ML20154L010

Reactor Containment Bldg Integrated Leak Rate Test, Final Rept

ML20154L010
Person / Time
Site:	Grand Gulf
Issue date:	11/30/1985
From:	BECHTEL GROUP, INC.
To:
Shared Package
ML20154L003	List: AECM-86-0039, Forwards Reactor Containment Bldg Integrated Leak Rate Test Final Rept,Per 10CFR50,App J.Maint Schedule for Type a Tests Requested.Summary of Corrective Actions for Cause of Test Failure Also Encl.Fee Paid ML20154L010
References
SU-088A, SU-88A, TAC-60862, NUDOCS 8603110372
Download: ML20154L010 (67)

Text

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I ATTACllM124T 2 i

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Mississippi Power &

i Light Company I

l GRAND GULF i

NUCLEAR STAYlON l

UNIT 1 l

O Primary Reactor Containment i

Integrated Leakage Rate Test Final Report November 1985 P

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NISSISSIPPI POWER AND LICHT COWANY i

CRAND CULF NUCLEAR STATION i

UNIT 1 i

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REACTOR CONTA!!# TENT SUILDING IlffECRATED LEARACE RATE TEST f

i FINAL REP 0fff l

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Prepared by Bechtel Powr Corporation San Francisco, CA November 198S O

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TABLE OF C0fffEhTS 1

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Secttons No. of Pagea

1.0 INTRODUCTION

1-1 to 1-1 2.0 MSULTS

SUMMARY

2-1 to 2-1 3.0 CNRONOLOGY 3-1 to 3-2 4.0 MTN0DOLOGY 4-1 to 4-5 5.0 TEST DATA AND M SULTS ANALYSIS 5-1 to 5-2 5 6.0 MFEMMCES 6-1 to 6-1 Appendice s A.

Description of Bechtel ILRT Computer Program A-1 to A-11 5.

Instrument Error Analysis (ISC) 3-1 to 3-1 C.

Local Leakage Rate Test Data C-1 t o C-6 D.

Summary of Major Modifications and Component D-1 t o D-2 Replacement s E.

Summary Report of Type A, 3, and C Test s Which E-1 t o E-4 Failed to Meet 10CFR50, Appendix J, Acceptance Criteria i

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SU-048a

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1.0 INTRODUCTION

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The first periodic Integrated Leakage Rate Test (ILRT) on the Grand Culf Nuclear Station Unit I reactor containment building was performed on November 3-4, 1985. The test was conducted to demonstrate that leakage f rom the containment system at the design loss of coolant accident pressure does not exceed the maximum allowed by the Technical Specif1-cation (Ref. 6.1). The ILRT was conducted in accordarre with a mechanical surveillance procedure (Ref. 6.2) which conformed to the general testing requirements established in Appendix J to 10CFR50 (Ref. 6.3), ANSI N45.4-1972 (Ref. 6.6), ANSI /ANS 56.8-1981 (Ref. 6.4) and Bechtel Topical Report BN-TOP-1 (Ref. 6.5).

The balance of this report presents test results, describes test eve nt s and methodology and lists the data necessary to support the stated re sult s.

The ensuing material is organized into the following sections.

o Section 2, Results Summary, lists the leakage rates determined during the test and the acceptance criteria.

o Section 3 Chronology, describes the activities performed in support of the test.

o Section 4, Nethodology, describes test methods and inst rumentation.

o Section 5, Test Data and Results Analysis, discusses the data acquired to establish the results and presents an analysis of the results.

1 i,/

o Section 6. References, lists the documents cited in the body of the s

repo rt.

o The Appendices contain a description of the ILRT computer program and tabular listings of all supporting data.

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2.0 RESULTS

SUMMARY

,9k,)

Containment pressurization was completed at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on November 3, 1985. Temperature stabilization criteria were met by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />.

However, initially calculated leakage was outside the acceptance limit a nd the start of the formal test was delayed until the leakage source (main steam lines C and D isolation valves and spare standby liquid control isolation valves) had been found and isolated. The formal test commenced at 0545 hotra on November 4 and was completed at 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />. Results of the 8.5-hour test, which confirmed an acceptable leakage rate, are tabulated below.

Calculation Mass Point Total Time

• Method Ca lcula t ed 95% UCL Ca lc ula t ed 95% UCL Calculated 0.137 wt.%/ day 0.141 wt.%/ day 0.129 wt.%/ day 0.183 vt.%/ day Rate Additions (per Section 5) 0.004 wt.%/ day 0.004 vt.%/ day 0.004 wt.%/ day 0.004 wt.%/ day Net Rate 0.3 41 wt.%/ day 0.145 wt.%/ day 0.133 wt. % / day 0.18 7 wt. Z /d ay Accep tanc e Limit 0.328 wt.%/ day 0.328 wt.%/ day 0.328 wt.2/ day 0.328 wt.2/ day i

The supplemental test calibrated leakage was imposed immediately following the 1415 hour0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> data point. The supplemental test commenced at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />, following the required one hour stabilization period, and was completed at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />. Results of the 4.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> supplemental test, which confirmed the correctness of the leakage rate calculational method, are tabulated below.

Calculation Method Mass Point Total Time Upper Acceptance Limit 0.684 wt.%/ day 0.675 wt.!/ day l

Calculated Rate 0.543 wt.%/ day 0.555 wt.%/ day Lower Acceptance Limit 0.465 wt.%/ day 0.457 wt.%/ day

• Additional Total Time results based on trend values and the corresponding acceptance criteria, which were satisfied, are presented in Section 5.

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3.0 CHRONOLOGY OO Test prerequisites specified in Ref. 6.2, including the containment exterior and interior inspections mandated in Ref. 6.3, were completed by November 3, 1985. No evidence of structural deterioration was found during the containment inspection. Completion of prerequisites, containment systems status and inspection results are documented in the Official' Test Copy of Ref. 6.2, which is maintained as a part of permanent plant records. Containment pressurization commenced at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br /> on November 3, and was stopped at 1425 hours0.0165 days <br />0.396 hours <br />0.00236 weeks <br />5.422125e-4 months <br /> on the same day when containment pressure had reached 12.25 psig, which is 0.75 psig above the minimum test pressure of 11.5 psig. Pressurizing equipment consisted of air compressors with an aggregate capacity of approximately 6,000 SCFM, aftercooler/ moisture separators and a refrigerated air dryer. This equipment maintained an almost constant pressurization rate of about 1.5 psi /hr. Containment fan coolers were run during pressurization to minimize temperature stratificaion. Cooling water was run through the fan cooler coils to control containment air temperature.

Fan coolers and cooling water were shut off immediately following the completion of pressurization. Containment lights had been previously turned off.

Temperature stabilization criteria specified in Ref. 6.2 were met by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, four hours following the completion of pressurization. Calcula-tions performed using data recorded during the stabilization period indicated a stable leakage rate of about 0.7 wt.%/ day, which was more than

+

twice the 0.328 wt.%/ day allowable. Data recorded over the next few hours (N /"')

confirmed this initially calculated rate. Leak search teams examined 211 containment penetrations and identified significant leakage at the open s

vents outboard of main steam isolation valves QlB21F028C and QlB21F028D.

A possibly significant leak was identified at the open vent outboard of isolation valve Q1C41F150 in the spare standby liquid control line passing through penetration 61.

These leakages were reduced to negl!gible values by shutting the vents.*

This corrective action was completed at 0104 hours0.0012 days <br />0.0289 hours <br />1.719577e-4 weeks <br />3.9572e-5 months <br /> on November 4.

During the stabilization and subsequent leak search periods, reactor water level had dropped to 65 inches and required makeup. Level was restored'to 84 inches by an injection starting at 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> and ending at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />.

Calculations performed using data recorded following the reactor makeup indicated that leakage had been reduced to an acceptable level.

When this reduction had been confirmed using data recorded over. a three-hour period, a formal test start was declared at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br />.

Calculations usind data recorded during the first 8. hours of test (the minimum acceptable test duration) showed a stable and acceptable leakage rate.

It was intended to end the primary test and initiate the imposed leak for the supplemental test at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />. However, due to a delay in receiving the release authorization from Health Physics, the imposed leak Additions to the calculated leakage rate are required by the resulting

- (--)

non-standard valve lineups. These are discussed in Section 5.

SU-088a 3-1

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was not initiated until af ter 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />.

The primary test was extended t}

for the additional half hour so that its end would coincide with the start

(

j of the supplemental test. The one-hour stabilization period for the supplemental test ended at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> and the supplemental test itself was concluded at 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br /> (giving it a duration of 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> which is half the duration of the primary test).

The pressure at the end of the supplemental test was 12.1 psig.. Duri ng the entire test period, pressure was between 12.25 psig and 12.1 psig, well within the 11.5 to 13.5 psig acceptable range.

The containment was depressurized following the supplemental test and plant systems aligned for the ILRT were restored, as required, to conditions required for the support of subsequent outage activities.

Depressurization and restoration are documented in the Official Test Copy of the procedure (Ref. 6.2).

Various items of data needed to support or supplement the ILRT were recorded at regular intervsl<s during the test.

These data include outside atmospheric conditions, reactor level, suppression pool level, upper pool level and the quantity of water removed from the drywell sumps (the last two items were recorded only before and af ter the test). All recorded data are included in the Official Test Copy of the procedure (Ref. 6.2).

Data required to support reported ILRT results are included in Section 5.

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4.0 NETHODOLOGY

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The integrated leakage rate test is performed to verify that leakage f rom the containment system (steel liner, mechanical / electrical penetrations and accessways) at calculated accident pressure does not exceed the specified limit. The containment is prepared for the test by closing all accessways and aligning valves in specified post-accident positions.* All items which could be damaged by test pressure or which contain gasses at pressures higher than the test pressure are either removed from the containment or vented. The test objective is accomplished by pressurizing the containment with clean, relatively dry air, closing the pressurizing line valves, measuring containment atmosphere parameters and using those measurements to determine air mass loss over a specified time period.

Af ter the leakage rate has been determined, the calculational method is verified by a supplemental test during which an additional known leakage is imposed on the containment.

4.1 Leakage Rate Calculational Methods Cont ainment leakage rate is calculated using the mass point and total time methods described in References 6.4 and 6.5.

Both methods use containment pressures and temperatures recorded at 15-minute intervals as input data.

The mass of dry air ** in the containment is calculated for each 15 minutes data set using the ideal gas law.

Dry air partial pressure is computed by subtracting the partial pressure of the water vapor (as determined f rom measured dew point temperature) from measured total pressure. The mass point leakage rate is defined as the normalized (divided by the calculated s

y,)

start of test air mass) slope of a line fitted to the mass / time data by the method of least squares. The total time leakage rate is defined as the end of test ordinate (normalized) of a line fitted to a series of.

measured leakage rate / time data points. A measured leakage rate is defined as the calculated change in air mass since the start of the test divided by the time since the start of the test. Both the mass point and total time methods utilize the variance of data points about the fitted line to establish the 95% upper confidence limit on leakage rate.

References 6.4 and 6.5 describe the calculations in detail.

The leakage rate is calculated for a test period of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> duration (which provides a minimum of 33 data points). The first data

• Certain valves may not be in specified positions during the ILRT.

Measured leakage through these valves is added to the calculated leakage rate to account for the non-standard lineup as described in Section 5.

• • Evaporation and condensation of water change the partial pressure of the vapor phase. This partial pressure is eliminated f rom the leakage rate calculation so that internal phase changes are not erroneously accounted for as actual out (or in) leakage.

O SU-088a 4-1

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point used in the calculation is recorded at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> af ter the completion of containment pressurization. This allows the containment O~.

staosphere to attain a reasonable degree of temperature equilibrum l

following the transient conditions created by pressurization.' Ref e re nc es 6.4 and 6.5 impose conditions on temperature changes which must be met 7

prior to using recorded data in leakage rate calculations. The se cond i-i tions are normally met within the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (minimum) stabilization period.

i Following the determination of. leakage rate (8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> miniaua test) a supplemental test is conducted to verify the correctness of the calcu-lations.* The supplemental test consists of venting a small flow

.(approximately equal to the allowable leakage rate) f rom the containment through a flow measuring device and calculating the increased leakage rate. The calculated increased rate must equal the previously calculated rate plus the imposed flow plus or minus a tolerance of 25 percent of the r

allowable leakage rate, as required by References 6.3, 6.4, and 6.5.

In addition, Reference 6.1 requires that the calculated increased rate minus t

the imposed flow shall be within plus or minus a tolerance of 25 percent of the previously calculated rate. The supplemental test has a duration of at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />. All calculations are performed by the computer program described in Appendix A.

4.2 Instrumentation and Test Data Acquisition The calculations performed for the ILRT (primary and supplemental tests) require the measurement of containment absolute pressure, drybulb temperature, dewpoint temperature (or relative humidity), time and flow rate (supplemental test). Pressure is measured at a single point using one primary and one backup gauge. Temperatures, both drybulb and dewpont,

are measured at numerous points to permit determination of reasonably accurate volume weighted mean value s.

Volume weights are calculated for each temperature sensor based on the geometry of the surrounding region, i

the presence of heat / moisture sources or sinks, and the tendency of temperature to stratify in the vertical direction in open areas. Time and flow are single point measurements.

i Table 4.1 lists the locations of, and volume weights assigned to,** the 22 l

drybulb and 6 dewpoint temperature sensors placed in the Grand Gulf cont ainment. As noted on the table, about 1/3 of the temperature sensors are located in the drywell, which is an essentially closed compartment with its own temperature arvi vapor pressure regimes.

Since the drywell is vented to the rest of the containment through the blocked open personnel air lock, total pressure is equalized and separate compartment pressure measurements are not necessary.

The drybulb and dewpoint temperature sensors are connected to a data logger which provides appropriate conditioning for the sensor input

[

The supplemental test also verif f es the absence of a significant systematic error in the pressure measurement sy st em.

• • Calculations of volume weights are retained in permanent plant rec o rd s.

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signals. The logger, which has a built-in clock for time measurement, 7s

('*')

automatically generates date/ time and temperature records at 15-minute intervals. Logger output consists of a printed paper tape and serial data transmission to a desktop computer which performs the leakage rate computations. Pressure.and flow data are manually recorded and manually entered into the computer via keyboard.

Table 4.2 provides descriptions and performance specifications for the sensors and logger used to acquire data for the Grand Gulf test.

Reference 6.4 specifies an upper limit of 0.25 La (th'e allowable leakage rate = 0.437 wt.%/ day) on the mean square random error of the instrumentation system. The mean square error is based on the sensitivities sad repeatabilities listed in Table 4.2.

The complete calculation of the Instrument Selection Guide (ISG), which is given in Appendix B, shows this error to be 0.044 L for an 8-hour test.

a v

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TABLE 4.1 INSTRUMEKI LOCATIONS Ins'trument Type Designation Elevation Radius Azimuth (1)C/D Fraction Drybulb Temperature TE-1 290' 18' 0*

C 0.023 i

Drybulb Temperature TE-2 280' 18' 180*

C 0.038 Drybulb Temperature TE-3 260' 40' 270*

C 0.062 Drybulb Temperature TE-4 270' 12' 90*

C 0.052

-Drybulb Temperature TE-5 228' 30' 45' C

0.087 Drybulb Temperature TE-6 250' 30' 135*

C 0.067 Drybulb Temperature TE-7 215' 30' 225' C

0.090 Drybulb Temperature TE-8 240' 30' 315' C

0.077 Drybulb Temperature TE-9 184' 52' 222' C

0.058 Drybulb Temperature TE-10 174' 52' 305*

C 0.057 Drybulb Temperature TE-11 165' 27' 150' D

0.022 Drybulb Temperature TE-12 150' 52' 150*

C 0.057 Drybulb Temperature TE-13 150' 52' 90*

C 0.057 Drybulb Temperature TE-14 122' 52' 0*

C 0.057 Drybulb Temperature TE-15 122' 52' 180*

C 0.058 Drybulb Temperature TE-16 148'-

27' 230*

D 0.027 Drybulb Temperature TE-17 114' 27' 90*

D 0.022 Drybulb Temperature TE-18 130' 27' 180*

D 0.023 Drybulb Temperature TE-19 165' 27' 340' D

0.022 Drybulb Temperature TE-20 149' 27' 32' D

0.022 Drybulb Temperature TE-21 114' 27' 270*

D 0.022

'Drybulb Temperature TE-22 108' 0'

0*

D 0.005 Dewpoint Temperature ME-1 264' 54' 90*

C 0.175 Dewpoint Temperature ME-2 232' 58' 225' C

0.321 Dewpoint Temperature ME-3 174' 52' 305*

C 0.172 Dewpoint Temperature ME-4 122' 48' 0*

C 0.172 Dewpoint Temperature ME-5 148' 32' 32' D

0.080 Dewpoint Temperature ME-6 114' 26' 270*

D 0.080 (1) C - Containment /D - Drywell i

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TABLE 4.2 s

ILRT INSTRUMENTATION Number Used Function / Description (1) Specifications Pressure 2

Quartz Bourdon Tube Calibrated Range: 0-30 PSIA Precision Pressure Calibration Accuracy: 0.015% of Range Gage with Optical Sensitivity: 0.001 PSIA Sensor Tracking Repeatability: 0.001 PSIA Resolution: 0.0003 PSIA Drybulb Temperature 22 100 Ohm Platinum Calibrated Range:

60-120*F Resistance Temperature Calibration Accuracy:

0.l'F Detector (2) System Accuracy:

0.6*F Sensitivity:

0.l*F 6

Dewpoint Temperature Calibrated Range:

40-100*F Chilled Mirror Hygro-Calibration Accuracy:

0.l*F meter (2) System Accuracy:

1.05'F Sensitivity:

0.l*F 1

Flow Calibrated Range:

2-20 SCFM

('s Float in Sight Glass Calibration Accuracy:

0.2 SCFM Flowmeter Sensitivity:

0.1 SCFM Repeatability:

0.1 SCFM Resolution: Analog 1

Time Resolution: 1 sec.

Digital Clock with Accuracy: 1 sec/24 hours Julian Date, Hour, Minute and Second-Display 1

Data Logger Repeatability:

0.Ol*F Relay Type Multiplexer for Drybulb and Dewpoint with A/D Converter and Temperatures Printed Paper Tape /

RS232 Output (1) Calibration data are on file in permanent plant records. Calibration due date is May 1,1986 for all instruments.

(2) System accuracy is established by comparing the data logger indication for an installed test sensor to the indication of a standard sensor placed

'alongside the test sensor.

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5.0 TEST DATA AND RESULTS ANALYSIS gS

)

The data required to calculate containment leakage rate include: c ont a in-l ts ment atmosphere parameters for determination of air mass; pool and sump j

levels to correct computed air mass for changes in containment free j

volume; and leakages through isolation valves in penetrations which were not in the specified drained and vented postLOCA configuration during the test. The leakages through the isolation valves are,added to the calcu-lated leakage rate to determine the rate which would have been acasured had the associated penetrations been drained and vented., Subsections 5.1, 5.2 and 5.3 cover, respectively, calculated leakage (including the supple-mental test), f ree volume corrections and local leakage rate (isolation valve leakage) additions.

Subsection 5.4 summarizes composite test re sult s.

Subsection 5.5 lists plant specific data which are of interest i

and tabulates the types of data which are retained in permanent rec ord s.

5.1 Calculated Leakage Rate Containment atmosphere parameters (pressure, drybulb temperature and dewpoint temperature) were recorded at' 15 minute intervals f rom the completion of containment pressurization through the completion of the supplemental test.*

Air masses (dry air component) calculated using these data are plotted with time in Figure 5.1.

The transient conditions generated during pressurization affect the first two hours of the plot (initially rising followed by unchanging calculated air mass). After about 1630 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20215e-4 months <br /> (November 3), the distribution of temperatures in the containsent had reached a condition of dynamic equilibrium and subsequent O'

calculated masses followed the expected straight line trend. The slope of the initial line was C.69wt.2/ day which is in excess of the allowable leakage rate of 0.437vt.%/ day. As discussed in Section 3, this large leakage rate was found to result f rom excessive flows through the isola-tion valves in main steam lines C and D and the spare standby liquid control line. These leaks were isolated at about 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> on November 4.

There appears to be a change in the slope of the mass / time plot starting at this point but the start of a new trend is obscured by the calculated mass increase resulting f rom an injection of makeup water to the reactor vessel between.0212 and 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />. The makeup water injection appears as a mass increase since it reduces containment f ree volume.**

Following the injection, the air mass plot follows a straight line t re nd for 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br />. The slope of the line is equivalent to 0.14wt.%/ day which is well below the acceptance limit of 0.329wt.%/ day. The acceptance

• Additional data were recorded during pressurization but are not used in leakage rate determination.

These data are retained in permanent plant re c ord s.

• • Mass is eniculated using the equation M = PV/RT where M is air mass, P is absolute pressure, V is f ree volume, R is the gas constant for air, and T is absolute temperature.

O SU-OS8a 5-1

limit, which applies to the composite leakage rate as discussed in x

^ 'j subsection 5.4, is equal to 75% of the allowable leakage rate of O 437wt%/ day.

The final segment of the mass / time plot covers the supplemental test period. An additional leakage of 0.44wt.%/ day was imposed just after 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> and terminated just after 1945 hours0.0225 days <br />0.54 hours <br />0.00322 weeks <br />7.400725e-4 months <br />. The slope of the mass / time plot over this 5.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period is 0.54wt.%/ day which is close to the expected value of 0.58wt.%/ day.

The official test start was declared at 0545 hours0.00631 days <br />0.151 hours <br />9.011243e-4 weeks <br />2.073725e-4 months <br /> on November 4 following the completion of reactor makeup water injection and subsequent evaluation of the effectiveness of main steam penetration isolation. The test continued until 1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br /> (8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> duration) when Health Physics authorized the release of supplemental test flow into the auxiliary building. The following paragraphs discuss temperature stabilization, mass point calculation results, total time calculation results and supplemental test results.

5.1.1 Temperature Stabilization Temperature variations which are excessively unsteady and nonuniform will distort mass calculations since the limited number of temperature sensors will not provide true mean temperature data under these conditions. Three temperature stabilization criteria must be met prior to starting a test. e These are:

_j 1.

(Kefs. 5.4 and 5.5) A minimum of four hours must have elapsed since the completion of pressurization.

2a.

(Ref. 5.5) The rate of change of mean temperature is less than 1*F/ hour averaged over the last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> OR 2b.

The rate of change of mean temperature change is less than 0.5'F/ hour 2 averaged over the last two hours.

3.

(Ref. 5.4) The rate of change of mean temperature over the last hour does not deviate by more than 0.5'F/ hour from the rate of change over the last four hours.

These criteria were all met by 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, four hours following the completion of pressurization, as shown in Table 5.1.

Figure 5.2 is a plot of mean temperature over the entire period from completion of pressuriza-tion to completion of the supplemental test.

Figure 5.3 plots mean vapor pressure (derived from dewpoint temperature) over the same time period.

Both mean temperature and mean vapor pressure have smooth, asymptotic trends. Absolute pressure measured over the same time period is shown in Figure 5.4 for information. The effect of increasing reactor level is illustrated on the plot.

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5.1.2 Mass Point Calculation Results Mass point. calculation summary data and results are listed in Table 5.2 and illustrated in Figure 5.5.

The end of test 95% upper confidence limit (UCL) on the calculated leakage rate is 0.141wt.%/ day which is well below the acceptance limit of 0.328vt %/ day (shown as 0.75L, where L, is the 0.437 wt.%/ day allowable leakage rate, on Figure 5.5).

As is illustrated in Figure 5.5, the UCL converges to the calculated leakage rate as the calculation time interval increases.* Figure 5.6 expands the mass / time plot of Figure 5.1 over the 8.5-heur test period.

5.1.3 Total Time Calculation Results Total time calculation summary data and results are listed in Tables 5.3 and 5.4 and illustrated in Figure 5.7..The end of test UCL on the calculated leakage rate (Table 5.3) is 0.183wt.%/ day which is well below the acceptance limit of 0.328 vt.%/ day. As illustrated in the Figure, the UCL is' tending to converge on the calculated rate. The calculated mass point and total time end of test rates are close to' equal (0.137 and 0.129, respectively). However, the total time er.d of test UCL is well above the mass point end of test UCL. This results from the conservatism inherent in the total time UCL calculation.

Table 5.4 lists the total time trends for leakage rates calculated in quarter-hour increments from 2 to 8.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of data. This trend report shows that the calculated rate is tending to stabilize at a value below 0.328vt.%/ day.

Table 5.3 lists the mean of the measured leakage rates determined for the last 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of test data. The mean is less than 0.328vt.1/ day.

5.1.4' Supplemental Test The supplemental test was conducted for 4.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> with a 9.24 SCFM flow vented from the containment through a calibrated flow meter. This flow is equivalent to L. - 0.437wt.%/ day at test pressure (no temperature correc-tion is made in converting SCFM to wt.1/ day since test and standard temperatures are not sufficiently different to justify the conversion).

The containment was allowed to stabilize for one hour after imposing the flow. Supplemental test calculation summary data and results, using the acceptance criteria of references 6.3, 6.4, and 6.5, are listed in Table 5.5 and illustrated (Mass Point Analysis) in Figure 5.8.

Calculated leakage rates and acceptance limits are:

The rates and UCLs plotted are for calculations starting with 0545 data and ending with data taken at 0745, 0800, 0815,......, 1400 and 1415.

SU-088a 5-3

CALCULATION METHOD

,ms i}

Mass Point Total Time Upper Limit 0.684wt.%/ day 0.675wt.%/ day Calculated Leakage Rate 0.543 0.555 Lower Limit 0.465 0.457 Calculated leakage rates are well within the limits for both the mass point and total time cases. Determination of the upper and lower limits is discussed in Section 4.

The acceptance criteria of Reference 6.1 are significantly more conservative than those of References 6.3, 6.4, and 6.5 for the supplemental test. The calculated leakage rates and acceptance limits are:

CALCULATION METHOD Mass Point Total Time Calculated leakage rate during ILRT (L )

.137

.129 y

Imposed leakage rate (L )

.437 437 o

Calculated leakage rate during Supplemental Test (L )

.543

.555 c

_ (s Upper Limit (1.25 L )

.171

.161 y

L ' = L -L

.106

.118 y

e o Lower Limit (.75 L )

.103

.097 y

Although the containment leakage rate (L ') is close to the lower limit.by y

Mass Point calculations, it is still acceptable. The containment leakage rate is well within the limits by Total Time calculation.

5.2 Free Volume Corrections The initial free volume of the containment (including drywell) with the upper and lower pools at specified levels was calculated at 1,670,360 cubic feet.

Pre-and post-test measurements showed that upper pool and suppression pool levels did not change.

The drywell equipment drain tank / sump and floor drain sump were pumped down between 2200 and 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> on. November 2 and again between 0800 and 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br /> on November 5.

The following quantities of water were removed during the post-test pump down.

i

' O V

SU-088a 5-4 l

l t

L

d

/N Equipment Drain Tank / Sump 520 gal.

Floor Drain Sump 4,779 gal.

TOTAL 5,299 gal.

Reactor vessel levels recorded over the same time period are listed below:

Date/ Time Le vel Comme nt 2 Nov/2330 81 in.

i 4 Nov/0211 65 in.

4 Nov/0226 84 in.

Raised by injection 5 Nov/0730 75 in.

Gross Drop 6 in.

Drop Restored By Injection 19 i n_.

• Net Drop 25 in.

4 Volume Lost at 200 gal./in. = 5,000 gal.

The net gain in water inventory over the 56 hour6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> (3 Nov/0000 to 5 Nov/0800) period is:

1 O

Drywell Tank / Sump Gain 5,299 gal, e

Reactor Loss

-5,000 gal.

NET GAIN 299 gal.

The net gain of 299 gal. equates to 40 cubic feet. For a uniform rate of gain, 40 cubic feet in 56 hours6.481481e-4 days <br />0.0156 hours <br />9.259259e-5 weeks <br />2.1308e-5 months <br /> is equivalent to 17.1 cubic feet in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. In the absence of containment leakage other than water inleakage, the net water gain would calculate to a negative leakage rate of 17.1/1,670,360 or 0.001 wt.%/ day. Therefore, calculated leakage rates and UCL's are increased by 0.001 wt.%/ day to account for gain in water inve nt ory.

I complete data on tank, sump, reactor and pool levels are retained in permanent plant records.

• It is assumed that level would have dropped from 81 to 56 inches had there been no injection.

SU-088a 5-5

__ _ ___.___ _ _._,______- ___ _ __.. ~ _ _ -_

4 J

5.3 Local Leakate Rate Additions A number of mechanical systems that penetrate contairaient and systems that 7

are assumed (for design purposes) to be drained and vented postLOCA were maintained in operation during the test. Several penetrations were used for pressurisation, pressure sensing and other purposes essential to test conduct, and were not in the specified postLOCA configurations. The penetrations serving main steam lines C and D and penetration 61, which serves as a spare standby liquid control line, were observed to be leaking potentially significant quantities of air during the initial phase of the j

test (see Section 3). These were isolated by closing vents.

i To account for the leakage which would have passed through these i

penetrations in the normal postLOCA configuration, the ministen pathway local leakage for each is summed and the total is added to the calculated leakage rate UCLs. The leakages to be summed are determined as f ollows:

I o For all penetrations, the lesser of the leakages measured for a series i

{

path (in the simplest case, the lesser of the leakages measured through the inboard and outboard isolation valves).

o For penetrations serving systems in service (including test penetrations), the as-lef t a.inimum pathway leakage determined durim a local leakage rate test conducted bef ore or af ter the integrated leakage rate test.

l t

o For test penetrations isolated with blind flanges having double 0-ring d

cr Flexitallic gasket seals, the local leakages measured following post-test replacement of the flanges.

l o For penetrations isolated to reduce leakage rate, the miniaun pathway local leakage measured following post-test normal closure

• or repair of i

the isolation valves.

~

Table 5.6 idsntifies all penetrations for which the penalty additions will l

be taken and lists the minimum pathway leakage rate. The total penalty leakage is 1650 SCCM which equates to a leakage rate of 0.003 wt.%/ day at l

i l

test pressure.

J Appendix C contains a complete tabular listing of local leakage rate test results for all contairunent penetrations.

l t

i l

t During the pre-test val' e lineup, the main steaa isolation valves were v

l slow-closed using the test switches, rather than fast-closed. The SLC i

isolation valve, Q1C41F150, was not fully tightened.

(

SU-088s 5-6 f

f l

5.4 Composite Test Results The composite. leakage rate is the sum of the calculated rate, the free voluse correction and the local leakage rate penalty. Composite rates are sunenarised below:

Mass Point Total Time Ca lculat ed_

95% UCL Ca lc ulat ed 1 UCL Calculated Rate 0.137 wt.%/ day 0.141 wt.%/ day 0.129 wt.%/ day 0.183 wt.%/ day Free Volume Correc tion 0.001 wt.%/ day 0.001 wt.%/ day 0.001 wt.%/ day 0.001 wt.%/ day Local 14akage Penalty 0.003 wt.%/ day 0.003 wt.%/ day 0.003 wt.!/ day 0.003 wt.%/ day Total (Composite) 0.141 wt.%/ day 0.145 vt.%/ day 0.133 wt.!/ day 0.187 wt.%/ day Acceptance Limit 0.328 wt Z/ day 0.328 wt.%/ day 0.328 wt.1/ day 0.328 wt.!/ day 5.5 Plant Specific and Retained Data Table 5.7 lists various items of plant specific data and the major test paramet ers. Table 5.8 is a categorized listing of test backup data which is retained in permanent plant record s.

O SU-088a 5-7

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

TABLE 5.1 GRAND GULF NUCLEAR STATION 1965 ILRT

{^N

(_)

TEMPERATURE STABILIZATION FROM A STARTING TIME AND DATE OF:

1430 1103 1985 TIME TEMD ANSI BN-TOP-1 (HOUR 58

('R)

AVE AT AVE /ST DIFF AVE /ST (4 HRS)

(1HR)

(2 HRS) l

.00 541.65

.25 541.17

.50 540.93

.75 540.77 1.00 540.68 1.25 540.62 1.50 540.58 1.75 540.55 2.00 540.52

.562+

2.25 540.50

.335+

i 2.50 540.49

.221*

2.75 540.47

.148 3.00 540.47

.106+

3.25 540.46

.079 3.50 540.45

.063*

3.75 540.44

.055 l

)

4.00 540.42

.306

.042

.26*

.025+

l

• INDICCTES TEMPERATURE STABILI2ATICN HAS BEEN SATISFIED l

i l

5.8 t

TABLE 5.2

[

')

GRAND GULF NUCLEAR STATION 1985 ILRT

\\/

LEAKAGE HATE (WEIGHT PEFCENT/DAV)

MASS POINT ANALYSIS l

TIME AND DATE AT START OF TEST:

545 1104 1985 TEST DUEATION:

8.50 HOURS TIME TEMP PRESSukE CTMT. AIR MASS LOSS AVERAGE MASb (R)

(PSIA)

MASS (LBM)

(LBM)

LOSS (LBM/nR) l 545 540.230 26.3894 220236.

600 540.230 26.3886 220230.

6. 3 25.3 615 540.231 26.3880 220224.

5. 9 24.5 630 540.221 26.3876 220225.

.8 15.2 645 540.218 26.3870 220221.

3. 7 15.2 700 540.215 26.3866 220219.

2. 2 13.9 715 540.210 26.3860 220217

2. 5 13.2 730 540.211 26.3855 220212.

4. 4 13.8 745 540.206 26.3851 220210.

1. 8 13.0 800 540.203 26.3842 220205.

5. 9 14.2 615 540.206 26.3840 220201.

3. 5 14.2 l

830 540.200 26.3831 220196.

4. 6 14.6 845 540.202 26.3627 220192.

4. 0 14.7 l

900 540.196 26.3821 220190.

2. 4 14.3 l

315 540.198 26.3817 220185.

4. 9 14.7

~

930 540.191 26.3814 220186.

.9 13.5 (g) 945 540.192 26.3804 220177.

9.1 14.9 l

1000 540.189 26.3801 220176.

1. 0 14.3 1015 540.189 26.3797 220173.

3.1 14.2 l

1030 540.185 26.3788 220166.

6. 4 14.8 1945 540.173 26.3786 220170.

-3. 8 13.3 1100 540.169 26.3781 220167.

3. 4 13.3 1115 540.167 26.3775 220163.

4.1 13.4 1130 540.166 26.3769 220158.

4. 3 13.6 1145 540.167 26.3765 220155.

3. 3 13.6 1200 540.169 26.3763 220152.

3. 3 13.6 1215 540.167 26.3754 220145.

6. 3 14.0 1230 540.159 26.3751 220146.

.8 13.4 1245 540.153 26.3750 220148.

-1.4 12.7 1300 540.161 26.3744 220140.

8.1 13.4 1315 540.147 26.3739 220142.

-2.0 12.6 1330 540.147 26.3732 220135.

6. 5 13.1 l

1345 540.144 26.3729 220134

1. 4 12.8 1400 540.135 26.3727 220136.

-2.0 12.2 l

1415 540.138 26.3721 220129.

6. 3 12.6 FREE AIR VOLUME USED (CU. FT.)

=1670360.

REGRESSION LINE INTEh2EPT (LBM)

= 220232.

-12.6 SLOPE (LBM/HR)

=

437 MAXIMUM ALLOWABLE LEAMAGE RATE

=

.328 75% OF MAXIMUM ALLOWABLE LEAHAGE RATE

=

(

THE UPPER 95% CONFIDENCE LIMIT

.141

=

(

THE CALCULATED LEAKAGE RATE

.137

=

5.9 t

TABLE 5.3 GRAND GULF NUCLEAR STATION 1985 ILRT 73 LEAKAGE RATE (WEIGHT PERCENT /DAV)

( )

TOTAL TIME ANALYSIS TIME AND DATE AT START OF TEST:

545 1104 1985 TEST DURATION:

8.50 HOURS TIME TEMP PRESSURE MEASURED (R)

(PSIA)

LEAKAGE RATE 545 540.230 26.3894 600 540.230 26.3886

.276 615 540.231 26.3880

.267 630 540.221 26.3876

.166 645 540.218 26.3870

.165 700 540.215 26.3866

.151 715 540.210 26.3860

.144 730 540.211 26.3855

.151 745 540.206 26.3851

.142 800 540.203 26.3842

.154 815 540.206 26.3840

.155 830 540.200 26.3831

.159 845 540.202 26.3827

.160 900 540.196 26.3821

.156 915 540.198 26.3817

.160 930 540.191 26.3814

.147 f-'

945 540.192 26.3804

.163

(,)/

1000 540.189 26.3801

.156 1015 540.169 26.3797

.154 1030 540.185 26.3788

.161 1945 540.173 26.3786

.144 1100 540.169 26.3781

.145 1115 540.167 26.3775

.146 1130 540.166 26.3769

.148 1145 540.167 26.3765

.148 1200 540.169 26.3763

.148 1215 540.167 26.3754

.153 1230 540.159 26.3751

.146 1245 540.153 26.3750

.138 1300 540.161 26.3744

.146 1315 540.147 26.3739

.138 1330 540.147 26.3732

.143 1345 540.144 26.3729

.140 1400 540.135 26.3727

.133 1415 540.138 26.3721

.137

.157 MEAN OF THE MEASURED LEAKAGE RATES

=

437 MAXIMUM ALLOWABLE LEAKAGE RATE

=

.338 75% OF MAXIMUM ALLOWABLE LEAKAGE RATE

=

.183 THE UPPER 95% CONFIDENCE LIMIT

=

.123 THE CALCULATED LEAKAGE RATE

=

(x 5.10

TABLE 5.4 GRAND GULF NUCLEAR STATION 1985 ILRT

(~N

(_)

TREND REPORT TIME AND DATE AT START OF TEST:

d45 110* 1965 NO.

END TOTAL TIME ANALYSIS MAb5 POINT ANALYSIS PTS TIME MEAS. CALCULATED UCL CALCULATED UCL 4

630

.166

.181

.546

.175

.331 5

645

.165

.154

.307

.154

.232 6

700

.151

.135

.248

.140

.189 7

715

.144

.123

.222

.131

.166 8

730

.151

.121

.220

.133

'.158 9

745

.142

.116

.210

.130

.149 10 800

.154

.119

.214

.125

.151 11 815

.155

.121

.216

.139

.253 12 830

.259

.125

.218

.144

.156 13 845

.160

.128

.220

.147

.158 14 900

.156

.130

.219

.149

.158 15 915

.160

.132

.219

.151

.159 16 930

.147

.131

.214

.149

.156 17 945

.163

.134

.216

.152

.159 18 1000

.156

.135

.214

.152

.159 19 1015

.154

.135

.213

.152

.158 20 1030

.161

.137

.213

.154

.159 21 1945

.144

.136

.209

.151

.157

[~

22 1100

.145

.135

.206

.149

.154

(

23 1115

.146

.134

.203

.147

.153 24 1130

.148

.134

.201

.147

.152 25 1145

.148

.134

.200

.146

.151 26 1200

.148

.134

.198

.146

.150 27 1215

.153

.134

.198

.146

.150 28 1230

.146

.134

.196

.146

.149 29 1245

.138

.133

.193

.144

.148 30 1300

.146

.133

.192

.143

.147 31 1315

.138

.132

.190

.142

.145 32 1330

.143

.131

.289

.141

.145 33 1345

.140

.131

.187

.140

.144 34 1400

.133

.129

.185

.138

.142 35 1415

.137

.129

.183

.137

.141 O

I 5.11

TABl.E 3.5 (SH. 1/2)

['N GRAND GULF NUCLEAR STATION 1985 ILRT

\\--

LEAKAGE RATE (WEIGHT PERCENT / DAY)

MASS POINT ANALYSIS TIME AND DATE AT START OF TEST: 1530 1104 1985 TEST DURATION:

4.25 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS AVERAGE PASS (R)

(PSIA)

MASS (LBM)

(LBM)

LOSS (LBM/HR) 1530 540.117 26.3631 220063.

1545 540.121 26.3623 220054

8. 3 33.3 1600 540.119 26.3599 220035.

19.1 54.8 1615 540.118 26.3584 220024 11.4 51.8 1630 540.107 26.3566 220013.

11.2 50.1 1645 540.109 26.3553 220001.

11.4 49.2 1700 540.107 26.3537 219989.

12.7 49.4 1715 540.097 26.3517 219976.

12.3 49.4 1730 540.096 26.3493 219961.

15.3 S0. 8 1745 540.096 26.3488 219952.

8. 9 49.1 1800 540.086 26.3466 219938.

14.7 50.1 1815 540.089 26.3451 219924 13.5 50.5 1830 540.088 26.3437

219913, 11.0 49.9 1845 540.078 26.3422 219904

8. 6 48.7 1900 540.081 26.3401 219886.

18.8 S0. 6 1915 540.076 26.3384 219874.

11.9 50.4

[

')

1930 540.068 26.3372 219867.

6.9 49.0

\\/

194S 540.073 26.3356 219852.

15.0 49.7 FREE AIR VOLUME USED (CU. FT.)

=1670360.

REGRESSION LINE INTERCEPT (LBM)

= 220063.

SLOPE (LBM/HR)

=

-49.8

.684 VERIFICATION TEST LEAKAGE RATE UPPER LIMIT

=

465 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT

=

.543 THE CALCULATED LEAKAGE RATE

=

(v~3 5.12

TABLE 5.5 (SH. 2/2) f GRAND GULF NUCLEAR STATION 1985 ILRT

\\--

LEAKAGE RATE (WEIGHT PERCENT /LAV)

TOTAL TIME ANALYSIS TIME AND LATE AT START 03 TEST: 1530 1104 1985 TEST DURATION:

4.25 HOURS TIME TEMP PRESSURE MEASURED (R)

(PSIA)

LEAKAGE RA*E 1530 540.117 26.3631 1545 540.121 26.3623

.363 1600 540.119 26.3599

.598 1615 540.118 26.3584

.564 1630 540.107 26.3566

.546 1645 540.109 26.3553

.536 1700 540.107 26.3537

.539 1715 540.097 26.3517

.539 1730 540.096 26.3493

.555 1745 540.096 26.3488

.536 1800 540.086 26.3466

.546 1815 540.089 26.3451

.550 1830 540.088 26.3437

.545 1845 540.078 26.3422

.531 1900 540.081 26.3401

.552 1915 540.076 26.3384

.550 1930 540.068 26.3372

.534 1945 540.073 26.3356

.542

.537 MEAN OF THE MEASURED LEAKAGE RATES

=

VERIFICATION TEST LEAKAGE RATE UPPER LIMIT =

.675 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT =

457

.555 THE CALCULATED LEAMAGE RATE

=

x 5.13 4

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

m

l i

TABLE 5.6 I

LOCAL LEAKAGE RATE PENALTIES Penet.

Leakage No.

Service For Penalty SCCM l

4 Fuel Transfer Tube See Note (1) 10 7

Main Steam C See Note (2) 0 l

8 Main Steam D See Note (2) 436 i

s 9

Feedwater A See Note (3) 59 l

2 l

10 Feedwater B See Note (3) 813 14 RHR Shutdown Cooling Suction See Note (3) 0 i

18 RHR to RPV Head Spray See Note (3) 0 20 RHR LPCI A See Note (3) 232 21 RHR LPCI B See Note (3) 0 22 RHR LPCI C See Note (3) 0 1

26 HPCS Discharge to RPV See Note (3) 0 31 IECS Discharge to RPV See Note (3) 40 36 Plant Service Water Return See Note (3) 0 37 Plant Service Water Supply See Note (3) 0 1

38 Chilled Water Supply See Note (3) 0 39 Chilled Water Return See Note (3) 0 1

40 Contaiment Pressurization (ILRT)

See Note (4) 0 56 Condensate Makeup to Upper Containment Pool See Note (3) 0 j

61 Standby I.1 quid Control (Spare)

See Note (2) 29 73 RHR Relief Valve Discharge See Note (3)

O 76B RRR Relief Valve Discharge See Note (3) 0 t

82 Drywell Pressurization (ILRT)

See Note (4)

.0 j

101C Drywell Pressure Instrumentation See Note (3) 0 101F Drywell Pressure Instrsonentation See Note (3) 30 r

102D Drywell Pressure Instrumentation See Note (3) 0 j

103D Contaissent Pressure Instrumentation See Note (3) 0 l

104D Containment Pressure Instrumentation See Note (3) 0 l

105A Contaissent Hydrogen Sample See Note (3) 0 106A Drywell Hydrogen Sample See Note (3) 0

.106B Drywell Hydrogen Sample See Note (3) 0 f

106E Containment Hydrogen Sample See Note (3) 0 1

107B Containment Hydrogen Sample See Note (3) 0 107D Drywell Hydrogen Sample See Note (3) 0 107E Drywell Hydrogen Sample See Note (3) 0 108A Contaiment Hydrogen Sample See Note (3) 0 109A Drywell Fission Products Monitor Sample See Note (3) 0 109B Drywell Fission Products Monitor Sample See Note (3) 0 t

i 109D Contalment Pressure Instrumentation See Note (3) 0 110A Drywell Pressure Sensing (ILRT)

See Note (4) 0 j

110C Containment Pressure Sensing (ILRT)

See Note (4) 0 110F Verification Flow (ILRT)

See Note (4) 0 114 Suppression Pool Level Instrumentation See Note (3) 0 116 Suppression Pool Level Instrumentation See Note (3) 0 t

118 Suppression Pool Level Instrtssentation See Note (3)

O 4

120 Suppression Pool Level Instrumentation See Note (3) 0 TUTAL (SCCM) 1650 SU-088a 5-14 i

l l

Notes O

(1) The transfer tube closure flange was locally tested using air but submerged in water during the ILRT.

(2) Penetration isolated to reduce leakage during the ILRT.

(3) Penetration in service or in standby during the ILRT (or could not be l

isolated from a system in service or in standby).

(4) Penetration dedicated to ILRT functions.

P I

l' O

i l

O SU-088s 5-15 i

r

TABLE 5.7 PLANT SPECIFIC DATA l

A.

Plant Information:

Middle South Energy, Inc.

Owner:

Docket No:

50 - 416 Grand Gulf Nuclear Station Unit 1 Plant Conventionally Reinforced Concrete Mark III Containment Type:

NSSS Supplier, Type:

General Electric, BWR Date Test Completed:

November 4,1985 B.

Technical Data Centainment Pree Air Volumet 1,670,360 cubic feet Calculated Loss of Coolant Accident Pressure:

11.5 psig Containment Design Pressure:

15 psig Containment Design Temperature:

185'T Test Pressure Limits:

11.5 - 13.5 peig Limits on Containment Air Temperature During Tests 40 - 120*F Maximus Allowable Leakage Race, L,:

0.437wt.% of Contained Air Mass per Day (24 hrs).

Acceptance Leakage Rate as Determined During the Test:

The upper 95% confidence limit on calculated leakage rate plus local leakage rate additions shall be less than 0.75L, = 0.328 wt.2/ day OV SU-088a 5-16

TABLE 5.8 g

k-RETAINED TEST BACKUP DATA s

1.

Access control procedures that were established to 11rit ingress to containment during testing.

2.

A listing of all containment penetrations, including penetration size, and function.

3.

A Itsting 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 f rom initial survey of containment to restoration of all tested systems.

6.

Documentation of instrumentation calibration and standards.

7.

The Official Test Copy of the procedure which includes signature sign-of f of procedural steps.

(-'

8.

The procedure and all data that verifies completion of penetration

(

local leakage testing (Type B&C tests).

9.

Computer printouts of Integrated Leakage Rate Test Data.

10.

A listing of all test exceptions including changes in containment system boundaries instituted to conclude successful testing.

11. Description of method of leak rate verification of instrument measuring system (superimposed leakage), with calibration information on flowmeters.

12. The P&lDs of pertinent systems penetrating the containsent or af fected by ILRT.

13. Calculation of containment and drywell volume f ractions.

1 i

l l

l l

SU-088a 5-17

O O

O GRAND GULF NUCLEAR STATION 1985 ILRT 4

AIRMASS LBM X 1999 AND REGRESSION LINE I

220.85 f '\\.N.,ST ABILIZATI ON s

i

's-9.68 X/ DAY 220.65" t

\\

[

f N

l 229.45" N

ILRT 0 14 x/pgy m

b

.~~-

220.25" k_f a

1

~ ~

MSIU LEAES STOPPED

~.

l 220.05" MAMEUP TO U ERI FI CA T I ON '*

REACTOR 0.54 X/ DAY 219.85 1.

l

.439 1103 TIME HOURS 1945 1194 l

START TIME DATE END TIME DATE i

i t

FIGURE 5.1

l O

0 o

GRAND GULF NUCLEAR STATION 1985 ILRT TEMPERATURE DEGREES F

l l

,1 82.000 l

)

81.600" 4

'l t

I 81.200" l t

w

,g \\.

~;

80.800"

~ ~ ~ ~.

s 80.400" 80.000.............................

.430 1103 TIME HOURS 1945 1194 START TIME DATE END TIME DATE FICtfRE 5.2

O O

O i

GRAND GULF NUCLEAR STATION 1985 ILRT UAPOR PRESSURE PSIA

.425 t

(

~-

l t

~ ~ ~ -

1 j

.410"

)

.395" t

1 I

E$

i

.380"

/

..J

'4 3

l i

.365" l

~

1 i

.350

.430 1.1.El3 TIME HOllRS 1945 1104 r

START TIME DATE END TIME DATE l

i VICURE 5.3

i O

O O

GRAND GULF NUCLEAR STATION 1985 ILRT PRESSURE PSIA (DRV AIR) 26.550 i

I l

\\

26.500'\\

. \\.,

26.450"

- s i

~.

. ~

'u

~~

26.400"

/

26.350"

~~~ -

26.300

.430 1103 TIME HOURS 1945 1104 l

START TIME DATE END TIME DATE 1

l FIGURE 5.4 i

i i

i

~

O O

O GRAND GULF NUCLEAR STATION 1985 ILRT MASS POINT LEAMAGE RATE AND UCL X/ DAY ~

.500

.400 9.75 La

)

.300 5,

\\

b

.200 95X UCL r

-==

-==

RATE

.100 l

.000 545 1194 TIME HOURS 1415 1104 START TIME DATE END TIME DATE FICURE 5. 5

4 GRAND GULF NUCLEAR STATION 1985 ILRT AIRMASS LBM X 1000 AND REGRESSION LINE i

t i

220.24 at%.

I f

0.137 X/ DAY

?

\\

l 220.18" N;

220.13 9.75 L 's' i

e

=

(0.328 x/pgyy'.

220.98 l

l 1

l 220.03

~.

219.98 STARTTMEbhfE "Npffkhhh l

i FIGURr 5.6 l

O e

o GRAND GULF NUCLEAR STATION 1985 ILRT l

TOTAL TIME LEAHAGE RATE AND UCL X/ DAY

.500 l

)

.400" 0.75 La i

1

.300

\\

i l

'\\

95x UCL l

s

.m_

.200 1

l s

l

.100 RATE l

i 1

.000 545 1104 TIME HOURS 1415 1104 START TIME DATE END TIME DATE l

FICURE 5.7 l

I O

O O

GRAND GULF NUCLEAR STATION 1985 ILRT AIRMASS LBM X 1000 AND REGRESSION LINE UERIFICATION TEST j

220.96 220.01"

_~~

LOWER LIMIT

._~

~~

219.96-y l

3

~~.

~.

~ ~ ~ ~ ~ ~

219.90" UPPER LIMIT

~.

.~~'

i 219.85-219.89

.530 1104 TIME HOURS 1945 1104 i

START TIME DATE END TIME DATE i

FICURE 5.8 l

l

.I.

6.0 REFERENCES

6.1 Grand Gulf Nuclear Station, Unit 1. Technical Specification 3/4.6.1.

6.2 Grand Gulf Nuclear Station, Surveillance Procedure 06-ME-1M10-0-0002, Contairunent Integrated Leak Rate Test, Revision 20.

6.3 Code of Federal Regulations, Title 10, Part 50, Appendix J - Primary Reactor Contalment Leakage Testing for Water Cooled Power Reactors.

6.4 ANSI /ANS-56.8-1981, Contaiment System Leakage Testing Requirements.

6.5 Bechtel Topical Report BN-TOP-1, Revision 1 Testing Criteria for Integrated Leakage Rate Testing of Primary Contairunent Structures for Nuclear Power Plant s.

6.6 ANSI N45.4 - 1972, Leakage Rate Testing of Containment St ructures for Nuclear Reactors.

O SU-088a 6-1

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APPENDIX A i

l Description of Bechtel ILRT Computer Program j

1.

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SU-088b i

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,1 0

i APPENDIX A i

l v

DESCRIPTION OF BECHIEL ILRT COMPUTER PROGRAM A.

Program and Report Description i

I i

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, free air volume, containment atmosphere total pressure, drybulb temperature, and dewpoint temperature (water vapor pressure).

1 Isakage rate is computed 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 le akage testing. Current leakage rate values may be obtained at any time during the testing period using one of two computational methods, i

yielding three dif ferent report printouts.

2.

In the first printout, the Total Time Report, leakage rate is com-puted from initial values of free air volume, containment atmosphere i

drybulb temperature and partial pressure of dry air, the latest

}

values of the same parameters, and elapsed time. These individually j

computed leakage rates are statistically averaged using linear re-gression by the method of least squares. The Total Time Method is the computational technique upon which the short duration test criteria'of BN-TOP-1, Rev 1, " Testing Criteria for Integrated Leakage Rate Testing of Primary Contairusent Structures for Nuclear Power Plant " are based.

I 3.

The second printout is the Mass Point Report and is based on the 1

Mass Point Analysis Technique described in ANSI /ANS 56.8-1981, I

" Containment System Leakage Testing Requirements." The mass of dry j

sir in the containment is computed at each data point (time) using the Equation of State, from current values of containment atmosphere l

drybulb temperature and partial pressure of dry air. Contained mass i

is " plotted" versus time and a regression line is fit to the data I

using the method of least squares. Imakage rate is determined from j

the statistically derived slope and intercept of the regression line.

I 4

The third printout, the Trend Report, is a summary of leakage rate l

l values based on Total time and Mass Point computations presented J

as a function 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.

i 5.

The progree is written in a high level language and is designed 7

for use on a micro-computer with direct data input from the data acquisition system. Brief descriptions of program use, formulae i

DN-103 g.g

)

i 4

l used for leakage rate computations, and program logic are provided Q

in the following paragraphs.

D B.

Explanation of Program 1.

The Bechtel ILRT comp.ater program is written. for use by experi-enced ILRT personnel, to determine containment inteersted 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 or at the start of the test:

a.

Number of contairunent atmosphere drybulb temperature sensors, dewpoint temperature (water vapor pressure) sensors and pressure gages 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 sensors d.

Tes t title e.

Test pressure f.

Maximum allowable leakage rate at test pressure 3.

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

a.

Time and date b.

Containment atmosphere drybulb temperatures c.

Containment staosphere pressure (s) d.

Containment atmosphere dewpoint tempe ra tures e.

Containment free air volume.

4 Af ter 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.

5.

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

O DH-103 A-2

C.

Leakare Rate Formulae

~

)

't) 1.

Computation using the Total Time Method:

a.

Measured leakage rate, from data:

PV1 i = W RT1 (1) 1 PVi i = W RT -

(:)

i i 2400 (W1-W) i li (3)

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

2400 /

TPVh 1ii l 1-l (4)

L

=

g ati (

TPVi1i)

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

ti respectively, lbs.

-T, Ti = Containment atmosphere drybulb te=perature 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,Vi = Containment free air volume at times t iandtgresgec-1 tively, (constant or variable during the test),

ft ti, tg = Time at let and ith data points respectively, hours.

att = Elapsed time from ti to ti, hours.

R = Specific gas constant for air = $3.35 ft.lbf/lbm.*R.

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

In order to reduce truncation error, the computer program uses the following equivalent formulation:

-2400(aW) i Li=

l ati( W /

1 nU A-3 DH-103

where, Le AWi Wi-W1 W1 W1 api AVi AP aVi ATg i

+

+

P1 V1 PV1i T1 y,ATt Ti api =Pi-P1 AVi=Vi-V1 STi=Ti-T1 b.

Calculated leakage rate from regression analysis, I = a + b ats (5) where:

L = Calculated leakage rate, wt.%/ day, as determined f rom the regression

'line.

a = (ILt - bIatg)/N (6)

N( L ati) - (IL )(Iott) i i

N(Iatg ) - (Iatg)2 A

N = Number of data points N

I=I i=1 c.

Calculated leakage rate at the 95% confidence level.

I95 = a + b atN + S (8)

I where:

E95 = calculated leakage rate at the 95% confidence level, wt.%/ day, at elapsed time atN*

O U

DH-103 44

For.atN < 2' p)

C S

= to.025;N-2 [(ILt - a:Lt - brL ati)/(N-2)]II2 x [1'+ 1,+ (at -E)2/

(9a) 2 i

3 T

N (Iat 2 _ (g3ti)2f3)jl/2 g

where, to.02! N-2 = 1.95996 + 2.37226 + 2.82250 ;

N-2 (N-2)-

For atN 12' 2 - arLt - btt ati)/(N-2)]1/2 x (1,+(at3 - E)2/

(9b)

S_ = to.025;N-2 [(ILg g

L N

2 _ gg et)2f3);1/2 (ratt 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 where, to.025;N-2 =

(N-2)2 + 1.2209(N-2) - 1.5162 I = Calculated leakage rate computed using equation (5) at total elapsed t

time att, %/ day.

Iati at =

N O-2.

Computation using the Mass Point Method a.

Contained mass of dry air from data:

T (10) whe re A11' symbols are as previously defined.

b.

Calculated leakage rate from regression analysis, W = a + b at b

E = -2400 -

(11) a where L

= Calculated leakage rate, wt.%/ day, as determined f rom the regression line.

O DH-103 g_3

= (IW -bu t )/N (12) a i

t O)

(

N(IW atg) - ( N )( Utg) g g

b.

(13)

=

N(U tg-) - (U tg)*

th att = Total elapsed time at time of i data point, hours N = Number of data' points Wg = Contained mass of dry air at ich data point, 1be, as computed from equation (10).

N I=I i=1 In order to reduce truncation error, the computer program uses the following equivalent formulation:

AWg b

a=

W 1 + (I IAtg)/N g

W~

W1 1

O aWg AWg N (I Atg) - I Iac g Wi Wi b=

W N(Dtg ) _ (gggi)2 2

AWg

'where, is as previously defined.

W1 c.

Calculated leakage rate at the 95* confidence level.

-2400 b5=

(b - s )

(14) b a

where:

I93 = Calculated leakage rate at the 95* confidence level, wt.2/ day.

DH-103 A-6 w.

1/2 SN d - (u tg) W (15) s * "0 025;N-2 (.M tg b

-where, to.025;N-2, 1.6449(N-2)2 + 3.5283 (N-2)2 + 0.85602 (N-2)2 + 1.2209 (N-2) - 1.5162

'I(Wg - (a + b atg)]I N-2 a

rg

=W, I(aw /W )2. ggg3g fw )j2fg.

g g g i1 N-2

[I(AW /W ) a tt - I(aw /W )(u tg)/N]2

• U2 g g g 1 d

I(a tt ) - (I act)d/N O

O DM-103 A-7 e

r-l l

l

,fm D.

Program Logic l (v) l 1.

The Bechtel 11JtT computer program logic flow is controlled by a set i

of user options. The user options and a brief description of their associated f unction are presented below.

l OPTION COMMAND FUNCTION l

Af ter starting the program execution, the user either l

enters the name of the file containing previously I

entered data or initializes a new data file.

DATA Enables user to enter raw data. When the system requests values of time, volume, temperature, pressure l

and vapor pressure, the user enters the appropriate l

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 Summary Report of time, data, average temperature, partial pressure of dry air, and water vapor pressure is printed.

TREND A Trend Report is printed.

O I h TOTAL A Total Time Report is printed.

MASS A Mass Point Report is printed.

TEP.M Enables user to sign-of f temporarily or permanently.

All data is saved on a file for restarting.

CORR Enables user to correct previously entered data.

LIST A Summary Data Report is printed.

t READ Enables the computer to receive the next set of data l

from the data acquisition system directly.

PLOT Enables user to plot summary data, individual sensor data or air mass versus time.

DELETE Enables user to delete a data point.

INSERT Enables user to reinstate a previously deleted data point.

VOLFRA Enables user to change volume f ractions.

O DH-103 A-8 I

OPTION

[}

COSNAND FUNCTION v

TIME Enables the user to specify the time interval for a report or plot.

VERT Enables the user to input imposed leakage rate and calculated ILRT leakage rates at start of verification test.

E.

COMPUTER REPCRT AND DATA PRINTOUT MASS POINT REPORT The Mass Point Repott presents leakage rate data (wt%/ day) as deter-mined by the Mass Point Method. The " Calculated Leakage Rate" is the value determined from the regression analysis. The "Containnent Air Mass" values are the masses of dry air in the containment (ibm).

These air masses, determined from the Equation of State, are used in the regression analysis.

TOTAL TIME RIPORT The Total Time Report presents data leakage rate (wt%/ day) as deter-mined by the Total Time Method. The " Calculated Leakage Rate" is the g

value deter =ined from the regression analysis. The " Measured Leakage I,

Rates" are the leakage rate valuas determined using Total Time calcu-lations. These values of leakage rate are used in the regression analysis.

TREND REPORT The Trend Report presents leakage rates as determined by the Mass Point and Total Time methods in percent of the initial contained mass of dry air per day (wt%/ day), versus elapsed time (hours) and number of data points.

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 six column headings are TIME, DATE, TEMP, PRISSURE, VPRS, and VOLUME 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).

~

DH-103 A-9 e

4.

PRESSURE:

Partial pressure of the dry air component of the con-tainment atmosphere in absolute units (psia).

5.

VPRS:

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

6.

VOLUME:

Containment free air volume (cu. ft.).

F.

SUMMARY

OF MEASURED DATA AND

SUMMARY

OF CORRECTED DATA The Summary of Measured Data presents the individual containment atmosphere drybulb temperatures, dewpoint temperatures, absolute total pressure and free air volume measured at the time and date.

1.

TEMP 1 through TEMP N are the drybulb temperatures, where N = No. of RTD's.

The values in the right-hand column are temperatures ('F) as read from the data acquisition system (DAS).

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

. PRES 1 through PRES N are the total pressures, absolute, where N = No.

of pressure sensors. The right-hand value. in parentheses, is a number in counts as read f rom the DAS. This count value is converted to a value in psia by the computer via the instrument's calibration table, counts versus psia. The left-hand column is the absolute total pressure, psia.

3.

VPRS 1 throueh VPRS N are the dewpoint temperatures (water vapor pressures), where N = No. of dewpoint sensors. The values in the right-hand column are temperatures (*F) as read f rom the DAS. The values in the lefthand column are the water vapor pressures (psia) f rom the steam tables for saturated steam corre-sponding to the dewpoint (saturation) temperatures in the center column.

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

1.

TEMPERATURE (*R) is the volume weighted average containment steosphere drybulb temperature derived from TEMP 1 through TEMP N.

2.

CORRECTED PRESSURE (psla) is the partial,sressure of the dry air component of the containment atmosphere in absolute units. The volume weighted average containment atmosphere water vapor pressure is subtracted from the volume weighted average 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 derived f rom VPRS 1 through VPRS N.

O DH-18$

A-10

4.

VOLT.HE (cu. ft.) is the containment f ree air volu:se.

5.

CONTAINMENT AIR MASS (Ibe) 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.

O 5

O DN-103 A-11

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APPENDIX B j

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i Instrument Error Analysis (ISG) l l

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APPENDIX D l

(~N ISG CALCULATION 1,)

1981 )

( ANSI /ANS 56.8 CALIBRATION DATA

1. OF SENSORS SENSITIVITY (E)

REPEATABILITY (r)

TEMPERATURE (T) 22 0.1000 deg. F 0.0100 deg. F PRESSURE (P) 2 0.0003 paia 0.0003 pais VAPOR PRESS (Pv) 6 0.1000 deg. F 0.0100 dag.

F' Length of Test (t) 8.0 hrs Test Pressure (P) 11.5 paig

==>

26.2 paia From Steam Table 0.0124 pai/deg. F (at 70 deg. F)

La 0.4370 wtt/ day

[)

INSTRUMENT MEASUREMENT ERRORS v

2 2

1/2 1/2 eT. ((ET)

+ (rT) 3

/t# of sensors) e7 0.0214 deg. F 2

2 1/2 1/2 eP = ((EP)

+ (rP) 3

/tm of sensors) eP =

0.0003 pain 2

2 1/2 1/2 ePv. ((EPv)

+ (rPv) 3

/t# of sensors) 0.0005 pais ePv.

INSTRUMENT SELECTION GUIDE 2

2 2

1/2 ISG. 2400/tt 2(eP/P)

+ 2(ePv/P)

+ 2(eT/T) 3 ISG.

0.0194 wt2/ day

)

25% of La 0.1093 wt4/ day

1 1

O l

i l-t APPENDIX C Local Leakage Rate Testing Results t

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SU-088b l

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APPENDIX C

\\j Local Leakage Test Summary Data Type B Test Results Penetration Description Leakaoe, SCC" 1

Equipment Hatch 0 1 11 2

Upper Personnel Lock 116 2 12 3

Lower Personnel Lock 294 2 11 4

rual Transfer Tube 02 11 201 Reactor Protection System 020 202 Low Voltage Power 020 203 Instrumentation 010 204 Instrumentation 010 205 Neutron Monitoring 020 206 Low Voltage Power and Control Ot0 207 Control and Power 020 208 Instrumentation 020 209 Low Voltage Power 020 210 Radiation Monitoring 020 211 Control 010 212 Instrumentation 020 213 Rod Position Indication 010 214 T. I. P.

020 215 6.9 Kv-Reactor Recirculation Pump A 020 f-~g 216 Test Systems and Communications 010

(' ')

217 Low Voltage Power and Control 020 218 Neutron Monitoring 020 219 Instrumentation 020 220 Instrumentation 020 221 Control 020 222 Reactor Protection 010 223 Low Voltage Power and Control 020 224 Instrumentation 010 225 Low Voltage Power 010 226 Control 020 227 Instrumentation 020 228 Instrumentation 020 229 Low Voltage Power and Control 020 230 Reactor Protection 020 231 Instrumentation 020 232 Neutron Monitoring 020 233 Rod Position Indication 020 234 CRD Hydraulic System Power and Control 020 235 Neutron Monitoring 01 0 237 Instrumentation 020 238 Reactor Protection System O10 239 Control 020 240 Instrumentation 020 241 Low Voltage Power and Control 020 2 4.'

Low Voltage Power and Control 010 C-1

(

APPENDIX C (Cont'd)

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

Penetration Description Leakage, SOCM 243 Instrumentation 020 244 Low Voltage Power 020 245 Low Voltago Power and Control 020 246 Radiation Monitoring 020 247 6.9 KV Reactor Recirculation Pump B 020 248 Power 020 249 Control 020 ISI Inspection Ports 010 TOTAL = 420 2 23

• Twenty-two inspection ports on guard pipes, two ea:h per penetration on eleven penetrations (5-10, 14, 17-19, & 87).

,em,

\\

)

xa 1

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/

x /

C-2 l

()

APPENDIX C (Cont'd)

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

(Maximum Pathway Leakage)

Penetration Description Leakage, SCCM Main steam Line A 7,174 2 100 6

Main steam Line B 30 2 17 7

Main steam Line C 01 16 8

Main steam Line D 588 1 11 9

Feedwater Line A 11,011 2 151 10 feedwater Line B 2,552 1 151 14 RHR shutdown Cooling suction 02 17 17 steam supply to RCIC Turbine and RHR Heat Exchangers 02 17 18 RHR to RPV Head spray 02 19 19 Main steam Drain to Condenser 40119 20 RHR A to LPCI 393 1 26 21 RHR 8 to LPCI 0 2 27 22 RHR C to LPCI 1,472 2 19 24' RHR Pump C Test Return Line To suppression Pool 0 2 20 26 HPCs Pump Discharge to RPV 20 2 19 O-31 LPCS Pump Discharge to RPV 179 1 16 32' LPCs Pump Test Return Line to suppression Pool 0 2 19 33 CRD Pump Discharge 0 2 16 34 Containment Purge supply 98 2 16 35 Containment Purge Eshaust 49 2 17 36 Plant service Water Return 0 1 11 37 Plant service Water supply 02 16 38 Chilled Water supply 180 1 20 39 Chilled Water Return 02 16 40 ILRT Containment Pressurization /

Depressurtration 0 1 11 41 Plant service Air 0 2 16 42 Instrument Air 450 2 12 43 RWCU to Main Condenser 02 16 44 Component Cooling Water supply 01 17 45 Component Cooling Water Return 0 2 17 47 Reactor Recirculation Post Accident sample 40 2 12

• Penetrations 24 and 32 test return lines were extended into the suppression Pool below the minimum drawdown level during the outage.

Hydraulic local leakage test is specified by Tech specss however, pneumatic leakage test results are current, pneumatic testing is conservative, and results are included in Type B and C totals. The next O

scheduled leakage tests on these penetrations will be with water.

C-3

l O) i APPENDIX C (Cont'd)

(

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

(Maximum Pathway Leakage) 1 Penetration Description Leakaan, ECTt 49 RWCU Backwash Transfer Pump to Spent Resin Storage Tank 40 1 12 l

50 DW & Containment Equipment Drain Surep l

Pumps Discharge to Auxiliary Building Transfer Tank 150 1 12 51 DW & Containment Floor Drain Surp Pumps Discharge to Auxiliary Building Transfer Tank 78 1 11 I

54 Upper Containment Pool to and from Refueling Water Storage Tank 02 11 56 Condensate Makeup to Upper Containment Pool 453 2 11 l

57 Discharge fron ruel Fool Cooling and C. U.

I system to Upper Containment Pool 160 2 17 l

58 Inlet Upper Contairment Pool Skimmer Tanks to ruel Pool Cooling and C. U. System 02 10 l

60 Auxiliary Building Floor and Equipment Drain Return 0 2 16 I

v 61 Standby Liquid Control Mixing Tank (Future Use) 30 2 17 65 Containment Normal Vent Supply and Combustible Gas Control 150 2 17 66 Containment Normal Vent and Combustible Gab Control Purge Exhaust 02 17 l

70 Automatic Depressurization System (Instrument Air) 20 2 12 l

73 RHP Shutdown Helief Valve Discharge to l

Suppression Pool 0 t 12 l

75 RCIC Pump Turbine Exhaust Vacuum Pelief 151 2 12 76B RHR Shutdown Suction Relief Valve l

Discharge to suppression Pool 02 12 1

81 Reactor Pecirculation Post Accident sample 20 2 12 82 ILRT Drywell Pressurization /

l Depressurization 02 11 83 PWCU Line from Pegenerative Heat Exchanger l

to Teodwater 299 2 12 1

04 Drywell and Containment Chemical Waste 02 11 85 Suppression Pool Cleanup peturn 304 t 19 l

86 Dominera11ted Water Supply to containment 01 12 87 PWCU Punp Suetion from Peeirculation Loops 0t li 80 PWCU Pump Discharge to RWCU Heat Exchanger 01 17

)

l 1

C-4

[)

APPENDfX C (Cont'd)

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

(Maximum Pathway Leakage)

Penetration Description Leakace, ECC" 101C Drywell Pressure Instrumentation (Narrow Range)

Ot 11 101r Drywell Pr,ssure Instrumentation (Wide Range) 30 2 11 1020 Drywell Pressure Instrumentation (Wide Range) 02 11 103D Containment Pressure Instrumentation (Wide Range) 02 12 i

104D Containment Pressure Instrumentation (Wide Range) 02 12 10$A Containment Hydrogen Analyzer Sample 02 11 106A Drywell Hydrogen Analyzer Sample 02 11 106B Drywell Hydrogen Analyzer Sample Return S2 11 106E Containment Hydrogen Analyzer Sample Return 01 11 107B Containment Hydrogen Analyzer Sample Neturn 02 12 107D Drywell Hydrogen Analyzer Sample 01 12 i

107E Drywell Hydrogen Analyzer Sample 0 2 11 108A containment Hydrogen Analyzer Sample 02 11 Os 109A Drywell - rission Product Monitor Sample 02 11 109B Drywell - Fission Product Monitor Sample Return 02 12 109D Containment Pressure Instrumentation (Harrow Range) 02 12 110A ILRT Instrumentation (Drywell Pressure) 02 11 1

110C ILRT Instrumentation (Verification Flow) 02 11 110F ILRT Instrumentation (Containment Pressure) 02 11 114 Suppression Pool Water Level Instrumentation 0 2 12 116 Suppression Pool Water Level Instrumentation 0 2 12 110 Suppression Pool Water Level Instrumentation 0 2 11 120 Suppression Pool Water Level Instrumentation 0 2 11 TOTAL = 26,734 1 306 I

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APPENDIX C (Cont'd)

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

Penetration Description Leakage, M1/ Min 11 RHR Pump A Suction 010 12 RHR Pump B Suction 53 2 1 13 RHR Pump C Suction 02 0 23 RHR A Pump Test Return Line to suppression Pool 020 24*

RHR C Pump Test Return Line to Sappression Pool N/A 25 HPCS Pump Suction 020 27 HPCS Test Return Line to Suppression Pool 020 20 RCIC Pump Suetion 020 29 RCIC Turbine Exhaust 17 1 1 30 LPCS Pump Suetion 020 32*

LPCS Test Return Line to Suppression Pool N/A 46 RCIC Pump Discharge Minimum Flow Line 011 48 RHR Heat Exchanger B Relief Valve Discharge To Suppression Pool 15711 67 RHR Pump B Test Return Line To g-~3 Suppression Pool 5311 69 Refueling Water Transfer Pump Suction

( j From Suppression Pool 020 71A LPCS Relief Valve Discharge to Suppression Pool 010 71B RHR "C" Relief Valve Discharge to Suppression Pool and Post-Accident Sample Return 010 77 RHR Heat Exchanger A Relief Valve Discharge to Suppression Pool 01 1 89 Standby Service Water Supply A 010 90 Standby Service Water Return A 020 91 Standby Service Water Supply B 020 92 Standby Service Water Return D 010 113 Suppression Pool Water Level Instrumentation 0 1 0 115 Suppression Pool Water Level Instrumentation 0 2 0 117 Suppression Pool Water Level Instrumentation 0 1 0 119 Suppression Pool Water Level Instrumentatiot. 0 1 0 TOTAL = 280 1 2.4 l

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• Penetration 24 and 32 test return line were extended into the Suppression Pool below the minimum drawdown level during the outage.

Hydraulic local leakage test is specified by Tech. Specs.# however, I

pneumatic leakage test results are current, pneumatic testing is conservative, and results are included in Type B and C totals. The next

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scheduled leakage tests on these penetrations will be with water.

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APPENDIX D J

SUMMARY

OF MAJOR MODIFICATION 3 4

i AND COMPONENT REPI.ACEMENTS i

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APPENDIX D Summary of Major Modifications And Component Replacements 1.

Carbon steel' instrument air piping and valves through Penetration 70 were replaced with stainless steel components to prevent corrosion particles from contaminating the air supply to the Automatic Depressurization System. The following Type C tests were performed:

Component Date Leakage (SCCM)

Penetration 70 pipe seal 6-6-83 0

Weld to containment wall Valve Q1PS3F006 9-8-83 40 Valve Q1P53F003 9-9-83 10 Valve Q1P53F043-9-9-83 0

2.

The carbon steel disk in Feedwater (Penetration 10) outboard isolation check valve OlB21F032B was replaced with a stainless steel disk due to concerns about fracture toughness. At the time the work was completed, Type C testing of the feedwater check valves was not required by the GGNS local leak rate testing

/' N program. Work completed on 5-4-84.

3.

A motor-operated 6-inch gate valve (01E12F394) was welded into the RPV head spray line to replace check valve QlE51F066 as the inboard containment isolation valve on Penetration 17, due to the difficulty of performing Type C tests on Q1E51F066. The modification changed the containment isolation boundary so that 1-inch drain valve QlE12F344, which was previously a containment isolation valve, is now outside the containment isolation boundary. After the new gate valve was connected electrically and stroke tested, a Type C test on 10-22-85 indicated no leakage.

4.

The plugs on feedwater inboard isolation plug-check valves Q1B21F010A (Penetration 9) and Q1B21F010B (Penetration 10) were replaced with plugs with resilient seating surfaces to enable the valves to pass Type C tests.

Prior to the replacements, the test volumes could not be pressurized to Type C test pressure. Type C tests performed after the. replacements were as follows:

Component Date Leakage (SCCM)

Q1B21F010A 10-27-85 59 Q1B21F010B 10-25-85 814 5.

Residual Heat Removal Loop C (Penetration 24) and Low Pressure Core o

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APPENDIX D (cont'd)

Summary of Major Modifications And Component Replacements (cont'd)

Spray (Penetration 32) pump test return pipes were extended down into the Suppression Pool to below the minimum drawdown level by welding spoolpieces (approximately 18 inches long) to each pipe.

No Type B or C tests were performed because the previous Type B and C tests on the isolation valves are current. The penetrations now meet the requirements 10CFR50, Appendix J, Paragraph III.C.3 for valves sealed with fluid; hence, the next local leak rate tests of the isolation valves will be with water. Work was completed on Penetration 24 on 11-14-85 and on Penetration 32 on 11-25-85.

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APPENDIX E

SUMMARY

REPORT OF TYPE A, B, AND C TESTS WHICH FAILED TO MEET 10CFR50, APPENDIX J ACCEPTANCE CRITERIA O

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APPENDIX E y

' Summary Report Of Type A, B, And C Tests Which Failed To Meet 10CFR50, Appendix J, Acceptance Criteria INTRODUCTION: This summary report provides details of Type B and C tests which failed to meet the acceptance criteria of 10CFR50, Appendix J, Paragraphs III.B.3 and III.C.3.

The details of the Type A test which failed to meet the acceptance requirements of 10CFR50, Appendix J, Paragraph III. A.S. (b). (2), are described in the summary report to which this report is appended.

DISCUSSION:

The following summary table provides details of Type B and C tests which were considered to have failed to meet the acceptance criteria of 10CFR50, Appendix J, Paragraphs III.B.3 and III.C.3.

In each case, the actual leakage'resulting from the test could not be measured.

The Type B test was conducted with a bubble column test apparatus which provides only two results:

No leakage (no bubbles in the bubble column) or test failure (bubbles observed). While it is probable that the leakage would have been very low if it had been measured-with a rotometer, this was not dones therefore, the leakage was conservatively considered infinite.

All of the Type C tests which failed were due to inability to pressurize the test volune to the required test pressure of 11.5 psig. The leakages were beyond the makeup capability of a 3/4-inch or 1-inch I. D. hose supplying air at approximately 90 psig to 110 psig. Due to the inability to pressurize the volumes as required to measure the leakages, each of the leakages was assumed to be infinite.

In each case where infinite leakage was determined, action was taken immediately to correct the problem and another Type B or C test was performed to verity that the corrective action was sufficient. The measured leakages were added to the combined Type B and C test totals.

It should be noted that the combined Type B and C test totals at Grand Gulf have been determined conservatively by adding together the leakages from all of the components which are Type B or C tested. This method provides a significantly higher combined leakage than the Maximum Pathway Leakage method which is recommended in ANSI /ANS 56.8-1981.

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TYPE D AND C TEST IICH FAILED TO MFET

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10CFR50, APPENDIX J, ACCEPTANCE CRITERIA RETEST DATA COMPONENT COMPONENT DATE OF DESCRIPTION OF DESCRIPTION OF TYPE OF DATE MEASURED NUMBER DESCRIPTION TEST FAILURE FAILURE CORRECTIVE ACTION TEST OF TEST LEAKAGE (SCCM)

QlE12F041C 12" Swing Check 1-20-84 Test Volume could Lapped Seats C

1-23-84 0

Valve not be pressurized for Type C test QlE12D003C Orifice plate 1-20-84 Bubbles Detected Replaced orifice B

2-8-84 0

with double-O-during Type B plate and 0-rings ring seals on Test 18" line Q1G36F101 4" Air operated 12-1-84 Test volume could Replaced disk C

12-5-84 0

Gate Valve not be pressurized for Type C test Q1E12F028A 18" Motor 2-20-85 Test volume could Adjusted valve C

2-20-85 1688 operated not be pressurized closing torque Gate Valve for Type C test switch setting Q1E12F064C 4" Motor 3-7-85 Test volume could Replaced wedge C

3-8-85 0

operated Gate not be pressurized disk Valve for Type C test during retest for electrical work Q1B21F028D 28" Air operated 2-21-85 Test volume could Replaced poppet C

3-9-85 0

globe Valve not be pressurized with Poppet for Type C test QlE12F064C 4" Motor 10-24-85 Test volume could Adjusted valve C

10-24-85 0

operated Gate not be pressurized closing torque Valve for Type C test switch setting Q1B21F010B 24" Plug Check 10-19-85 Test volume could Replaced plug C

10-25-85 814 Valve not be pressurized with modified for Type C test plug having resilient seat QlB21F010A 24" Plug Check 10-17-85 Test volume could Replaced plug C

10-27-85 59 Valve not be pressurized with modified for Type C test plug having resilient seat E-2

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CH FAILED TO MEET

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10CFR50, APPENDIX J, ACCEPTANCE CRITERIA RETEST DATA COMPONENT COMPONENT DATE OF DESCRIPTION OF DESCRIPTION OF TYF.= OF DATE MEASURED NUMBER DESCRIPTION TEST FAILURE FAILURE CORRECTIVE ACTION TECT OF TEST LEAKAGE (SCCM)

Q1E51F076 1" Motor 10-29-85 Test volume could Repacked valve C

11-2-85.

101 operated not be pressurized Globe Valve for Type C test due to packing leak Q1B21F022C 28" Air 11-3-E5 Leakage from vent Valves were C

11-7-85 4987 Q1B21F028C operated noted during Type determined to (Combined Globe Valves A test preparation.

have been slow-Leakage) with Poppets 11-7-85 Test volume between closed prior to valves could not be Type A. test.

pressurized for valves were Type C test.

opened and then fast-closed.

Q1B21F022D 28" Air-11-3-85 Leakage from vent Valves were C

11-8-85 588 Q1B21F028D operated Globe noted during Type determined to have (Q1B21F022D valves with A test preparation.

been slow-closed only)

Poppets 11-7-85 Test volume between prior to Type A Q1R21F022D and test.

Valves were F028D could not be opened and then pressurized for fast-closed.

Type C test.

Q1B21F028D 28" Air 11-7-85 Test volume could Replaced stem and C

12-15-85 436 Operated not be pressurized lapped seat.

Globe Valve after Q1B21F022D with Poppet and F028D were opened and fast-closed.

Q1C41F151 2" Manual 11-3-85 Leakage from vent Cleaned valve C

11-17-85 29 Stop-noted during Type internals, lapped check Valve A test preparation.

seat and disk.

11-7-85 Test volume could not be pressurized for Type C test.

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TYPE B AND C TEST IICH FAILED TO MEET 10CF R57, APPENDIX J, ACCEPTANCE CRITERI A RETEST DATA COMPONENT COMPONENT DATE OF DESCRIPTION OF DESCRIPTION OF TYPE OF DATE MEASURED NUM'ER DESCRIPTION TEST FAILURE FAILURE CORRECTIVE ACTION TEST OF TEST LEAKAGE (SCCM)

Q1E12F041C 12" Swing 11-8-85 Leakage of 10,000 Relapped disk and C

11-21-85 1472 Check Valve seem measured seat during Type C test.

11-17-85 After initial lapping, test volume could not be pressurized for Type C retest.

Q1C41F150 3" Manual Gate 11-3-85 Leakage from vent Closed valve C

11-7-85 65 Valve noted during Type using valve A test preparation.

wrench.

Also, noted stem Valve was very position indicated hard to close.

valve not fully Disassembled C

11-29-85 30 closed.

valve, cleaned 11-7-85 Test volume could and lubricated not be pressurized stem and for Type C test.

reassembled.

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