ML20097D483

Reactor Containment Bldg Integrated Leak Rate Test San Onofre Nuclear Generating Station,Unit 3

ML20097D483
Person / Time
Site:	San Onofre
Issue date:	06/05/1992
From:	Krugir R SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9206100166
Download: ML20097D483 (14)

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Southom Califomia Edison Company S AN ONOf fW NUCL EAR OF N0 8' ATING ST AllON P O DO E IT -

E. AN CLE M E NTE C ALIF ORNIA 92674 01;'B t*,

W, K R:E G E F4 IILE

. w w waoca June 5, 1992 U.

S. 11uclear Regulatory Commission Document Control Desk Uashington, D. c.

20555

Subject:

Docket No. 50-362 Reactor Containment Building Integrated Leak Rate Test San Onofre Nuclear Generating Station, Unit 3 An Integrated Leak Rate Test (ILRT) was performed at San Onofre Unit 3 during March 3992.

The test was performed in accordance with the requirements of the Unit 3 Technical Specificationn.

Both the measured leak rate test and supplemental verification test mot the acceptanco critorja set forth in the Technical Specifications.

The enclosed ILRT report for San Onofre Unit 3 constitutes our final report and is being submitted pursuant to 10 CFR 50, Appendix J.

If additional information is required, please so advice.

Sincerely, F

/

N

(,A b i

,.)

Enclosure cc:

C.

W. Caldwell (USNRC Senior Resident Inspector, Units 1, 2 and 3)

J. B. Martin (Regional Administrator, USNRC Region V)

M.

B. Fields (USNRC Project Manager, San Oncfre Units 2 and 3) 9206100166 920605 ADOCK0500g2

/7

_M DR lit j

e SOUTHERN CALIFORNIA EDISON COMFANY SAN ONOFRE NUCLEAR GENERATING STATION UNT.T 3 REACTOR CONTAldMENT DUILDING INTEGRATED LEAK RATE TEST FINAL REPORT MARCH 1992 TEST

4 SONGS 3 1992 ILRT TEST REPORT PAGE 2 TABLE OF CONTENTS

1.0 INTRODUCTION

3 1.1 GENERAL 3

3.2 TEST SYNOPSIS 3

1.3 DOCUMENTS AND TEST INFORMATION RETAINED AT SONGS 5

2.0 GENERAL DATA (PLANT INFORMATIOli) 5 3.0 TECHNICAL DATA 5

4.0 TEST DATA

SUMMARY

6 5.0 VERIFICATION TEST DATA

SUMMARY

6 6.O LOCAL LEAK RATE TEST DATA

SUMMARY

7 6.1 PENETRATIO!IS NOT ALIGliED TO POST-ACCIDENT POSITIONS 7

6.2 AS FOUND / AS LEFT LLRT PENALTY 8

7.0 ANALYSIS AND INTERPRETATION 9

7.1 PRESSURIZATION 9

7.2 CONTAINMENT ATMOSPNERE STABILIZATION 9

7.3 ILRT (Total Time) 10 7.4 ILRT (Mass Point) 10 7.5 IMPOSED LEAKAGE VERIFICATION TEST 11 8.0 LOCAL LEAK RATE TESTING

SUMMARY

13

SONGS 3 1992 ILRT 10ST REPORT PAGE 3

1.0 INTRODUCTION

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

The test was-performed as part of the Unit 3 Cycle 6 refueling outage.

The successful Type A and supplemental verification tests were performed in accordance with the requirements of San Onofro 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 H45.4-1972, "American National Standard Leakage-Rate Testing of Containment Structures for Nuclear Reactors"; and ANSI /ANS-56.8-1987, " Containment System Leakage Testing Requirements".

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

Test duration was determined from thrse e

standards and from Bechtel Topical Report BN-TOP-1,

" Testing Criteria.for Integrated Leakage Rate Testing

- of Primary Containment Structures for Nuclear Power Plants."

The test results are reported in accordance with the requirements of 10CFR50, Appendix J, Section V.B.3, and ANSI /ANS 56.8-1987.

1.2 IEST SYNOPSIS Containment pressurization commenced on 3-7-92 at 22:15 and. test pressure was obtained on 3-8-92 at 1345.

The Primary Containment Integrated Leakage Rate Test (ILRT) was successfully completed on 3-9-92 at 1100 for San Onofre Nuclear Generating Station, Unit 3.

All ILRT requirements of the Technical Specifications were satisfied.

TEST SEOUENCE START COMPLETION PRESSURIZATION 2215 3-7-92 1345 3-8-92 STABILIZATION 1345 3-8-92 2200 3-8-92 TEST 2200 3-8-92 0600 3-9-92 VERIFICATION (Stabilization) 0600 3-9-92 0700 3-9-92 (Test) 0700 3-9-92 1100 3-9-92 BLOWDOWN 1105 3-9-92 2000 3-9-92

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, SONG'S 3 1992 ILRT TEST REPORT PAGE 4 TOTAL TIME ANALYSIS From Total Time ca' 'qations of test data, recommended in ANSI 45.4-1972 s N-TOP-1, the measured leak rate was 0.0516 %/ day, the

.lculated leak rate van 0.0427

%/ day and the 95% probacility upper confidence limit (UCL) leak rate was 0.0649.

The upper confidence limit leak rate, plus a 0.0003 %/ day, as left, and a 0.0032

%/ day, as found, Local Loak Rato penalties, gives overall leak rates of 0.0652 %/ day, as left, and a 0.0681 %/ day, as found.

This meets the acceptanco criterion of loss than 0.075 %/ day.

BASS POINT ANALYSIS This section is provided for information only.

Masa Point Analysis is not used to determine test acceptability in BN-TOP-1 Short Duration Tests.

Mass Point Analysis of test data gave a calculated leak rate of 0.0457 %/ day and a 95 % probability upper confidence limit (UCL) leak rate of 0.0504 %/ day. The upper confidence leak rate, plus a 0.0003 %/ day, as left, and a 0.0032 %/ day, as found, Local Leak Rate penalties, gives overall leak rates of 0.0507 %/ day, as loft, and a 0.0536 %/ day, as found.

This meets the acceptance critorion of loss than 0.075 %/ day.

VERIFICATIrN TEST Following the completion of the ILRT test, a successful verification test was performed with an imposed leakage of 7.9 SCFM.

The Total Time measured leak rate of 0.1513 %/ day and calculated leak rate of 0.1599 %/ day were within the allowablo limits of 0.1183 %/ day to 0.1683 %/ day.

The Mass Point calculated leakage, presented for information only, of 0.1609 %/ day during the verification test, was within the allowable limits of 0.1212 %/ day to 0.1712 %/ day.

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

. SONGS 3 1992 ILRT TEST REPORT PAGE 5 1.3 DOCUMENTS AND TEST INFORMATION RETAINED AT SONGS The -following documents and test information are available for review at San Onofre Nuclear Generating Stationt 1)

A listing of all containment penetrations, peretration sizen, and functions.

2)

A listing of normal operating instrumentation used in the leak rate test.

3)

All system test lineups showing required valvo positions and st atus of piping.

4)

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

5)

Documentation of instrument calibrations and standards.

6)

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

7)

Computer printouts from the Southern California Edison program of the Integrated Leak Rate Test data reports, oraphs, and plots.

8)

P& ids 9)

Local Leak Rate Test History Files.

2.0 GENERAL DATA fPLANT INFORMATION) 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, hemispherical dome 2.6 NSSS Supplier Combustion Engineering, PWR 3.0 TECHNICAL DATA 3.1 Containment Net 2,305,000 cubic feet Free Air Volume 3.2 Design Pressure 60.0 PSIG 3.3 Design Metal 300.0 degrees F Temperature

i 6

SONSI 3 1992 ILRT TEST REPORT PAGE 6 3.4 Calculated Peak 55.7 PSIG Accident Pressure (Pa) 3.5 Calculated Peak 287.0 degrees F Accident Vapor Temperature 4.0 TEST DATA:

SUMMARY

4.1 Test Method Absolute Method 4.2 Data Analysis Techniques 1)

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

. Mass Point per ANSI /ANS 56.8-1987 4.3 Test Pressure 57.7 PSIG + 0.2,

-0.0 PSIG 4.4 -Maximum-Allowable 0.100%/ day Leakage Rate-(La)

-4.5 ILRT Results Leakage Rate (wt. %/ day)

Lam Lcalc 95% UCL 95% UCL 95% UCL

+ LLaf*

+ LLa l

• Tot Timet 0.0516 0.0427 0.0649 0.0681 0.0652 Mass Pt:

0.0457 0.0504 0.0536 0.0507

• LLaf/al = Local-Leak Rate Penalty (as found/as left)

5. 0.

VERIFICATION TEST DATA

SUMMARY

5.1 Verification. Test

.1006%/ day (7.9 SCFM)

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

Results

-Limits Calculated 1)'

Total Time 0.1183 to 0.1683 0.1599 2)

Mass Point 0.1212 to 0.1712 0.1609

~.

4 SONdS 3 1992 ILRT TEST REPORT PAGE 7 6.0 LOCAL LEAK RATE TEST DATA

SUMMARY

6.1 PENETRATIONS NOT_ ALIGNED TO POST-ACCIDENT CONDITIONS During the ILRT, the penetrations listed below were not aligned to their post accident configuration.

The total for the measured local leak rates, for the following penetrations, obtained from Test proecdure SO3-V-3.13, " Containment 7enetration. Leak-Rate Testing," is given below.

T.t is added to the ILRT results as the As Left penalty and as a portion of the As Found penalty.

PEN #

DESCRIPTION VALVE #

10C

'ILRT PRESSURE SENSOR S31500MUO36 S31500MUO39 Z3C ILRT TLOW CONNECTION N/A 34 ILRT TEST CONNECTION N/A 42 COMPONENT COOLING WATER 3HV-6211 3HV-6223

-1

.43 COMPONENT COOLING WATER 3HV-6216 I

3HV-6236 45 NORMAL A/C CHILL WATER 3HV-9900 3HV-9920 46 NORMAL A/C CHILL WATER 3HV-9921 3HV-9371 LLRT AS LEFT PENALTY =

0.0003 %/ day i

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SONdS 3'1992 ILRT TEST REPORT PAGE 8 6.2 AS FOUND / AS LEFT LET P_ Ell %TX In accordance with IE information Notice Nr. 85-71,

" Containment Integrated Leak Rate Tests," an As Found/

As Loft LLRT penalty was calculated and added to the l

ILRT results.

The following penetrations apply to this calculation:

Pf,li_f, DESCRIPTION yALVE #

3C203 ESCAPE HATCH seals 3C406 PERSONNEL AIRLOCK SEALS 3C501 EQUIPMENT HATCH SEALS 2

LETDOWN LINE 3TV-9267 3HV-9205 4

HOT LEG SAMPLE 3HV-0508/09/17 8

CHARGING LINE S31208MU122 3HV-9200 13 CONTAINMENT SUMP 3HV-5803/04 A4 FIRE PROTECTION S32301MUO61 3HV-5686 15 FUEL TRANSFER TUBE BELLOWS / GASKET 18 CNTMT PURGE SUPPLY 3HV-9821/23/48/49 19 CNTMT PURGE EXHAUST 3HV-9824/25/50/51 21 SERVICE AIR S32423MUO17 S32423MUO55 23A NITROGEN SUPPLY S32418MUOO2 3HV-5437 26 RCDT DISCHARGE 3HV-7512/13 45 A/C CHILL WATER 3HV-9900/20 46 A/C CHILL WATER 3HV-9921/71 47 WASTE GAS VENT HDR 3HV-7258/59 53 CNTMT SPRAY INLET S31206MU006 3HV-9368 67 HOT LEG INJECTION S31204MU157 3HV-9434 68 AUX SPRAY BYPASS S31201MU129 S31208MU130 AS FOUND / LEFT PENALTY = 0.0029 %/ DAY The +-tal as found LLRT penalty is the sum of the va'

,in sections 6.1 and 6.2, or:

l TOTAL AS FOUND LLRT PENALTY = 0 0032 %/ DAY l

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-p SON $8 3 1992.LRT TEST REPORT PAGE 9 7.0 M GLYSIS AND INTFRPRETATION 7.1 PRESSUR17ATION Pressurization started at 2215 on 3-7-92.

Tes t pressure of 72.6 PSIA was-achieved at 1345 on 3-8-92.

Average pressurization rate was 3.7 PSI /HR using a 12,000 SCFM diesel _ compressor system.

7.2 CONTAINMENT ATMOSFHEBE STARILIZATION The acceptance criteria for contninment atmosphere temperature stabilization at test pressure 'are provided by ANSI /ANS 56.8-1987 and BN-TOP-1.

These criteria ensure that the' rate of change of the containment temperature is proportional to the rate oJl change of containment pressarc and that containment atmosphere is at test pressure for-at least four hours.

An additional criterion for mass stabilization was also used.

This required mass differentials :to be trending towards a constant, negative value to er.sure that temperature-and pressure were moving together.

Stabili7.ation commenced at 1345 and was achieved at 2200.

All ANSI /ANS 56.8-1987, BN-TOP-1 and mass stabilization criteria were met.

Unit 3' Cycle 6 stabilization facts:

The stabilization duration was 8.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

34' data points were us;d in the calculations.

Data was collected a' 15 minute intervals.

~

The rate of change of temperatute was less than 1.0 F/ hour, overaged over the last two hours.

The rate of change _of temperature changes was less than 0.5 F/ hour / hour, averaged over the last two

-hours.

. Plobl of average temperature and -pressure versus time were maintained.

Individual sensor plots were maintained and reviewed prior to completion of stabilization.

14 i

SON 55 ' 'fS97 ILRT TEST-REPORT PAGE 39 j

7.3 ILRT (Total Time)

The ILRT leak rate is determined using the 95% UCL for Total Time, plus the sums of the measured leak rates for. penetrations not included in the ILRT and the_

-difference between as found/as left leakage rates for all penetrations.

This must be less than 75% of the

-allowable leakage rate (La) at the peak accident pressure (Pa).

SONGS Unit 3. Cycle 6 ILRT Test Facts:

The test duration was 8.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

33 data points were L ed i the malculations.

Data was collected at 15 minute intervals.

The Total Time double bounded 95% UCL calcr ated leak rate was 0.0649%/ day.

The as left penalty was 0.0003 %/ day and the as found penalty was 0.0032 %/ day (See Section 6.0).

75% of the allowable leak rate of 0.10%/ day is 0.075%/ day.

The 20 data point mean leak rate was 0.0588 %/ day

. with an established downward trend.

The' acceptance criterion for the ILRT, using the Total

_ Time _ technique, is satisfied, i.e.,

E 95%'UCL + Penalty (as left or as found) <.75'LA-(as found) 0.0649%/ day + 0.0032%./ day < 0.075%/ day 0.0681%/ day < 0.075%/ day (as left) 0.0649%/ day + 0.0003%./ day < 0.075%/ day 0.0652%/ day-< 0.075%/ day 7.4 ILRT'(Mass Point)_

The acceptance criteria for a short duration ILRT does not. allow the use of the Mass Point Method.

Data is supplied for information only.

SONGS Unit 3 Cycle 6 Mass Point Facts:

The Mass Point Leakage Rate calculated with a 95%

,4 probability UCL is 0.0504%/ day.

+

.._.s_.

SONGS-3~1992 ILRT' TEST REPORT PAGE 11 The LLRT penalty,-for penetrations not included-in the ILRT, and the as found/ah left leakage is 0.0032 %/dsy_-(See Section 6.0).

75% of the allowable leakage rate of-0.10%/ day is 0.075%/ day._

The Mass Point acceptance criterion for ILRT leakage is satisfied, i.e.,

95% UCL + Penalty (as left or e found) <.75 La (as fcund) 0.0504%/ day +'O.Ous2%/ day < 0.075%/ day 0.0536%/ day < 0.075%/ day (as left) 0.0504%/ day + 0.0003%/ day < 0.075%/ day 0.0507%/ day < 0.075%/ day 7.5 1MPOSED LEAKAGE VERIFICATION TEST 7.5.1

' TOTAL TIME CALCULATIONS The acceptance criterion for the imposed leakage verification test is given by-the following equation:

Lo + Lcalc

.25 La s Lver s Lo + Lcalc +.25 La imposed leak rate which must

where, Lo

=-

be in the range

.75 La $ Lo $ 1.25 La Lcalc =

ILRT calculated leakage rate at the end of tne test Verification test calculated

Lyer

=

leakage rate Additional criteria are:

. Calculations shall utilize at least 10 data points',

The imposed leak shall be allowed to stabilize for one hour.

L l

Verification test duration, as required by L

-BN-TOP-1, shall be at least five hours which is approximately one half the test duration.

I

9

. SONGS 3 1992 ILRT TEST REPORT PAGE 12 Actual Test Data ama as follows:

0.1006%/ day (7.9 SCFM)

Lo

=

0.025%/ day 0.25 Ia

=

Lcalc 0.0427%/ day

=

0.1599%/ day Lver___

=

Data Points 17-

=

Duration 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

=

The acceptance criterion for the Tutal Tine technique for determining the imposed leak rate was satisfied, i,e.,

Lo + Lcalc

.25 La 5 Lver i Lo + Lcalc +.25 La 0.1006 + 0.0427 - 0.025 $ 0.1599 5 0.1006 + 0.0427 + 0.025 0.1183 $ 0.1599 $ 0.1683 7.5.2 MASS POINT CALCULATIONS The acceptance criterion for the imposed leakage verification test osing the Mass Point technique is the same as Total Time technique defined in Section 7.5.

Actual. Test Data are as follows:

0.1006%/ day (7.9 SCFM)

Lo

=

0.025%/ day

0. I La

=

Lealc 0.0457%/ day

=

0.1609%/ day Lver

=

Data Points 17

=

Duration 4.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />

=

The acceptance criterion for the Mass Point technique for determining the imposed leakage was satisfied, i.e.,

Lo_+ Lcalc -.25 La 1 Lver s Lo

+ Lcalc +.25 La 0.1006 + 0.0457 - 0.025 1 0.1609 5 0.1006 + 0.0457 + 0.025 0.1213 $ 0.1609 $ 0.1713 NOTE:

-As-a result of using four significant figures, 0.1213 and 0.1713 reflect round off errors. The ILRT program used'eight significant figures and did not get this error, resulting in 0.1212 and 0.1712 being used as limits in the ILRT.

g.

SONGS 3.1992 ILRT TEST. REPORT' PAGE 13 j

8.O LQO];L LEAK RATE TESIIJ1G SUMMARJ Penetration (Type B and C) testing was ' accomplished in

-accordance with-the requirements'of the Technical Specification 4.3.1 and per SO3-V-3.13.

The penetrations were tected using the pressure decay and make up methods.

The allowable leakage for all penetrations is 0.060 wtt/dayL

_(0.6 La)-of containment air mass at 57.7 PSIG.

Leakages in excess of the Unit 3 Technical Specification limit of 0.005 wt%/ day-for_ Penetration 18,-Purge Valve Supply, were detected and repaired during the quarterly surveillances performed on-5/15/89 and on 7/24/89.

Neither of these events resulted in.an overall containment leakage rate in excess of 60% La, or 0.060 wt%/ day.

The followingfis~an Operational History of Unit 3 since the previous.ILRT.(conducted in July 1988) and the through~

penetration leakage expressed in wt%/ day.

DATE.

DESCRIPTION LEAKAGE {wt_%/ DAY) 8-88 ENTERED MODE 4 0.011 4-16-90 ENTERED MODE 5 0.010 7-7-90 ENTERED MODE 4 0.009 1-26-93 ENTERED MODE 5~

0.008 1

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