature Versus Time E-1 Pressure Versus Time E-3 Air Mass Versus Time E-5 F.

Verification Flow Test Summary Data F-1 G.

Verification Flow Test Calculations Mass Point Analysis G-1 Total Time Analysis G-2 Trend Report Analysis G-3 H.

Bypass Leakage Rate Calculation H-1 1.

Local Leakage Test Summary Data I-l O

DH-103 11

_ ~ _ _

[]

I.

INTRODUCTION U

The Reactor Containment Building Integrated Leakage Rate (Type A) test is performed to demonstrate that leakare through the primary reactor containment systems and components penetrating the primary containment does not exceed the allowable leakage rate specified in the Grand Gulf Nuclear Station Final Safety Analysis Re port (FSAR).

The successful preoperational Integrated Leakage Rate Test (ILRT),

Verification Test, and Drywell Bypass Tert were completed on January 5, 1962 at Grand Gulf Nuclear Station Unit 1.

Acceptance criteria for both ANSI /ANS 56.8-1981, " Containment System Leakage Testing Require-ments," and BN-TOP-1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants,"

were met for an 8-hour chort duration test.

Calculations were per-formed using the ANSI /ANS 56.8-1981 " Mass Point Analysis Method" and BN-TOP-1, " Total Time Analysis Method." The test results are reported in accordance with the requirements of ANSI /ANS 56.8-1981, Section 5.8 and 10CFR50, Appendix J, Section V.B.3.

The purpose of this report is to provide information pertinent to the activities related to the preparation, test performance, and reporting of the Grand Gulf Nuclear Station Unit 1 ILRT.

Section II, Test Synopsis, presents the highlights of activities and events which occurred prior to and during the ILRT.

I s_s/

Section III, Test Data Summary, contains the data and results necessary to demonstrate containment atmosphere stabilization, an acceptable leakage rate, and a successful verification test.

In addition, plots provided in Appendix E supply a visual history of containment atmos-pheric conditions beginning with the stabilization condition, through-out the 8-hour short duration ILRT period, and ending with the verification test.

Section IV, Analysis and Interpretation, contains technical details of the integrated leakage rate measuring system used during the ILRT, and provides analysis to show that the containment 95% upper confidence limit leakage rate does not exceed 75% of the allowable rate as speci-fied in the plant FSAR.

Section V, Computer Report and Data Printout, describes the ILRT com-puter program and report printouts.

]

DH-103 1-1

l II.

TEST SYNOPSIS TEST PREPARATION ACTIVITIES Prior to containment pressurization for the Structural Integrity Test (SIT) on January 1, 1982, Grand Gulf Nuclear Station Unit 1 test personnel were engaged in measuring containment leakage to ensure a successful preoperational ILRT.

Sources of containment leakage were identified through Types B and C leakage rate testing programs and reduced by repairing those systems and containment components having relatively excessive leakage rates. The results of the Local Leakage Rate Test (LLRT) are presented in Appendix I.

Highlights of the test preparation activities included monitoring both upper and lower personnel hatch pneumatic systems leakage and repairing MSIV guard pipe inspection port seals, positioning sensors, verifying associated volume fractions, and conducting a temperature survey to ensure that all sensors could accurately monitor their respective subvolumes. An in-situ check, as specified in ANSI /ANS 56.8-1981, Section 4.2.3, was conducted to verify that all ILRT instrumentation was indicating correctly. The following items are presented in chronological order, and detail significant activities performed during the test preparation and successful execution.

The Type A test procedure was reviewed to verify compliance with a

Plant Technical Specifications, 10CFR50 Appendix J, ANSI /ANS 56.8-1981, BN-TOP-1, and the FSAR. In addition, test personnel reviewed the valve lineups to verify that the containment systems were in as close to post-accident alignment as possible.

CONTAINMENT PRESSURIZATION Containment pressurization for the ILRT began at 1030 on January 3, 1982. At the start of pressurization, containment fans M41-B001A and M41-B001B, and the containment, steam tunnel, and drywell cooling systems were operating. During pressurization with the containment at 10 to 12 psig, containment fan M41-B001B tripped off on overcurrent j

at approximately 68 amperes.

ILRT pressure of 12.27 psig (26.24 psia) was reached at 1525. Containment fan M41-B001A was then manually tripped to prevent a possible uncontrolled trip.

CONTAINMENT STABILIZATION Af ter reaching ILRT pressure, the containment atmosphere was allowed to stabilize. The temperature stabilization criteria of ANSI /ANS 56.8-1981, Section 5.3.1.3, and BN-TOP-1, Section 2.2.B, were satisfied. The ILRT stabilization data are given in Appendix B.

l Dil-103 2-1

During containment stabilization the outer doors on the upper and lower personnel locks were opened. A number of small leaks were de-tected through the inner door seals. Leaks were repaired on the upper and lower lock containment pressure sensing systems. The outer doors were closed at 1853.

DURING ILRT Subsequent to containment air mass temperature stabilization, the ILRT for Grand Gulf Nuclear Station Unit 1 started at 2030 on January 3, 1982, and terminated at 0430 on the following day, for an 8-hour short duration test. The accumulated data were statistically analyzed (see Section III (C), Test Results - Type A Test.) The maximum allowable leakage rate (L ) for the primary containment is 0.437 wt.%/ day. The a

Total Time Analysis (BN-TOP-1) yields a leakage rate of 0.068 wt.%/ day with an upper 95% confidence limit of 0.139 wt.%/ day.

Based on the Mass Point Analysis (ANSI /ANS 56.8-1981), the calculated leakage rate is 0.072 wt.%/ day with,an upper 95% confidence limit of 0.079 wt.%/ day.

These values are well below the Grand Gulf Nuclear Station Unit 1 acceptance criterion of 0.328 wt.%/ day (0.75 L )*

a VERIFICATION FLOW TEST A successful verification flow test was performed subsequent to the

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ILRT from 0615 to 1015 on January 4, 1982.

ILRT instrumentation per-formance was checked by imposing a leakage rate (L ) of 0.364 wt.%/ day o

(7.67 scfm). After imposing the leakage rate, the containment atmos-pheric conditions were allowed to stabilize for one (1) hour.

Due to an apparent flow restriction in the verification flow line, the imposed leakage rate could not reach the maximum allowable leakage rate (La) of 0.437 wt.%/ day. The imposed leakage rate (Lo) of 0.364 wt.%/ day is within the acceptance limits of La + 25% as given in ANSI /ANS 56.8-1981, Section 3.2.6(b)(1). The results of the verification test correlated to the ILRT are summarized as follows:

Measured (Acceptance Limit) 95% UCL Test Method Leakage wt.%/ day wt.%/ day a.

ILRT/ Mass Point 0.072 (0.328) 0.079 ILRT/ Total Time 0.068 (0.328) 0.139 b.

Verification / Mass Point 0.431 (0.327-0.545)

NA Verification / Total Time 0.434 (0.323-0.541)

NA DH-103 2-2

= _,

DEPRESSURIZATION AND DRYWELL BYPASS TEST Following the successful completion of the ILRT and verification flow test, containment depressurization began at 1030 on January 4, 1982. At 4.3 psig, a containment entry was made to close the drywell lock for the Drywell Bypass Test. The containment was then depressurized to O psig and the dry-well, whose pressure had dropped to 2.2 psig, was repressurized to 3 psig.

During repressurization of the drywell it was necessary to raise the sup-pression pool level to prevent leakage through the weir wall. After raising the suppression pool level, leakage through the weir wall was observed at 3.02 psig. The drywell pressure was then maintained between 3.00 and 3.01 psig with no observed leakage through the weir wall. The drywell atmosphere was allowed to stabilize for one hour, after which the Bypass Leakage Test began at 0400 on January 4,1982. The Bypass Leakage Test was successfully completed at 0800. The calculated bypass leakage rate of 609.7 scfm is well below the allowable rate of 3500 scfm. Refer to Appendix H Drywell Bypass Test Summary Data for calculations.

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O III. TEST DATA

SUMMARY

Pursuant to the requirements of ANSI /ANS 56.8-1981, Section 5.8, Reporting of Results, the information in this section is provided to supply adequate data for an independent review of the containment system leakage rate test results and instrumentation.

A.

Plant Information Owner:

Mississippi Power and Light Company Plant:

Grand Gulf Nuclear Station Unit 1 Location:

Port Gibson, MS Containment Type:

Mark III NSSS Supplier, Type: General Electric, BWR Date Test Completed: January 5, 1982 B.

Technical Data 1.

Containment Net Free Air Volume 1,670,360 cu ft 2.

Design Pressure P = 15 psig d

3.

Design Temperature T = 185*F 4.

Calculated Peak Accident Pressure P = 11.5 psig a

S 5.

Calculated Peak Accident Temperature T = 181*F a

)

6.

Containment ILRT Average Temperature 40*F-120*F Limits C.

Test Results - Type A Test 1.

Test Method Absolute 2.

Data Analysis Technique Mass Point Leakage Rate per ANSI /ANS 56.8-1981 Total Time per BN-TOP-1 3.

Test Pressure (actual)

P = 11.97 to 12.27 psig 4.

Maximum Allowable Leakage Rate L = 0.437 wt.%/ day a

5.

75% of L 0.328 we.%/ day a

6.

Integrated Leakage Rate Test Results Leakage Rate, L,. wt.%/ day From Regres-At Upper sion Line 95% Confi-dence Limit Mass Point Analysis 0.072 0.079

/~'T Total Time Analysis 0.068 0.139 Dil-103 3-1

1 5

C) 7.

Verification Test Imposed Lo = 0.364 wt.%/ day (7.67 scfm)

Leakage Rate 8.

Verification Test Results Leakage Rate, L., wt.%/ day y

Mass Point Analysis 0.431 Total Time Analysis 0.434 9.

Verification Test Limits:

Test Limits, L, wt.%/ day y

Mass Point Total Time Analysis Analysis 1

j Upper Limit (Lo+ Lam + 0.25L )

0.545 0.541 a

j Lower Limit (Lo + Lam - 0.25L )

0.327 0.323 a

1 10.

Report Printouts:

The report printouts and data plots for the Type A and verification test calculations are provided in Appendixes C through G.

D.

Drywell Bypass test results are provided in Appendix H.

E.

Test Results - Type B and C Tests 4

[N Refer to Appendix 1 for a summary of local leakage rate test results.

F.

Integrated Leakage Rate Measurement System (For ILRT Data Acquisition System, see Figure.2).

1.

Absolute Pressure (2 channels):

Mensor Quartz Manometer Model No. 10100-001 i

PI-l Capsule S/N 2407, Gage S/N 1522 PI-2 (Spare) Capsule S/N 2406, Gage S/N 1555 Range:

0-100,000 counts; 0-100 psia l

Accuracy:

+ 0.015% reading l

Sensitivity:

0.001 psia f

Repeatability:

0.001 psia Calibration Date:

12/23/81 s

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DH-103 3-2 i

2.

Drybulb Temperature (22 sensors):

Rosemount resistance temperature detector Model No.

14632 Series 78 Element:

Platinum Resistance:

Ro = 100 ohms @ 32*F Lead Type:

3 lered potentiometric configuration

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Temperature Range:

32' to 120*F (from calibration data)

Volumetrics Bridge Model No. VSTD 333 Input Voltage:

1 15 volts and 5.2 volt Resistance:

100 ohms @ 32*F Output:

1.0 millivolt /*F; 32*F = 32 mv.,

100*F = 100 av.; 3-wire configuration with l

constant current Adjustment:

Zero, span and linearity (lic:ited)

Accuracy:

1 0.l'F Sensitivity:

0.0l*F Repeatability:

0.0l*F Calibration Date:

12/21/81 N

3.

Dewpoint Temperature (6 sensors):

Dewpoint Temperature Systems - EG6G, Inc., Dewpoint Hygromater, Model No. 660 with 6 sensors and signal conditioning.

Accuracy:

1 0.1*F Sensitivity:

0.0l*F Repeatability:

0.05*F Calibration Date:

12/18/81 4.

Verification Flow (1 channel):

Volumetric thermal mass flow meter, TSI model No. 2013 S/N 1516 Range:

0-10.0 scfm Accuracy:

1 1% F.S.

Sensitivity:

1 0.01 scfm Repeatability:

1 0.01 scfm Calibration date:

10/20/81 5.

Drybulb and Dewpoint Temperature Sensor Volume Fractions (see j

Tables 1 and 2).

\\o DH-103 3-3

l' G.

Information Retained at Plant O'

The following information is available for review at the facility:

1.

Access control procedures established to limit ingress to, containment during testing.

2.

A listing of all containment penetrations, including the total number of like penetrations, penetration size, and function.

3.

A listing of normal operating instrumentation used for the leakage rate test.

4.

A system lineup (at time of test) showing required valve positions and status of piping systems.

5.

A continuous, sequential log of events from initial survey of containment to restoration of all tested systems.

6.

Documentation of instrumentation calibrations and standards (included with documentation should be an error analysis of instrumentation).

7.

Data to verify temperature stabilization criteria as estab-lished by test procedure (Appendix B).

%l f 8.

The working copy of the test procedure that includes signature sign-off of procedural steps.

9.

The procedure and all data that verify completion of penetra-tions and valve testing (B&C-type tests) including as-found leak rates, corrective action taken, and final leak rate.

10.

Computer printouts of ILRT data and manual data accumulation along with summary description of computer program (Appendix C).

11.

The Quality Assurance audit plan or checklist used to monitor ILRT with proper sign-offs.

12.

A listing of all test exceptions including changes in contain-ment system boundaries instituted by licensee to conclude successful testing.

13.

Description of sensor malfunctions, repairs, and methods used to redistribute volume fractions to operating instrumentation where applicable.

14.

A review of confidence limits of test results with accompanying computer printouts where applicable.

v DH-103 3-4

15.

Description of method of leakage rate verification of instru-ment measuring system (superimposed leakage), with calibration information on flow meters along with calculations used to measure the verification leakage rate (Appendixes F and G).

16.

Plots presenting 1LRT data obtained during the test (Appendix E).

17. The P& ids of systems which penetrate the containment.

30

)O Dii-103 3-5

TABLE 1 CONTAINMENT TEMPERATURE AND DEWPOINT SENSOR LOCATIONS AND VOLUME FRACTIONS (ILRT)

Containment Azimuth Distance from Volume RTD Instrument No.

Elevation

( Degrees)

Center Fraction TE-N001-01 274'-0" 352 20'-0" 0.062 TE-N001-02 274'-0" 172 20'-0" 0.062 TE-N001-03 247'-9" 90 30'-8" 0.062 TE-N001-04 245'-9" 265 27'-6" 0.062 TE-N001-05 214'-4" 45 50'-6" 0.062 T E-N001-06 229'-2" 155 49'-8" 0.062 TE-N001-07 216'-0" 225 49'-8" 0.062 TE-N001-08 227'-0" 319 49'-0" 0.062 TE-N001-09 173'-0" 220 52'-0" 0.058 TE-N001-10 163'-0" 305 50'-8" 0.057 TE-N001-11 164'-6" 155 28'-8" 0.022 TE-N001-12 141'-6" 162 50'-3" 0.058 TE-N001-13 141'-2" 90 55'-6" 0.057 TE-N001-14 122'-2" 335 41'-2" 0.057 TE-N001-15 124'-0" 177 51'-6" 0.057

'h-)

TE-N001-16 150'-6" 219 25'-4" 0.022 TE-N001-17 120'-0" 95 27'-8" 0.022 TE-N001-18 129'-0" 187 29'-0" 0.022 TE-N001-19 168'-0" 350 30'-3" 0.022 TE-N001-20 153'-5" 41 27'-3" 0.023 TE-N001-21 119'-9" 278 26'-9" 0.022 TE-N001-22 102'-6" 0

4' O.005 1.000 Containment Azimuth Distance from Volume ME Instrument No.

Elevation (Degrees)

Center Fraction ME-N002-01 247'-9" 90 30'-8" 0.210 ME-N002-02 216'-0" 225 49'-9" 0.210 ME-N002-03 167'-0" 305 50'-8" 0.210 ME-N002-04 122'-2" 355 41'-2" 0.210 ME-N002-05 158'-5" 41 27'-3" 0.080 ME-N002-06 118'-2" 278 26'-9" 0.080 1.000 i

Dil-103 3-6 a

TABLE 2 DRYWELL TEMPERATURE AND DEWPOINT SENSOR LOCATIONS AND VOLUME FRACTIONS (BYPASS TEST)

Drywell Azimuth Distance from Volume RTD Instrument No.

Elevation (Degrees)

Center Fraction TE-N001-11 164'-6" 155 28'-8" 0.138 TE-N001-16 150'-6" 219 25'-4" 0.138 TE-N001-17 120' 95 27'-8" 0.138 TE-N001-18 129' 187 29'-0" 0.138 TE-N001-19 168' 350 30'-3" 0.138 TE-N001-20 153'-5" 41 27'-3" 0.138 TE-N001-21 119'-9" 278 26'-9" 0.138 TE-N001-22 102'-6" 0

4'-0" 0.034 1.000 Drywell Azimuth Distance from Volume ME Instrument No.

Elevation (Degrees)

Center Fraction ME-N002-05 158'-5" 41 27'-3" 0.5 ME-N002-06 118'-2" 278 26'-9" 0.5 1.0 k

DH-103 3-7

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IV.

ANALYSIS AND INTERPRETATION oC\\

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A.

This section is provided pursuant to ANSI /ANS 56.8-1981, Section 5.8.6, which requires analysis of leakage rate data and provides an interpretation of the test results to show proper compliance with acceptance criteria specified in ANSI /ANS 56.8-1981, 10CFR50, Appendix J, and the Grand Gulf Nuclear Station FSAR.

Several corrections must be added to the calculated results of the Unit 1 ILRT. The Plant Chilled Water System (Pen 38 + 39) was not in the post LOCA lineup position and therefore the LLRT result of 2.69 SCFH must be added to the ILRT calculated results. The seal systems on the upper and lower personnel locks required makeup flows of 0.12 and 0.005 SCFH respectively during the ILRT period.

The total correction to be added to the calculated Type A leakage rate is 2.82 SCFH or 0.004%/ day.

Pre-and post-test containment water level measurements indicated that the upper pool. water volume had decreased by 574 cu f t from 1700 December 31, 1981, to 1200 January 5, 1982, and that the dry-well sump water volume had increased by 95 cu f t from 1000 January 3 to 1200 January 5, 1982. This resulted in a net water volume decrease rate of 74 cu ft per day. The indicated water volume change is most likely due to measurement accuracy. At any rate, a decrease in water volume would not mask an in-leakage, and therefore is not added as a correction.

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The corrected and uncorrected Type A leakage rates are tabulated

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below:

L wt%/ day 95% UCL wt%/ day am I

II III I

II III 1.

ILRT/ Mass Point 0.072 0.076 0.328 0.079 0.083 0.328 ILRT/ Total Time 0.068 0.072 0.328 0.139 0.143 0.328 2.

Verification /

Mass Point 0.431 0.327-0.545 Total Time 0.434 0.323-0.541 Uncorrected leakage rate calculated during where Column I

=

ILRT.

Column II Corrected leakage rate corresponding to Column

=

I plus corrections.

Column III = Acceptance limits O

DH-103 4-1

The ILRT results at the upper 95% confidence level satisfy the

= 0.328%/ day, at Pa = 11.5 P

tance criterion of Lam < 0.75La B.

ISG CALCULATION The ISG calculation provided below was performed according to the format specified in ANSI /ANS 56.8-1981, Appendix G.

a.

Calibration Data Number of l

Sensors Sensitivity, E Repeatability,6 Temperature, T 22 0.0l*F (*R) 0.01*F (*R)

Pregsure, P 1

0.001 psia 0.001 psia Vapor Pressure (Dewpoint), Pv 6

0.0l*F 0.05'F b.

_ Instrument Measurement Errors 1.

Tempe ratures l/2 (No. of Sensors)1/2 T = [(E ) +I)I

/

e T

T

= [(0.01)2 + (0,01)2]l/2/(22)1/2

= 0.003*F'(*R) 2.

Pressures

= [(E )2 + (s )2jl/2 (No. of Sensors)1/2

/

e p

p p

= [(0.001)2 + (0.001)2]1/2/(1)l/2

= 0.0014 psia 3.

Vapor Pressure For a dewpoint temperature range of 68.25'F + 0.05*F the average rate of change in dewpoint pressure is 0.0118 psi /*F, i.e.,

vapor pressure @ 68.3*F = 0.34243 psi

@ 68.2*F = 0.34125 psi change for 0.1*F = 0.00118 psi The sensitivity and repeatability in terms of pressure are:

E

= (0.0118 psi /*F)(0.0l*F) = 0.000118 psi py Spv = (0.0118 psi /*F)(0.05'F) = 0.00059 psi D

DH-103 4-2

)

Therefore, py)2 + (g )2]l/2 (No. of Sensors)l/2 e

= [(E

/

py py

= [(0.000118)2 + (0.00059)2)l/2 (6)1/2

/

= 0.00025 psi c.

ISG Calculation for 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ILRT P = 12.27 psig + 14.7 = 26.97 psia T = 77'F + 460 = 537*R ISG = + 2400 2

2+2 2+2 2

1/2 p

ISG = 1 2400 ~ 2 0.0014)2+2(0.00025 2+2 0.003 2 1/2 8

26.97 /

\\ 26.97 537

= 1 300 (0.54 x 10-8 + 0.0169 x 10-8 + 0.006 x 10-8)l/2

= 1 300 (0.75 x 10-4) 0.0225 wt.%/ day

=

j 25% La = 0.437 x 0.25 = 0.10925 wt.%/ day 0.0225 < 0.10925 meets the criterion of ANSI /ANS 56.8-1981 and BN-TOP-1.

I i

i IlO DH-103 4-3

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V.

COMPUTER REPORT AND DATA PRINTOUT

%/

A.

MASS POINT REPORT The Mass Point Report presents leakage rate data (wt%/ day) as determined by the Mass Point Method described in the " Computer Program" section of this report. The " Calculated Leakage Rate" is the value determined from the regression analysis. The

" Containment Air Mass" values are the masses of dry air in the containment (lbm). These values, determined from the Equation of State, are used in the regression analysis.

B.

TOTAL TIME REPORT The Total Time Report presents data leakage rate (wt%/ day) as determined by the Total Time Method. The " Calculated Leakage Rate" is the value determined from the regression analysis. The

" Measured Leakage Rates" are the leakage rate values determined using Total Time calculations used in the above regression analysis.

C.

TREND REPORT The Trend Report presents leakage rates (as determined by the Mass Point and Total Time methods described in the " Computer Program"

(

)

section of this report) in percent of the initial contained mass

\\_ '

of dry air per day (wt%/ day), elapsed time (hours), and number of data points.

D.

SUMMARY

DATA REPORT The Summary Data report presents the actual data used to calculate leakage rates by the various methods described in the " Computer Program" section of this report. The five column headings are TIME, DATE, TEMP, PRESSURE, and VPRS, and contain data defined as follows:

1.

TIME:

Time in 24-hour notations (hours and minutes).

2.

DATE:

Calendar date (month and day).

3.

TEMP:

Containment weighted-average drybulb temperature in absolute units, degrees Rankine (*R).

4.

PRESSURE: Partial pressure of the dry air component of the containment atmosphere in absolute units (psia).

5.

VPRS:

Partial pressure of water vapor of the containment atmosphere in absolute units (psia).

p.

(

)

v DH-103 5-1

s E.

SUMMARY

OF MEASURED DATA AND

SUMMARY

OF CORRECTED DATA p

( -)

The Summary of Measured Data presents the individual containment atmosphere drybulb temperatures, dewpoint temperatures, and absolute total pressure measured at the time and date as indicated and is used to determine the temperature and pressure described in V.D.3-5 above.

1.

TEMP 1 through TEMP 22 are the drybulb temperatures. The values in the right-hand column are temperatures (*F), multi-plied by 100, as read from the data acquisition system (DAS).

The values in the left-hand column are the corrected tempera-tures expressed in absolute units (*R).

2.

PRES 1 is the total pressure, absolute. The right-hand value, in parentheses, is a number in counts as read from the DAS.

This count value is converted to a value in psia by the com-puter via the instrument's calibration table, counts versus psia. The left-hand column is the absolute total pressure, psia.

3.

VPRS 1 through VPRS 6 are the dewpoint temperatures (water vapor pressures). The values in the right-hand column are temperatures (*F), multiplied by 100 as read from the DAS.

The values in the left-hand column are the water vapor pres-sures (psia) from the steam tables for saturated steam corresponding to the dewpoint (saturation) temperatures in

(

j the center column.

G The Summary of Corrected Data presents corrected temperature and pressure values and calculated air mass determined as follows:

1.

TEMPERATURE (*F) is the volume weighted average containment atmosphere drybulb temperature (refer to Section III, Tables 1 and 2, for sensor volume fractions) derived from TEMP 1 through TEMP 22.

2.

CORRECTED PRESSURE (psia) is the partial pressure of the dry air component of the containment atmosphere, absolute. The volume weighted average containment atmosphere water vapor pressure is subtracted from PRES 1, total pressure, yielding the partial pressure of the dry air.

3.

VAPOR PRESSURE (psia) is the volume weighted average contain-ment atmosphere water vapor pressure, absolute (refer to Section III, Tables 1 and 2 for sensor volume fractions),

derived from VPRS 1 through VPRS 6.

4.

CONTAINMENT AIR MASS (lbm) is the calculated mass of dry air in the containment. The mass of dry air is calculated using the containment free air volume and the above TEMPERATURE and CORRRECTED PRESSURE of the dry air.

[)

Note: This printout is not included in the report, but is

\\'/

retained at the facility.

Dil-103 5-2

APPENDIX A (m

/

)

BECHTEL ILRT COMPUTER PROGRAM q,/

A.

Program and Report Description 1.

The Bechtel ILRT computer program is used to determine the inte-grated leakage rate of a nuclear primary containment structure.

The program is used to compute leakage rate based on input values of time, containment atmosphere total pressure, drybulb tempera-ture, and dewpoint temperature (water vapor pressure). Leakage rate is computer using the Absolute Method as defined in ANSI /ANS 56.8-1981, " Containment System Leakage Testing Requirements" and BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants".

The program is designed to allow the user to evaluate containment leakage rate test results at the jobsite during' containment leakage testing. Current leakage rate values may be obtained at any time during the testing period using one of two computational methods, yielding three different report printouts.

2.

The first printout, the Total Time Report, is based on the Total Time Method described in BN-TOP-1.

Leakage rate is computed from initial values of free air volume, containment atmosphere drybulb temperature and partial pressure of dry air, the latest values of the same parameters, and elapsed time.

These individually computed g-~g leakage rates are statistically averaged using linear regression by

(

)

the method of least squares. The Total Time Method is the computa-tional technique upon which the short duration test criteria of BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plant,"

are based.

3.

The second printout is the Mass Point Report and is based on the Mass-Point Analysis Technique described in ANSI /ANS 56.8-1981,

" Containment System Leakage Testing Requirements." The mass of dry air in the containment is computed at each data point (time) using the Equation of State, from current values of containment atmosphere drybulb temperature and partial pressure of dry air.

Contained mass is " plotted" versus time and a regression line is fit to the data using the method of least squares.

Leakage rate is determined from the statistically derived slope and intercept of the regression line.

4.

The third printout, the Trend Report, is a summary of leakage rate values based on Total time and Mass Point computations presented as a fuction of number of data points and elapsed time (test dura-tion). The Trend Report provides all leakage rate values required for comparision to the acceptance criteria of BN-TOP-1 for conduct of a short duration test.

5.

The program is written in a high level language and is designed for use on a mini-computer with direct data input from the data acquisition system. Brief descriptions of program use, formulae

[s'- ')

used for leakage rate computations, and program logic are provided in the following paragraphs.

DH-103 A-1 i

4 O) i l

(

B.

Explanation of Program l.

The Bechtel ILRT computer program is written, for use by experi-enced ILRT personnel, to determine containment integrated leakage rates based on the Absolute Method described in ANSI /ANS 56.8-1981 and BN-TOP-1.

2.

Information loaded into the program prior to the start of the test:

Number of containment atmosphere drybulb temperature sensors a.

and dewpoint temperature (water vapor pressure) sensors to be f

used in leakage rate computations for the specific test b.

Volume fractions assigned to each of the above sensors e

Calibration data for above sensor, if required c.

d.

Calibration data for pressure sensor.

3.

Information entered into the program at the start of the test:

a.

Test title b.

Current test pressure and peak test pressure Maximum allowable leakage rate at peak test pressure s

c.

5' d.

If the test is a verification test:

4 (1) Imposed leakage rate (2) Leakage rates determined using the two computational methods described in Paragraph A above during the ILRT.

4.

Data received from the data acquistion system during the test, and used to compute leakage rates:

r a.

Time and date b.

Containment atmosphere drybulb temperatures c.

Containment atmosphere pressure i

d.

Containment atmosphere dewpoint temperatures 5.

After all data at a given time are received, a Summary of Measured Data report (refer to " Program Logic," Paragraph D, " Data" option

}

command) is printed on the data terminal. The date, containment atmosphere weighted average drybulb temperature, partial pressure of the dry air and water vapor pressure are stored on a data file.

DH-103 A-2 I

- - - - - - - - - - -, - - - - - - - - - - ~ - - - ~ ' ~ ~ ~ '- '

l 6.

If drybulb and dewpoint temperature sensors should fail during the test, the data from the sensor (s) are not used. The volume frac-tions for the remaining acnsors are recomputed and reloaded ~into the program for use in ensuing leakage rate computations.

C.

Leakage Rate Formulae 1.

Computation using the Total Time Method:

a.

Measured leaka e rate, from data:

t P V = W 1tTi (1) 1 1

P V = W RTi (2) i i

2400 (W1-W) i att W1 Solving for W1 and Wi and substituting equations (1) and (2) into (3) yields:

Li = 2400/ati(1-T P /T P )

(4) 1i i1 whe re:

W,Wi = Weight of contained mass of dry air at times tt-and 1

ti respectively, lbm.

T,Ti = Containment atmosphere drybulb temperature at times 1

el and ti respectively,

• R.

P,Pi = Partial pressure of the dry air component of the con-1 tainment atmosphere at times ti and ti respectively, psia.

V = Containment free air volume (assumed to be constant 3

during the test), ft.

th ti, tt = Time at 1st and i data points respectively, hours.

1 ati = Elapsed time f rom ti to ti, hours.

i R = Specific gas cons tant for air = 53.35 f t.lbf/lbm. *R.

Li = Measured leakage rate computed during time interval ti to ti, %/ day.

]

4 DH-103 A-3 1

7 e

..~ - -,, -, -

a

b.

Calculated leakage rate from regression analysis:

V)

/

L = a + batN (5) where:

L = Calculated Icakage rate, %/ day, as determined from the regression line.

2 IL (Eatg ) - EAtf( E att) i t

a=

A (6)

N(Eatt ) - U4tt)2 N(IL ati) - EL (IAti) i i

b=

2 (7)

N(eat 1 ) - (Eatt)2 N = Number of data points I=E J

1-1 c.

Calculated leakage rate at the 95% confidence level.

L95 = a + bacN + S._

(8)

L i

where:

I,95 = Calculated leakage rate at the 95% confidence level,. %/ day, at j

elapsed time AtN*

J For AtN < 24 I

0 025;N-2 (I(L -I )2 (N-2)}1/2 x [1 + 1 + (At - H ) /ECAt -E) ]II (9a)

S_

=t

/

1 t N

i L

N I

where, to.025;N-2 = 1.95996 + 2.37226 + 2.82250 ;

N-2 (N-2)4 i

For AtN2.24 1 - L )2 (N-2)]1/2 x (1 +(AtN - E) /E(Ot -

) ]II (9b) s_ = tg.025;N-2 (E(L

/

1 i

L N

Y 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 j

where, t0 025;N-2 =

(N-2)2 + 1.2209(N-2) - 1.5162 4

~i = Calculated leakage rate computed using equation (5) at total elapsed L

time Att, %/ day.

O Iat i u=

l N

l l

DH-103 A-4 I -

J b

2.

Computation using the Mass Point Method Contained mass of dry air from data:

4 a.

-Wi = 144 Pg RTi (10) where:

All symbols as previously defined.

~

b.

Calculated leakage rate from regression analysis:

l

.i b

L = -2400 -

(11) a I

where:

L

= Calculated leakage rate, %/ day, as determined from the regression line.

IW -bEAti i

a

=

(12) s N

s j

E[(Wi - EW /N) (Ati - E)] -

i b

(13)

=

E(At -h t

th Ati = Total elapsed t'ime at time of--i data point, hours N = Number of data points th Wi

• Contained mass of dry air at i data point, lbm, as computed f rom equation (10).

i N

I=E i=1 i

E = Eat /N i

2 Calculated leakage rate at the 95% confidence level.

c.

-2400

~

L95 =

(b + S )

(14) b i

a where:

4 1

L95 = Calculated leakage rate at the 95% confidence level, %/ day.

\\

DH-103 A-5 i

i

.. ~ -

- E(w - Ui)2 i

Sb"C0 025;N-2 1/2 (15)

(N-2)t(ati - IE)2 _1 1.6449(N-2)2 + 3.5283 (N-2)2 + 0.85602 where, t0 025;N-2 =

(N-2)2 + 1.2209 (N-2) - 1.5162 5 = Contained mass of dry air, Ibm, computed at the i (16) th 1

data point from the regression equation

= a + bati All other symbols are previously defined.

\\

/

/

l DH-103 A-6 i

~

( j_

Procran Loeic D.

1.

A flow chart of Bechtel ILRT computer program usage is pre-sented in Figure 1, following.

The various user options and a brief description of their associated function are presented below:

OPTION-C010LuiD FUNCTION DATA Enables operator to enter raw data.

When the sys-tem requests values of time, volume temperature, pressure and vapor pressure, the user enters the appropriate data. Af ter completing the data entry, a summary is printed out.

The user then verifies that the data were entered correctly.

If errors are detected, the user will then be given the opportunity to correct the errors.

After the user verifies that the data were entered correctly, a Corrected Data Su= mary Report o'f time, date, average temperature, partial pressure of dry air, and water vapor pressure is printed.

TREND Terminal will print out a Trend Report.

[

TOTAL Terminal will print out a Total time Report.

\\ 'T MASS Terminal will print out a Mass Point Report.

TERM Enables operator to sign off temporarily or pe rmanently.

SAVE

' Enables operator to store the Data Summary on a file.

PREV Enables operator to call up an old, previously stored, file.

CORR Enables operator to correct data stored on a file.

LIST When used with a given file name, the printer will print cut a list of the Summary Data stored on the file.

1 READ l

Enable the computer to receive the next set of raw data from the data acquisition system directly.

)

A-7

( SIGtJ ON) t

\\ ENTER BASIC /

NO

/ ENTER PREVIOUS \\

{ INFO RMATION/

\\ VALUES FROM FILES /

YES r

DATA -

(OPTIONSg AA TORED ON o-PREV (ENTER D ATA)

CO RRECTS o-CORR

SUMMARY

DATA

[ YES STO RES

SUMMARY

\\

ENTER

/

NO r-SAVE D ATA ON A CORRECTIONS /

SELECTED FILE

SUMMARY

OF rTRENO

[ TREND REPORT)

MEASURED DATA

[

)

<r-TOTAL TOTAL TIME L._ A -

YES REPORT

'E R R O R?)

1 NO

"- M ASS MASS POINT REPORT CORRECTED CUMMARY DATA PRINTOUT o-LIST PRINT DUT OF

SUMMARY

DATA o-TERM

- ( SIGN OFF )

N J

BECHTEL CONTAINMENT INTEGRATED LEAKAGE RATE TEST COMPUTER PROGRAM FLOW CHART FIGURE 1

/O N_ I A-8

O APPENDIX B ILRT STABILIZATION DATA TEST.STA GRAND GULF STABILIZATION ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.000 VRATEM = 0.000 VRATEP = 0.000 TIME DATE TEMP PRESSURE VPRS 1529 103 537.56366 26.425938 0.34851480 1545 103 537.01373 26.402582 0.34475750 1603 103 536.61597 26.383574 0.34468400 1615 103 536.46893 26.377193 0.34303159 1630 103 536.30707 26.368984 0.34320599 1645 103 536.20459 26.363253 0.34291309 1700 103 536.09918 26.357325 0.34281561 1715 103 536.03223 26.353136 3.34298769 1730 103 535.95685 26.348457 0.34264520

\\

(\\ms) 1745 103 535.88330 26.344131 0.34295520 1800 103 535.82629 26.340103 0.34296569 1815 103 535.76117 26.337587 0.34246781 1830 103 535.70874 26.334372 0.34267199 1845 103 535.66150 26.332005 0.34202629 1900 103 535.61688 26.329777 0.34224480 i

1915 103 535.56860 26.327791

.O.34222180 l

1930 103 535.54742 26.324705 0.34229621 1945 103 535.43054 26.323195 0.34179929 2000 103 535.44885 26.320612 0.34237379 2015 103 535.40631 26.318562 0.34241500 O

B-1 l

e c

---

v

- =

-n.

+

I d

APPENDIX C ILRT

SUMMARY

DATA TEST.DAT GRAND GULF ILRT ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.000 VRATEM = 0.000 VRATEP = 0.000 TIME DATE TEMP PRESSURE VPRS 2030 103 535.38818 26.316441 0.34252653 2045 103 535.37219 26.315517 0.34244490 2100 103 535.34686 26.313202 0.34275225 2115 103 535.32245 26.311718 0.34222719 2130 103 535.28601 26.310568 0.34237543 2145 103 535.26984 26.309896 0.34204134 2200 103 535.23566 26.307184 0.34274417 2215 103 535.21973 26.304913 0.34300748 2230 103 535.19214 26.304295 0.34262270 2245 103 535.16925 26.302761 0.34315175 2300 103 535.14685 26.301828 0.34307989 2315 103 535.11749 26.300154 0.34274691 2330 103 535.10406 26.299398 0.34249672 0

2345 103 535.09546 26.299583 0.34231171 0

104 535.06689 26.296225 0.34366253 15 104 535.05304 26.297117 0.34277007 30 104 535.03369 26.295589 0.34329468 45 104 535.01672 26.293724 0.34415492 100 104 534.99390 26.293665 0.34321022 115 104 534.98413 26.292389 0.34348071 130 104 534.96783 26.291492 0.34337339 4

145 104 534.96344 26.290226 0.34363529 200 104 534.94757 26.289938 0.34392363 i

215 104 534.93909 26.288767 0.34409159 230 104 534.92371 26.287523 0.34432954 245 104 534.91162 26.287708 0.34414417 300 104 534.89838 26.286375 0.34447473 315 104 534.89233 26.285236 0.34460890 i

330 104 534.87921 26.285433 0.34441105 345 104 534.86578 26.284437 0.34440356 400 104 534.85150 26.283850 0.34499204 415 104 534.84827 26.283432 0.34440419 430 104 534.82874 26.283085 0.34475130 i

i l

t C-1

~ APPENDIX D ILRT CALCULATIONS (O) ss GRAND GULF ILRT m

LEAHAGE RATE (WEIGHT PERCEllT/ DAY)

MAS 3-POINT ANALtSIS TIME AND DATE.AT START OF TEST:

2030 0103 ELAPSED TIME:

8.00 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS TOT. AVG. MASS (R)

(PSIA)

MASS (LBM)

(LBM)

LOSS (LBM/HR) 2030 535.388 26.3164 221566.

2045 535.372 26.3155 221565.

1.1 4.6 2100 535.347 26.3132 221556.

9.0 20.3 2115 535.322 26.3117 221550.

2.4 16.8 2100 535.286 26.3106 221559.

-5.4 7.2 2145 535.270 26.3099 221560.

-1.0 4.9 2200 535.236 26.3072 221551.

8.7 9.9 2215 535.220 26.3049 221539.

12.5 15.6

') 2230 535.192 26.3043 221545.

-6.2 10.6

' 2245 535.169 26.3028 221541.

3.4 10.9 2300 535.147 26.3018 221543.

-1.4 9.3 2315 535.117 26.0002 221541.

1.9 9.1 2300 535.104 26.2994 221540.

0.8 8.6 2345 535.095 26.2996 221545.

-5.1 6.4

(^N O

535.067 26.2962 221529.

16.5 10.6

\\

15 535.053 26.2971 221542.

-13.3 6.4 30 535.034 26.2956 221537.

4.9 7.2 45 535.017 26.2937 221528.

8.7 8.8 100 534.994 26.2937 221537.

-9.0 6.4 115 534.984 26.2924 221531.

6.7 7.4 100 534.968 26.2915 221530.

0.8 7.2 145 534.963 26.2902 221521.

8.9 86 200 534.948 26.2899 221525.

-4.2 7.4 215 534.939 26.2888 221519.

6.4 8.2 230 534.924 26.2875 221515.

4.1 8.5 245 534.912 26.2877 221521.

-6.6 7.2 300 534.898 26.2864 201515.

5.8 7.8 315 524.892 26.2852 221508.

7.1 8.5 330 534.879 26.2854 221515.

-7.1 7.2 345 534.866 26.2844 221513.

2.8 7.4 400 534.852 26.2838 221514.

-1.0 7.0 415 534.848

'26.2934 221511.

2.2 7.0 400 534.829 26.2831 221517.

-5.2 6.2 FREE AIR VOLUME USED (MILLIONS CF CU. FT.)

1.670

=

REGRESSION LINE INTERCEPT (LEM) 2215cl.

=

SLOPE (LBM/HR)

-6.7

=

MAXIMUll ALLOWAELE LEAKAGE RATE 0.4 7

=

g) 75 % OF MAXIMUM ALLOWABLE LEAKAGE RATE 0.028

=

THE UFFER 95% CONFIDENCE LIMIT 0.079

=

THE CALCULATED LEAKAGE RATE 0.072

=

D-1

\\,

r'~5

(

)

GRnND GULF ILRT

\\_/

LEiikAGE RATE (WEIGH 1 PERCENT / DAY)

TO1HL-TIME ANALYSIS TIME AND DATE AT START CC TEST:

2000 0100 ELAPSED TIME:

E.OO HOURS TIME TEMP.

PRESSURE MEASURED (R)

(PSIA)

LGAKAGE RATE

_- __-- ~ ----- ___

2000 505.388 26.3164 2045 535.072 26.3155 0.050 2100 505.347 26.3132 0.220 2115 505.022 26.3117 0.181 2130 535.286 26.0106 0.078 2145 505.270 26.3009 0.053 2000 505.236 26.0072 0.107 2215 535.220 26.3049 0.169 2230 535.192 26.3043 0.115 22d5 535.169 26.3028 0.118 2000 535.147 26.3018 0.100

)

2015 505.117 26.3002 0.099 2000 535.104 26.2994 0.094 2045 535.095 26.2996 0.069 0

505.067 26.2962 0.11,5

('"y 15 535.053 26.2971 0.06'9 x

)

30 535.034 26.2956 0.078

" ~ '

45 535.017 26.2907 0.096 100 534.994 26.2937 0.069 115 534.984 26.2924 0.081 100 534.968 26.2915 0.078 145 534.963 26.2902 0.093 200 534.948 26.2899 0.080 215 534.939 26.2888 0.089 200 534.924 26.2875 0.093 245 534.912 26.2877 0.078 300 534.898 26.2864 0.084 315 534.892 26.2852 0.092 330 534.879 26.2854 0.078 345 534.866 26.2844 0.080 400 504.852 26.2008 0.076 415 504.848 26.2834 0.076 400 534.829 26.2831 0.067 MEAN OF MEASURED LEAKAGE RATES 0.095

=

)

MAXIMUM ALLOWADLE LEAKAGE RATE 0.437

=

75 % OF MAXIMUM ALLOWABLE LEAKAGE RATE 0.328

=

THE UPPER 95% CONFIDENCE LIMIT 0.139

=

THE CALCULATED LEAKAGE RATE 0.068

=

G I

I v

D-2

m (G

)

GRhilb GULF ILRT TREi!D REPORT LEAL.: AGE Rf. TEE tWElGHT FERCEllT/ DAY)

TIME AtJD DATE AT START OF TEST:

2000 0103 ELAPEED TIi1E:

9.00 HOURS NO. DATA ELAPSED TOTAL-TIME ANALYSIS't1 ASS-POIf1T At1ALYSIS FOINTS TIME MEAT 1 CALCULATED

___________________ _ ______________ ___ CALCULATED ___________

95:. UCL 10 2.25 O.121 0.119 0.119 0.162 11 2.50 0.119 0.112 0.110 0.146 12 2.75 O.117 0.107 0.104 O.134 13 3.00 0.115 O.101 0.098 0.124 14 3.25 0.112 0.091 0.035 0.111 15 3.50 0.112 0.094 0.093 0.116 16 3.75 O.109 0.086 0.083 0.105 17 4.00 0.107 0.082 0.079 0.099 13 4.25 0.107 0.082 0.031 0.099 19 4.50 0.105 O.077 0.075 O.092 20 4.75 0.103 0.075 O.074 0.089 21 5.00 0.102 0.073 0.073 0.087 p!

22 5.25 0.102 0.074 0.075 0.088 i

23 5.50 0.101 0.073 0.075 O.086 24 5.75 O.100 0.073 0.076 0.087 25 6.00 0.100 0.074 0.078 0.03G 26 6.25 O.099 0.073 0.077 C.086 27 6.50 0.098 0.073 0.077 0.086 29 6.75 O.098 0.074 0.079 0.087 29 7.00 0.097 0.073 0.078 0.085 30 7.25 O.097 0.072 0.077 0.084 31 7.50 0.096 0.071 0.076 0.083 32 7.75 0.095 0.070 0.075 0.081 30 8.00 0.095 O.068 0.072 0.079 1

v D-3

A_PPENDIX E ILRT PLOTS ILRT T EHF EF.n I UF.E 502.00 533.00 534.00 5 5.00 536.00 538,00 539.

+_________+_________._________._________._____537.00

+

+

2100 -

+

+

+

+

2296 -

+

+

a

+

+

2000 -

+

+

+

+

0-

+

+

+

+

i 1QQ -

+

+

+

~

+

290 -

+

+

+

+

l 300 -

+

6

+

+

+

400 -

+

+

500 -

+

4

)

1 i

O E-1

- - - - ~ ' ~

VERIFICATION TEMPERATURE 532.00 533.00 534.00 535.00 536.00 537.00 539.00

+__-------+-____----+-________+_________,_________,_____538.00

+

+

+

600 -

+

+

+

+

700 -

+

+

+

~

+

800 -

+

~

+

+

+

900 -

+

+

+

+

1000 -

+

,=

+

!O i

s STABILIZATION l

1 TEMPERATURE 533.00 533.00 534.00 535.00 536.00 537.00 538.00 539.00

+-----

-+-

-___+-_____

f i

+

1 IGO3 -

t

+

t

+

l

+

i l700 -

i

+

i

=

+

+

+

i ISOC -

)

i i

+

+

+

l 1900 -

+

+

i i

+

+

2000 -

1

+

e E-2

i ILRT

l i

PRESSURE 2c.150 26.000 26.250 26.300 26.050 23.asc 26.sc

+_________+_________+_________+_________+____26.400

+

+

2100

+

+

+

2200 -

+

+

+

mm..

+

I l

ee W

~

+

l

+

j

+

0-

+

+

+

+

100 -

+

+

+

+

200 -

+

+

~

+

~

+

200 -

+

+

+

+

400 -

+

+

+

+

500 -

+

E-3

VERIFICATION PRE 55URE 26.150 26.200 26.250 26.200 2

2o.400 26.450 26.5OO

+-_--_-__-+_________+_________+_____6.250

+

+

+

600 -

+

+

+

+

700 -

+

+

+

+

GOO -

+

+

+

+

900 -

+

~

+

+

+

1000 -

+

+

STABILIZATION PF. ESSURE 26.150 26.000 26.250 26.200 26.250 26.400 26.450 26.500

+ _ _ _ _ _ _ _ _ _ + _ _ - -

__+__

_ _ _ _ + _ _ _ _ _ _ _ _ _ _ _ _

+

1603 -

+

+

+

+

1700 -

+

+

+

+

1800 -

+

+

+

+

+

1900 -

+

+

+

+

2OOO -

+

+

E-4

ILRT es1RMetSS 221000.

221100.

221200.

221300.

221400.

221300.

221:

+---------+---------+--------_,-----_-__,-__----__.______221 COO.

=

+

+

2100 -

+

+

+

+

m. m,, k.,

m_v -

+

+

t

+

2000 -

+

+

+

+

0-

+

+

+

+

100 -

+

+

+

+

200 -

+

+

+

+

200 -

+

1

+

+

400 -

+

+

+

+

500 -

+

t i

I i

l I

l l

i i

i l

1 i

E-5 i

VERIFICATION AIRMitSS 221000.

221100.

221200.

221200 221400.

221500.

2216 2217-

+---------+---_----.-+---------+--.

--_---+_-.-------+---------.00.

+

+

600 -

+

+

+

+

700 -

+

+

+

i,

+

+

800 -

+

+

+

+

900 -

+

+

+

+

1000 -

+

+

STABILIZATION AIRMASS 221000.

221100,

- 1,0U.

,,1 00.

-'1400.

-0

,mieOO.

221600.

2217c

+-----

-- s

- - - + _ - - - _ _ - - _ + - _ _.

-+_

- + = -

+

/603 -

+

+

+

+

1700 -

+

+

+

+

1800 -

+

+

+

+

1900 -

+

+

)

+

+

2000 -

+

+

E-6

O APPENDIX F VERIFICATION FLOW TEST

SUMMARY

DATA TEST.VER GRAND GULF VERIFICATION ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.432 VRATEM = 0.436 VRATEP = 0.364 TIME DATE TEMP PRESSURE VPRS 515 104 534.80566 26.280268 0.34556079 530 104 534.79596 26.278370 0.34544951 545 104 534.78748 26.277615 0.34520060 600 104 534.77368 26.276218 0.34559339 615 104 534.76746 26.274252 0.34554970 630 104 534.75714 26.272772 0.34602681 645 104 534.76361 26.272007 0.34578761 700 104 534.74396 26.269663 0.34612215 715 104 534.73499 26.268349 0.34643370

(*~')s 730 104 534.73236 26.267462 0.34631500 s.

745 104 534.72797 26.265524 0.34624526 800 104 534.71405 26.264580 0.34618655 815 104 534.70410 26.262316 0.34644118 830 104 534.69879 26.261040 0.34671304 845 104 534.68665 26.259174 0.34656873 900 104 534.63726 26.257030 0.34670511 915 104 534.67273 26.256052 0.34667951 930 104 534.65894 26.252333 0.34738570 945 104 534.64771 26.252180 0.34753838 1000 104 534.64069 26.250376 0.34733403 1015 104 534.63062 26.249893 0.34681413 1

1 F-1

O APPENDIX G VERIFICATION FLOW TEST CALCULATIONS

- GRAND GULF VERIFICATION LEAKAGE RATE (NEIGHT PERCENT / DAY)

MASS-FOINT ANALYSIS TIME AND DA1E AT START OF TEST:

615 0104 ELAPSED TIME:

4.00 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS TOT. AVG. MASS (R)

(PSIA)

MASS (LBM)

(LEM)

LOSS (LEM/HR)

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

615 534.767 26.2743 221467.

630 534.757 26.2729 221459.

8,2 32.8 645 534.764 26.2720 221450.

9.1 34.7 700 534.744 26.2697 221439.

11.6 38.6 715 534.735 26.2683 221431.

7.4 36.3 730 534.732 26.2675 221425.

6.4 34,2 745 534.728 26.2655 221410.

14.5 38.1 300 534.714 26.2646 221408.

2.2 34.0 815 534.704 26.2623 221393.

15.0 37.2 830 534.699 26.2610 221335.

S'.6 36.9 Q

845 534.687 26.2592 221374.

10.7 37.5 900 534.687 26.2570 221356.

18.3 40.7 915 534.673 26.2561 221350.

2.2 38.1 930 534.659 26.2523 221328.

~25.6 43.0 945 534.648 26.2522 221331.

-3.4 39.0 1000 534.641 26.2504 221319.

12.3 39.7 1015 534.631 26.2499 221319

-0.1 37.2 FREE AIR VOLUME USED (MILLIONS OF CU. FT.)

=

1.670 REGRESSION LINE INTERCEPT (LBM) 221471.

=

SLOPE (LBM/HR)

-39.8

=

VERIFICATION TEST LEAKAGE RATE UFPER LIMIT =

0.545 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT =

0.327 THE CALCULATED LEAKAGE RATE 0.431-

=

l 1

1 o

G-1 l

• w OY GRAND GULF VERIFICATION LEAKAGE RATE (WEIGHT FERCENT/ DAY)

TO THL-T IME ANALYSIS TIME AND DATE AT STAR T OF TEST:

615 0104 ELAP$ED TIME:

4.00 HOURS TIME TEMP.

PRESSURE MEASURED (R)

(PSIA)

LEAKAGE RA

________-____-_______________________1E 615 534.767 26.2743 630 534.757 26.2728 0.356 645 534.764 26.2720 0.376 700 534.744 26.2697 0.418 715 534.735 26.2683 0.394 730 534.732 26.2675 0.370 745 534.728 26.2655 0.413 800 534.714 26.2646 0.368 815 534.704 26.2623 0.403 800 534.699 26.2610 0.399 845 534.687 26.2592 0.406 900 534.687 26.2570 0.441 915 534.673 26.2561 0.413

(~N 930 534.659 26.2523 0.466

\\ s) 945 534.640 26.2522 0.423 m

1000 534.641 26.2504 0.430 1015 534.631 26.2499 0.403 MEAN OF MEASURED LEAKAGE RATES

=

0.405 VERIFICATION TEST LEAKAGE RATE UPPER LIMIT =

VERIFICATION TEST LEAKAGE RATE LOWER LIMIT =

0.541 THE CALCULATED LEAKAGE RATE 0.323

=

0.434 O

V G-2

'J GRAND GULF VERIFICATION TREND REPORT LEAKAGE RfiTES (WEIGHT FERCENT/ DAY)

TIME AND DATE AT START OF TESY:

615 0104 ELAPSED TIME:

4.00 HOURS NO. DATA ELAPSED TOTAL-TIME ANALYSIS' MASS-FOINT ANALYSIS POINTS TIME MEAN CALCULATED CALCULATED 10 2.25 0.389 0.400 0.397 11 2.50 0.390 0.404 0.402 12 2.75 0.395 0.418 0.420 13 3.00 0.396 0.420 0.420 14 3.25 0.402 0.436 0.440 15 3.50 0.403 0.436 0.438 16 3.75 0.405 0.439 0.439 17 4.00 0.405 0.434 0.431

\\

1

(

c-3

(

APPENDIX H BYPASS LEAKAGE RATE CALCULATIONS The formula for computing leakage rate by flow totalizer method is:

Lt = (P /T1 - P /T ) x (VT /60tP ) + F/60t 1

2 2 s

s 1

where:

I Lt=

Leakage rate, standard cubic feet per minute (SCFM)

P,P2 = Test volume absolute pressure at start and end of test 1

4 respectively, absolute units i

T,T2 = Test volume absolute temperature at start and end of test 1

respectively, absolute units V

= Total test free air volume, cubit feet (270,128 cu.ft.)

1 Ts

= Standard temperature (68'F)

Ps

= Standard pressure (14.6959 psia)

-s) t

= Tes t duration, hours (4 hrs.)

O F

= Makeup air (to maintain test pressure), standard cubic feet = F2-F1 F,F2 = Makeup air flow meter reading at start and end of test 1

respectively, SCF (convert from actual cubic feet to standard cubic feet).

(1)

Calculate drywell average temperature at start and end of test, where VF = Volume Friction.

T1 - 76.102*F = 535.772*R T2 = 76.271*F = 535.941*R (2) Drywell pressure at start and end of test:

P1 = 17.793 psia P2 = 17.785 psia s

O d

DH-103 i

H-1 4

- - ~ -

i (3) Calculate drywell makeup air volume, convert from actual cubic feet to standard cubic feet:

F1 = 118070 cu.ft.

i F2 = 86350 cu.ft (50+14.6959 % (44+459.67 /68+459.67) 14.6959

)*\\

F = (F1-F) 2

/'64.6959 527.67) x(503.67 /

31720 x14.6959

\\

=

146295.19 cu.ft.

=

(4) Bypass Leakage Rate Calculation:

[17.793 17.785 270,128x68 }

146295.19 Lt = \\535.772 535.941 60x4x14.6959/ '

60x4 609.7 SCFM

=

O J

O DH-103 H-2

l APPENDIX I Local Leakage Test Summary Data Type B Test Results i

Penetration Description Leakage, SCCM 1

Equipment Hatch 2+2 2

Upper Personnel Lock 2

3 Lower Personnel Lock 4

Fuel Transfer Tube 0 + 11 201 Reactor Protection System 030 202 Low Voltage Power 0+0 203 Instrumentation 030 9

204 Instrumentation 0+0 205 Neutron Monitoring 0IO 206 Low Voltage Power 0IO 207 Control and Power 0I0 4

208 Control 0{0 J

209 Low Voltage Power 0+0 210 Radiation Monitoring 0+0 211 Control 0+0 i

212 Instrumentation 0IO 213 Rod Position Indication OIO 214 T.I.P.

OT0 0

215 6.9 Kv-Reactor Recirculate Pump A 0[0 t

216 Spare 0+0 217 LV Power and Control 0I0 218 Neutron Monitoring 0{0 219 Ins trument ation 0+0 I

220 Instrumentation 0{0 221 Spare 0+0 i

222 Reactor Protection 0IO 223 LV Power and Control 0I0 224 Spare 0IO l

225 LV Power 0IO 226 Control 0IO 227 Instrumentation 0I0 228 Instrumentation (Neutron Monitoring) 0{0 229 LV Power and Control 0+0 230 Reactor Protection 0{0 t

231 Instrumentation 0+0 232 Neutron Monitoring 0[0 233 Rod Position Indication 0+0 234 Spare 0IO 235 Neutron Monitoring 0I0 l

237 Instrumentation (SRV Inplant Test) 0{0 238 Reactor Protection System 0+0 239 Control 0+0 240 Instrumentation 0I0 241 LV Power and Control 0I0 1

242 LV Power and Control 0{0 Dil-119 I-1 i

e

,r._.

-,,..,,n,.

APPENDIX I (Cont'd)

Local Leakage Test Summary Data Type B Test Results (Cont'd)

Penetration Description Leakage, SCCM 243 Spare 010 244 LV Power 0+0 245 Control Bop 010 246 Radiation Monitoring 010 247 6.9 KV Reactor Recirculate Pump B 010 249 Instrumentation 010 Drywell Personnel Hatch Drywell Head Drywell Equipment Hatch 30 1 11 Drywell Head Manhole TOTAL = 32 1 16 O

O DH-119 I-2

APPENDIX I (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)

Penetration Description Leakage, SCCM 5

Main Steam Line A 10,500 i 150 6

Main Steam Line B 552 + 19 7

Main Steam Line C 20 + 17 8

Main Steam Line D 3,3901148 17 Steam Supply to RCIC Turbine and RHR Hx 114.0 1 17 19 Main Steam Drain to Condenser 4 i 12 33 CRD Pump Discharge 0 1 12 34 Containment Purge Supply 135 1 17 35 Containment Purge Exhaust 80 + 17.

36 Plant Service Water Return 58 1 12 37 Plant Service Water Supply 38 Chilled Water Supply 1,250 i 120 39 Chilled Water Return 20 + 12 40*

ILRT Containment Pressurization /

Depressurization 286 + 12 41 Plant Service Air 220 + 12 42 Instrument Air 800 1 12 O

43 RWCU to Main Condenser 10 1 17

\\

44 Component Cooling Water Supply 40 1 17 45 Component Cooling Water Return 48 + 17 47 Reactor Recirculate Post Accident Sample 0 i 11 49 RWCU Backwash Transfer Pump to Spent Resin Storage Tank 72 + 12 50 DW & Containment CRW Sump Pumps Discharge to Auxiliary Building Collector Tank 1,385 1 104 51 DW & Containment DRW Sump Pumps Discharge to Auxiliary Building Collector Tank 1,395 1 100 54 To Upper Containment Pool and f rom Refueling Water Storage Tank 5 + 12 56 Condensate Makeup to Upper Containment Pool 230 + 11 57 Discharge from Fuel Pool Cooling and C.U.

System to Upper Containment Pool 172 + 12 58 Inlet Upper Containment Pool skimmer Tanks to Fuel Pool Cooling and C.U. System 142 1 12 60 Auxiliary Building Floor and Equipment Drain Return 23 + 17 65 Containment Normal Vent Supply and Combustible Cas 350 1 17 66 Containment Normal Vent and Combustible Gas Exchange 30 + 17 A

• Leakage rate for penetration 40 and 82 is included in this total Dil-119 I-3

APPENDIX I (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)(Cont'd)

Penetration Description Leakage, SCCM i

70 Automatic Depressurization System (Instrument Air) 20 + 17 4

)

75 RCIC Pump Turbine Exhaust Vaccum Relief 12112 j

81 Reactor Recirculate Sample 0 1 12 82*

ILRT Drywell Pressurization /Depressurization 286 1 12 83 RWCV Line from Regenerative Ht. Exchange to Feedwater 100 + 12 84 Drywell and Containment Chemical Waste 60112 85 Suppression Pool Cleanup Return 180 1 21 86 Demineralization Water Supply to Containment 330 1 12 87 RWCV Putap Suction from Recirculate Loops 60 1 17 88 RWCV Pump Discharge to RWCV Ht. Exchange 40 1 12 101C Drywell Pressure Instrumentation (Narrow Range) 0 1 12 101F Drywell Pressure Instrumentation (Wide Range) 6 1 12 l

102D Drywell Pressure (Wide Range) 15 1 12 103D Containment Pressure (Wide Range) 10 + 12 0

104D Containment Pressure (Wide Range) 10112 j

105A Containment Drywell H2 Analyzing 110 1 12 106A Drywell H2 Analyzing Sample 14 i 12 l

106B Drywell H2 Analyzing Sample Return 10 i 12 l

106E Containment H2 Analyzing Sample Return 10 1 12 107B Drywell H2 Analyzing Sample Return 158 1 12 107D Drywell H2 Analyzing Sample 50112 107E Drywell H2 Analyzing Sample Return 15 1 12 108A Containment H2 Analyzing 95 1 12 109A Drywell - Fission Products Monitor Sample 0 1 12 109B Drywell - Fission Products Monitor Sample i

Return 100 i 12 109D Containment Pressure Instrument (Narrow Range) 10 1 12 110A ILRT Instrumentation Drywell Pressure 0 1 11 110C ILRT Instrumentation Verification Flow 0 + 11 i

110F ILRT Instrumentation Containment Pressure 10 + 11 114 Suppression Pool Water Level Control 9 1 12 116 Suppression Pool Water Level Control 45 1 12 118 Suppression Pool Water Level Control 7 1 12 120 Suppression Pool Water Level Control 5 1 12 1

TOTAL = 22822 1 300 N

• Leakage rate for penetration 40 and 82 is included in this total.

DH-119 I-4 i

APPENDIX I (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Hydraulic)

Penetration Description Leakage, SCCM 9

Feedwater A 3.8 + 2.5 10 Feedwater B 16-2/3{2.5 11 RHR Pump A Suction 180 1 36 12 RHR Pump B Suction 503 + 92

~

13 RHR Pump C Suction 917 + 74 14 RHR Shutdown Suction 010 18 RHR to RPV Head Spray 3.8 1 5 20 RHR A to LPCI 010 21 RHR B to LPCI 5.60 1 3.5 22 RHR C to LPCI 519 + 28

~

23 RHR A Pump Test Line to Suppression Pool 180 1 35 24 RHR C Pump Test Line to Suppression Pool 917 1 74 25 HPCS Pump Suction 6.23 + 4.3 26 HPCS Pump Discharge to RPV 25 + 20 27 HPCS Test Line to Suppression Pool 6.3 1 2.5 28 RCIC Pump Suction 010

)

29 RCIC Turbine Exhaust 0+0 30 LPCS Pump Suction 0I0 31 LPCS Pump Discharge to RPV 471 1 53 32 LPCS Test Line to Suppression Pool 0+0

~

46 RCIC Pump Discharge Minimum Flow Line 010 48 RHR Hx B Relief Valve Vent Header to 8.5 1 5 Suppression Pool 67 RHR Pump B Test Line to Suppression Pool 503 1 54 69 Refueling Water Transfer Pump Suction From Suppression Pool 50 + 7 71A LPCS Relief Valve Discharge to Suppression Pool 0+0 71B RHR "C" Relief Valve Discharge to Suppression Pool 917 + 74 73 RHR Shutdown Relief Valve Discharge to i

Suppression Pool (H.P.)

82.6 1 24 76B RHR A Shutdown Suction Relief Valve Discharge to Suppression Pool (H.P.)

12.75 1 5 77 RHR HT. Exchanger A Relief Valve Discharge to Suppression Pool 180 + 35 89 Standby Service Water Supply A 22[7 90 Standby Service Water Return A 0+0 91 Standby Service Water Supply B 010 92 Standby Service Water Return B 5+6 113 Suppression Pool Water Level Control 5.3 I 5

~

i 115 Suppression Pool Water Level Control 010 i

117 Suppression Pool Water Level Control 5 + 12 I

1 119 Suppression Pool Water Level Control 17 _ 12 TOTAL = 5563 _+ 192 DH-119 I-5

r 1

4 1

!O

)

I MISSISSIPPI POWER AND LIGHT CO.

GRAND GULF NUCLEAR STATION UNIT 1 DOCKET NO. 50-416 j

)

PRIMARY REACTOR CONTAINMENT INTEGRATED LEAKAGE RATE TEST REPORT i

a J

i i

4 8

i 1

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I Submitted To The United States Nuclear Regulatory Commission Pursuant To Facility Operating License i

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i TABLE OF CONTENTS O

Page No.

I.

INTRODUCTION 1-1 4

II.

TEST SYNOPSIS 2-1 III. TEST DATA

SUMMARY

3-1 IV.

ANALYSIS AND INTERPRETATION 4-1 l

V.

COMPUTER REPORT AND DATA PRINTOUT 5-1 i

APPENDIXES A.

Bechtel ILRT Computer Program A-1 B.

ILRT Stabilizaticn Data B-1 C.

ILRT Summary Data C-1 D.

ILRT Calculations 1

Mass Point Analysis D-1 Total Time Analysis D-2 Trend Report Analysis D-3 E.

ILRT Plots Temperature Versus Time E-1 Pressure Versus Time E-3 Air Mass Versus Time E-5 F.

Verification Flow Test Summary Data F-1 G.

Verification Flow Test Calculations Mass Point Analysis G-1 1

Total Time Analysis G-2 Trend Report Analysis G-3 H.

Bypass Leakage Rate Calculation H-1 I.

Local Leakage Test Summary Data I-l 11 DH-103

()

I.

INTRODUCTION (s /

The Reactor Containment Building Integrated Leakage Rate (Type A) test is performed to demonstrate that leakage through the primary reactor containment systems and components penetrating the primary containment does not exceed the allowable leakage rate specified in the Grand Gulf Nuclear Station Final Safety Analysis Report (FSAR).

The successful preoperational Integrated Leakage Rate Test (ILRT),

Verification Test, and Drywell Bypass Test were completed on January 5, 1982 at Grand Gulf Nuclear Station Unit 1.

Acceptance criteria for both ANSI /ANS 56.8-1981, " Containment System Leakage Testing Require-ments," and BN-TOP-1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Powcr Plants,"

were met for an 8-hour short duration test.

Calculations were per-formed using the ANSI /ANS 56.8-1981 " Mass Point Analysis Method" and BN-TOP-1, " Total Time Analysis Method." The test results are reported in accordance with the requirements of ANSI /ANS 56.8-1981, Section 5.8 and 10CFR50, Appendix J, Section V.B.3.

The purpose of this report is to provide information pertinent to the activities related to the preparation, test performance, and reporting of the Grand Gulf Nuclear Station Unit 1 ILRT.

Section II, Test Synopsis, presents the highlights of activities and events which occurred prior to and during the ILRT.

3 x_,/

Section III, Test Data Summary, contains the data and results necessary to demonstrate containment atmosphere stabilization, an acceptable leakage rate, and a successful verification test.

In addition, plots provided in Appendix E supply a visual history of containment atmos-pheric conditions beginning with the stabilization condition, through-out the 8-hour short duration ILRT period, and ending with the verification test.

Section IV, Analysis and Interpretation, contains technical details of the integrated leakage rate measuring system used during the ILRT, and provides analysis to show that the containment 95% upper confidence limit leakage rate does not exceed 75% of the allowable rate as speci-fied in the plant FSAR.

Section V, Computer Report and Data Printout, describes the ILRT com-puter program and report printouts.

Ib DH-103 1-1

II.

TEST SYNOPSIS TEST PREPARATION ACTIVITIES Prior to containment pressurization for the Structural Integrity Test (SIT) on January 1,1982, Grand Gulf Nuclear Station Unit 1 test personnel were engaged in measuring containment leakage to ensure a successful preoperational ILRT.

Sources of containment leakage were identified through Types B and C leakage rate testing programs and reduced by repairing those systems and containment components having relatively excessive leakage rates. The results of the Local Leakage

~ Rate Test (LLRT) are presented in Appendix I.

Highlight 3 of the test preparation activities included monitoring both upper and lower personnel hatch pneumatic systems leakage and repniring MSIV guard pipe inspection. port seals, positioning sensors, verifying associated volume fractions, and conducting a temperature' survey to ensure that all sensors could accurately monitor their respective subvolumes. An in-situ check, as specified in ANSI /ANS 56.8-1981, Section 4.2.3, was conducted to verify that all ILRT instrumentation was indicating correctly. The following items are presented in chronological order, and detail significant activities performed during the test preparation and successful execution.

The Type A test procedure was reviewed to verify compliance with 3

Plant Technical Specifications, 10CFR50 Appendix J, ANSI /ANS 56.8-1981, BN-TOP-1, and the FSAR.

In addition,-test personnel reviewed the valve lineups to verify that the containment systems were in as close to post-accident alignment as possible.

CONTAINMENT PRESSURIZATION j,

Containment pressurization for the ILRT began at 1030 on January 3, 1982. At the start of pressurization, containment fans M41-B001A and M41-8001B, and the containment, steam tunnel, and drywell cooling systems were operating.

During pressurization with the containment at 10 to 12 psig, containment fan M41-B001B tripped off on overcurrent at approximately 68 amperes.

ILRT pressure of 12.27 psig (26.24 psia) was reached at 1525. Containment fan M41-B001A was then manually tripped to prevent a possible uncontrolled trip.

CONTAINMENT STABILIZATION l

After reaching ILRT pressure, the containment atmosphere was allowed to l

stabilize. The temperature stabilization criteria of ANSI /ANS 56.8-1981, Section 5.3.1.3, and BN-TOP-1, Section 2.2.B, were satisfied.

The ILRT stabilization data are given in Appendix B.

O DU-103 2-1

(}

During containment stabilization the outer doors on the upper and

(_,/

lower personnel locks were opened. A number of small leaks were de-tected through the inner door seals. Leaks were repaired on the upper and lower lock containment pressure sensing systems. The outer doors were closed at 1853.

DURING ILRT Subsequent to containment air mass temperature stabilization, the ILRT for Grand Gulf Nuclear Station Unit 1 started at 2030 on January 3, 1982, and terminated at 0430 on the following day, for an 8-hour short duration test.

The accumulated data were statistically analyzed (see Section III (C), Test Results - Type A Test.) The maximum allowable leakage rate (L ) for the primary containment is 0.437 wt.%/ day. The a

Total Time Analysis (BN-TOP-1) yields a leakage rate of 0.068 wt.%/ day with an upper 95% confidence limit of 0.139 wt.%/ day.

Based on the Mass Point Analysis (ANSI /ANS 56.8-1981), the calculated leakage rate is 0.072 wt.%/ day with an upper 95% confidence limit of 0.079 wt.%/ day.

These values are well below the Grand Gulf Nuclear Station Unit 1 acceptance criterion of 0.328 wt.%/ day (0.75 L )*

a VERIFICATION FLOW TEST A successful verification flow test was performed subsequent to the

')

ILRT from 0615 to 1015 on January 4, 1982.

ILRT instrumentation per-s_J formance was checked by imposing a leakage rate (L ) of 0.364 wt.%/ day a

(7.67 scfm). Af ter imposing the leakage rate, the containment atmos-pheric conditions were allowed to stabilize for one (1) hour.

Due to an apparent flow restriction in the verification flow line, the imposed leakage rate could not reach the maximum allowable leakage rate (La) of 0.437 wt.%/ day. The imposed leakage rate (Lo) of 0.364 wt.%/ day is within the acceptance limits of La + 25% as given in ANSI /ANS 56.8-1981, Section 3.2.6(b)(1). The results of the verification test correlated to the ILRT are summarized as follows:

Measured (Acceptance Limit) 95% UCL Test Method Leakage wt.%/ day wt.%/ day a.

ILRT/ Mass Point 0.072 (0.328) 0.079 ILRT/ Total Time 0.068 (0.328) 0.139 b.

Verification / Mass Point 0.431 (0.327-0.545)

NA Verification / Total Time 0.434 (0.323-0.541)

NA 0)

\\s_

1 DH-103 2-2

DEPRESSURIZATION AND DRWELL BYPASS TEST Following the successful completion of the ILRT and verification flow test, containment depressurization began at 1030 on January 4, 1982. At 4.3 psig, a containment entry was made to close the drywell lock for the Drywell Bypass Test. The containment was then depressurized to O psig and the dry

• well, whose pressure had dropped to 2.2 psig, was repressurized to 3 psig.

During repressurization of the drywell it was necessary to raise the sup-pression pool level to prevent leakage through the weir wall. After raising the suppression pool level, leakage through the weir wall was observed at 3.02 psig. The drywell pressure was then maintained between 3.00 and 3.01 psig with no observed leakage through the weir wall. The drywell atmosphere was allowed to stabilize for one hour, after which the Bypass Leakage Test began at 0400 on January 4, 1982. The Bypass Leakage Test was successfully completed at 0800. The calculated bypass leakage rate of 609.7 scfm is well below the allowable rate of 3500 scfm. Refer to Appendix H, Drywell Bypass Test Summary Data for calculations.

OG DH-103 2-3

l GGNO OIT/ ILRT PR699UR.6 Vs. TME C URVE LEGEND 61 T

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I III. TEST DATA

SUMMARY

Pursuant to the requirements of ANSI /ANS 56.8-1981, Section 5.8, Reporting of Results, the information in this section is provided to supply adequate data for an independent review of the containment system leakage rate test results and instrumentation.

4.

Plant Information 1

Owner:

Mississippi Power and Light Company Plant:

Grand Gulf Nuclear Station Unit 1 Location:

Port Gibson, MS Containment Type:

Mark III NSSS Supplier, Type: General Electric, BWR Date Test Completed: January 5, 1982 B.

Technical Data 1.

Containment Net Free Air Volume' 1,670,360 cu ft 2.

Design Pressure P = 15 psig d

{

3.

Design Temperature T = 185'F 4.

Calculated Peak Accident Pressure P = 11.5 psig a

5.

Calculated Peak Accident Temperature T = 181'F a

6.

Containment ILRT Average Temperature 40*F-120*F Limits C.

Test Results - Type A Test 1.

Test Method Absolute I

l 2.

Data Analysis Technique Mass Point Leakage Rate per ANSI /ANS 56.8-1981

)

Total Time per BN-TOP-1 3.

Test Pressure (actual)

P = 11.97 to 12.27 psig 4

4.

Maximum Allowable Leakage Rate L = 0.437 wt.%/ day a

5.

75% of L 0.328 wt.%/ day a

6.

Integrated Leakage Rate Test Results Leakage Rate, L,. wt.%/ day From Regres-At Upper sion Line 95% Confi-dence Limit Mass Point Analysis 0.072 0.079 Total Time Analysis 0.068 0.139 DH-103 3-1

/%

7.

Verification Test Imposed Lo = 0.364 wt.%/ day (7.67 scfm)

(_,/

Leakage Rate 8.

Verification Test Results Leakage Rate, L wt.%/ day yg, Mass Point Analysis 0.431 Total Time Analysis 0.434 9.

Verification Test Limits:

Test Limits, L, wt.%/ day y

Mass Point Total Time Analysis Analysis Upper Limit (Lo+ Lam + 0.25L )

0.545 0.541 a

Lower Limit (Lo + Lam - 0.25L )

0.327 0.323 a

10.

Report Printouts:

The report printouts and data plots for the Type A and verification test calculations are provided in Appendixes C through G.

D.

Drywell Bypass test results are provided in Appendix H.

E.

Test Results - Type B and C Tests O

Refer to Appendix 1 for a summary of local leakage rate test results.

F.

Integrated Leakage Rate Measurement System (For ILRT Data Acquisition System, see Figure 2).

1.

Absolute Pressure (2 channels):

Mensor Quartz Manometer Model No. 10100-001 PI-l Capsule S/N 2407, Gage S/N 1522 PI-2 (Spare) Capsule S/N 2406, Gage S/N 1555 Range:

0-100,000 counts; 0-100 psia Accuracy:

+ 0.015% reading Sensitivity:

0.001 psia Repeatability:

0.001 psia Calibration Date: 12/23/81 I

i i O DH-103 3-2

i 2.

Drybulb Temperature (22 sensors):

Rosemount resistance temperature detector Model No.

14632 Series 78 r

Element:

Platinum Resistance:

Ro = 100 ohms @ 32*F Lecd Type:

3 lead potentiometric configuration Temperature Range:

32' to 120*F (from calibration data)

Volumetrics Bridge Model No. VSTD 333 Input Voltage:

i 15 volts and 5.2 volt Resistance:

100 ohms @ 32*F j

Output:

1.0 millivolt /*F; 32*F = 32 mv.,

100*F = 100 mv.; 3-wire configuration with constant current Adjustment:

Zero, span and linearity (limited)

Accuracy:

0.l*F Sensitivity:

0.0l*F Repeatability:

0.0l*F Calibration Date:

12/21/81 3.

Dewpoint Temperature (6 sensors):

Dewpoint Temperature Systems - EC&G, Inc., Dewpoint Hygrometer, Model No. 660 with 6 sensors and signal conditioning.

Accuracy:

1 0.l*F Sensitivity:

0.0l*F Repeatability:

0.05'F Calibration Date:

12/18/81 4.

Verification Flow (1 channel):

Volumetric thermal mass flow meter, TSI model No. 2013 S/N 1516 Range:

0-10.0 scfm Accuracy:

i 1% F.S.

Sensitivity:

1 0.01 scfm Repeatability:

1 0.01 scfm Calibration date:

10/20/81 5.

Drybulb and Dewpoint Temperature Sensor Volume Fractions (see Tables 1 ar.d 2).

O DH-103 3-3

+,

,-,t m.,

(

G.

Information Retained at Plant The following information is available for review at the facility:

1.

Access control procedures established to limit ingress to containment during testing.

2.

A listing of all containment penetrations, including the total i

number of like penetrations, penetration size, and function.

1 3.

A listing of normal operating instrumentation used for the leakage rate test.

4.

A system lineup (at time of test) showing required valve positions and status of piping systems.

5.

A continuous, sequential log of events from initial survey of containment to restoration of all tested systems.

6.

Documentation of instrumentation calibrations and standards (included with documentation should be an error analysis of instrumentation).

7.

Data to verify temperature stabilization criteria as estab-lished by test procedure (Appendix B).

O 8.

The working copy of the test procedure that includes signature sign-off of procedural steps.

9.

The procedure and all data that verify completion of penetra-tions and valve testing (B&C-type tests) including as-found leak rates, corrective action taken, and final leak rate.

10.

Computer printouts of ILRT data and manual data accumulation along with summary description of computer program (Appendix C).

11.

The Quality Assurance audit plan or checklist used to monitor ILRT with proper sign-offs.

12.

A listing of all test exceptions including changes in contain-ment system boundaries instituted by licensee to conclude successful testing.

13.

Description of sensor malfunctions, repairs, and methods used to redistribute volume fractions to operating instrumentation where applicable.

l 14.

A review of confidence limits of test results with accompanying computer printouts where applicable.

lO i

DH-103 3-4

i l

i i

i 15.

Description of method of leakage rate verification of instru-

}

ment measuring system (superimposed leakage), with calibration

,1 information on flow meters along with calculations used to-J measure the verification leakage rate (Appendixes F and G).

5 16.

Plots presenting ILRT data obtained during the test

l (Appendix E).

I i

17. The P& ids of systems which penetrate the containment.

i a

e J

l t

i l

i i

4 f

I f

l l

l DH-103 3-5 i

{

TABLE 1 CONTAINMENT TEMPERATURE AND DEWPOINT SENSOR LOCATIONS AND VOLUME FRACTIONS (ILRT)

Containment Azimuth Distance from Volume RTD Instrument No.

Elevation (Degrees)

Center Fraction TE-N001-01 274'-0" 352 20'-0" 0.062 TE-N001-02 274'-0" 172 20'-0" 0.062 TE-N001-03 247'-9" 90 30'-8" 0.062 TE-N001-04 245'-9" 265 27'-6" 0.062 TE-N001-05 214'-4" 45 50'-6" 0.062 TE-N001-06 229'-2" 155 49'-8" 0.062 TE-N001-07 216'-0" 225 49'-8" 0.062 TE-N001-08 227'-0" 319 49'-0" 0.062 TE-N001-09 173'-0" 220 52'-0" 0.058 1

TE-N001-10 163'-0" 305 50'-8" 0.057 TE-N001-11 164'-6" 155 28'-8" 0.022 TE-N001-12 141'-6" 162 50'-3" 0.058 TE-N001-13 141'-2" 90 55'-6" 0.057 TE-N001-14 122'-2" 335 41'-2" 0.057 TE-N001-15 124'-0" 177 51'-6" 0.057 O.

TE-N001-16 150'-6" 219 25'-4" 0.022 TE-N001-17 120'-0" 95 27'-8" 0.022 TE-N001-18 129'-0" 187 29'-0" 0.022 TE-N001-19 168'-0" 350 30'-3" 0.022 TE-N001-20 153'-5" 41 27'-3" 0.023 TE-N001-21 119'-9" 278 26'-9" 0.022 TE-N001-22 102'-6" 0

4' O.005 1.000 Containment Azimuth Distance from Volume ME Instrument No.

Elevation (Degrees)

Center Fraction ME-N002-01 247'-9" 90 30'-8" 0.210 ME-N002-02 216'-0" 225 49'-9" 0.210 ME-N002-03 167'-0" 305 50'-8" 0.210 ME-N002-04 122'-2" 355 41'-2" 0.210 ME-N002-05 158'-5" 41 27'-3" 0.080 ME-N002-06 118'-2" 278 26'-9" 0.080 1.000 i

O l

3-6 DH-103 i

.=

TABLE 2 DRYWELL TEMPERATURE AND DEWPOINT SENSOR LOCATIONS AND VOLUME FRACTIONS (BYPASS TEST)

Drywell 1

Azimuth Distance from Volume 1

RTD Instrument No.

Elevation (Degrees)

Center Fraction TE-N001-ll 164'-6" 155 28'-8" 0.138 TE-N001-16 150'-6" 219 25'-4" 0.138 TE-N001-17 120' 95 27'-8" 0.138 TE-N001-18 129' 187 29'-0" 0.138 I

TE-N001-19 168' 350 30'-3" 0.138 TE-N001-20 153'-5" 41 27'-3" 0.138 TE-N001-21 119'-9" 278 26'-9" 0.138 TE-N001-22 102'-6" 0

4'-0" 0.034 1.000 Drywell Azimuth Distance from Volume ME Instrument No.

Elevation (Degrees)

Center Fraction ME-N002-05 158'-5" 41 27'-3" 0.5 ME-N002-06 118'-2" 278 26'-9" 0.5 4

1.0 i

i O

DH-103 3-7 i

-__.--..,__-_.-_.m___

m M C N

e, 5mu m

mm mc 22 m -4 l

l 3"

EE ac

_ _ __ _ _ __ _, = a:

1 w.

I I

=,m B,mN I

=

>mm

>m l

2mm Emm mmm l

~

1

~uss

-ENS E"<E 85a

-c_

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o ma a-

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-4 me r r= m I

ama am=

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=

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\\

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a 1

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H C "4 I

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l i

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I H

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n i

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2: c Ea

=9 i

o Na i

8 o

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m

="

i c

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=

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en, 1

I g

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o i

i 2

m I

g I

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=g i

l._.______.____________l l

to i

I i

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i x

,=

n e

ig;

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I g

en 8c I

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me o>c P

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nm nm r-yy e-M y g n m -4 e m -4

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U m g:=

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m 2

I I

,_-._____.___-.________J_.__._____.._I, AV FIGURE 2 3-8

IV.

ANALYSIS AND INTERPRETATION O

A.

This section is provided pursuant to ANSI /ANS 56.8-1981, Section 5.8.6, which requires analysis of leakage rate data and provides an interpretation of the test results to show proper compliance l

with acceptance criteria specified in ANSI /ANS 56.8-1981, 10CFR50, Appendix J, and the Grand Gulf Nuclear Station FSAR.

Several corrections must be added to the calculated results of the Unit 1 ILRT. The Plant Chilled Water System (Pen 38 + 39) was not in the post LOCA lineup position and therefore the LLRT result of 2.69 SCFH must be added to the ILRT calculated results. The seal systems on the upper and lower personnel locks required makeup flows of 0.12 and 0.005 SCFH respectively during the ILRT period.

The total correction to be added to the calculated Type A leakage rate is 2.82 SCFH or 0.004%/ day.

1 Pre-and post-test containment water level measurements indicated that the upper pool water volume had decreased by 574 cu f t from 1700 December 31, 1981, to 1200 January 5, 1982, and that the dry-well sump water volume had increased by 95 cu ft from 1000 January 3 to 1200 January 5, 1982. This resulted in a net water volume decrease rate of 74 cu ft per day. The indicated water volume change is most likely due to measurement accuracy. At any rate, a decrease in water volume would not mask an in-leakage, and therefore is not added as a correction.

The corrected and uncorrected Type A leakage rates are tabulated below:

L wt%/ day 95% UCL wt%/ day am I

II III I

II III 1.

ILRT/ Mass Point 0.072 0.076 0.328 0.079 0.083 0.328 ILRT/ Total Time 0.068 0.072 0.328 0.139 0.143 0.328 2.

Ve rification/

Mass Point 0.431 0.327-0.545 Total Time 0.434 0.323-0.541 where Column I Uncorrected leakage rate calculated during

=

ILRT.

Column II Corrected leakage rate corresponding to Column

=

I plus corrections.

Column III = Acceptance limits O

DH-103 4-1

~

~ - _ _ _. _

The ILRT results at the upper 95% confidence level satisfy the b

acceptance criterion of Lam < 0.75La = 0.328%/ day, at Pa = 11.5 V

psig.

B.

ISG CALCULATION The ISG calculation provided below was performed according to the format specified in ANSI /ANS 56.8-1981, Appendix G.

a.

Calibration Data Number of Sensors Sensitivity, E Repeatability,C Temperature, T 22 0.01*F (*R) 0.01*F (*R)

Pressure, P 1

0.001 psia 0.001 psia Vapor Pressure (Dewpoint), Py 6

0.01*F 0.05'F b.

Instrument Measurement Errors 1.

Temperatures

)2jl/2 (No. of Sensors)l/2 T = [(F )2,

/

e 7

[(0.01)2 + (0,01)2]l/2/(22)1/2

=

0.003*F (*R)

=

2.

Pressures p = [(E )2 + (g )2)1/2 (No. of Sensors)l/2

/

e p

p

[(0.001)2 + (0,001)2]l/2/(1)1/2

=

0.0014 psia

=

3.

Vapor Pressure For a dewpoint temperature range of 68.25'F + 0.05'F the average rate of change in dewpoint pressure is 0.0118 psi /*F, i.e.,

vapor pressure @ 68.3*F = 0.34243 psi

@ 68.2*F = 0.34125 psi change for 0.l*F = 0.00118 psi The sensitivity and repeatability in terms of pressure are:

(0.0118 psi /*F)(0.Ol*F) = 0.000118 psi E

=

py gpy (0.0118 psi /*F)(0.05'F) = 0.00059 psi

=

U DH-103 4-2

___.__m I

i 4

Therefore, py)2 + g )2 1/2 (No. of Sensors)1/2

{

3

/

e

= [(E py py l

= [(0.000118)2 + (0.00059)2]1/2/(6)1/2 I

l

= 0.00025 psi l

i 1

i c.

ISC Calculation for 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ILRT

[

j t

P = 12.27 psig + 14.7 = 26.97 psia l

T = 77*F + 460 = 537*R ISC = 1 2400 2

2+2 2+2 p

y e

f ISG = 1 2400 2 [0.0014 ) 2 + 2 [0.00025g 2 + 2 / 0.003) 2 1/2

~

i 8

\\ 26.97 /

\\ 26.97 /

( 537 /

= 1 300 (0.54 x 10-8 + 0.0169 x 10-8 + 0.006 x 10-8)1/2 l

= 1 300 (0.75 x 10-4)

J

= 0.0225 wt.%/ day i

25% La = 0.437 7 0.25 = 0.10925 wt.%/ day 0.0225 < 0.10925 meets the criterion of ANSI /ANS 56.8-1981 and BN-TOP-1.

i l

2 1

i t

r i

i

!O l

DR-103 4-3 I

r

f\\

V.

COMPUTER REPORT AND DATA PRINTOUT N,

A.

MASS POINT REPORT The Mass Point Report presents leakage rate data (wt%/ day) as determined by the Mass Point Method described in the " Computer Program" section of this report. The " Calculated Leakage Rate" is the value determined from the regression ~ analysis. Thel i

a-

" Containment Air Mass" values are the masses of dry air in the containment (lbm). These values, determined from the Equatica' of State, are used in the regression analysis.

)

B.

TOTAL TIME REPORT 1

([

The Total Time Report presents data leakage rate (wt%/ day) as determined by the Total Time Method. The " Calculated Leakage Rate" is the value determined f rom the regression analysis. The

" Measured Leakage Rates" are the leakage rate values determined using Total Time calculations used in the above regression analysis.

~

C.

TREND REPORT The Trend Report presents leakage rates (as determined by the Mass Point and Total Time methods described in the " Computer Program" g

section of this report) in percent of the initial contained mass of dry air per day (wt%/ day), elapsed time (hours), and number of s

data points.

D.

SUMMARY

DATA REPORT The Summary Data report presents the actual data used to calculate leakage rates by the various methods described in the " Computer Program" section of this report. The five column headings are TIME, DATE, TEMP, PRESSURE, and VPRS, and contain data defined as follows:

1.

TIME:

Time in'24rhourinotations (hours and minutes).

2.

DATE:

Calendar date (month and day).

3.

TEMP:

Containment weighted-average drybulb temperature in absolute units, degrees Rankine (*R).

4.

PRESSURE: Partial pressure of the dry air component of the containment atmosphere in absolute units (psia).

5.

VPRS:

Partial pressure of water vapor of the containment atmosphere in absolute units (psia).

OG DH-103 5-1

E.

SUMMARY

OF MEASURED DATA AND

SUMMARY

OF CORRECTED DATA

)

(m,/

The Summary of Measured Data presents the individual containment atmosphere drybulb temperatures, dewpoint temperatures, and absolute total pressure measured at the time and date as indicated and is used to determine the temperature and pressure described in V.D.3-5 above.

1.

TEMP 1 through TEMP 22 are the drybulb temperatures. The values in the right-hand column are temperatures (*F), multi-l plied by 100, as read from the data acquisition system (DAS).

l l

The values in the left-hand column are the corrected tempera-tures expressed in absolute units (*R).

2.

PRES 1 is the total pressure, absolute. The right-hand value, in parentheses, is a number in counts as read from the DAS.

This count value is converted to a value in psia by the com-puter via the instrument's calibration table, counts versus psia. The left-hand column is the absolute total pressure, psia.

3.

VPRS 1 through VPRS 6 are the dewpoint temperatures (water vapor pressures). The values in the right-hand column are temperatures (*F), multiplied by 100 as read from the DAS.

The values in the left-hand column are the water vapor pres-sures (psia) from the steam tables for saturated steam corresponding to the dewpoint (saturation) temperatures in f~'T the center column.

s_ /

The Summary of Corrected Data presents corrected temperature and pressure values and calculated air mass determined as follows:

1.

TEMPERATURE (*F) is the volume weighted average containment i

atmosphere drybulb temperature (refer to Section III, Tables 1 and 2, for sensor volume fractions) derived from TEMP 1 through TEMP 22.

2.

CORRECTED PRESSURE (psia) is the partial pressure of the dry air component of the containment atmosphere, absolute. The volume weighted average containment atmosphere water vapor pressure is subtracted from PRES 1, total pressure, yielding the partial pressure of the dry air.

3.

VAPOR PRESSURE (psia) is the volume weighted average contain-ment atmosphere water vapor pressure, absolute (refer to Section III, Tables 1 and 2 for sensor volume fractions),

derived from VPRS 1 through VPRS 6.

4.

CONTAINMENT AIR MASS (1bm) is the calculated mass of dry air in the containment. The mass of dry air is calculated using the containment free air volume and the above TEMPERATURE and CORRRECTED PRESSURE of the dry air.

/T Note: This printout is not included in the report, but is

(_-)

retained at the facility.

DH-103 5-2

APPENDIX A

{

BECHTEL ILRT COMPUTER PROGRAM

'v/

A.

Program and Report Description 1.

The Bechtel ILRT computer program is used to determine the inte-grated leakage rate of a nuclear primary containment structure.

The program is used to compute leakage rate based on input values of time, containment atmosphere total pressure, drybulb tempera-ture, and dewpoint temperature (water vapor pressure). Leakage rate is computer using the Absolute Method as defined in ANSI /ANS 56.8-1981, " Containment System Leakage Testing Requirements" and BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants".

The program is designed to allow the user to evaluate containment leakage rate test results at the jobsite during' containment leakage testing.

Current leakage rate values may be obtained at any time during the testing period using one of two computational methods, yielding three different report printouts.

2.

The first printout, the Total Time Report, is based on the Total Time Method described in BN-TOP-1.

Leakage rate is computed from initial values of free air volume, containment atmosphere drybulb temperature and partial pressure of dry air, the latest values of the same parameters, and elapsed time. These individually computed gg leakage rates are statistically averaged using linear regression by 2

'~- )

the method of least squares. The Total Time Method is the computa-t tional technique upon which the short duration test criteria of BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plant,"

are based.

3.

The second printout is the Mass Point Report and is based on the Mass-Point Analysis Technique described in ANSI /ANS 56.8-1981,

" Containment System Leakage Testing Requirements." The mass of dry air in the containgent is computed at each data point (time) using the Equation of State, from current values of containment atmosphere drybulb temperature and partial pressure of dry air.

Contained mass is " plotted" versus time and a regression line is fit to the data using the method of lepst squares.

Leakage rate is determined from the statistically derived slope and intercept of the regression line.

4.

The third printout, the Trend Report, is a summary of leakage rate values based on Total time and Mass Point computations presented as a fuction of number of data points and elapsed time (test dura-tion). The Trend Report provides all leakage rate values required for comparision to the acceptance criteria of BN-TOP-1 for conduct of a short duration test.

5.

The program is written in a high level language and is designed for use on a mini-computer with direct data input from the data acquisition system.

Brief descriptions of program use, formulae

(< s-)

used for leakage rate computations, and program logic are provided in the f ollowing paragraphs.

DH-103 A-1

I B.

Explanation of Program

(,j 1.

The Bechtel ILRT computer program is written, for use by experi-enced ILRT personnel, to determine containment integrated leakage rates based on the Absolute Method described in ANSI /ANS 56.8-1981 and BN-TOP-1.

2.

Information loaded into the program prior to the start of the test:

Number of containment atmosphere drybulb temperature sensors a.

and dewpoint temperature (water vapor pressure) aansors to be used in leakage rate computations for the specific test b.

Volume fractions assigned to each of the above sensors c.

Calibration data for above sensor, if required d.

Calibration data for pressure sensor.

3.

Information entered into the program at the start of the test:

a.

Test title b.

Current test pressure and peak test pressure f"'

c.

Maximum allowable leakage rate at peak test pressure N,-]S d.

If the test is a verification test:

(1) Imposed leakage rate (2) Leakage rates determined using the two computational methods described in Paragraph A above during the ILRT.

4.

Data received from the data acquistion system during the test, and used to compute leakage rates:

a.

Time and date l

b.

Containment atmosphere drybulb temperatures 1

[

c.

Containment atmosphere pressure I

d.

Containment atmosphere dewpoint temperatures i

i 5.

After all data at a given time are received, a Summary of Measured l

Data report (refer to " Program Logic," Paragraph D, " Data" option command) is printed on the data terminal.

The date, containment atmosphere weighted average drybulb temperature, partial pressure of the dry air and water vapor pressure are stored on a data file.

I I

n%.s l

l DH-103 A-2 l

l t

(

6.

If drybulb and dewpoint temperature sensors should fail during the i

V test, the data from the sensor (s) are not used.

The volume frac-i tions for the remaining sensors are recomputed and reloaded into the program for use in ensuing leakage rate computations.

C.

Leakage Rate Formulae 1.

Computation using the Total Time Method:

1 a.

Measured leakage rate, from data:

i P V = W RT1 (1) 1 1

P V = W RTi (2) i t

2400 (W1-W) i L

=

i (3)

Solving for W1 and Wi and substituting equations (1) and (2) into (3) yields:

Li = 2400/ati(1-T P /T P )

(4) 1t t1 where:

W,Wi = Weight of contained mass of dry air at times ti and 1

ti respectively, lbm.

T,Ti = Containment atmosphere drybulb temperature at times 1

ti and ti respectively,

• R.

P,Pi = Partial pressure of the dry air component of the con-1 tainment atmosphere at times ti and ti respectively, psia.

V = Containment free air volume (assumed to be constant 3

during the test), ft.

th ti, tt = Time at ist and i data points respectively, hours.

Att = Elapsed time from ti to ti, hours.

R = Specific gas constant for air = 53.35 f t.lbf/lbm.*R.

Li = Measured leakage rate computed during time interval el CO C1, %/ day.

I DH-103 A-3

b.

Calculated Icakage rate from regression analysis:

O L = a + batN (5) where:

L = Calculated leakage rate, %/ day, as determined from the regression line.

2 IL (Eatg ) - Eatf(EL att) i i

a=

2 (6)

N(Eatg ) _ (gggi)2 N(EL ati) - EL (eat )

i i

i b=

2 (7) i N(Eatg ) - (EAtt)2 N = Number of data points N

I=E i=1 Calculated leakage rate at the 95% confidence level.

c.

L95 = a + batN+S-(8)

O L

where:

i L95 = Calculated leakage rate at the 95% confidence level, %/ day, at elapsed time AtN*

For AtN < 24 0 025;N-2 [E(L -I )2 (N-2)]l/2 x [1 + 1 + (At - ) /E(at -It) ] /

(9a)

S_

=t

/

t g N

i L

N where, to.025;N-2 = 1.95996 + 2.37226 + 2.82250 ;

N-2 (N-2)4 j

For AtN2.24 1 - L )2 (N-2)]1/2 x [1 +(AtN-

) /E(Ot - t)2)l/2 (9b) i S_ = t0 025;N-2 [I(L

/

g i

L N

i 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 where, t0 025;N-2 =

(N-2)2 + 1.2209(N-2) - 1.5162 Li = Calculated leakage rate computed using equation (5) at total clapsed time Ati, %/ day.

{

_At =

Eat t v

4 N

4 I

DH-103 A-4

2.

Computation using the Mass Point Method t

a.

Contained mass of dry air from data:

Wi = 144 P d j

RTi (10) where:

j All symbols as previously defined.

b.

Calculated leakage rate from regression analysis:

b

__L = -2400 -

(11) a where:

~

L

= Calculated leakage rate, %/ day, as determined from the regression line.

EW -bEAti i

a

=

(12)

N E[(Wi - IW /N) (Ati - E )]

i E(At - b)2 i

Ati = Total elapsed time at time of ith data point, hours N = Number of data points Wi = Contained mass of dry air at ith data point, Ibm, as computed from equation (10),

i N

E=E i=1 E = IAt /N i

c.

Calculated leakage rate at the 95% confidence level.

1 i

-2400 f

L95 =

(b + S )

(14) b

{

a where:

s

__95 = Calculated leakage rate at the 95% confidence level, %/ day.

L

)

DH-103 A-5 i

i

)

4 3

i 4

h

- E(W1 - W )2 1/2 1

.sb"t0 025;N-2 (15) i

_(N-2)E(ati - It)2 J

1.6449(N-2)2 +-3.5283 (N-2)2 + 0.85602 j

where, t0 025;N-2 =

(N-2)2 + 1.2209 (N-2) - 1.5162 i

-g = Contained mass of dry air, lbm, computed at the i (16) f W

th j

data point from the regression equation i

= a + bati i

All other symbols are previously defined.

1 i

e c

't l

i DH-103 A-6

X

)

D.

Procran Loeic 1.

A flow chart of Bechtel ILRT computer program usage is pre-sented in Figure 1, following.

The various user options and a brief description of their associated function are presented below:

OPTION ComiAND FUNCTION DATA Enables operator to entet raw data. When the sys-tem requests values of time, volume temperature, pressure and vapor pressure, the user enters the appropriate data. After completing the data entry, a summary is printed out.

The user then verifies that the data were entered correctly.

If errors are detected, the user will then be given the opportunity to correct the errors.

After the user verifies that the data were entered correctly, a Corrected Data Su= mary Report of time, date, average temperature, partial pressure of dry air, and water vapor pressure is printed.

TREND Terminal will print out a Trend Report.

'~'\\

TOTAL Terminal will print out a Total Time Report.

f MASS Terminal will print out a Mass Point Report.

TERM Enables operator to sign off temporarily or pe rmanently.

SAVE

~ Enables operator to store the Data Sunnary on a file.

PREV Enables operator to call up an old, previously stored, file.

CORR Enables operator to correct data stored on a file.

LIST When used with a given file name, the printer will print out a list of the Summary Data stored on the file.

t READ Enable the computer to receive the next set of raw data from the data acquisition system directly.

1 A-7

~

O

( SIGtJ DN)

I ENTER BASIC /

t

-- N O

/ ENTER PREVIOUS \\

\\ INFORMATION/

\\ VALUES FROM FILES /

YES r

DATA ENTERS

SUMMARY

(OPTIONSp DATA STORE 0 ON (r PREV EO FILE s

(ENTER D ATA)

CORRECTS o-CORR

SUMMARY

D ATA

[ YES (E RRO R?)

o STO RES

SUMMARY

\\

ENTER

/

N0 o-S AV E - -

DATA DN A CORRECTIONS /

SELECTED FILE

SUMMARY

OF o-TREND MEASURED DATA

= (TREND REPORT l

~-

O+-

o-TOTAL TOTAL TIME u

(

YES s-REPORT N0 o MASS MASS POINT REPORT CORRECTED

SUMMARY

DATA PRINTOUT o-LIST PRINT OUT OF

=

SUMMARY

DATA o-TERM

' ( SIGN OFF )

N J

l BECHTEL CONTAINMENT INTEGRATED LEAKAGE RATE TEST COMPUTER PROGRAM FLOW CliART FIGURE 1 C\\

U i

A-8

)

APPENDIX B ILRT STABILIZATION DATA TEST.STA GRAND GULF STABILIZATION ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.000 VRATEM = 0.000 VRATEP = 0.000 TIME DATE TEMP PRESSURE VPRS 1529 103 537.56366 26.425938 0.34851480 1545 103 537.01373 26.402582 0.34475750 1603 103 536.61597 26.383574 0.34468400 1615 103 536.46893 26.377193 0.34303159 1

1630 103 536.30707 26.368984 0.34320599 1645 103 536.20459 26.363253 0.34291309 1700 103 536.09918 26.357325 0.34281561 1715 103 536.03223 26.353136 0.34298769 1730 103 535.95685 26.348457 0.34264520

[~}

1745 103 535.88330 26.344131 0.34295520

(,j 1800 103 535.82629 26.340103 0.34296569 1815 103 535.76117 26.337587 0.34246781 1830 103 535.70874 26.334372 0.34267199 1845 103 535.66150 26.332005 0.34202629 1900 103 535.61688 26.329777 0.34224480 1915 103 535.56860 26.327791

.O.34222180 1930 103 535.54742 26.324705 0.34229621 1945 103 535.43054 26.323195 0.34179929 2000 103 535.44885 26.320612 0.34237379 2015 103 535.40631 26.318562 0.34241500 O

I B-1

/~'N b

APPENDIX C ILRT

SUMMARY

DATA TEST.DAT GRAND GULF ILRT ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.000 VRATEM = 0.000 VRATEP = 0.000 TIME DATE TEMP PRESSURE VPRS 2030 103 535.38918 26.316441 0.34252653 2045 103 535.37219 26.315517 0.34244490 2100 103 535.34686 26.313202 0.34275225 2115 103 535.32245 26.311718 0.34222719 2130 103 535.28601 26.310568 0.34237543 2145 103 535.26984 26.309896 0.34204134 2200 103 535.23566 26.307184 0.34274417 2215 103 535.21973 26.304913 0.34300748 2230 103 535.19214 26.304295 0.34262270 2245 103 535.16925 26.302761 0.34315175 2300 103 535.14685 26.301828 0.34307989 2315 103 535.11749 26.300154 0.34274691 7_s 2 30 103 535.10406 26.299398 0.34249672

(\\ -)

2345 103 535.09546 26.299583 0.34231171 0

104 535.06689 26.296225 0.34366253 15 104 535.05304 26.297117 0.34277007 30 104 535.03369 26.295589 0.34329468 45 104 535.01672 26.293724 0.34415492 100 104 534.99390 26.293665 0.34321022 115 104 534.98413 26.292389 0.34348071 130 104 534.96783 26.291492 0.34337339 145 104 534.96344 26.290226 0.34363529 200 104 534.94757 26.289938 0.34392363 215 104 534.93909 26.288767 0.34409159 230 104 534.92371 26.287523 0.34432954 245 104 534.91162 26.287708 0.34414417 300 104 534.89838 26.286375 0.34447473 315 104 534.89233 26.285236 0.34460890 330 104 534.87921 26.285433 0.34441105 345 104 534.86578 26.284437 0.34440356 l

400 104 534.85150 26.283850 0.34499204 415 104 534.84827 26.283432 0.34440419 400 104 534.82874 26.283085 0.34475130 li-(

(_

C-1 i

~ APPENDIX D ILRT CALCULATIONS O\\--)

GRAND GULF ILRT LEAKAGE RATE (WEIGHT PERCEtJT/ DAY)

MAS 3-POINT ANAL (SIS TIME AND DATE.AT START OF TEST:

2030 01(3 ELAPSED TIME:

8.00 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS TOT. AVG. MASS (R)

(PSIA)

MASS (LEM)

(lLBM)

LOSS (LBM/HR)

---

_-_ =-_

2030 535.388 26.3164 221566.

2045 535.372 26.3155 221565.

1.1 4.6 2100 535.347 26.3132 221556.

9.0 20.3 2115 535.322 26.3117 221553.

2.4 16.8 2100 535.236 26.3106 221559.

-5.4 7.2 2145 535.270 26.0099 221560.

-1.0 4.9 2200 535.236 26.3072 221551.

8.7 9.9 2215 535.220 26.3049 221539.

12.5 15.6

'}

2230 535.192 26.3043 221545.

-6.2 10.6

' 2245 535.169 26.3028 221541.

3.4 10.9 2300 535.147 26.3018 221543.

-1.4 9.3 2315 535.117 26.0002 221541.

1.9 9.1 2330 535.104 26.2994 221540.

0.8 8.6 2345 535.095 26.2996 221545.

-5.1 6.4 0

535.067 26.2962 221529.

16.5 10.6

(

15 535.053 26.2971 221542.

-13.3 6.4 30 535.034 26.2956 221537.

4.9 7.2 45 535.017 26.2937 221528.

8.7 8.8 100 534.994 26.2937 221537.

-9.0 6.4 115 534.984 26.2924 221531.

6.7 7.4 100 534.968 26.2915 221530.

0.8 7.2 145 534.963 26.2902 221521.

8.9 8.6 200 534.948 26.2899 221525.

-4.2 7.4 215 534.939 26.2888 221519.

6.4 8.2 230 534.924 26.2875 221515.

4.1 8.5 245 534.912 26.2877 221521.

-6.6 7.2 300 534.898 26.2864 221515.

5.8 7.8 315 534.892 26.2852 221508.

7.1 8.5 330 534.879 26.2854 221515.

-7.1 7.2 345 534.866 26.2844 221513.

2.8 7.4 400 534.852 26.283G 221514.

-1.0 7.0 415 534.848

'26.2834 221511.

2.2

7. 0 400 534.829 26.2831 221517.

-5.2 6.2 j

FREE AIR VOLUt1E USED (NILLIONS OF CU. FT.)

1.670

=

REGRESSION LINE t

INTERCEPT (LEM) 221561.

=

SLOPE (LBM/HR)

-6.7

=

O MAXIMUtl ALLONABLE LEAKAGE RATE 0.4~7

=

'~j 75 % OF MAXIMUM ALLOWABLE LEAKAGE RATE s

0.028

=

THE UFFER 95% CONFIDENCE LIMIT 0.079

=

THE CALCULATED LEAL: AGE RATE 0.072

=

D-1 1

I

_=-

q i-i, l

r"'

(

GRAND GULF ILRT LEAMAGE RATE (WEIGHT PERCENT / DAY'i TOTAL-TIME ANALYSIS 4

I TIME AND DATE AT START OF TEST:

2000 0103 ELAPSED TIME:

8.00 HOURS:

. TIME TEMP.

PRESSURE MEASURED (R)

(PSIA)

LEAKAGE RATE

---

= _

- = -

2000 535.388 26.3164 2045 535.372 26.3155 0.050 2100 535.347 26.3132 0.220 2115 535.322 26.3117 0.181 2130 535.286 26.3106 0.078 2145 535.270 26.0099 0.053 2200 535.236 26.3072 0.107 2215 535.220 26.3049 0.169 2230 535.102 26.3043 0.115 2245 535.169 26.3028 0.118 2300 535.147 26.3018 0.100

)

2015 535.117 26.3002 0.099 2330 535.104 26.2994 0.094 2345 535.095 26.2996 0.069 0

535.067 26.2962 0.11,5 gg 15 535.033 26.2971 0.06'9

(

J-30 535.034 26.2956 0.078 45 535.017 26.2937 0.096 100 534.994 26.2937 0.069

)

115 534.984 26.2924 0.081 1

130 534.968 26.2915 0.078 145 534.963 26.2902 0.093 200 534.948 26.2S99 0.080 215 534.939 26.2888 0.089 230 534.924 26.2875 0.093 245 534.912 26.2877 0.078 300 534.898 26.2864 0.084 315 534.892 26.2852 0.092 330 534.879 26.2854 0.078

~345 534.866 26.2844 0.080 3

400 534.852 26.2838 0.076 415 534.848 26.2834 0.076 430 534.829 26.2831 0.Oe7 MEAN OF MEASURED LEAKAGE RATES 1

0.095

=

MAXIMUM ALLOWADLE LEAKAGE RATE 0.437

=

75 % OF MAXIMUM ALLOWABLE LEAKAGE RATE 0.328

=

THE UPPER 95% CONFIDENCE LIMIT 0.139

=

THE CALCULATED LEAKAGE RATE 0.068

=

)

a D-2

/\\\\

' 'v)

GRAllD E-ULF ILRT TREliD REPORT LEM AGE R,.i TES t WEIGHT PERCEllT/ DAY)

TIME At1D DATE AT START OF TEST:

2030 0103 ELAPEED TIME:

S.00 HOURS NO. DATA ELAPSED TOTAL-TIME ANALYEIS' fMSS-POItiT ANALYSIS FOINTS TIME Menti CALCULATED CALCULATED 95% UCL 10 2.25 O.121 O.119 O.119 o,g33 11 2.50 O.119 O.112 O.110 0.146 12 2.75 O.117 O.107 O.104 O.134 13 3.00 0.115 0.101 0.098 0.124 14 3.25 O.112 O.091 0.085 O.111 15 3.50 0.I12 0.094 O.093 O.116 16 3.75 O.109 O.086 O.083 O.105 17 4.00 O.107 0.082 O.079 0.099 13 4.25 O.107 O.082 0.031 O 099 19 4.50 O.105 O.077 0.075 O.092 20 4.75 O.100 O.075 O.074 O.089 21 5.00 O.102 O.073 O.073 0,ve7 (3

22 5.25 O.102 O.074 0.075 O 088 (j

23 5.50 O.101 O.073

.O.075 O.086 24 5.75 O.100 0.073 O.076 O.087 25 6.00 O.100 O.074 O.078 0 OSS 26 6.25 O.099 O.073 O.077 O.086 27 6.50 0.099 0.073 0.077 0.086 28 6.75 0.098 0.074 0.079 0.087 29 7.00 0.097 0.073 0.078 0.085 30 7.25 0.097 0.072 0.077 0.084 31 7.50 0.096 0.071 0.076 0.083 32 7.75 O.095 O.070 0.075 O.081 30 8.00 O.095 O.068 0.072 O 079 s/

i a

D-3

-en,,-m-i--

---,m.

e

_w

,,,,,.,e

,-.m 7

e

,-g-y

A_PPENDIX E ILRT PLOTS 1

ILRT 1

T EHF EF.si1 UF.E 502.00 5~C.00 534.00 535.00 536.00 537.0 535.00 5 9.

)

i

+---------+---------,-----_---+----_----.-------__0,__-______,________.)

+

+

2100 -

+

+

1

+

I l

+

2200 -

l

+

+

+

+

2000 -

+

+

+

+

0-

+

+

+

+

100 -

+

+

+

+

200 -

+

+

+

+

COO -

+

+

i

+

+

400 -

+

+

+

+

500 -

+

I l

l E-1

,,,_---,--w

---r--

VERIFICATION O

TEM.ERATURE e n..m.. O'.y

.e.

e s. L,,)

J.a en c.~ c.,)U aag.UU

.J.s a

c. _

aw*.UV c.

. U U aas c~e e

n,,,.,,.,,1

+-_-__-_-- _-______ + ---__ --+-________+ ________,.______s3.Us) a y,

___ _________+

+

+

+

600 -

+

+

+

+

700 -

+

+

+

+

S00 -

+

~

+

+

+

900 -

+

+

+

+

1000 -

+

+

STABILI*.ATION TEMPERATURE 533.00 533.00 534.00 535.00 536.00 537.00 538.00 539.00

+ _ - - _ - - _ _ _ + - --

--_+_--

. _ _ _ _ _ + _ _ _ _ _ _ _ _ _, _ _ _ _ _

+

IGo3 -

+

+

+

+

L700 -

+

+

+

+

[S00 -

+

+

+

+

1900 -

+

e g

~

+

+

2000 -

i

+

E-2 m

J ILRT PRESSURE 2c.150 26.200 26.250 26.200 26.250

's.4

_ b. z e..,

. c. a t..

+_________+_________+_________+_________,________00

+

+

2100 -

+

1

+

_m m -.-

• p e.

+

+

m V() -

+

_w

+

V

~

+

I 0-

+

+

+

+

100 -

+

+

~

+

200 -

+

i

+

~

+

~

+

j 200 -

~

+

+

+

t 400 -

+

+

+

+

500 -

+

l l

l l

l l

l l

l l

l I

1 j

1 I

i E-3 i

l I

VERIFICATION PRE 55URE 26.150 26.200 26.250 26.200 26.400 26.450 sm

+_-_______+_________+_________,____26.250

+

+

+

600 -

+

+

+

+

700 -

+

+

+

+

GOO -

+

+

+

+

900 -

+

+

+

+

1000 -

+

+

STABILIZATION PRESSURE 26.150 26.200 26.250 26.200 26.250 26.400 26.450 26.500

+-------_-+-__--

.+-________,_____

+

IGO3 -

+

+

+

+

1700 -

+

+

+

1900 -

+

+

+

+

1900 -

+

+

+

+

"006 -

+

+

M E-4

[

ILRT AIRMASS

221000, 221100.

221200.

221000.

221400.

22250 221600.

221:

+_-----___+--_-__---,___--____,__-______,_________,_0.

+

+

2100 -

+

+

+

+

2200 -

+

+

+

+

2000 -

+

+

+

+

0-

+

+

+

+

100 -

+

+

+

+

200 -

+

+

+

+

300 -

+

l

+

+

400 -

+

+

+

+

500 -

+

m E-5

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

A 1

s i

i.

4 l

f' VERIFICATION 1

AIRMASS l

221000.

221100.

221200.

'"<-0 1

- - + - -

- -_^!_0_____-_]3'f___221500.

221600.

22174 j

+--

---+--

_ +--------_._-_______.

+

+

600 -

+

i

+

+

+

t i

700 -

l

+

+

+

I.

t

+

1 800 -

+

+

t

+

'900 -

i

+

A i

1000 -

+

4

+

i i Q

+

l 1

1 i

f i

STABILIZATION 1

AIRMASS 221t00.

221100.

221200.

221200.

221400.

221500.

221600.

o' 17 t.-

- - + - - -

_ + - -

~~

- - + - - -

- ---+---__ ___+___

e i

+

l

/603 -

+

\\

+

l 1

+

- +

1700 -

+

+

l

+

~

+

1900 -

+

+

+

+

1900 -

+

1

+

i

+

+

2000 -

+

+

+

I

.E-6 i

i

-wmesure- - & w ge' imp,muerg__

.--M

.-eme-..

me--wh--**-se

J v APPENDIX F VERIFICATION FLOW TEST

SUMMARY

DATA TEST.VER GRAND GULF VERIFICATION ALMAX = 0.437 VOL = 1670000.00 VRATET = 0.432 VRATEM = 0.436 VRATEP = 0.364 TIME DATE TEMP PRESSURE VPRS 515 104 534.80566 26.280268 0.34556079 530 104 534.79596 26.278370 0.34544951 545 104 534.78748 26.277615 0.34520060 600 104 534.77368 26.276218 0.34559339 615 104 534.76746 26.274252 0.34554970 630 104 534.75714 26.272772 0.34602681 645 104 534.76361 26.272007 0.34578761 700 104 534.74396 26.269663 0.34612215 715 104 534.73499 26.268349 0.34643370 730 104 534.73236 26.267462 0.34631500 s,/

745 104 534.72797 26.265524 0.34624526 800 104 534.71405 26.264580 0.34618655 815 104 534.70410 26.262316 0.34644118 830 104 534.69879 26.261040 0.34671304 845 104 534.68665 26.259174 0.34656873 900 104 534.68726 26.257030 0.34670511 915 104 534.67273 26.256052 0.34667951 930 104 534.65894 26.252333 0.34738570 945 104 534.64771 26.252180 0.34753838 1000 104 534.64069 26.250376 0.34733403 1015 104 534.33062 26.249893 0.34681413 OU F-1

4

)

APPENDIX G VERIFICATION FLOW TEST CALCULATIONS

- GRANO GULF VERIFICATION LEAKAGE RATE (WEIGHT PERCENT / DAY)

MASS-FOINT ANALYSIS TIME AND DALE AT START OF TEST:

615 0104 ELAPSED TIME:

4.00 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS TOT. AVG. MASS (R)

(PSIA)

MASS (LBM)

(LEM)

LOSS (LBM/HR) 615 534.767 26.2743 221467.

600 534.757 26.2728 221459.

8.2 32.S 645 534.764 26.2720 221450.

9.1 34.7 700 534.744 26.2697 221439.

11.6 38.6 715 534.735 26.2603 221431.

7.4 36.3 730 534.732 26.2675 221425.

6.4 34.2 745 534.728 26.2655 221410.

14.5 38.1 800 534.714 26.2646 221408.

2.2 34.0 815 534.704 26.2623 221093.

15.0-37.2 830 534.699 26.,2610 221385.

S'. 6 36.9 q

845 534.687 26.2592 221374.

10.7 37.5 900 534. 68 ~t-26.2570 221356.

18.3 40.7 915 534.673 26.2561 221353.

2.0 38.1 930 534.659 26.2523 221329.

25.6 43.0 945 534.648 26.2522 221331.

-3.4 39.0 1000 534.641 26.2504

221319, 12.3 39.7 1015 534.631 26.2499 221319

-0.1 37.2 FREE AIR VOLUME USED (MILLIONS OF CU. FT.)

=

1.670 REGRESSION LINE INTERCEPT (LBM) 221471.

=

SLOPE (LBM/HR)

-39.8

=

VERIFICATION TEST LEAKAGE RATE UFPER LIMIT =

0.545 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT =

0.327 THE CALCULATED LEAKAGE RATE 0.431-

=

G-1

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

,~,_,

O c

GRAND GULF VERIFICATION LEAKAGE RATE (WEIGHT FERCENT/ DAY)

TOTAL-TIME ANALYSIS TIME AND DATE AT STAR T OF TEST-615 0104 ELAPSED TIME:

4.00 HOURS TIME TEMP.

PRESSURE MEASURED (R)

(PSIA)

LEAKAGE RATE 615 534.767 26.2743 630 534.757 26.2728 0.356 645 534.764 26.2720 0.37e 700 534.744 26.2697 0.418 715 534.735 26.2683 0.394 700 534.732 26.2675 0.370 745 534.728 26.2655 0.413 800 534.714 26.2646 0.368 815 534.704 26.2623 0.403 830 534.699 26.2610 0.399 845 534.687 26.2592 0.406 900 534.c87 26.2570 0.441 915 534.673 26.2561 0.413'

(#')

930 534.659 26.2523 0.466

\\._ /

945 534.648 26.2522 0.'423 1000 534.641 26.2504 0.430 1015 534.631 26.2499 0.403 MEAN OF MEASURED LEAKAGE RATES 0.405

=

VERIFICATION TEST LEAKAGE RATE UPPER LIMIT =

0.541 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT =

0.323 THE CALCULATED LEAKAGE RATE

=

0.434 ul c-2

__._._.__.m I

i' i

1 g

i

-1 1

1 i

i 3

GRAND GULF VERIFICATION

.!i-

{

TREND REPORT LEAKAGE RATES (WEIGHT PERCENT / DAY) 3 j

TIME AND DATE AT START OF TEST:

615 0104 ELAPSED TIME:

4.00 HOURS j

NO. DATA ELAPSED TOTAL-TIME ANALYSIS'MASE-POINT ANALYSIS POINTS TIME l

MEAN CALCULATED CALCULATED 10 2.25 0.389 0.400 0.397 11 2.50 0.390 0.404 0.402 12 2.75 0.395 0.418 0.420 13 3.00 0.396 0.420 0.420

{

14 3.25 0.402 0.436 0.440

{

15 3.50 0.403 O.436 O.439 16 3.75 0.405 0.439 0.439

(

17 4.00 0.405 0.434 O.431 4

1 4

s e

i I

f f

t l

G-3 s

4 1

. ~...

h

' (O APPENDIX H j

BYPASS LEAKAGE RATE CALCULATIONS The formula for computing leakage rate by flow totalizer method is:

LL = (P /T1 - P /T ) x (VT /60tP ) + F/60t 1

2 2 s

s where:

LL=

Leakage rate, standard cubic feet per minute (SCFM)

P,P2 = Test volume absolute pressure at start and end of test 1

respectively, absolute units T,T2 = Test volume absolute temperature at start and end of test 1

respectively, absolute units V

= Total test free air volume, cubit feet (270,128 cu.ft.)

Ts

= Standard temperature (68'F)

Ps

= Standard pressure (14.6959 psia)

-~

t

= Tes t duration, hours (4 hrs.)

F

= Makeup air (to maintain test pressure), standard cubic feet = F2-F1 F,F2 = Makeup air flow meter reading at start and end of test 1

respectively, SCF (convert from actual cubic feet to standard cubic feet).

(1)

Calculate drywell average temperature at start and end of test, where VF = Volume Friction.

Ti = 76.102*F = 535. 772 *R T2 = 76.271*F = 535.941*R (2) Drywell pressure at start and end of test:

P1 = 17.793 psia P2 = 17.785 psia O

DH-103 H-1

.. ~

i (3) Calculate drywell makeup air volume, convert from actual cubic feet to standard cubic feet:

2 F1 = 118070 cu.ft.

F2 = 86350 cu.ft i

50+14.6959 68+459.67 F = (F1-F) 14.6959 44+459.67 2

i

/'64.6959 x((503.67 /

527.67) 31720 g 14.6959

=

146295.19 cu.ft.

=

(4) Bypass Leakage Rate Calculation:

l t=C535.772 _ 535.941 60x4x14.6959/ '

60x4 17.793 17.785 270,128x68 }

146295.19 L

4 609.7 SCFM

=

i i

i. O j

1 i

1 1

i J

i l

l 1

i j

l' i

a i

DH-103 H-2

{

1 1

i l

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

APPENDIX I Local Leakage Test Summary Data Type B Test Results Penetration Description Leakage, SCCM 1

Equipment Hatch 212 2

Upper Personnel Lock 3

Lower Personnel Lock 4

Fuel Transfer Tube 0 i 11 201 Reactor Protection System 010 202 Low Voltage Power 010 203 Instrumentation 010 204 Instrumentation 010 205 Neutron Monitoring 010 206 Low Voltage Power 010 207 Control and Power 0+0 208 Control 010 209 Low Voltage Power 010 210 Radiation Monitoring 010 211 Control 0+0 212 Instrumentation 010 213 Rod Position Indication 010 214 T.I.P.

0+0

[

215 6.9 Kv-Reactor Recirculate Pump A 010 V'

216 Spare 010 217 LV Power and Control 010 218 Neutron Monitoring 010 219 Instrumentation 0+0 220 Instrumentation 0[0 221 Spare 010 222 Reactor Protection 0+0 223 LV Power and Control 0[0 224 Spare 010 225 LV Power 010 226 Control 010 227 Instrumentation 010 228 Instrumentation (Neutron Monitoring) 010 229 LV Power and Control 010 230 Reactor Protection 010 231 Instrumentation 010 232 Neutron Monitoring 010 233 Rod Position Indication 0+0 234 Spare 010 235 Neutron Monitoring 010 237 Instrumentation (SRV Inplant Test) 010 238 Reactor Protection System 010 239 Control 010 240 Instrumentation 010 1

241 LV Power and Control 0+0 242 LV Power and Control 010 DH-119 I-l

.~

m

..m.

..____3.....___.m.

?-

4 s

• i 4

APPENDIX I (Cont'd) s l

Local Leakage Test Summary Data l

Type B Test Results (Cont'd) i c

Penetration Description Leakage, SCCM 243 Spare 010 j

244 LV Power 0+0 l

245 Control Bop 010

):

246 Radiation Monitoring 0+0 l

247 6.9 KV Reactor Recirculate Pump B 030 249 Instrumentation 0+0

^

I Drywell Personnel Hatch i

Drywell Head a'

]

Drywell Equipment Hatch 30111 k

Drywell Head Manhole 4

)

l TOTAL = 32 + 16 3

x f

i 1

1 l

l'

=

l I

{

i i

l l

)

l l

l 1

i i

4 i

i, Dil-119 I-2 l

1 1

i...

.______..__...__,_..._..___,_.._._,__..__.__.-...__...,,,_.._-...__.,,.,__m.,,_

l APPENDIX I (Cont'd)

V)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)

Penetration Description Leakage, SCCM 5

Main Steam Line A 10,500 1 150 6

Main Steam Line B 552 + 19 7

Main Steam Line C 20 I 17 8

Main Steam Line D 3,390}148 17 Steam Supply to RCIC Turbine and RHR Hx 114.0 + 17 19 Main Steam Drain to Condenser 4312 33 CRD Pump Discharge 0 + 12 34 Containment Purge Supply 135{17 35 Containment Purge Exhaust 80 + 17 36 Plant Service Water Return 58 1 12 37 Plant Service Water Supply 38 Chilled Water Supply 1,250 1 120 39 Chilled Vater Return 20 + 12 40*

ILRT Containment Pressurization /

~

Depressurization 286 + 12 41 Plant Service Air 220 + 12 42 Instrument Air 800 I 12

( )')

43 RWCU to Main Condenser 10 I 17

(

44 Component Cooling Water Supply 40[17 45 Component Cooling Water Return 48 1 17 47 Reactor Recirculate Post Accident Sample 0111 49 RWCU Backwash Transfer Pump to Spent Resin Storage Tank 72 1 12 50 DW & Containment CRW Sump Pumps Discharge to Auxiliary Building Collector Tank 1,385 1 104 51 DW & Containment DRW Sump Pumps Discharge to Auxiliary Building Collector Tank 1,395 1 100 54 To Upper Containment Pool and f rom Refueling Water Storage Tank 5 1 12 56 Condensate Makeup to Upper Containment Pool 230 1 11 57 Discharge from Fuel Pool Cooling and C.U.

System to Upper Containment Pool 172 1 12 58 Inlet Upper Containment Pool skimmer Tanks to Fuel Pool Cooling and C.U. System 142 1 12 60 Auxiliary Building Floor and Equipment Drain Return 23 1 17 65 Containment Normal Vent Supply and Combustible Gas 350 1 17 66 Containment Normal Vent and Combustible Gas Exchange 30 1 17

(

i V

• Leakage rate for penetration 40 and 82 is included in this total DH-119 I-3

APPENDIX I (Cont'd)

Local Leakage Test Summary Data Type C Test Results (Pneumatic)(Cont'o)

Penetration Description Leakage, SCCM 70 Automatic Depressurization System (Instrument Air) 20 + 17 75 RCIC Pump Turbine Exhaust Vaccum Relief 12112 81 Reactor Recirculate Sample 0 1 12 82*

ILRT Drywell Pressurization /Depressurization 286 + 12 83 RWCV Line from Regenerative Ht. Exchange to Feedwater 100 + 12 84 Drywell and Containment Chemical Waste 60112 85 Suppression Pool Cleanup Return 180 1 21 86 Demineralization Water Supply to Containment 330 i 12 87 RWCV Pump Suction from Recirculate Loops 60 1 17 88 RWCV Pump Discharge to RWCV Ht. Exchange 40112 101C Drywell Pressure Instrumentation (Narrow Range) 0 1 12 101F Drywell Pressure Instrumentation (Wide Range) 6 + 12 102D Drywell Pressure (Wide Range) 15112 103D Containment Pressure (Wide Range) 10 + 12 104D Containment Pressure (Wide Range) 10112 105A Containment Drywell H2 Analyzing 110 1 12 106A Drywell H2 Analyzing Sample 14 1 12 106B Drywell H2 Analyzing Sample Return 10112 106E Containment H2 Analyzing Sample Return 10 1 12 107B Drywell H2 Analyzing Sample Return 158 1 12 107D Drywell H2 Analyzing Sample 50 i 12 107E Drywell H2 Analyzing Sample Return 15 1 12 108A Containment H2 Analyzing 95 i 12 109A Drywell - Fission Products Monitor Sample 0 i 12 109B Drywell - Fission Products Monitor Sample Return 100 1 12 109D Containment Pressure Instrument (Narrow Range) 10 1 12 110A ILRT Instrumentation Drywell Pressure 0 1 11 110C ILRT Instrumentation Verification Flow 0111 110F ILRT Instrumentation Containment Pressure 10 + 11 114 Suppression Pool Water Level Control 9112 116 Suppression Pool Water Level Control 45112 118 Suppression Pool Water Level Control 7112 120 Suppression Pool Water Level Control 5 1 12 TOTAL = 22822 + 300 0

• Leakage rate for penetration 40 and 82 is included in this total.

DH-119 I-4

APPENDIX I (Cont'd)

G Local Leakage Test Summary Data Type C Test Results (llydraulic)

Penetration Description Leakage, SCCM 9

Feedwater A 3.8 + 2.5 10 Feedwater B 16-2/3{2.5 11 RHR Pump A Suction 180 + 36 12 RilR Pump B Suction 503 + 92 13 RIIR Pump C Suction 917 + 74 14 RHR Shutdown Suction 010 18 RiiR to RPV Head Spray 3.8 + 5 20 RiiR A to LPCI 0+0 21 RHR B to LPCI 5.60 1 3.5 22 RHR C to LPCI 519 + 28 23 RHR A Pump Test Line to Suppression Pool 180 1 35 24 RilR C Pump Test Line to Suppression Pool 917 1 74 25 HPCS Pump Suction 6.23 + 4.3 26 HPCS Pump Discharge to RPV 25[20 27 HPCS Test Line to Suppression Pool 6.3 1 2.5 28 RCIC Pump Suction 0+0 29 RCIC Turbine Exhaust 010 30 LPCS Pump Suction 010 31 LPCS Pump Discharge to RPV 471 + 53 32 LPCS Test Line to Suppression Pool 0 ~ 0 46 RCIC Pump Discharge Minimum Flow Line 0[0 48 RilR Ilx B Relief Valve Vent Ileader to 8.5 + 5 Suppression Pool 67 RHR Pump B Test Line to Suppression Pool 503 1 54 69 Refueling Water Transfer Pump Suction From Suppression Pool 5017 71A LPCS Relief Valve Discharge to Suppression Pool 0+0 71B RilR "C" Relief Valve Discharge to Suppression Pool 917 + 74 73 RHR Shutdown Relief Valve Discharge to l

Suppression Pool (H.P.)

82.6 + 24 76B RHR A Shutdown Suction Relief Valve Discharge to Suppression Pool (ll.P.)

12.75 1 5 77 RHR llT. Exchanger A Reif.ef Valve Discharge j

to Suppression Pool 180 1 35 89 Standby Service Water Supply A 22 + 7 90 Standby Service Water Return A 0+0 91 Standby Service Water Supply B 010 92 Standby Service Water Return B 5+6 113 Suppression Pool Water Level Control 5.3 + 5 l

115 Suppression Pool Water Level Control 010 l

117 Suppression Pool Water Level Control 5 i 12 119 Suppression Pool Water Level Control 17 + 12 l pb TOTAL = 5563 + 192 I-5 Dil-119