ML20245G894
| ML20245G894 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 04/30/1989 |
| From: | BECHTEL GROUP, INC. |
| To: | |
| Shared Package | |
| ML20245G891 | List: |
| References | |
| NUDOCS 8908160246 | |
| Download: ML20245G894 (79) | |
Text
III SYSTEM ENERGY RESOURCES, INC.
GRAND GULF NUCLEAR STATION UNIT 1 m
...... PRIMARY REACTOR CONTAINMENT
..M INTEGRATED LEAKAGE n~ ......
RATE TEST g ......
FINAL REPORT co APRIL i989 )
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SYSTEM ENERGY RESOURCES, INC.
GRAND GULF NUCLEAR STATION UNIT 1 l
l-REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST FINAL REPORT
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PREPARED BY BECHTEL POWER CORPORATION SAN FRANCISCO, CA j
AFRIL, 1989 j
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-J' TABLE OF CONTENTS SECTION PAGE ,
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- 1. INTRODUCTION 1 i
- 2. TEST SYNOPSIS 2
- 3. TEST RESULTS
SUMMARY
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- 4. TEST METHODOLOGY 10
- 5. ANALYSIS AND INTERPRETATION 12
- 6. REFERENCES 17 APPENDICES l A. DESCRIPTION OF BECHTEL ILRT COMPUTER PROGRAM B.. INSTRUMENT ERROR ANALYSIS C. ILRT TEST DATA D. LLRT TEST DATA E.
SUMMARY
REPORT OF TYPE A, B AND C TESTS WHICH FAILED TO MEET ACCEPTANCE' CRITERIA OF 10CFR50, APPENDIX J l
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- 1. INTRODUCTION ]
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The' second periodic. Integrated Leakage Rate Test (ILRT) was J conducted on the reactor containment building at the Grand Gulf )
Nuclear Station during the period April 15-16, 1989. The test was conducted to demonstrate that' the leakage from the reactor containment system at the design loss of coolant accident >
pressure does not . exceed the maximum allowed by the plant Technical Specifications-.(Reference 6.1). The ILRT was conducted :
in accordance with GGNS Surveillance Procedure 06-ME-1M10-0-0002, i Rev.-22 (Ref. 6.2). The surveillance test procedure is based on general tasting criteria established in 10CFRSO Appendix J (Ref. l 6.3) , ANSI N45.4 1972 (Ref. 6.4) , ANSI /ANS 56.8-1987 (Ref. 6. 5) !
and Bechtel Topical Report BN-TOP-1 (Ref. 6.6).
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- 2. TEST SYNOPSIS Preparation for the Integrated Leakage Rate Test (ILRT) began with installation of a temporary pressurization system that included oil free air compressors and refrigerated dryer; instrumenting the containment with temperature, dew point and pressure monitoring sensors; and process system valve lineups.
Prior to pressurization of the containment, test prerequisites specified in the test procedure (Ref. 6.2) were completed. A survey of the containment accessible exterior and interior surfaces was performed per 10CFR50 Appendix J (Ref. 6.3). No evidence of structural deterioration was found during the containment inspection. Also, a containment temperature survey was conducted to determine that the ILRT instrumentation would accurately represent containment atmospheric conditions during the test. Satisfactory completion of the test pre-requisites is documented in the Official Copy of the test procedure (Ref. 6.2) .
Containment lights were shut off in conjunction with final containment walkdown.
Containment pressurization was started at 1413 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.376465e-4 months <br /> on April 15 and a pressurization rate of approximately 1.7 psi /hr was maintained. The pressurization system consisted of air compressors with an aggregate capacity of 6,000 scfm, an air filter, after cooler, and a refrigerated air dryer. During containment pressurization the containment fan coolers, with cooling water through the cooling coils, were run to control air temperature and prevent stratification. At 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br /> on the same day the containment pressure reached the test condition of 12 psig. Containment fans and cooling water to the cooling coils were shutoff and a temperature stabilization period was started.
Temperature stabilization criteria specified in Ref. 6.2 were met at 2345 on April 15. Following the temperature stabilization, the actual ILRT was started at 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> on April 16. During the test period, a step change of 4'F was observed in temperature sensor SM61-TE-N001-01 (RTD # 1) . Also, during the same period approximately 4,060 gallons of water were inadvertently added to the suppression pool. At the end of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> and 15 minutes after the ILRT start, the leakage rates and 95 percent Upper Confidence Limits as specified in Ref. 6.2, for both Total Time and for Mass Point Analysis, were satisfied.
Following the 8% hours of ILRT, a supplemental verification test was conducted. At 0823 hours0.00953 days <br />0.229 hours <br />0.00136 weeks <br />3.131515e-4 months <br /> on April 16 a steady leakage of air from the containment at a rate of 9.13 scfm (equal to La) was
) established. After one hour of stabilization the leakage rate f was measured for a period of 4% hours to verify accuracy of the ILRT instrumentation and the test methodology. The supplemental verification test validated the test results and ILRT 2 ;
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t-instrumentation. After completion of the verification test the containment was depressurized. Following depressurization of'the containment, plant systems that had been aligned for the -ILRT were restored for normal operation.
During the entire test period the containment pressure remained between 11.8 and 12.0 psig, which is above the required test pressure of 11.5 psig.
Following the test a calibration check on SM61-TE-N001-01 (RTD
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the test. From an insitu check using a calibrated decade box.it was determined that RTD #1 was reading 9'F above what it should have read for the given input at the end of the test. Based'en .
the uncertainty about RTD #1, it was decided that RTD #1 should !
be taken out of the ILRT calculations. The Volume fraction for l RTD #1 was reassigned to RTO #2 and RTD #3. i Correction was made for the change in suppression pool water level during the ILRT. The addition of approximately 4,060 gallons of water was seen as an inleakage to the ; containment during the test. In order to discount this water addition, 540 cubic feet of air volume were subtracted in equal increments of 90 cubic feet per 15 minute interval from the containment free air volume for the period 0145 through 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on April 16.
The ILRT results were recalculated using the new volume fractions and the variable volume.for the above mentioned period. -The corrected results satisfied the acceptance criteria specified in the test procedure (Ref. 6.2). The recalculated results are included in Section 3 of this report.
Various items of data needed to support or supplement the ILRT were recorded at regular intervals during the test. These data include ambient conditions and reactor and suppression pool levels. Also, prior to pressurization start and at the'end of the ILRT, water levels in the upper refueling pool and in the drywell sumps were recorded. All recorded' data are included in the official Test copy of the procedure (Ref. 6.2). Data required to support ILRT results are included in Appendix C to this report.
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- 3. TEST RESULTS
SUMMARY
A. Plant Information owner: System Energy Resources, Inc.
NRC Docket No.: 50 - 416 Plant: Grand Gulf Nuclear Station Unit 1 Location: Port Gibson, MS Containment Type: Reinforced Concrete Mark III NSSS Supplier: General Electric, BWR Date Test Completed: . April 16, 1989 B. Technical Data-
- 1. Containment Free Air Volume 1,670,360 Cu. Ft.
- 2. Design Pressure 15 psig
- 3. Design Temperature 185'F
- 4. Calculated Peak Accident Pressure 11.5 psig
- 5. Calculated Peak Accident Temperature 181*F
- 6. Containment Average Temperature 40-120*F Limits during ILRT C. Test Results - Type A Test at Peak Accident Pressure
- 1. Test Method Absolute
- 2. Data Analysis Techniques Mass Point Leakage Per ANSI /ANS 56.8-1987 Total Time Leakage per BN-TOP-1
- 3. Test Pressure (actual) 11.9 psig
- 4. . Maximum Allowable Leakage Rate La 0.437 wt%/ day
- 5. 75% of La 0.328 wt%/ day
- 6. ILRT Test Results (Lm) Isakage Rate (wt%/ day)
From Rearession at 95% UCL Mass Point 0.125 0.129 Total Time 0.127 0.178
- 7. Verification Test Imposed Leakage Rate Li 0.437 wt%/ day (=La) 9.13 scfm
- 8. Verification Test Results (Lvm) Leakace Rate (wt%/ day)
Mass Point 0.509 Total Time 0.511
- 9. Verification Test Limits (Lv) Test Limits (wt%/ day) 4 i
! Mass Point Total Time Upper Limit (Li+Ln+0.25La) 0.666 0.668 Lower Limit (Li+La-0.25La) 0.448 0.450 :
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- 10. Report Printouts:
The report printouts and data plots for the Type A test and Verification calculations are provided for the mass point analysis and total time analysis in Appendix C.
- 11. ILRT Adjustments and Other Penalties:
Sucoression Pool Water Addition 1 During the Type A test, approximately 4,060 gallons of water were added to the suppression pool. This water addition was treated as equivalent to 540 cu.ft of decrease in containment free air volume during the period 0145 hrs to 0315 hrs during the test period. Equal increments of 90 cu. ft. of volume were subtracted from the containment free air volume for each 15 minute increment starting at 0200 hrs and ending at 0315 hrs.
The type A results calculated with this variable containment volume are reported in 3.C.6 above.
Containment Sumo Water Level Chances Containment drywell sump level changes were measured before l and after the test. No significant water level changes were observed during the test. Thus, addition to the type A results due to water level changes is zero.
Reactor and Unoer Refuelina Pool Water Level Chances No significant level changes in the reactor and upper refueling pool were observed. Hence no penalty is to be attributed to these leve) changes.
Adiustment for Pressurized Air Bottle l
A pressurized air bottle was installed in the containment during the ILRT to control and maintain water level in the upper containment pools. The bottle was equipped with a highly accurate pressure gauge which was read before and after the ILRT. The change in the bottle pressure was converted to an in-leakage which was conservatively assumed to have occurred entirely during the Type A test.
Local Leakace Rate Penalties The penetrations not in their Post LOCA lineup during the ILRT are listed in Table 5.1 in Section 5. Minimum pathway leakage ;
from these penetrations is added to the ILRT results. The analysis of these penalties is presented in Section 5.
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Total Penalties i Total penalties to be added to ILRT results above for final as left conditions are 0.004 %/ day.
( Wt% Day) 95% UCL Penalties As Left Mass Point 0.129 0.004 0.133 Total Time 0.178 0.004 0.182 Acceptance Limit 0.328 -
0.328 D. Integrated Leakage Rate Measurement System The following instrumentation system was used for ILRT:
- 1. Absolute Pressure Gages Quartz Bourdon Tube with Optical Tracking PI-1 SM61-PIT-N003-1 PI-2 SM61-PIT-N003-2 Calibrated Range 0-30 psia Calibration Accuracy 0.02% of reading Sensitivity 0.001% of full scale Resolution 0.001% of full scale Repeatability 0.001% of full scale
,s' 2. Dry Bulb Temperature sensors 100 Ohm platinum RTD TE-1 through TE-22 SM61-TE-N001-XX Calibrated Range 60 - 120*F Calibration Accuracy 0.5'F Sensitivity 0.01*F Repeatability 0.01*F
- 3. Dew Point Temperature Sensors Chilled Mirror ME-1 through ME-6 SM61-ME-N002-XX Calibrated Range 40-100*F Calibration Accuracy 2.*F
' Sensitivity 0.5'F Repeatability 0.56*F
- 4. Flowmeters 1 Rotameter FT-1 and FT-2 SM61-FT-N004-1&2 Calibrated Range 2-20scfm Calibration Accuracy 2% of Full scale {
Sensitivity 1% of full scale Resolution 0.1 scfm 6
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=5. . Data Acquisition System Multiplexing with 16 bit A/D converter and digital clock Output Numeric display /RS232 interface Calibration' Range i 100 mV/ 4-20 mA Calibration Accuracy 0.1 mV on 100 mV range j r
0.02 mA cn 4-20 mA range j L 1 min /24 hour ]
Resolution 0.01% of range j 1 second for clock Repeatability 0.01% of range Sampling Rate 2 samples /sec .;
- 6. Table 3-1 provide locations and associated Volume Fractions used during the test for the dry bulb and dew point sensors.
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d TABLE 3-1 CONTAINMENT TEMPERATURE AND DEW POINT SENSOR LOCATIONS AND VOLUME FRACTIONS FOR ILRT RTD Elevation Azimuth Distance Volume Fractions l Instrument No. Ft Above
- From Ft. From Per As MSL Plant 0* Center Line Procedure Tested SM61-TE-N001-01 290' 0* 18' O.023 0.000*
SM61-TE-N001-02 280' 180* 18' O.038 0.050*
SM61-TE-N001-03 270' 90* 25 10' O.052 0.063*
SM61-TE-N001-04 260' 270* 30i10' O.062 0.062 SM61-TE-N001-05 228' 45' 58' O.087 0.087 SM61-TE-N001-06 250' 135' 35 10' O.067 0.067 SM61-TE-N001-07 215' 225' 58' O.090 0.090 SM61-TE-N001-08 240' 315* 35 10' O.077 0.077 SM61-TE-N001-09 173' 222' 35 10' O.058 0.058 SM61-TE-N001-10 163' 305* 54' O.057 0.057 SM61-TE-N001-11 165' 150* 24' O.022 0.022 SM61-TE-N001-12 145' 150' 56' O.057 0.057 SM61-TE-N001-13 145' 90* 56' O.057 0.057 SM61-TE-N001-14 122' 0* 46' O.057 0.057 SM61-TE-N001-15 122' 180* 46' O.058 0.058 SM61-TE-N001-16 148' 230* 30' O.022 0.022 SM61-TE-N001-17 120' 90* 24' O.022 0.022 SM61-TE-N001-18 130' 180* 31' O.023 0.023 SM61-TE-N001-19 165' 340' 34 0.022 0.022 SM61-TE-N001-20 150' 32' 32' O.022 0.022 SM61-TE-N001-21 120' 270* 26' 0'.022 0.022 SM61-TE-N001-22 100' 0* 26' O.022 0.02 Dew Point Elevation Azimuth Distance Volume Fractions Instrument No. Ft Above
- From Ft From Per As l MSL Plant O' Center Line Procedure Tested SM61-ME-N001-01 264' 90* 54' O.210 0.210 l SM61-ME-N001-02 232' 225' 58' O.210 0.210 l SM61-ME-N001-03 174' 305* 54' O.210 0.210 SM61-ME-N001-04 122' 0* 46' O.210 0.210 SM61-ME-N001-05 148' 32* 32' O.080 0.080 SM61-ME-N001-06 114' 270* 26' O.080 0.080 1
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l-E. Local Leakage Rate Results:
Local leakage rate tests on required containment penetrations were conducted in accordance with plant procedures. A ' summary of "As Found" and "As Left" local leakage rate test results is included in Appendix D. Also, based on LLRT results, "As Found" and "As Left" ILRT results were calculated. The "As Found" and "As Left" analysis is presented in Section 5 of this report.
F. Information~ Retained at Plant The following information is available for review at the facility:
- 1. A system lineup at time of test showing required valve positions and status of piping systems.
- 2. The P& ids of systems which penetrate the containment.
- 3. A listing of all containment penetrations, including number !
of the penetration, penetration size and function.
- 4. A continuous, sequential log of events from initial survey of containment to restoration of all tested systems.
- 5. The working copy of the Official Test Procedure that includes signature sign-offs of procedural steps.
- 6. Documentation of all test exceptions.
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- 7. Documentation of instrument calibration and standards used for calibration and their traceability to National Institute of Standards and Technology (NIST).
- 8. Computer printouts of all test data collected through the data acquisition system, and manual data collected during the test.
- 9. Procedures for performing all type B and C testing and LLRT ,
test data including "As Found" leakage rates, corrective action taken and "As Left" or final leakage rates.
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- 4. TEST METHODOLOGY The integrated leakage rate test is performed to verify that the leakage from the containment system at calculated peak accident i pressure does not exceed the specified limit. The containment is prepared for the test by closing all access ways and aligning valves in post accident position. All valves are closed using normal means and without exercising or using excessive force. The penetrations not in the post accident condition are listed in Section 5 of this report. Measured leakage through these valves, using minimum pathway analysis, is added to the UCL to account for the non-standard lineup. All items that could be damaged by test pressure are removed from the containment or vented. Non essential pressure sources inside the containment are vented or removed.
Measured leakage into containment from pressure sources essential to plant safety is added to the UCL.
Leakage Rete Measurements The test objective is accomplished by pressurizing the containment with clean and relatively dry air. The containment atmospheric parameters are measured using the ILRT instruments described in Section 3. Containment average dry bulb temperature, wet bulb temperature and absolute pressure are measured. Using the ideal gas law, containment air mass is calculated at 15 minute intervals. The loss of containment air mass over a specified period determines the leakage from the containment. After a 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 and a new leakage rate is calculated.
Leakage Rate Calculational Methods Containment leakage rate is calculated using the mass point and total time methods described in References 6.4 and 6.6. Both methods use containment pressure, dry bulb temperatures and dew point temperatures recorded every 15 minutes as input data. The measured dew point temperatures are used to calculate the water vapor pressure in the containment atmosphere. Evaporation and condensation of water changes the partial pressure of the vapor phase. This partial pressure is subtracted from the containment absolute pressure so that the internal phase changes are not erroneously accounted for as actual in or out leakage from the containment. The mass of dry air in the containment is calculated using the ideal gas law, with average containment temperature and dry air pressure.
The calculated air mass is plotted against time. The slope of the regression line (best fit line) through the air masses is defined as the mass point leakage rate. The measured leakage rate at a given time is defined as the calculated change in the air mass 10 i
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Both mass point and total time methods utilize the variance of data points about the regression line to establish a 95 percent Upper l Confidence Limit (UCL) on the leakage rate. References 6.4 and 6.6 describe the calculation methods in detail.
After pressurizing the containment to test pressure the containment' atmosphere is required to stabilize for a minimum of four hours.
Once the stabilization criteria specified in the test procedure are satisfied the' test is started. The leakage rate is calculated for 'j 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 />, providing a minimum of 33 data points. Following determination of the leakage rate the ability of the test instrumentation and calculations to accurately determine the leakage rate is verified by the supplemental verification test.
The supplemental test consists of imposing a known amount of leakage from containment (normally La) and measuring the increased leakage rate. The new calculated leakage rate must equal the previously calculated leakage rate plus the imposed leakage within the allowable tolerance of 25%La. The supplemental test bas a duration of at least 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> with the first hour for atmospheric stabilization.
Test data collected during the test and leakage rate analysis are presented in Appendix c.
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5'.- ANALYSIS AND INTERPRETATION The summary of test results presented in Section 3 of this report is based'on data collected during the test., These results must be corrected for the penetrations not vented or drained and not exposed to the ILRT pressure and for the. pressure sources inside the . containment. Adjustment must be made for any water level changes during the test. Also, for the periodic ILRTs, both "As Found" and "As Left" leakage rates must be determined.
Local-Leakage Rate Addition A number of mechanical systems that penetrate containment and systems that are assumed to be drained and vented post LOCA were maintained-in operation or were not vented during the test.
To account for leakage which would have passed through these penetrations in the normal post LOCA configuration, the minimum pathway local leakage is totaled and the total is added to the calculated leakage rate UCL. Table 5.1 lists all such penetrations and the penalties associated with them.
Some penetrations which were vented and drained during the ILRT had maintenance work performed on them before or after the ILRT; thus, they were in the "As Found" or the "As Left" condition during the ILRT, but not both. Some other penetrations were vented and drained during the ILRT but were not in either the "As Found" or the "As Left" condition.
To account for the difference in the leakage through these penetrations in the "As Tested" condition vs. the "As Found" and/or "As Left" conditions, the minimum pathway local leakage "As Found" and "As Left" is totaled and the total is conservatively added to the calculated leakage rate UCL. The "As Tested" local leakage rate through these penetrations is often not known, is ignored in these ' calculations, and is conservatively assumed to be zero.
Table 5.1 lists these penetrations and the penalties associated with them.
Adjustment for Pressurized Air Bottle During the ILRT a pressurized air bottle was installed in the containment to maintain pressurized the seals on a gate between the fuel transfer canal and the rest of the upper containment pools.
The gate prevented water in the upper containment pools from entering the fuel transfer canal, which had been drained for modifications of the horizontal fuel transfer system and the fuel transfer tube door. The bottle was equipped with a pressure gauge having an accuracy of io.1 percent.
The pressure gauge was read before containment pressurization for the ILRT began and again after containment depressurization was completed after the ILRT. The difference in the pressure readings, 12 i
y which were adjusted for the local ambient atmospheric pressure, was converted to an in-leakage which was conservatively assumed to have occurred entirely during the Bh hours of Type A test. The inleakage was adjusted for the change in the bottle temperature during the ILRT. The adjusted in-leakage of 1.24x10 wt.%/ day was added to the calculated leakage rate and the 95% UCL as a penalty.
Water volume correction The initial free air volume of the containment with the suppression pool and ' the upper refueling pool at specified levels was calculated as 1,670,360 cubic feet. During the conduct of the test approximate 19 4,060 gallons of water were inadvertently added from-the condenccte storage tank to the suppression pool. Pre- and post-test meam:rements of reactor level and upper pool level did not change ripilicantly and there was no significant change in the containmer-r and drywell equipment drain and floor drain sumps.
Thus, the only correction required for the' water level changes was-due to water addition to the suppression pool.
Since the suppression pool water addition was a step change during the test, the containment free air volume was decreased by 540 cubic feet over the time period when water was being added. This is equivalent to subtracting 90 cubic feet from containment free air volume for every 15 minute interval during the period from 0145 through 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> on April 16. By adjusting the free air volume of the containment, the water addition into the suppression pool is accounted for and no additional correction to the test data for the wateg level is required.
COMPOSITE TEST RESULTS The composite leakage rate is the sum of the calculated rate, the correction for the water level changes and penalties for local leakage rate and pressurized bottle. The final results are summarized as follows:
Mass Point (wt%/ day) Total Time (wt%/ day)
Calculated 95% UCL Calculated 95 %UCL From Test Data 0.125 0.129 0.127 0.178 Local Leakage 0.004 0.004 0.004 0.004 Penalty (Table 5.1)
Correction for 1.24x10 1.24x10 1.24x10 1.24x10
Pressure Source Composite 0.129 0.133 0.131 0.182 Acceptance Limit 0.328 0.328 0.328 0.328 13
i AS FOUND/ AS LEFT. ANALYSIS Maintenance performed on the containment isolation valves prior to the ILRT during the outage may result in improvement of the ILRT test results. In order to determine the "As Found" ILRT test results, it is necessary to perform a minimum pathway analysis for LLRTs performed on isolation valves and penetrations. If repair to an isolation valve results in reduced leakage through that penetration, the improvement should be added'to the ILRT results to determine an "As Found" value. ' Appendix D lists LLRT results for containment penetrations and isolation valves for the current and past refueling outages since performance of the last ILRT.
From Appendix D the "As Found" minimum pathway LLRT total for all penetrations that were pneumatically tested during the refueling outage RF03 is 76,037 1 1808 secm. Some of these penetrations were repaired to improve leakage prior to the ILRT. Others were worked on after the ILRT or were accepted as tested. The final "As Left" minimum pathway leakage rate for all these penetrations is 3223 421 secm. Assuming that all the improvements in minimum pathway i leakage rate resulted in improving the ILRT results, to find the "As Found" ILRT it is necessary to add these improvements to the test results. For a conservative estimate we assume that the total improvement in the minimum pathway leakage through the penetrations is (76,037+1808)-(3223-421) secm. This translates to total improvement equal to 0.127 wt%/ day (75,043 scem).
1 Based'on minimum pathway analysis, the ILRT results are as follows:
Mass Point (wt%/ day) Total Time (wt%/ day)
Calculated 95% UCL Calculated 95 %UCL From Test Data 0.125 0.129 0.127 0.178 Local Leakage 0.127 0.127 0.127 0.127 !
Improvements 4 4 Correction for 1.24x10 1.24x10 1. 2 4 x10" 1. 2 4 x10" I
Pressure Source Composite 0.252 0.256 0.254 0.305 i The above "As Found" results are less than both La (0.437 wt%/ day) 4 and 0.75La (0.328 wt%/ day). ,
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TABLE - 5.1 LOCAL LEAKAGE RATE PENALTIES Reason for Penetra- Penalty . Penalty Irakane (SCChD tion No. Service See Note: As-found - As-left 1 Containment Equipment Hatch G 40 0 4 Fuel Transfer Tube G 0 0 5 Main Steam A C 12,443 1996 6 Main Steam B C 14,734 0 7 Main Steam C - C 18,624 280 8 Main Steam D C 0 0 9 Feedwater A B 0 60 -
10 Feedwater B B 0 0 14 RHR Shutdown Cooling Suction B 0 0 17 Steam Supply to RCIC Turbine C 0 0 18 RHR to RPV Head Spray B 0 0 20 RHR A to LPCI D 0 0 21 RHR B to LPCI D 0 0 22 RHR C to LPCI D 0 0 26- HPCS Pump Discharge to RPV D 0 0 31 LPCS Pump Discharge to RPV D 0 0 35 Containment Purge Exhaust E 0 --
36 Drywell Chilled Water Return C 0 0 37 Drywell Chilled Water Supply C 0 0 38 Chilled Water Supply C 0 0 39 Chilled Water Return C 0 0 40 Containment Pressurization (ILRT) A 0 0 42- Instrument Air E 900 --
56 Condensate Makeup to Upper Contain- C 0 0 ment Pool .
57 Discharge from Fuel Pool Cooling & C 20 20 Cleanup System to Upper Contain-ment Pool RHR Shutdown Cooling Relief Valve B 0 0 73 Discharge to Suppression Pool RCIC Pump Turbine Exhaust Vacuum F -- 0 75 Relief RHR Shutdown Cooling Suction Relief B 0 0 76B Valve 82 Drywell Pressurization A 0 0 Containment Hydrogen Analyzer Sample B 0 0 105A Drywell Hydrogen Analyzer Sample B 0 0 106A Drywell Hydrogen Analyzer Sample Return B 0 0 106B 15 l
TABLE - 5.1 (Continued)
LOCAL LEAKAGE RATE PENALTIES Reason for Penalty Penalty 12akane (SCChD Penetra-tion No. Service See Note: As-found As left 106E Containment Hydrogen Analyzer Sample B 0 0 Return '
107B- Containment Hydrogen Analyzer Sample B 0 0 Return 107D Drywell Hydrogen Analyzer Sample B 0 0 107E Drywell Hydrogen Analyzer Sample Return B 0 0 0
108A Containment Hydrogen Analyzer Sample B 0 110A Drywell Pressure Sensing (ILRT) . A 0 0 110C. Containment Pressure Sensing (ILRT) A 0 0 110F Verification Flow (ILRT) A 0 0-114 Suppression Pool Water Level Instrument B .0 0 ,
116 Suppression Pool Water level Instmment B 'O 0 118 Suppression Pool Water Level Instrument B 0 0 120 Suppression Pool Water Level Instrument B 20 20 ,
i NOTES: A. Penetration dedicated to ILRT service '!
B. Penetration in service or standby to support plant operation C. Penetration was not drained or vented due to plant status D. Penetration part of normally water-filled system that operates under post- l '
accident conditions E. Penetration was not in as-found condition during ILRT but was exposed to ILRT pressure in as-left condition l F. Penetration was not in as-left condition during ILRT but was exposed to l ILRT pressure in as-found condition G. Penetration was not in as-found or as-left condition during ILRT but was exposed to ILRT pressure 16 1
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6.0 REFERENCIS I
6.1 Grand Gulf Nuclear Station Unit No.1, Technical Specification i 3/4.6.1 6.2 Grand Gulf Nuclear Station, Surveillance Procedure, 06-ME- .
1M10-0-0002, Containment Integrated Leak Rate Test, Revision
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6.3 Code of Federal Regulations, Title 10, Part 50, Appendix J-Primary Reactor Containment Leakage Testing for Water Cooled Reactors.
6.4 ANSI /ANS-56.8-1987, Containment System Leakage Testing Requirements.
6.5 ANSI N45.4-1972, Leakage Rate Testing of Containment Structures for Nuclear Reactors.
6.6 Bechtel Topical Report BN-TOP-1, Testing Criteria for 1
Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants, Revision 1, 1972.
l 17
'M f k APPENDIX A DESCRIPTION OF BECHTEL ILRT COMPUTER PROGRAM i
I l
t f
l l
I
L l
L APPENDIX A I
IESCRIPTIN OF BPmmr. IIRP COMEUMt PRXRAM J
~
~A. Ptuutam and Reoort Descrioticm
\
- 1. 'Ihe Bedtel IIRr omputer prwtam is used to determine the integrated leakage rate of a nuclear primary containment structure. '1he prwtam is used to ocupute leakage rate based on input values of time, free air volume, containment atmosphere total pressure, drybulb temperature, and dewpoint temperature (water vapor pressure).
Isakage rate is conputed using the Absolute Method as defined in l ANSI /ANS 56.8-1987, " Containment System Isakage Testing Requirements" and BMOP-1, Rev 1, "7bsting Criteria for Integrated Isakage Rate Testing of Primary Containment Structures for Nuclear Power Plants".
'Ibe 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 testire period using one of two ocmputational methods, yielding three different report printouts.
- 2. In the first printout, the Total Time Report, leakage rate is emputed 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. 'Ibese individually camputed leakage rates are statistically averaged usirg linear r% tussion by the method of least squares. 'Ibe 'Ibtal Time Method is the ran*2tional technique upon which the short duration test criteria of Bi 'IOP-1, Rev 1, "Testirq Criteria for Integrated Isakage Rate Testing of Primary Contalment Structures for Nuclear Power Plants," are M =d.
- 3. 'Ihe second printout is the Mass Point Report and is based on the Mass Point Analysis Technique rkwribed in ANSI /ANS 56.8-1987, "Ctritainment System Isakage Testing Requirements". The mam of dry air in the containment is emputed at each data point (time), using the Ideal Gas Law, frm 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. Isakage rate is determined from the statistically derived slope and intercept of the r%tession line. l
- 4. 'Ihe third printout, the Trend Report, is a sumary of leakage rate values based on Total Time and Mass Point computations presented as a function of number of data points and elapsed time (test duration).
The Trend Report provides all leakage rate values required for ccraparison to the acceptance criteria of Bi-TOP-1 for conduct of a l short duration test. !
A-1
V 1 .
5.. S e program generatas a predictor; a w t based on "Suggestad critaria for a Short Duration IIRI", 'hd Brt:wn and louis Estanssaro, .
h.v- Mirus of the First E.dkMs en OcutaiW Testim, January . !
18,1982. Se " predictor" is an. estimate of the upper bound at the l diange in mass point calculated leakage rate whidt will occur during the next four hatr:s. Se estimata is had crt the mass point i' m1mlated leakage ratas and 95% UC[s during the previous four hours.
- 6. Se program is. written in a high level larguage and designed for use cm a mid-yater with direct data irput fran the data acquisition system. Brief descriptions of program use, formulae used for leakage rate ocmputations, and program logic are provided in the following V parmsaga.
- 7. If drybulb and dewpoint tauperature sensors should fail durisq the test, the data from the sensor (s) are not used. S e volume fractions for the rmairling sensors are r@ and reloaded into the l rwta= for use in ensuing leakage rata amputations. Se program must hava' the capabilities of. reassigning volume fraction and recalculate values during the test.
l B. Explanation of hwiam
- 1. Se IIRF canputer program is written, for use by experienced IIRP personnel, to determine containment integrated leakage rates haamrt on the Absolute Method described in ANSI /ANS 56.8-1987 and IN 'IOP-1.
- 2. Information loaded into the sv:p- prior to or at the start of the test should include but not limited to :
- a. Number of containment a'Wm. drybulb temperature sensors, dowpoint temperature (water vapor pressure) sensors and pressure gages to be used in leakage rate ocmputations for the specific test
- b. Volume fractions assigned to endt of the above sensors
- c. Calibration data for abcne sensors
- d. Test title .
i i
- e. Mavi== allowable leakage rate at test pressure
- 3. Data received frcan the data acquisition system during the test, and used to computa leakage rates: I
- a. Time and data .
- b. Ocsth atacerdsre drybulb temperatures 3
}
A-2
L ,
- c. Containment c.tmosphere pressure (c)'
)
- d. Containment ato@#re dewpoint temperatures
- e. . Contalment free air volume.
- 4. After all data at a given time are received, a Sunnary of Measured Data report (refer to " Program logic," Paragraph D, " Data" optim
-M) is printed. .
C. TmM Rate W*
j
- 1. Cagutaticais Usirq the 'Ibtal Time Method:
- a. Measured leakage rate from data:
(1)
PVgi=WW1 1 (2)
Pi Vg = W i ni 2400 (W1-W) i (3)
Ati W1 Solving for W3 and Wi and substitutirq equations (1) and (2) into (3) yielos:
= 1- (4)
Li ati ( TPVi11)
W re W,Wi 1 = Weight of cxxitained mass of dry air at times ti j ard t i
, rWdvaly, Iba.
T,Ti 1 = Containment a'Were drybulb temperature at i times t i and t i, respectively, 'R. l P,Pi 1 = cxx1tainment M1 pressure of W dry & w@M of h atmosphere at times ty and t ,
i rydvaly, psia.
y and V'Y 1 i = Containment free air volume at times t t i, rq+11vpy (constant or variable during the test), ft .
st and ith data points respectively, hr.
t,ti i = Time at 1 J Ati = Elapsed time from ti to t i, hr.
R = Specific gas constant for air = 53.35 ft.lbf/lbm.*R.
Li = Messured leakage rate canputed during time interval ti to t ,iwt.%/ day.
)
A-3
h
(
To reduce truncaticri error, the computer program uses the
-following equivalent fornula:
-2400 ( AWi j att (W1) w ere AWi _
Wi-W1 N1 W1 AP aV ATi i+ i+ AP iAVi PV Ty Py V1 yi -. .
aTi 1 +
Ty api =Pi-A vt = ViT1 ATi=Ti- 1
- b. Calculated leakage rate fr m r%i s ion analysis:
(5)
E=a+ baty w ere E=Calculatedleakagerate,wt.%/ day,asdeterminedfromthe r%tession line.
(6) a=(ILi - b I A t i)/N N(IL 1At i) - (Iy)(Eat i)
(7) b= 2 N(I a ti ) - ( E at i)2 N = Number of data points.
N I= I i=1
- c. 95% upper confidence limit on the calculated leakage rate:
LN1 = a + b a tN + S-L A-4
l l
l l
uhere IXL = 95% upper confidence limit wt.%/ day, at elapsed time aty .
I l
For a tg < 24 t, ((I Li2 - a ILi- b IL Ai t )/(N-2) )V2 l
S- = i (1 + 1 + ( a tN - At)2 / (IAti2 - (Iot )2/N))
i W (9a)
N where ts= 1.95996 + 2.37226 + 2.82250 ;
N-2 (N-2)d 1
For atN 2 24 S-g =t s ((ELi - AIL 1- b E Liat )/(N-2))1/2 i 1/2 (1 + ( o ti - AE)2 / (IAti2 - (It )2/N)] i (9b)
N 1.6449(N-2)2 + 3.5283(N-2) + 0.85602 where t , =
(N-2)2 + 1.2209(N-2) - 1.5162
~
1g = calculated leakage rate omguted usirq equation (5) at total elapsed time at ,twe.4/ day.
At = Iati j N
l
- 2. Car:tutation usire the Mass Point Method
- a. Contained mass of dry air frtzn data: f Wi = 144 P Vii (10)
RTg where All symbols as previously defined.
1 i
A-5 i I
- b. Calculated leakage rate fran regression analysis, W = a + bat E .= -2400 b (11) a where E = calculated leakage rate, wt.%/ day, as determined from the regressim line.
(12) a =
(IWi - bIat i)/N N(IWi Ati ) - (IWi)(Eat i) ,
d N(I Ati ) - (I At i)# ,
ati= Total elapsed time at time of i th data point, hr. .
N = Number of data points.
= contained mass of dry air at ith data point, Ilma, Wi as couputed fr a equation (10).
N I = I i=1 To rMr* truncation error, the couputer p%sa= uses the folloWing equivalent fomil Ation:
AWi b -
(14) a = Wy 1 + (I -
-I At i)/N W1 W1 .
AWi AWi N (I At)-I i
W1 Iati W1 (13) b =
wi 2
. N(Iati ) - (Iat i)2 .
AWi e where is as previously defined.
W1
- c. 95% upper confidence limit.
-2400 (16)
UdL = (b - Sb) a A-6
[,
- i UCL = 95% upper confidence limit, wt.4/ day.
I g l/2 (NIAti2 - (I At i)2)l/2 (17) 1.6449 (N-2)2 + 3.5283 (N-2) + 0.85602 when t, = -
(N-2)2 + 1.2209 (N-2) - 1.5162
% IWi - (a + b Ati))2 W
s=
, N-2 .
~
h
= W1 I ( AWiN1)2 _ g 3 g 3 wig 1))2jg .
)N-2 N
[I( AWi N1 ) Ati- I( AW i N1 )(I Ati )N)I (18) 2 I( A ti ) - (I A t )2/N i .
- d. Pradir+en :
2[ GurL) + 4 (l Al + 2 S3 ))
100 la whem UCL = 95% upper confidence limit of mass point calculated leakage rate at end of test.
L = Mass point calculated leakage rate at end of test.
Ia - Allowable leakage rata.
B = Value of linear regmssion analysis slope of mass point calculated leakage rate vs. time for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of test data.
M I 4 hr Imi Ati-I4 hr gI 4 hr Ati (19)
B =
2 MIAti -(I A ti)2 4 hr 4 hr A-7
dure sg = Linear repassion analysis stardard deviation of slope.
I 4 hr I Imi - B 4hr Iai - A 4hr I Iai Ati (20)
Sg =
2 M
(M-2) (M I At I At)2) 4 hr i - (4 hr i Mare -
A' =
M I
4 hr i-BI4 hr Ati
, . (21)
Imi
= mass point calculated leakage rate evaluated minJ data qp to time A t i.
4 hr = sumation over last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of test data.
N I = I N-M+1 M = nunber of data points for last 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> of test.
In terms of elapsed time, At and mass poigcaldated leakage ;
time interval.
rate Imi are calculated at the end of the i
)
A-8
.--_-_--_--_____-_-____--_---____-_a
F f
- l. o. r tm u 1
- 1. 'Jhe Bechtal IIRP ocmputer program logic flow is controlled by a set
[
of user opticris. Same user options and brief hiptions of their i l associated functions are presented below.
OPTICH CCM9ND FUNCTICH After starting the sujtaun executicri, the user either enters the rame of the file cantaining previously entered data or initialized a nea data file.
DNIA Enables user to enter raw data. When the systen requests values of time, volume, tanperature, pressure and vapor pressure, the user enters the appropriate data. After ocmpleting the data entry, a summary is printed out. 'Ihe user then verifies that the data were entered correctly. If errors are detected, the user will then be given the wrtunity to correct the errors. After the user verifies that the data were entered u.u.t#dy, a Corrected Data Stmanat'f Report of time, data, average temperature, partial pressure of dry air, and water vapor pressure is printed.
TREND A Trerd Report is printed.
'IUIAL A Total Time Report is printed.
MASS A thss Point Report is printed.
TERM Enables user to sign-off temporarily or permanently. All data is saved on a file for restarting.
CDRR Enables user to correct previously entered data.
LIST A Sumary Data Report is printed.
ISM) Enables the canputer to receive the next set of data frun the data acquisition system dira?dy.
PIDF Enables user to plot sumary data, individual sensor data or air mass versus time.
na rrE Enables user to delete a data point.
INSERP Erables user to reinstate a previously deleted data point.
A-9
m :t' J
l OPTICM '
CtMEND FUNCTION VOLTRA Enables user to change volume fractions.
PRED A predictor report is printed.
TDE Enables the user to specify the time interval for a report or plot. !
VERF Enables the user to irput 3W leakage rate and calculated IIRP leakage rates at start of verification test.
1 E. hter Puerwt and Data Printout SLM ERY DA3A RE1CRP 1he 9=m=7 Data report presents the actual data used to calculated leakage rates by the various methods hibed in the Otmputer Fr% m" section of this report. The six column baarlinjs are TIME, IATE, TEMP, PRESSURE, VPRS, and VOIIME and contain data defined as follows:
- 1. TDE: Tine in 24-hour notations (hours and minutes).
- 2. DATE: \- Calendar date (month and day).
- 3. TEMP: Contairnent weighted-average drybulb temperature in ahelute units, degrees Rankine (*R).
- 4. PRESSURE: Partial pressure of the dry air W-ata of the containment a' Ware in absolute units (psia).
- 5. VPRS: Partial pressure of water vapor of the ocntalment ahnewpbers in absolute units (psia).
- 6. VOIDME: Containment free air volume (a1 ft.).
- 7. AIRMASS: Cala11ated dry air mass (lbm).
- 8. ADEX: May4== allowable leakage Rate (L awt%/ day)
- 9. VRA1TE: 7btal Time calallated leakage + Verification flow 4 W leaNage (wt%/ day)
- 10. VRATEM: Mass Point calculated leakage + Verificatico flow iw - a3 leakage (wt%/ day) 1 A-10
= _ _ - _ - - - - _ - - e
1- .
p ESS POINT RDNP
'Ihe Mass Point Report gui As leakage rate data (wt%/ day) as detamined by the Mass Point Method. 'Ibe " Calculated Isakage Rate" is the value determined fran the regression analysis. 'Ibe "Contalment Air Mass" l
values are the masses of dry air in the containment (llan). 'Ihase air l m , determined frun the Ideal Gas Iaw, are used in the regressian I analysis.
'IomL TDE RDCRP
'Iha 'Ibtal Time Report gosimits data leakage rate (wt%/ day) as determined by the 'Ibtal Time Method. 'Ihe "Cala11ated Imakage Rate" is the value determined fran the regression analysis. 'Ihe " Measured Iaae Rates" L are the leakage rate values determined using 'Ibtal Time calculations.
1,
'Ihese values of leakage rate are used in the regression analysis, rc _
p
'IREND RDORP
'Ihe Trend Report presents leakage rates as determined by the Mass Point ani 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.
PREDICITR RDORP
'Iha predictor reports presents a praiidari upper bound on the change in calculated mass point leakage rate over the next four hours.
A-11
_ _ _ _ . _ i
APPENDIX B INSTRUMENT ERROR ANALYSIS i
i 1
ISG CALCULATION
( ANSI /ANS 56.8 - 1987 )
CALIBRATION DATA SENSOR DISPLAY
- OF SENSORS SENSITIVITY (E) REPEATABILITY (r)
TEMPERATURE (T) 21 0.1000 deg. F 0.0100 deg. F PRESSURE (P) 2 0.0003 psia 0.0003 psia VAPOR PRESS (Pv) 6 0.1000 deg. F 0.0100 deg. F
' LENGTH OF TEST (t) 8.25 hrs PRESSURE (P) 26.20 psia TEMPERATURE (T) 542.8 deg. R VAPOR PRESS (Pv) 0.01394 psi /deg. F (at 74 deg. F)
La 0.437 wt%/ day.
INSTRUMENT MEASUREMENT ERRORS 2 2 1/2 1/2 eT . [(ET) +-(rT) ] /[# of sensors]
eT . 0.02193 deg. F 2 2 1/2 1/2 eP = [(EP) + (rP) ] /[# of sensors] l l- eP . 0.00030 psia l 2 2 1/2 1,'2 ePv . [(EPv) + (rPv) ] /[# of sensors]
ePv . 0.00057 psia INSTRUMENT SELECTION GUIDE.
2 2 2 1/2 ISG 2400/t[ 2(eP/P) + 2(ePv/P) + 2(eT/T) ]
ISG . 0.019 wt%/ day
.25La . 0.109 wt%/ day
,,.... - . , -.., g APPENDIX C ILRT DATA l
l l
l u_-_-
%.' s ese c
g- ..
-0 Qll g __
E E -- b d m i51 10 -
1 s e E $ n u --
.e-a pE$ g w GQ M W G \
c w a -
W
] T h -- I
- E U
- lS --
5
~
3 a .
g j
i~ / _
q g
G E E -- )
> g )
E: b ..
s m
a - i i
un ..
l N . . . . . . . . .
s a s g g <
n cn mi N N N N N N N N N N N N 4 1 1
_ T
_ S
_ E T
N O
I T
_ A C
6 1
I F
I 4 R
_ E U
E T
_ T A B D
. L 5
I F4 9 3 8S1 9E 1EE
_ RM
_ NGI
_ OET I D T D T AEN S TRE E
_ SU T
_ T RA5 A AR1 EE4 E LP P CM Y UEE T NTT A
FED LG UA0 GR0 E0 DV2 NA ' ll I A - E B M H G I C T I T
T A R Z A I T L S I B
A T
S ll r
0 0 0 0 0 0 0 0 0 0 6 5 4 3 2 1 1 1 1 1 7 7 7 7 7
' ;))l l11 ;
T S
E T -
~
l N -
O I
T A
C I
_' ^
=
6 F :
I F1 -
4 R -
- E U _
EE - _ _
S
= GT R TAA _
_ U O
ERD LE H IV5 D A4 E - : 5 9 3 L 7 8&1 9
12E I
A F
T=- :
7 1
2N -
NI 1 -
O1T I
TSD R
O T _
y, w _ - _
=
E ARN S S TOE N E - N
>=_
SS E T _ : I N S - T RE5 A _ D AS1 E 4 E P
3_ -
_ : E S
LE
~
CR j Y P
- A UUE T - L _
NTT _
FRD LE AA -
/-_~:
E
~
UP0
- GN0 DT2 N
ABE E0 i
"=
pp,t :
- RLN GUI BT
~[NO I
Y RT T
A l'w- '-
y_~
DR Z :
A I
= pf' T L S I B
^
.[
A T
S \;-
x
- s
, g -
0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 4 0 6 2 8 4 8 8 7 7 6 6 fI!, t
- i l
4 "
T :
S E
T N
O I
T :
A C
I 6 F I
1 4 R E
U :
E S T R T A U E D :O L H I 5 4 :
5 9 3 7 8 1
- 9) 7 1RE :1 I M NAI =
O T I Y :
TRD T E
ADN S N T( E E I S T :
T A
RI 5 A AS1 EP4 E F :E D
L P S CE Y P URE T A NUT :L SA -
E FSD LE :
UB0 GP0 D
0 2 - li N, :
N 3 A E R M 1 G I O :
T I
_ T A
T R
_ Z :
A I T L S I B :
A T
S - - . - . - .
0 0 0 0 0 0 0 9 8 7 6 5 3 2 2 2 2 Z.
6 6 6 6 6 6 2 2 2 2 2 2
1 llll T :
S E
T N
O I
T :
A
) C M I O6 F :
T1 I T4 R O
B -~ E U :
R D :O LP H I O5 T4 5 9( 3 :7 8 1 9A 7 1IE : 1 SM NPI O T =
I Z :
T D T ADN S E TNE E M SA T : I T
R ,5 A AE1 D EG4 E : E LA P S CR Y P UEE T A NUT :
L AA E F ,D L
U10 :
G 0 S0 DR2 :
NO lI ! l ASE RNM N GEI O :
ST I T
R A P T
' - ~ - .
S - ' .
0 0 0 0 0 0 2 0 8 6 4 2 6 6 5 5 5 5 6 6 6 6 6 6 2 2 2 2 2 2
7E% '
' s i, . ,j.-
l l
- l. ,
I l- 13
- '~
% g m
N ..
8
@ b --
A m T E W
D --
l;; g . ..
a
- .m m ,
w . . <
N N C W. - -
N
-g bkN 61 bNO b W
C DC Z M E
> W W .m M H .
N
% M' C m e oc 4 .W MAf M .
J k D DC > A CW H C kH
-J I 3 82 \ ..
j 1
'd .
E
- 5 --
> m ;
H l
> l M
- I C A M Crt . .
C H
m '
l l l l o o o o Y N @ T
- m. m. M. N. N. N.
%. I
\' ~
l\ 0
'l ~
l "
\ @
l - --
l i 6 e C --
wG Tc g --
ul \ a
-g mHE s y n -
d "Em- s
" 1 --s
$*M e:
9g ; --
E"C n CE. -
E8E 8 - um e
g , m e E
-g ng - -
ang e -
$M* E "N* 4 E 5 UEm g- ,
wm2 i
)
sgE
% i( --
1 g
l EMEM =
= l wec --
l E- e \
a5 N --
1 E d j g --
- i
. e , e . i e -
g o o o: o o o 8 8 8- 8 8 ;
l
r STABILIZATION GRAND GULF NUCLEAR STATION 1989 IIRT
SUMMARY
DATA ALMAX = .437 VOLUME = 1670360.
VRATET = .559 VRATEM = .557 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS 2000 415 531.135 26.2931 .2459 1670360.0 223190.6 4 2015 415 530.903- 26.2892 .2463 1670360.0 223254.3 2030 415 531.004 26.2924 .2513 1670360.0 223239.7 2045 415 530.989 26.2897 .2559 1670360.0 223222.7 2100 415 530.961 26.2891 .2567 1670360.0 223229.0 2115 415 530.925 26.2861 .2602 1670360.0 223219.3 2130 415 530.907 26.2840 .2628 1670360.0 223208.3 2145 415 530.876 26.2825 .2652 1670360.0 223208.9 2200 415 530.852 26.2806 .2677 1670360.0 223202.9 1 2215 415 530.837 26.2791 .2698 1670360.0 223196.5 1 2230 415 530.821 26.2777 .2715 1670360.0 223191.5 2245 415 530.807 26.2761 .2737 1670360.0 223183.4 2300 415 530.801 26.2753 .2754 1670360.0 223179.5 2315 415 530.797 26.2741 .2772 1670360.0 223171.2 2330 415 530.794 25.9721 .2788 1670360.0~ 220607.2 2345 415 530.793 26.2724 .2804 1670360.0 223158.3 0 416 530.799 26.2722 .2820 1670360.0 223153.5 f L
r b i l
I 1
['.l L.
y:
-GRAND GULF NUCLEAR STATION 1989 ILRT TEMPERATURE STABILIZATION l
~FROM A STARTING TIME AND DATE OF: 2000 415 1989 i
TIME' ' TEMP ANSI. BN-TOP-1
. (HOURS) (8R) AVE AT AVE AT DIFF AVE AT (4 HRS)' (1HR). (2 HRS)
.00 531'.135:
.25' 530.903
.50- 531.004
.75 _530.989 1.00 :530.961 1.25 .530.925 1.50: 530.907' l'.75 530.876
'2.00 530.852 .141*
2.25 530.837- .033*'
2.50 .530.821 .091*
I 2.75. 530.807 .091*
' .080* I 3.00- 530.801
-3.25 530.797 .064*
3.50 530.794' .057*
3.75- 530.793 .041*
-4.00 530.799 .084 .002 .082* .026*
- INDICATES TEMPERATURE STABILIZATION HAS BEEN SATISFIED t
{
u
.6
TYPE A TEST GRAND GULF NUCLEAR STATION 1989 ILRT
SUMMARY
DATA ALMAX = .437 VOLUME = 1670360.
VRATET = .559 VRATEM = .557 TIME DATE TEMP PRESSURE VPRS VOLUME AIRMASS 0 416 530.799 26.2722 .2820 1670360.0 223153.5 15 416 530.798 26.2718 .2836 1670360.0 223150.9 30 416 530.807 26.2720 .2845 1670360.0 223149.0 45 416 530.820 26.2712 .2864 1670360.0 223136.3 100 416 530.820 26.2710 .2877 1670360.0 223135.4 115 416 530.825 26.2713 .2889 1670360.0 223135.7 130 416 530.832 26.2713 .2903 1670360.0 223132.9 145 416 530.840 26.2715 .2916 1670360.0 223130.9 200 416 530.861 26.2734 .2926 1670270.0 223126.3 215 416 530.870 26.2746 .2941 1670180.0 223120.7 230 416 530.884 26.2758 .2954 1670090.0 223112.9 245 416 530.895 26.2776 .2966 1670000.0 223111.5 300 416 530.894 26.2793 .2978 1669910.0 223114.3 315 416 530.916 26.2809 .2991 1669820.0 223106.3 330 416 530.924 26.2811 .3002 1669820.0 223105.0 345 416 530.933 26.2812 .3012 1669820.0 223102.1 400 416 530.938 26.2810 .3024 1669820.0 223097.9 l 415 416 530.950 26.2810 .3036 1669820.0 223093.2 430 416 530.956 26.2811 .3047 1669820.0 223091.7 445 416 530.958 26.2813 .3059 1669820.0 223092.4 500 416 530.969 26.2818 .3070 1669820.0 223091.4 515 416 530.972 26.2819 .3079 1669820.0 223091.3 530 416 530.980 26.2818 .3092 1669820.0 223087.0 545 416 531.000 26.2818 .3100 1669820.0 223078.7 600 416 531.004 26.2820 .3108 1669820.0 223078.7 615 416 531.010 26.2818 .3123 1669820.0 223074.5 630 416 531.017 26.2823 .3129 1669820.0 223076.1 645 416 531.025 26.2825 .3138 1669920.0 223074.6 700 416 531.041 26.2826 .3150 1669820.0 223068,1 715 416 531.053 26.2826 .3160 1669820.0 2230VJ.3 730 416 531.055 26.3828 .3167 1669320.0 223064.0 745 416 531.063 26.2826 .3178 1669820.0 223058.6 ,
800 416 531.072 26.2829 .3185 1669820.0 223038.0 i 815 416 531.077 26.2826 .3195 1669820.0 223053.1 I l
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J, TYPE A TEST GRAND' GULF NUCLEAR STATION 1989 ILRT LEAKAGE RATE (WEIGHT PERCENT / DAY)
MASS POINT ANALYSIS TIME AND DATE AT START OF TEST:- 0 416 1989 l TEST DURATION: 8.25 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS AVERAGE MASS (R) (PSIA) MASS (LBM) (LBM) LOSS (LBM/HR) -
0 530.799 26.2722 223153.5 15 530.798 26.2718 223150.9 2.6 10.5 30 530.807 26.2720 223149.0 1.8 8.9 45 530.820 26.2712 223136.3 12.7. 22.9 100 530.820 26.2710 223135.4 .9 18.1 115 530.825 26.2713 223135.7 .3 14.2 130 530.832 26.2713 223132.9 2.8 13.7 145 530.840 26.2715 223130.9 2.0 12.9 200 530.861 26.2734 223126.3 4.6 13.6 215 530.870 26.2746 223120.7 5.6 14.6 230 530.884 26.2758 223112.9 7.8 16.2 245 530.895 26.2776 223111.5 1.4 15.3 300 530.894 26.2793 223114.3 -2.8 13.1 315 530.916 26.2809 223106.3 8.0 14.5 330 530.924 26.2811 223105.0 1.3 13.9 345 530.933 26.2812 223102.1 2.9 13.7 400 530.938 26.2810 223097.9 4.2 13.9 415 530.950 26.2810 223093.2 4.8 14.2 430 530.956 26.2811 223091.7 1.5 13.7 445 530.958 26.2813 223092.4 .7 12.9 500 530.969 26.2818 223091.4 1.0 12.4 I 515 530.972 26.2819 223091.3 .1 11.8 530 530.980 26.2818 223087.0 4.2 12.1 545 531.000 26.2828 223078.7 8.3 13.0 600' 531.004 26.2820 223078.7 .1 12.5 615- 531.010 26.2818 223074.5 4.2 12.6 630 531.017 26.2823 223076.1 -1.6 11.9 !.
645 531.025 26.2825 223074.6 1.5 11.7 700 531.041 26.2826 223068.1 6.5 12.2 715 531.053 26.2876 223063.3 4.8 12.4 730 531'.055 26.2028 223064.0 .7 11.9 745 531.063 26.2826 , 223058.8 5.2 12.2 800 531.072 26.2829 223058.0 .8 11.9 815 531.077 26.2826 223053.1 4.9 12.2 FREE AIR VOLUME USED (CU. FT.) =1670360.0 REGRESSION LINE INTERCEPT (LBM) = 223148.5 SLOPE (LBM/HR) = -11.6 MAXIMUM ALLOWABLE LEAKAGE RATE = .437 75% OF MAXIMUM ALLOWABLE LEAKAGE RATE = .328 :
THE UPPER 95% CONFIDENCE LIMIT = .129 {
THE CALCULATED LEAKAGE RATE
= .125 i
..D.
TYPE A-TEST-GRAND GULF NUCLEAR STATION 1989 ILRT LEAKAGE. RATE (WEIGHT PERCENT / DAY)
TOTAL TIME. ANALYSIS-TIME AND DATE AT-START OF TEST: 0 416 1989 TEST DURATION: 8.25 HOURS TIME TEMP- PRESSURE MEASURED.
.(R) (PSIA)' LEAKAGE RATE 0- 530.799 26.2722 15 530.798 26.2718 .113 30 530.807' 26.2720- .096 45 -530.820 26.2712 .246 100 530.820 26.2710 .195 115. 530.825 26.2713 .153
'130, 530.832 26.2713 .147 145 530.840 26.2715 .139-200 530.861. 26.2734 .146 215- 530.870 26.2746 .157 230 530.884 26.2758 .175 '
245 .530.895. '26.2776 .164 300 530.894 26.2793 .141 315 530.916 26.2809 .156 W 330 530.924 26.2811 .149 345 530.933 26.2812 .147 400- 530.938 -26.2810 .149 415- 530.950 26.2810 .153 430 530.956- 26.2811 .148 445 530.958 26.2813 .138 500 530.969 26.2818 .134 515 530.972 26.2819 .127 530 530.980 26.2818 .130 545 531.000 26.2818 .140 600 531.004 26.2820 .134 615- 531.010 26.2818 .136 630 S31.017 26.2823 .128 645 531.025 26.2.825 .136 L 700 531.041 26.2826 .131 715 531.053 26.2826 .134 l 730 531.055 26.2828 .128 745 531.063 26.282'6 .131 SCO 531.072 26.2829 .128 815 531.077 26.2826 .131 MEAN OF THE. MEASURED LEAKAGE RATES = .144 MAXIMUM ALLOWABLE LEAKAGE RATE = .437 -I 75% OF MAXIMUM ALLOWABLE-LEAKAGE RATE = .328-E' THE UPPER 95% CONFIDENCE LIMIT = .178 THE CALCULATED LEAKAGE RATE = .127 r
l l TYPE A TEST GRAND GULF NUCLEAR STATION 1989 ILRT '
l TREND REPORT j TIME AND DATE AT START OF TEST: 0 416 1989 i
No. END TOTAL TIME ANALYSIS MASS POINT ANALYSIS PTS TIME MEAS. CALCULATED UCL CALCULATED UCL i 2 15 .113 .113 99.000 .113 99.000 l 3 30 .096 .096 99.000 .096 .179 4 45 .246 .218 .880 .229 .457 l 5 100 .195 .222 .521 .218 .324 6 115 .153 .196 .440 .182 .259 7 130 .147 .179 .378 .162 .219 8 145 .139 .165 .335 .148 .192 9 200 .146 .159 .306 .145 .178 10 215 .157 .159 .289 .148 .174 11 230 .175 .165 .283 .159 .182 12 245 .164 .166 .274 .161 .181 13 300 .141 .160 .262 .153 .171 14 315 .156 .159 .255 .153 .169 15 330 .149 .157 .247 .151 .165 16 345 .147 .155 .240 .149 .161
'17 400 .149 .154 .235 .148 .159 18 415 .153 .153 .231 .149 .158 19 430 .148 .152 .227 .148 .156 20 445 .138 .149 .221 .145 .153 21 500 .134 .146 .216 .141 .149 22 515 .127 .142 .210 .136 .145 23 530 .130 .139 .205 .133 .142 24 545 .140 .139 .203 .134 .141 25 600 .134 .137 .199 .132 .140 26 615- .136 .136 .197 .132 .138 27- 630 .128 .134 .193 .130 .136 28 645 .126 .132 .190 .128 .134 29 700 .131 .131 .187 .127 .133
=30 715 .134 .130 .185 .127 .133 31 730 .128 .129 .183 .126 .131 32 745.- .131 .128 .181 .126 .131 33 800 .128 .127 .179 .125 .130 34 815 .131 .127 .178 .125 .129 i
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VERIFICATION TEST GRAND GULF NUCLEAR STATION 1989 ILRT
SUMMARY
DATA i ,
ALMAX = .437 VOLUME = 1670360.
VRATET = .559 VRATEM = .557 TIME'DATE TEMP PRESSURE VPRS VOLUME AIRMASS 830. 416 531.092 26.2821 .3204 1669820.0 223042.8 845' 416 531.090 26.2815 .3209 1669820.0 223038.1 900 416 531.090 26.2801 .3219 1669820.0 223026.6 915 416' '531.097- 26.2793 .3226 1669820.0 223017.4 930 416 531.091 26.2784 .3231 1669820.0 223011.5 945- 416 531.098 26.2772 .3239 1669820.0 222999.0 1000 416 531.097 .26.2768 .3243 1669820.0 222995.6 1015 416 531.105 -26.2753 .3252 1669820.0 222979.5' 1030. 416 531.116 26.2743 .3259 1669820.0 222966.4 1045 416 531.115 26.2734 .3265 1669820.0 222959.3 1100 416- 531.124 26.2724 .3272 1669820.0 222946.8-1115 416 531.129 26.2709 .3281 1669820.0 222932.2.
1130- 416 531.137- 26.2705 .3283 1669820.0 222925.2 1145 416 531.151 26.2689 .3292 1669820.0 222906.0 1200 416 531.158 26.2684 .3294 1669820.0 222898.9 1215- 416 531.168 26.2670 .3302 1669820.0 222882.6 1230 416 531.166 26.2657 .3309 1669820.0 222872.5 1245 416 531.182 26.2648 .3312 1669820.0 222858.5 1300 416 .531.183 26.2638 .3316 1669820.0 222849.6 1315 416 531.193 26.2630 .3321 1669820.0 222837.9 1330 416 531.195 26.2619 .3325 1669820.0 222828.4 1345 416 531.213 26.2607 .3331 1669820.0 222810.8
l VERIFICATION TEST
-GRAND GULF NUCLEAR STATION 1989 ILRT LEAKAGE RATE (WEIGHT PERCENT / DAY)
MASS POINT ANALYSIS TIME AND DATE AT START OF TEST: 930 416 1989 TEST DURATION: 4.25 HOURS TIME TEMP PRESSURE CTMT. AIR MASS LOSS AVERAGE MASS (R) (PSIA) MASS (LBM) (LBM) LOSS (LBM/HR) 930 531.091 26.2784- 223011.5 945 531.098 26.2772 222999.0 12.5 50.0 1000 531.097 26.2768 222995.6 3.4 31.8 l 1015 531.105 26.2753 222979.5 16.1 42.7 1030 531.116 26.2743 222966.4 13.0 45.0 1045 531.115 26.2734 222959.3 7.1 41.7 i 1100 531.124 26.2724 222946.8 12.5 43.1 1 1115 531.129 26.2709 222932.2 14.6 ~ 45.3 1130 531.137 26.2705 222925.2 7.0 43.1 1145 531.151 26.2689 222906.0 19.1 46.9 1200 531.158 26.2684 222898.9 7.1 45.0 1215 531.168 26.2670 222882.6 16.3 46.9 1230 531.166 -26.2657 222872.5 10.1 46.3 1245 531.182 26.2648 222858.5 14.0 47.1 1300 531.183- 26.2638 222849.6 8.9 46.2 1315 531.193 26.2630 222837.9 11.8 46.3 1330 531.195 26.2619 222828.4 9.5 45.8 1345 531.213 26.2607 222810.8 17.5 47.2 j FREE AIR VOLUME USED (CU. FT.) =1670360.0 REGRESSION LINE .
INTERCEPT (LBM) = 223015.1 SLOPE (LBM/HR) = -47.3 J VERIFICATION TEST LEAKAGE RATE UPPER LIMIT =
.666 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT = .448 THE CALCULATED LEAKAGE RATE = .509
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u___1__________ _ _ _ _ _ _ _ . _ _ . _ . _ . _ _ . . _ _ _
VERIFICATION TEST '
GRAND GULF NUCLEAR STATION 1989 ILRT LEAKAGE RATE (WEIGHT PERCENT / DAY)
TOTAL TIME ANALYSIS L
TIME AND DATE AT START OF TEST: 930 416 1989 TEST DURATION: 4.25 HOURS TIME TEMP PRESSURE MEASURED (R) (PSIA) LEAKAGE RATE 930 531.091 26.2784 945 531.098 26.2772 .538 1000 531.097 26.2768 .342 1015 531.105 26.2753 .459 1030 531.116 26.2743 .485 1045 531.115 26.2734 .449 1100 531.124 26.2724 .464 1115 531.129 26.2709 .487 1130 531.137 26.2705 .464 1145 531.151 26.2689 .504 1200 531.158 26.2684 .485 1215 '531.168 26.2670 .504 1230 531.166 26.2657 .499 1245 531.182 26.2648 .507 1300 531.183 26.2638 .498 1315 531.193 26.2630 .498 1330 531.195 26.2619 .493 1345 531.213 26.2607 .508 MEAN OF THE MEASURED LEAKAGE RATES = .481 VERIFICATION TEST LEAKAGE RATE UPPER LIMIT = .668 VERIFICATION TEST LEAKAGE RATE LOWER LIMIT = .450 THE CALCULATED LEAKAGE RATE = .511 i
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It VERIFICATION TEST GRAND GULF NUCLEAR STATION 1989 ILRT TREND REPORT j' TIME AND DATE AT START OF TEST: 930 .416 1989 No. END- TOTAL TIME ANALYSIS MASS POINT ANALYSIS PTS. TIME MEAS. CALCULATED UCL CALCULATED UCL 2 945 .538 .538 99.000 .538 99.000 3 1000 .342 .342 99.000 .342 1.309 4 1015 .459 .407 1.644 .428 .636 5 1030 .485 .450 .957 .472 .585 6 1045 .449 .447 .767 .460 .529 7 1100 .464 .454 .696 .465 .511 8 1115 .487 .469 .670 .480' .518 9 1130 .464 .469 .641 .476 .504 10 1145 .504 .484 .638 .492 .521 11 1200 .485 .487 .627 .493 .516 12 1215 .504 .495 .624 .501 .522 13 1230 .499- .500 .619 .504 14 .522 1245 .507 .505 .616 .509 .525 15 1300 .498 .507 .612 .509 .522 16 1315 .498 .508 .608 .509 17 .521 1330 .493 .508 .603 .507 .517 18 1345 .508 .511 .602 .509 .519
VERIFICATION TEST.
GRAND. GULF NUCLEAR STATION 1989 ILRT TREND REPORT TIME AND DATE AT START OF TEST: 930 416 1989 NO. END TOTAL TIME ANALYSIS MASS POINT ANALYSIS PTS TIME MEAS. CALCULATED UCL CALCULATED UCL 2 945 .538 .538 .99.000 .538 99.000 3 1000 .342 .342 99.000 .342 1.309 4 1015 .459 .407 1.644 .428 .636 5 1030 .485 .450 .957 .472 .585 6 1045 .449 .447 .767 .460 .529 7 1100 .464 .454 .696 .465 .511 8 1115 .487 .469 .670 .480 .518 9 1130 .464 . 469 .641 .476 .504 10 1145 .504 .484 .638 .492 .521 11 1200 .485 .487 .627 .493 .516 12 '1215 .504 .495 .624 .501 .522 i
13 1230 .499 .500 .619 .504 .522 14 1245 .507 .505- .616 .509 . 525 15 1300 .498 .507 .612 .509 .522 16 1315 .498 .508 .608 .509 .521 17 1330 .493 .508 .603 .507 .517 18 1345 .508 .511 .602 .509 .519
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APPENDIX D LLRT DATA i
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APPENDIX D ;
Local leak Rate Test Summary Data Tme B and C Test Results Pneumatic Testing 1
Minimum Pathway Leakare (std cu em/ min)
]
RFO1 RFO2 RFO3 RFO3 i Penetration Description As-12ft As-Left As-Found As-Left 1 Contaimnent Equipment Hatch 0124 0 1 24 79 1 24 0 1 24 ;
2 Upper Personnel Airlock 101 1 27 38 1 34 75 1 34 75 1 34 l 3 Lower Personnel Airlock 0 1 27 136 1 34 0 1 34 0 1 34 4 Fuel Transfer Tube 20 1 24 0 1 24 0 1 24 0 1 24 '
5 Main Stcam Line A 897 1 200 1395 1 300 12,443 1 300 1996 1 200 6 Main Steam Line B 108 1 24 0 1 12 14,734 1 300 0 1 24 7 Main Steam Line C 880 1 200 0 1 24 18,624 1 361 280 1 201 8 Main Steam Line D 0 1 24 0 1 24 0 1 303 0 1 42 9 Feedwater Line A 0 1 29 0 1 42 0 1 42 60 1 24 10 Feedwater Line B 10 1 27 01 42 0 1 42 0 1 42 14 RHR Shutdown Cooling Suction 0 1 34 0 1 34 0 1 24 0 1 24 17 Steam Supply to RCIC Turbine 0 1 34 20 1 34 0 1 34 0 1 34 and RHR Heat Exchangers 18 RHR to RPV Head Spray 0 1 24 0 1 24 0 1 42 0 1 42 19 Main Steam Drain to Condenser 0 1 24 0 1 24 0 1 24 0 1 24 20 RHR A to LPCI 877 1 24 0 1 32 0 1 24 0 1 24 21 RHR B to LPCI O 1 24 40 1 24 0 1 24 0 1 24 22 RHR C to LPCI O 1 34 0 1 24 0 1 34 01 34 23 RHR Pump A Test Return " 0. 0 010 010 010 24 RHR Pump C Test Return " 010 010 19 1 24 010 26 HPCS Pump Discharge to RPV 0 1 34 20 1 34 0 1 34 0 1 34 27 HPCS Pump Test Return " 0+0 0+0 0+0 010 31 LPCS Pump Discharge to RPV 0 1 27 01 34 0 1 34 0 1 34 32 LPCS Pump Test Return " 0+0 0+0 51 24 010 33 CRD Pump Discharge 0 1 34 01 24 261 1 24 261 1 24 34 Contaimnent Purge Supply 0 1 24 0 1 24 0 1 24 0 1 24 35 Containment Purge Exhaust 0 1 24 0 1 34 0 1 24 20 1 34 36 Plant Service Water Return 0 1 24 0 1 24 0 24 0 1 24 37 Plant Service Water Supply 0 1 34 60 1 24 0 1 24 0 1 24 38 Chilled Water Supply 0 1 24 0 1 24 0 1 34 0 1 34 39 Chilled Water Return 01 24 0 1 24 0 1 24 0 1 24 40 ILRT Containment Pressurization 0112 0 1 24 010 0 1 24 41 Plant Service Air 40 1 34 32 1 34 0 1 34 0 1 34 42 Instrument Air 119 1 34 0 1 34 900 1 201 0 1 34 43 RWCU to Main Condenser 0 + 12 0 + 24 0 1 24 0 1 24 44 Component Cooling Water Supply 0 1 17 0 1 24 0 1 24 0 1 24 45 Component Cooling Water Return 39 1 12 10 1 24 0 1 24 0 1 24 47 Reactor Recirculation Post Acci- 0 + 24 39 + 24 0 1 24 0 1 24 dent Sample
" Includes only restricting orifice O-ring seals and their test connection valves. The remainder of the penetration is hydrostatically leak rate tested.
D-1
APPENDIX D (Continued) .
Local 12ak Rate Test Summary Data Tyne B and C Test Results Pneumatic Testing (Continued) r Minimum Pathway l_eakare (std cu em/ min)
- RFO1 RFO2 RFO3 RFO3 Espetration Description' As-Left . As Left As-Found .A1LS[L 49 RWCU Backwash Transfer Pump to 0 1 24 0 1 24 0 1 24 0 1 24 Spent Resin Storage Tank 50 Drywell & Containment Equipment 0124 60 1 24 20 1 24 20 1 24 Drain Sump Pumps Discharge to Aux. Building Transfer Tank 51 Drywell & Containment Floor 0 1 24 0 1 24 0 1 24 0 1 24 Sump Pumps Discharge to Aux.
Building Transfer Tank 54 Upper Containment Pool to and 0 1 11 0 1 24 0 1 24 0 1 24 from Refueling Water Storage Tank 56 Condensate Makeup to Upper Con- 0 1 24 0 1 17 0 1 34 0 1 34 tainment Pool 57 Discharge from Fuel Pool Cooling 0 1 17 0 1 24 20 1 24 20 1 24 and Cleanup System to Upper Containment Pool 58 Inlet Upper Containment Pool 0111 0 1 24 0 1 24 0 1 24 Skimmer Tanks to Fuel Pool Cooling and Cleanup System 60 Auxiliary Building Floor & 0 1 16 0 1 24 271 1 34 271 1 34 Equipment Drain Return 61 Standby Liquid Control Mixing 0 1 16 0 1 34 01 34 0 1 34 Tank (Future Use) 65 Containment Normal Ventilation & 20 1 24 0 1 24 0 1 24 0 1 24 Combustible Gas Control Purge Supply 66 Containment Normal Ventilation & 01 24 01 24 0 1 24 0 1 24 Combustible Gas Control Purge Exhaust 67 RHR Pump B Test Return " 01 0 010 010 01 0 l 70 Automatic Depressurization System 01 34 0 1 24 0 1 24 0 1 24 (Instrument Air) 73 RHR Shutdown Cooling Relief 01 24 01 24 0 1 24 0 1 24 ;
Valve Discharge to Suppression {
Pool 75 RCIC Pump Turbine Exhaust Vac- 20 1 24 01 24 1202 1 24 0 1 24 uum Relief 76B RHR Shutdown Cooling Suction Re- 01 24 0 1 12 0 1 24 0 1 24 lief Valve 81 Reactor Recirculation Post Accident 0124 01 24 0 1 24 0 1 24 Sample
" Includes only restricting orifice O-ring seals and their test connection valves. The remainder of the penetration is hydrostatically leak rate tested.
D-2
1 I
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[ APPENDIX D (Continued) l Local I ==k Rate Test Summary Data Tyne B and C Test Results Pneumatic Testing (Continued)
Minimum Pathway Lenkwe (std cu em/ mini RFO1 RFO2 RFO3 RFO3 Description As-12ft As-12ft As-Found As-Left Penetration 82 ILRT Drywell Pressurization /De- 01 24 0 1 24 0 1 24 01 24 pressurization 83 RWCU Line from Regenerative 885 1 24 0 1 34 0 1 34 0 1 34 Heat Exchanger to Feedwater l 84 Drywell and Containment Chemi- 0 1 24 0 1 24 0 1 24 0 1 24 cal Waste 85 Suppression Pool Cleanup Return 01 42 199 142 300 1 42 100 1 42 86 Deminctuli:ed Water Supply to 0 1 24 0 1 24 01 24 0 1 24 Containment 87 RWCU Pump Suction from Recir- 0 1 24 01 34 60 1 34 60 1 34 culation Loops 88 RWCU Pump Discharge to RWCU 199 1 12 010 01 300 0 1 200 L Heat Exchanger 101C' Drywell Pressure Instrumentation 0 1 12 0124 0 1 24 0 1 24 (Narrow Range) 101F Drywell Pressure Instrumentation 0 1 24 0 1 24 0 1 24 01 24
@de Range) 102D Drywell Pressure Instrumentation 01120 1 24 01 24 0 1 24 (Wide Range)
- 103D Containment Pressure Instruments- 0 1 24 0 1 24 01 24 0 1 24 tion @de Range) 104D Containment Pressure Instruments- 0 1 24 0 1 24 0 1 24 0 1 24 tion @de Range)
Containment Hydrogen Analyzer 0124 01 24 0 + 24 0 + 24 105A Sample 106A Drywell Hydrogen Analyzer Sample 0 124 0 1 24 01 24 0 1 24 106B Drywell Hydrogen Analyzer Sample 0.124 0124 0 1 24 0 1 24 Return 106E . Containment Hydrogen Analyzer 0124 01 12 01 24 0 1 24 g
Sample Return 107B Containment Hydrogen Analyzer 0 1 24 0124 0 1 24 0 1 24 Sample Return 107D Drywell Hydrogen Analyzer Sample 0 1 24 0 1 24 0 1 24 0 1 24 0 1 24 l 107E Drywell Hydrogen Analyzer Sample 0 124 0 1 24 0 1 24 J
Return 108A Containment Hydrogen Analyzer 0124 01 24 0 1 24 0 1 24 Sample 109A Drywell Fission Product Monitor 0124 01 24 01 24 0 1 24 Sample Drywell Fission Product Monitor 0124 0 1 24 40 1 24 40 1 24 109B Sample Return 109D Containment Pressure Instrumen- 20 1 12 0 1 24 01 24 01 24 tation (Narrow Range) 0 + 24 0 + 24 110A ILRT Instrumentation (Drywell 0124 0 1 24 Pressure) i D-3
APPENDIX D (Continued)
Local leak Rate Test Summary Data True B and C Test Results Pncuraatic Testing (Continued)
Minimum Pathway 1.cakaee (std cu em/ min)
RFO1 RFO2 RFO3 RFO3 Penetration Qgssdgli2D As-Left As Left As Found As left 110C ILRT Instrumentation (Verifica- 0 1 12 0 1 24 0 1 24 0 1 24 tion Flow) 110F ILRT Instrumentation (Contain. 0 1 12 0 1 24 0 1 24 0 1 24 ment Pressure) 114 Suppression Pool Water level In- 0 1 24 0 1 24 0 1 24 0 1 24 strumentation 116- Suppression Pool Water Level In- 0 1 24 0 1 24 0 1 24 0 1 24-strumentation 118 Suppression Pool Water Level In- 0 1 24 0 1 24 0 1 24 0 1 24 strumentation 120 Suppression Pool Water level In- 0 1 24 0 1 24 20 1 24 20 1 24 strumentation 201 . Electrical Penetration (Reactor 0+0 0+0 0+0 0+0 Protection System) 202 Electrical Penetration (Iow 010 01 0 0+0 0+0 Voltage Power) 203 Electrical Penetration Onstru- 010 0 10 0+0 0+0 l mentation) 204 Electrical Penetration (Instru- 010 010 0+0 0+0 mentation) ,
205 Electrical Penetration (Neutron 010 010 0+0 0+0 l Monitoring) 206 Electrical Penetration (Low 010 010 010 0 10
- Voltage Power & Control) ,
207 Electrical Penetration (Control 010 0 10 01 0 010 l and Power) 208 Electrical Penetration Onstru- 01 0 01 0 0+0 0+0 mentation) 209 Electrical Penetration (Iow 010 0 10 010 01 0 J Voltage Power) 210 Electrical Penetration (Radiation 01 0 01 0 01 0 01 0 Monitoring) 211 Electrical Penetration (Control) 01 0 01 0 01 0 010 212 Electrical Penetration (Instru- 010 01 0 010 01 0 mentation) 213 Electrical Penetration (Rod Posi- 0 10 01 0 01 0 010 tion Indication) 214 Electrical Penetration (T.LP.) 010 0 10 0 10 01 0 215 Electrical Penetration (6.9 KV to 010 010 010 01 0 Reactor Recirculation Pump A) 216 Electrical Penetration (Test Sys- 0 10 010 0+0 0+0 tems and Communications) 217 Electrical Penetration (Low 010 010 0+0 0+0 j Voltage Power & Control)
D-4
=-_ _ - _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _ _ _ _
APPENDIX D (Continued)
Local Leak Rate Test Summary Data Tyne B and C Test Results Pneumatic Tuting (Continued)
Minimum Pathway Leakare (std eu em/ min)
RF01 RFO2 .RFO3 RFO3 Penetration Description As-left .Ardah. As-Found As-Left 218 Electrical Penetration (Neutron 010 010 0+0 0+0 Monitoring) 219 Electrical Penetration Gn:tru- 0 10 01 0 010 01 0 mentation) 220 Electrical Penetration Onstru- 010 010 01 0 01 0 mentation) 221 Electrical Penetration (Control) 01 0 01 0 01 0 010 222 Electrical Penetration (Reactor 010 01 0 0 10 010 Protection System) 223 Electrical Penetration (Low 01 0- 010 0+0 0+0 Voltage Power & Control) 224 Electrical Penetration (Low 010 010 010 01 0 Voltage Power) 225 Electrical Penetration (Low 0+0 0+0 0+0 0+0 Voltage Power) 226 E?ectrical Penetration (Control) 01 0 01 0 010 01 0 227 Electrical Penetration Onstru- 01 0 010 0+0 0+0 mentation) 228 Electrical Penetration Onstru- 010 010 0+0 0+0 mentation) 229 Electrical Penetration G.ow 01 0 01 0 010 010 Voltage Power & Control) 230 Electrical Penetration (Reactor 0 10 010 010 01 0 Protection System) 231 Electrical Penetration (instru- 010 01 0 010 01 0 merlation) 232 Electrical Penetration (Neutron 010 01 0 0 10 01 0 Monitoring) 233 Electrical Penetration (Rod 010 010 0+0 0+0 Position Indication)
Electrical Penetration (CRD Hy- 010 0+0 0+0 0+0 234 draulic Sys. Power & Control) 235 Electrical Penetration (Neutron 01 0 010 01 0 01 0 Monitoring)
Electrical Penetration (Instru- 01 0 01 0 0+0 0+0 237 mentation) 0+0 238 Electrical Penetration (Reactor 010 01 0 0+0 Protection System) 239 Electrical Penetration (Control) 01 0 01 0 01 0 01 0 240 Electrical Penetration Onstru- 01 0 010 010 010 mentation) 241 Electrical Penetration (Io, 010 010 0 10 010 Voltage Power & Control) 242 Electrical Penetration (Iow 0 10 0+0 0+0 010 Voltage Power & Control)
D-5 i
L f
APPENDIX D (Condnued) .
1 ~=I t ** R=ee Test Sa=== v n. . .
Tyne B and C Test Results Pneenatic Testing (Condnued)-
Minimum Pathway Leacame (std cu em/ mini RFO1 RFO2 RFO3- RFO3.
As 12ft As-12ft ' As-Found As-12ft Penetration : D1 Hill 21[QB 243- Electrical Penetration (Instru- 0+0 040 0+0 0+0 mentation) 244 Electrical Penetration (Iow 0 10 010 010' 010 Voltage Power) 245 Electrical Penetration (Iow 0 10 010 010 .0 1 0 Voltage Power & Control) 246. Electrical Penetration (Radiation 0 10 010 01 0 .01 0 Monitoring)
'247. Electrical Penetration (6.9 KV to 0 10 010 010 010 '.
Reactri: Recirculation Pump B) 248 Electrical Penetration (Power) 0 10 010 0 10 010 249 Electrical Penetration (Control) 01 0 010 0+0 0+0 4
- ' ISI Impaction Ports. 0 1-0 0 10 27,164 1 1643 010 l 4235 1 354 2049 1 379 76,037 1 1808 3223 1421
' Totals 1 Tolerance
.m ,. ,
i., ,
- Twenty-two inspection ports on guard pipes; two each per penetration on eleven penetrations (510,14, 17-19 and 87).
D4 i
> t i
l APPENDIX D (Continued)
I Local leak Rate Test Summary Data l Tyne C Test Results {
Ilydrostatic Testing j Minimum Pathway Leakare (milliliters / minute)
RFO1 RFO2 RFO3 RFO3 '
Description As-12ft As-Left As Found As-Left Penetration .
11 RHR Pump A Suction 010 12 RHR Pump B Suction 01 0 01 0 01 0 010 13 RHR Pump C Suction 1280 1760 228 1 140 633 1 380 633 1 380 23 RHR Pump A Test Return Line 1707 1 260 3150 1 2022 400 1 240 400 1 240 ;
to Suppression Pool l RHR Pump C Test Return Line l 24 i
to Suppression Pool "'
25 HPCS Pump Suction 11 1 10 0+0 0+0 27 HPCS Test Return Line to Sup- 23 1 20 01 0 010 010 pression Pool 28 RCIC Pump Suction 010 1267 1 760 01 0 010 29 RCIC Turbine Exhaust 010 195 1 89 610 1 135 610 1 135 30 LPCS Pump Suction 60 1 40 ' O1 0 010 010 32 LPCS Test Return Line to Sup- 220 1 122 01 0 0 10 01 0 pression Pool 46 RCIC Pump Discharge Minimum 010 010 01 0 010 Flow Line 48 RHR Heat Exchanger B Relief 01 0 # 010 01 0 Valve Discharge to Suppres-sion Pool 67 RHR Pump B Test Return Line 0 10 293 1 180 010 010 to Suppression Pool 69 Refueling Water Transfer Pump 010 010 267 1 160 267 1 160 Suction from Suppression Pool 71A LPCS Relief Valve Discharge to ## 0 10 0 10 010 Suppression Pool 71B RHR C Relief Valve Discharge to 010 010 010 01 0 Suppression Pool & Post-Acci-dent Sample Return *
- 77 RHR Heat Nhanger A Relief 010
- Valw Discharge to Suppression Pool 89 Standby Service Water A Supply 010 01 0 01 0 01 0 99 Standby Service Water A Return 01 0 010 010 01 0
- Penetration 11 and 77 leakage are included in Penetration 23 total.
" Penetration 24 leakage is included in Penetration 13 total.
{
'" Valve Q1E22F014 leakage was indeterminate due to being unable to pressurize the penetration j to the required test pressure with the test equipment. The maximum leakage rate would have been less than the allowable leakage rate of GGNS Technical Specification 3.6.1.2.d due to the valve's )
size (3/4" x l'). #
- Penetration 45 icainge b included hi Panctratian 57 to!..!.
- Penetration 71A leakage is included in Penetration 32 total.
l D-7 {
1 l
l J
APPENDIX D (Continued)
Local Laak Rate Test Summary pata Tyne C Test Results Hydrostatic Testing (Continued)
_Mjnimum Pathway 12=km.e (milliliters / minute)
RFO1 RFO2- RFO3 RFO3 Penetration Description As-12ft As 12ft As-Found As Left.
91 Standby Service Water B Supply 010 0 10 0+0 0+0 92 Standby Service Water B Return 010 010 010 010 113 Suppression Pool Water Level In- 010 010 010 0 10 strumentation 115 Suppression Pool Water Level In- 010 0 10 010 010 strumentation 117 Suppression Pool Water Level In- 0 10 010 010 01 0 strumentation 119 Suppression Pool Water Level In- 010 0 10 010 0 10 strumentation Totals 1 Tolerance 3301 1 814 5133 1 2174 ### 1910 1 496
- Totalleakage was indeterminate due to being unable to pressurize Penetration 25 to the required test pressure with the test equipment (See Footacte "* on Page D-7). The total leakage and tolerance for the remaining penetrations was 19101 4% ml/ min. .
D-8 i
p-
APPENDIX E
SUMMARY
REPORT OF TYPE A, B AND C TESTS WHICH FAILED TO MEET THE ACCEPTANCE CRITERIA OF 10CFR50, APPENDIX J b
W -
APPENDIX E i
SUMMARY
REPORT OF j 11PE A, B AND C TESTS l WHICH FAILED TO MEET THE ACCEPTANCE CRITERIA OF 10CFR50, APPENDIX J'
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 Type A test which i is described in this report was a successful test; therefore, there are no Type A tests since the last reported Type A test (completed on November 4, 1985) which have failed to meet the acceptance requirements of 10CFR50, Appendix J, Paragraph III. A. 5. (b) . (2) .
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, Paragrcphs III.B.3 and III.C.3.
The Type B and C tests reported in the summary table were performed during Refueling Outage No. 1 (RF01) during 1986, Refueling Outage No. 2 (RFO2) during 1987 and Refueling Outage No. 3 (RF03) during 1989.
Where the test is indicated to have failed due to being unable to pressurize the test volume to the required test pressure, the test volume could not be pressurized 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 310 psig. Due to the inability to pressurize the volumes as required to measure the leakages, each of the leakages was conservatively assumed to be infinite.
Where the test is indicated to have failed due to the total Type B and C leakage being higher than the Appendix J limit of 0.60 L,, 4 3
the indicated leakage for the valve was a significant contributed to causing the total Type B and C leakage to exceed 86,130 standard cubic centimeters per minute (sccm), which is the currently accepted limit at Grand Gulf Unit 1. It should be noted that we have conservatively continued to keep track of the total Type B and C leakage, even though there were other tests that had failed due to (assumed) infinite leakage, and that the total leakage of the remaining components, ignoring those tests determined infinite, was above 86,130 secm.
At Grand Gulf, the combined Type B and C test totals 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 E-1
APPENDIX E
SUMMARY
REPORT OF TYPE A, B AND C TESTS WHICH FAILED TO MEET THE ACCEPTANCE CRITERIA i OF 10CFR50, APPENDIX J J (CONTINUED)
Pathway Leakage method which is recommended in ANSI /ANS 56.8 -
1987, " Containment System Leakage Testing Requirements." i 1
In each case where excessive leakage was determined, we took action l immediately to correct the problem and performed another Type B or j C test to verify that the corrective action was sufficient. The measured leakages from the retests were added to the combined Type B and C test totals. l We did not follow up on those Type B and C tests which failed during 1986 and 1987 with diagnostic tests to determine whether or not the penetrations would have been below the 0.60 L allowable by minimum pathway leakage; however, based on experienc,es during the i outage reported in this document, we are confident that combined ,
Type B and C leakage, by minimum pathway leakage analysis, would have been less than 0.60 L, at all times when containment integrity was required. For all penetrations with at least two testable barriers in series, at least one of the barriers had acceptable leakage. For ISI inspection ports, which are Type B tested by pressurizing between the inboard and outboard seal gaskets, >
experience during the 1989 Type A test has shown that containment pressure causes the inboard ganket to seal, even though the Type !
B , test may have failed. In this respect the Type B test is excessively conservative and does not reflect the true sealing capability of the inspection port design during an accident.
l E-2
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