ML20155J354

Reactor Containment Bldg Integrated Leak Rate Test, Final Rept

ML20155J354
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Site:	San Onofre
Issue date:	07/31/1988
From:	SOUTHERN CALIFORNIA EDISON CO.
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NUDOCS 8810260039
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SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION o

UNIT 3 r

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REACTOR CONTAINMENT BUILDING l

i INTEGRATED LEAK RATE TEST i

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FINAL REPORT i

i JULY 1988 TEST 4

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8810260039 881018 4

PDR ADOCK 05000362 i

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 2 TABLE OF CONTENTS

1.0 INTRODUCTION

3 1.1 GENERAL 3

1.2 TEST SYNOPSIS 3

1.3 DOCUMENTS AND TEST INFORMATION 5

RETAINED AT SONGS 2.0 GENERAL DATA 6

3.0 TECHNICAL DATA 6

4.0 TEST DATA

SUMMARY

6 5.0 VERIFICATION TEST DATA

SUMMARY

7 6.0 LOCAL LEAK RATE TEST (LLRT) DATA

SUMMARY

7 6.1 PENETRATIONS NOT ALIGNED TO SIMULATE 7

POST-ACCIDENT CONDITIONS i

6.2 AS FOUND / AS LEFT LLRT PENALTY 8

7.0 ANALYSIS AND INTERPRETATION 8

4 7.1 PRESSURIZATION 8

7.2 CONTAINMENT ATMOSPHERE STABILIZATION 9

7.3 ILRT (Total Time) 9 7.4 ILRT (Mass Point) 10 i

7.5 IMPOSED LEAKAGE RATE VERIFICATION TEST 10 1

7.5.1 TOTAL TIME CALCULATIONS 11 7.5.2 MASS POINT CALCULATIONS 12 i

8.0 LOCAL LEAK RATE TESTING

SUMMARY

12 9.0 ATTACHMENT 1 14

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SONGS UNIT 3 1988 ILRT TEST REPORT

.PAGE 3

1.0 INTRODUCTION

1.1 GENERAL The reactor containment building Integrated Leakage Rate Test (Type A) was performed to demonstrate that the overall leakage rate through the primary reactor containment system does not exceed the allowable leakage rate as specified in the Unit 3 Technical Specification, Section 3.6.1.2.

The test was performed as part of the Unit 2 Cycle 4 refueling outage.

The successful Type A and supplemental verification tests were performed in accordance with the requirements of San Onofre Nuclear Generating Station, Unit 3 Procedure SO3-V-3.12, Revision 1, Containment Integrated Leak Rate Test.

The test method utilized was the absolute method described in ANSI N45.4-1972, "American National Standard Leakage-Pate Testing of Containment Structures for Nuclear Reactors, BN-TOP-1, Revision 1, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants",

and ANSI /ANS-56.8-1981, "Containment System Leakage Testing Requirements".

The leakage rate was calculated using the Total Time formulae and Mass Point method from these standards.

The test results are reported in accordance with the requirements of 10CFR50, Appendix J, Section V.B.3.

1.2 TEST SYNOPSIS Pressurizat'on was commenced at 1830 on 7-19-88.

Test pressure was obtained at 0740 on 7-20-88.

Stabilization was achieved in approximately eight and a half hours.

The test was commenced at 1615 on 7-20-83, and completed at 1615 on 7-21-88.

The verification test was started at 1730 on 7-21-88.

One hour was allowed for stabilization.

The verification test was completed at 2130 on 7-21-88.

Depressurization was started at 2131 on 7-21-88, and completed at 0433 on 7-22-88.

The Primary Containment Integrated Leakage Rate Test t

(ILRT) was successfully completed at 2130, on 7-23-88 at the San Onofre Nuclear Generating Station, Unit 3.

All ILRT requirements of the Technical Specifications were satisfied.

SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 4 TEST SFOUENCE START CQMPLETION PRESSURIZATION 1830 7-19-88 0740 7-20-88 STABILIZATION 0745 7-20-88 1530 7-20-88 TEST 1615 7-20-88 1615 7-21-88 VERIFICATION 1730 7-21-88 2130 7-21-88 BLOWDOWN 2131 7-21-88 0433 7-22-88 TOTAL TIME ANALYSIS Analysis of the measured data taken during the test resultad in a measured leakage rate of 0.0660 %/ day, a calculated leakage rate of 0.0616 %/ day and a 95 %

probability upper confidence limit (UCL) leakage of 0.0652 %/ day using the Total Time calculation technique as recommended in ANSI 45.4-1972 and BN-TOP-1.

The leakage rate at this upper confidence limit plus a 0.0016 %/ day Local Leak Rate penalty (See Section 6.0) yields an overall leakage rate of 0.0668 %/ day of contained air mass which satisfies the acceptance criteria of being less than 0.075 %/ day.

MASS POINT ANALYSIS Analysis of the measured data taken during the test resulted in a calculated leakage rate of 0.0607 %/ day and a 95 % probability upper confidence limit (UCL) leakage of 0.0623 %/ day using the Mass Point calculation technique as recommended in ANSI /ANS 56.8-1981.

The leakage rate at this upper confidence limit plus a 0.r. 6

%/ day Local Leak Rate penalty (See Section 6.0) yiel& an overall leakage rate of 0.0639 %/ day of contained air mass which satisfies tha acceptance criteria of being less than 0.075%/ day.

SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 5 YERIFICATION TEST Following the completion of the ILRT measurements, a successful verification test was performed with'an imposed leakage rate of 8.03 SCFM.

The Total Time measured leakage rate of 0.1609 %/ day and calculated leakage rate of 0.1537 %/ day was within the allowable limits of 0.1366 %/ day to 0.1866 %/ day.

The Mass Point calculated leakage rate of 0.1614 %/ day established during the verification test was within the allowable limits of 0.1357 %/ day to 0.1857 %/ day.

The leakage rates for this Primary Containment ILRT demonstrates that leakage through the primary reactor containment, systems and components penetrating primary containment do not exceed the allowable leakage rate specified in the SONGS 3 Technical Specifications.

1.3 QOCUMENTS AND TEST INFORMATION RETAINED AT SONGS The following documents and test infnrmation are available for review at the San Onofre Nuclear Generating Station:

1)

A listing of all containment penetrations, penetra-tion size, and functions.

2)

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

3)

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

4)

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

5)

Documentation of instrumentation calibrations and standards.

6)

The official test copy of the test procedure with sign-off of procedural steps.

7)

Computer printouts of Integrated Leakage Rate Test Data and Reports along with Graphs and Plots of the data obtained during the test using Southern California Edison developed computer ; program.

8)

P& ids 9)

Local Leak Rate Test History Files

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 6 2.0 GENERAL DATA (PLANT IN M NTION) 2.1 Owner Southern California Edison 2.2 Docket No.

50-362 2.3 Plant San Onofre Nuclear Generating Station, Unit 3 2.4 Location San Onofre, California 2.5 Containment Type Post-tensioned concrete, hemispheri-cal dome 2.6 NSSS Supplier Combustion Engineering, PWR 3.0 TECHNICAL DATA 3.1 Containment Net 2,305,000 cubic feet i

Free Air Volume 3.2 Design Pressure 6Ci.0 PSIG 3.3 Design Temperature 300.0 degrees F 3.4 Calculated Peak 55.7 PSIG Accident Pressure (Pa) 3.5 Calculated Peak 287 degrees F Accident Temperature 4.0 TFST DATA

SUMMARY

4.1 Test Method Absolute Method 4.2 Data Analysis Techniques 1)

Total Time per ANSI N 45.4-1972 and BN-TOP-1, Rev. 1 2)

Mass Point per ANSI /ANS 56.8-1981 4.3 Test Pressure 57.7 psig 4.4 Maximum Allowable 0.100%/ day Leakage Rate (Lc}

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 7 4.5 ILRT Results Leakage Rate (wt. %/ day) 95% UCL Lam Lcalc 95% UCL

+ LL*

Total Time 0.0660 0.0616 0.0652 0.0668 Mass Point 0.0607 0.0623 0.0639

• LL= Local Leak Rate Penalty I'

5.0 VERIFICATION TEST DATA

SUMMARY

5.1 Vcrification Test

.101 %/ day (8.03 SCFM)

Leakage Rate 5.2 Verification Test Leakage Rate (wt. %/ day)

Results Limit Rate 1)

Total Time 0.1366-0.1866 0.1537 2)

Mass Point 0.1357-0.1857 0.1614 6.0 LfCAL LEAK RATE TEST (LLRT) DATA

SUMMARY

6.1 PENETRATIONS NOT ALIGNED TO SIMULATE POST-ACCIDENT COfiDITIONS During the ILRT, the penetrations listed below were not aligned to simulate the configuration after a postulated accident.

The measured local leakage rates obtained from Test Procedure SO23-V-3.13, "Containment Penetration Leak Rate Testing", are given below and are l

added to the ILRT results.

PEN #

DESCRIPTION VALVE #

I 10B ILRT PRdSS SENSOR S31500MUO38/S31500MUO39 23C ILRT FLOW FLANGE 34 ILRT PRESS CONNECTION FLANGE 42 NON-CRIT CCW INLET 3HV6211/3HV6223 43 NON-CRIT CCW OUTLET 3HV6216/3HV6236 i

45 CTMT NORMAL INLET 3HV9900/3HV9920 46 CTMT NORMAL OUTLET 3HV9971/3HV9921 1

LLRT PENALTY 0.00092528 % / day

- SONGS UNIT 3 1988 ILRT.*'EST REPORT PAGE 8 6.2 AS FOUND / AS LEFT LLRT PENALTY In accordance with, IE Information Notice No. 85-71, "Containment Integrated Leak Rate Tests", an As Found /

As Left LLRT penalty vss calculated and added to the ILRT results.

The following penetrations were applicable to this calculation:

PEN #

DESCRIPTION VALVE #

1 PZR VAPOR SAMPLE 3HV0510/3HV0511 6

SI DRAIN TO RWST 3HV9334/S31204MUO99 8

CHARGING S31208MU122/3HV9200 16-A CONTAINMENT AIR SAMPLE 3HV0501/3HV0500 16-C CONTAINMENT AIR SAMPLE 3HV7805/3HV7810 27-C CONTAINMENT AIR MONITOR 3HV7806/3HV7811 30-B CONTAINMENT AIRBORNE 3HV7801/3HV7800/

RADIATION MONITOR 3HV7816 43 NON-CRIT CCW OUTLET 3HV6216/3HV6236 74 H2 PURGE 3HV9917/3sN9918 AS FOUND / AS LEFT PENALTY = 0.00066396 %/ DAY The total LLRT penalty is the sum of the values in sections 6.1 and 6.2.

In order to be consistent with the ILRT significant figures and rounding conservatively, the total LLRT penalty is:

TOTAL LLRT PENALTY = 0.0016 %/ DAY 7.0 ANALYSIS AND INTERPRETATION 7.1 PRESSURIZATION Pressurization started at 1830 on 7-19-88.

The test pressure ot 57.2 PSIG was achieved at 0740 on 7-20-88.

I The averago pressurization rate was 4.34 PSI /HR over the 13.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period using a 12,000 CFM diesel compressor j

system.

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE i' 7.2 CONTAINMENT ATMOSPHERE STABILIZATION The acceptance criteria for containment atmosphere-stabilization at test pressure is that the rato of change of the containment temperature (weighted averaga of RTD sentats) is less than 1.0 degree F averaged ovar the last two hours; or, the rate of change of temperature changes is less than 0.5 degree F /. hour /

4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> averaged over the last two hours; and that the containment atmosphera has been at test pressure for at least four hours.

Temperature stabilization commenced i.

at 0745 and was achieved at 1530 on 7-20-88, 7.3 ILRT (Total Timel

}'

The acceptance criteria for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT is that the

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leakage rate determined using the 95% UCL value for the calculated leakage rate plus.the local leak rate penalty j

must be less than 75% of the allowable leakage rate (La's at the peak accident pressure (Pa)e 1

The test duration was 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

97 data. points were used in the calculations.

Data was collected at 15 minute intervals.

The uppec bound 95% probability value for the l

calculated leak rats using the Total Time technique was 0.0652%/ day.

J The LLRT penalty for penetrations not aligned for the ILRT and as found/as left leakage is 0.0016 4

%/ day (See section 6.0).

LL = 0.0016 %/ day 75% of the allowable leakage rate of 0.10 %/ day is 0.075 %/ day.

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0.75La = 0.075 %/ day.

The acceptance criteria for tha test using the Total Time technique is satisfied, i.e.,

95% UCL + LL

<.75 LA i

0.0652 %/ day + 0.0016 %/ day < 0.075 %/ day O.0668 %/ day < 0.075 %/ day i

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 10 3

7.4 ILRT (Mass Point)

The acceptance criteria for a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT is that the leakage rate determined using the 95% UCL value for the calculated leakage rate plus the local leak rate penalty must be less than 75% of the allowable leakage rate (La) at the peak accident pressura (Pa).

The Mass Point Leakage Rate calculated with a 95%

probability UCL is 0.0623 %/ day.

95% UCL = 0.0623 %/ day The LLRT penalty for penetrations not aligned for the ILRT and as found/as left leakage is 0.0016

%/ day (See Section 6.0).

LL = 0.0016 t/ day 75% of the allowable leakage rate of 0.10%/ day is 0.075 %/ day.

75% La = 0.075 %/ day The acceptance criteria for the ILRT leakage rate using the Mass Point technique is satisfied, i.e.,

95% UCL + LL

.75 La 0.0023 %/ day + 0.0016 %/ day <

0.075 %/ day 0.0639 %/ day <

0.075 %/ day 7.5 IMPOSED LEAKAGE RATE VERIFICATION TEST The verification test was cominenced at 1730 on 7-21-88, following a one hour etabilization period.

The verification test was successfully completed at 2130 on 7-21-88.

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4 SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 11 7.5.1 TOTAL TIME CALCULATIONS The acceptanca criteria for the imposed' leakage verification test is given by the folleving equation:

Lcalc + 0. 75 La < Lver < Lealc + 1. 2 5 La imposed leakage rate which must

where, Lo

=

be in the range (8.03 SCFM =

0.101 %/ day)

.75 La S Lo i 1.25 La Lcalc ILRT calculated leakage rate

=

Verification test calculated Lver

=

leakage rate Furthermore, the calculations shall utilize at least 10 data points, recorded over a time span of at least 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Actual Test Data is as follows:

Lo 0.101 %/ day (8.03 SCFM)

=

0.75 La 0.0'/5 %/ day

=

1.25 La 0.125 %/ day u

Lcalc 0.C616 %/ day

=

Lver 0.1537 %/ day (Total Time)

=

Data Points 17

=

The acceptance critoria for the Total Time technique of determining the imposed leakage rate is satisfied, i.e.,

j Lcalc + 0.75 La < Lver < Lealc + 1.25 La 0.0616 + 0.075 < 0.1537 < 0.0616 + 0.125 0.1366 < 0.1536 < 0.1866 4

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. SONGS UNIT 3 19fS ILRT TEST REPORT PAGE 12 7.5.1 MASS POINT CALCULATIONS.

The acceptance criteria for the imposed leakage verification test using the Mass Point technique is the same as Total Time technique defined in Section 7.5.1.

Actual Test Data is as follows:

Lo 0.101 %/ day (8.03 SCFM).

=

0.75 La 0.075 %/dhy

=

1.25 La 0.125 %/ day

=

Lcalc 0.0607 %/ day

=

Lver n.1614 %/ day (Total Time)

=

Data Points 17

=

The acceptance criteria for the Mass Point technique of determining the imposed leakage rate is satisfied, i.e.,

Lcalc +.75 La < Lver < Lcalc + 1,25 La 0.0607 + 0.075 < 0.1614 < 0.0607 + 0.125 0.1357 < 0.1614 < 0.1857 8.O LOCAL LEAK RATE TESTING

SUMMARY

Penetration (Type B and C) testing was accomplished in accordance with the requirements of the Technical Specifica-tion 3/4.6.1 and por SO23-V-3.13.

The penetrations wore tested using the pressure decay method, make up method, and local test panels.

The allowable leakage for all penetrations is 0.06%/ day (0.6 La) of the mass of air in the containment at 55.7 psig.

The following is an Operational History of Unit 3 since the previous ILRT, conducted in November 1985.

The through penetration leakage is exprossed in %/ day, using IE Information Notice No. 85-71 methods for determining the through penetration leakage.

At no time during plant modes requiring containment integrity (Modes 1 through 4), did the Local Leakage Rate Test results exceed 0.6 La.

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SONGS UNIT 3 1988 ILRT TEST REPORT PAGE 13 DATE DESCRIPTION

%/ DAY 11-25-85 Completed ILRT Cycle 2 Refueling Outage 0.006 01-04-86 Entered Mode 4 0.005 02-28-86 Entered Mode 5 0.005 03-13-86 Entered Mode 4 0.005 10-01-86 Entered Mode 5 0.006 10-17-86 Entered Mode 4 0.007 01-04-87 Entered Mode 5 0.007 03-01-87 Entered Mode 4 0.003 05-01-88 En';ered Mode 5, Cycle 4 Refueling Outage 0.003 l

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LOCAL LEAKAGE RATE TEST RESULTS OF PENETRATIONS WHICH i

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CAUSED THE TOTAL LEAKAGE FOR ALL PENETRATIONS TO EXCEED 0.6 La (0.06 %/ DAY) f i

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'm GONGS UNIT 3 1988 ILRT TEST REPORT PAGE 15

1.0 INTRODUCTION

Leakage test results of penetrations which failed to meet the acceptance criteria of 0.6 La (0.06 %/ day) are given below.

The valuen given were calculated in accordance with SO23-V-3.13, "Containment Penetration Leak Rate Testing."

At no time during plant modes requiring containment integrity (Modes 1 through 4), did the Local Leakage Rate Test results exceed 0.6 La.

1.1 CQNTAIlTMENT PENETRATION 18 CONTAINMENT PURGE SUPPLY On 12-7-85, while in Mode 5, a Local Leakage Rate Test (LLRT) of Penetration 18 was conducted.

The LLRT was unsuccessful because the penetration never achieved test pressure.

The valve 3HV-9821, which is an eight inch mini purge valve located outside of containment, was determined to leak excessively.

Following rework of the actuator for 3HV-9821, a successful retest of Penetration 18 was conducced on 12-11-85.

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