ML13330B338

Reactor Containment Bldg Integrated Leak Rate Test, Final Rept

ML13330B338
Person / Time
Site:	San Onofre
Issue date:	03/31/1988
From:	Morgan H Southern California Edison Co
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8806280203
Download: ML13330B338 (16)

Text

SOUTHERN CALIFORNIA EDISON COMPANY SAN ONOFRE NUCLEAR GENERATING STATION UNIT 1 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST FINAL REPORT MARCH 1988 TEST 8806280203 80331" PDR ADOCK 05000206 P

- PDR

SONGS 1 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 5

3.0 TECHNICAL DATA 6

4.0 TEST DATA

SUMMARY

6 5.0 VERIFICATION TEST DATA

SUMMARY

7 6.0 LOCAL LEAK RATE TEST DATA

SUMMARY

7 7.0 ANALYSIS AND INTERPRETATION 8

7.1 PRESSURIZATION 8

7.2 CONTAINMENT ATMOSPHERE STABILIZATION 8

7.3 ILRT (Total Time) 8 7.4 ILRT (Mass Point) 9 7.5 IMPOSED LEAKAGE RATE VERIFICATION TEST 10 7.5.1 TOTAL TIME CALCULATIONS 10 7.5.2 MASS POINT CALCULATIONS 11 8.0 LOCAL LEAK RATE TESTING

SUMMARY

11 9.0 ATTACHMENT 1 13

SONGS 1 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 1 Technical Specification, Section 4.3.1.

The test was performed as part of the Unit 1 Cycle 9 second midcycle outage.

The successful Type A and supplemental verification tests were performed in accordance with the requirements of San Onofre Nuclear Generating Station, Unit 1, Procedure SO1-V-1.3, Revision 13, Sphere Integrated Leak Rate Test. The test method utilized was the absolute method described in ANSI N45.4-1972, "American National Standard Leakage-Rate 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, and ANSI/ANS 56.8-1981.

1Property "ANSI code" (as page type) with input value "ANSI/ANS 56.8-1981.</br></br>1" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..2 TEST SYNOPSIS Pressurization was commenced at 0533 on 3-19-88 and test pressure was obtained at 2051 on 3-19-88.

Stabilization was achieved in approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, with the test commencing at 0300 on 3-20-88. The verification test was started at 0515, on 3-21-88.

One hour was allowed for stabilization. The verification test was completed at 1115 on 3-21-88.

Depressurization was started at 1115, on 3-21-88 and completed at 2230, on 3-21-88.

The Primary Containment Integrated Leakage Rate Test (ILRT) was successfully completed at 1115, on 3-21-88 at the San Onofre Nuclear Generating Station, Unit 1.

All ILRT requirements of the Technical Specifications were satisfied.

SONGS 1 1988 ILRT TEST REPORT PAGE 4 TEST SEQUENCE START COMPLETION PRESSURIZATION 0533 3-19-88 2051 3-19-88 STABILIZATION 2100 3-19-88 0300 3-20-88 TEST 0300 3-20-88 0300 3-21-88 VERIFICATION 0515 3-21-88 1115 3-21-88 BLOWDOWN 1115 3-21-88 2230 3-21-88 TOTAL TIME ANALYSIS Analysis of the measured data taken during the test resulted in a measured leakage rate of 0.048 %/day, a calculated leakage rate of 0.041 %/day and a 95 %

probability upper confidence limit (UCL) leakage of 0.051 %/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 0.004%/day Local Leak Rate penalty (See Section 6.0) yields an overall leakage rate of 0.055 %/day of contained air mass which satisfies the acceptance criteria of being less than 0.090 %/day.

MASS POINT ANALYSIS Analysis of the measured data taken during the test resulted in a calculated leakage rate of 0.049 %/day and a 95 % probability upper confidence limit (UCL) leakage of 0.051 %/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 0.004%/day Local Leak Rate penalty (See Section 6.0) yields an overall leakage rate of 0.055 %/day of contained air mass which satisfies the acceptance criteria of being less than 0.090 %/day.

VERIFICATION TEST Following the completion of the ILRT measurements, a successful verification test was performed with an imposed leakage rate of 4.474 SCFM. The Total Time measured leakage rate of 0.137 %/day and calculated leakage rate of 0.147 %/day was within the allowable limits of 0.131 %/day to 0.191 %/day. The Mass Point calculated leakage rate of 0.141 %/day established during the verification test was within the allowable limits of 0.138 %/day to 0.198 %/day.

SONGS 1 1988 ILRT TEST REPORT PAGE 5 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 1 Technical Specifications.

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

1)

A listing of all containment penetrations, penetration 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 and Bechtel Power Corporation developed computer programs.

8)

P&IDs

9)

Local Leak Rate Test History Files 2.0 GENERAL DATA (PLANT INFORMATION) 2.1 Owner Southern California Edison 2.2 Docket No.

50-206 2.3 Plant San Onofre Nuclear Generating Station, Unit 1 2.4 Location San Onofre, California

SONGS 1 1988 ILRT TEST REPORT PAGE 6 2.5 Containment Type Steel Sphere 2.6 NSSS Supplier Westinghouse, PWR 3.0 TECHNICAL DATA 3.1 Containment Net 1,200,000 cubic feet Free Air Volume 3.2 Design Pressure 53.3 PSIG 3.3 Design Temperature 391.5 degrees F 3.4 Calculated Peak 49.4 PSIG Accident Pressure (Pa) 3.5 Calculated Peak 271.2 degrees F Accident 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 BN-TOP-1, Rev. 1

2)

Mass Point per ANSI/ANS 56.8-1981 4.3 Test Pressure 51 PSIG + 0.4, -0.0 PSIG 4.4 Maximum Allowable 0.120%/day Leakage Rate (La) 4.5 ILRT Results Leakage Rate (wt. %/day)

Lam Lcalc 95% UCL 95% UCL

+ LL*

Total Time 0.048 0.041 0.051 0.055 Mass Point 0.049 0.051 0.055

• LL = Local Leak Rate Penalty

SONGS 1 1988 ILRT TEST REPORT PAGE 7 5.0 VERIFICATION TEST DATA

SUMMARY

5.1 Verification Test

.12%/day (4.474 SCFM)

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

Results Limit Rate

1)

Total Time 0.131-0.191 0.147

2)

Mass Point 0.139-0.199 0.141 6.0 LOCAL LEAK RATE TEST DATA

SUMMARY

6.1 PENETRATIONS NOT ALIGNED TO SIMULATE POST-ACCIDENT CONDITIONS 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 SO1-V-1.12, "Containment Penetration Leak-Rate Testing," or by calculation are given below and are added to the ILRT results.

VOL #

DESCRIPTION VALVE #

21 INSTRUMENT AIR S1-ISA-001/

S1-ISA-955 31 HOT LEG ALT. RECIRC.

Sl-CRS-020/

S1-CRS-341 35 SPHERE TEST SYSTEM S1-STS-303 36 SPHERE TEST SYSTEM S1-STS-320 E15 SIS VENT SYSTEM S1-SIS-SV-702A, B, C, & D LLRT PENALTY 0.0002 % / day 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 was calculated and added to the ILRT results. The following penetrations were applicable to this calculation:

VOL #

DESCRIPTION VALVE #

1 ESCAPE HATCH SEALS 12 SPHERE VENTILATION POV-10/S1-CVS-313 17 SPHERE SUMP S1-RLC-CV-102 S1-RLC-CV-103

SONGS 1 1988 ILRT TEST REPORT PAGE 8 VOL #

DESCRIPTION VALVE #

27 PZR SAMPLE S1-RLC-CV-951 S1-RLC-CV-953 S1-RLC-CV-992 AS FOUND / LEFT PENALTY = 0.00329408 %/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 = 0.004 %/DAY 7.0 ANALYSIS AND INTERPRETATION 7.1 PRESSURIZATION Pressurization started at 0533 on 3-19-88. The test pressure of 65.958 PSIA was achieved at 2051 on 3-19

88.

The average pressurization rate was 3.34 PSI/HR over the 15.3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> period using a 5,100 SCFM diesel compressor system.

7.2 CONTAINMENT ATMOSPHERE STABILIZATION The acceptance criteria for containment atmosphere stabilization at test pressure is that the rate of change of the containment temperature (weighted average of RTD sensors) is less than 1.0 degree F averaged over the last two hours; or, the rate of change of temperature changes is less than 0.5 degree F / hour /

hour averaged over the last two hours; and that the containment atmosphere has been at test pressure for at least four hours. Temperature stabilization commenced at 2100 and was achieved at 0300.

7.3 ILRT (Total Time)

The acceptance criteria for the ILRT is that the leakage rate determined using the 95% UCL value for Total Time calculated leakage rate plus the sums of the measured leakage rates for penetrations not included in the ILRT with the difference between as found/as left leakage rates for all penetrations, must be less than 75% of the allowable leakage rate (La) at the peak accident pressure (Pa).

SONGS 1 1988 ILRT TEST REPORT PAGE 9 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 upper bound 95% probability value for the calculated leak rate using the Total Time technique was 0.051%/day.

The LLRT penalty for penetrations not included in the ILRT and as found / as left leakage is 0.004

%/day (See Section 6.0).

75% of the allowable leakage rate of 0.120%/day is 0.090%/day.

0.75La = 0.090%/day.

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

95% UCL + LL

<.75 LA 0.051%/day + 0.004%/day < 0.090%/day 0.055%/day < 0.090%/day 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 pressure (Pa).

The Mass Point Leakage Rate calculated with a 95%

probability UCL is 0.051%/day.

95% UCL = 0.051%/day The LLRT penalty for penetrations not included in the ILRT and as found / as left leakage is 0.004

%/day (See Section 6.0).

75% of the allowable leakage rate of 0.120%/day is 0.090%/day.

75% La = 0.090%/day The acceptance criteria for the ILRT leakage rate using the Mass Point technique is satisfied, i.e.,

SONGS 1 1988 ILRT TEST REPORT PAGE 10 95% UCL + LL <.75 La 0.051%/day + 0.004%/day < 0.090%/day 0.055%/day <

0.090%/day 7.5 IMPOSED LEAKAGE RATE VERIFICATION TEST 7.5.1 TOTAL TIME CALCULATIONS The acceptance criteria for the imposed leakage verification test is given by the following equation:

Lo + Lcalc -

.25 La < Lver < Lo + Lcalc +.25 La where, Lo

= imposed leakage rate which must be in the range

.75 La < Lo < 1.25 La Lcalc

= ILRT calculated leakage rate Lver

= Verification test calculated 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

=

0.120%/day (4.474 SCFM) 0.25 La

=

0.03%/day Lcalc

=

0.041%/day Lver

=

0.147%/day (Total Time)

Data Points

=

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

Lo + Lcalc -

.25 La < Lver. < Lo + Lcalc +.25 La 0.120 + 0.041 -

0.030 < 0.147 < 0.120 + 0.041 + 0.030 0.131 < 0.147 < 0.191

SONGS 1 1988 ILRT TEST REPORT PAGE 11 7.5.2 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.

Actual Test Data is as follows:

Lo

=

0.120%/day (4.474 SCFM) 0.25 La

=

0.03%/day Lcalc

=

0.049%/day Lver

=

0.141%/day (Total Time)

Data Points

=

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

Lo + Lcalc -

.25 La

< Lver

< Lo + Lcalc +.25 La 0.120 + 0.049 -

0.030 < 0.141 < 0.120 + 0.049 + 0.030 0.139 < 0.141 < 0.199 8.0 LOCAL LEAK RATE TESTING

SUMMARY

Penetration (Type B and C) testing was accomplished in accordance with the requirements of the Technical Specification 4.3.1 and per SO1-V-1.3.

The penetrations were 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 49.4 PSIG.

The following is an Operational History of Unit 1 since the previous ILRT (conducted in June 1984) and the through penetration leakage expressed in %/day.

DATE DESCRIPTION LEAKAGE (%/DAY) 11-02-84 ENTERED MODE 4 0.025 2-15-85 ENTERED MODE 5 0.022 2-25-85 ENTERED MODE 4 0.037 5-4-85 ENTERED MODE 5 0.037 5-9-85 ENTERED MODE 4 0.037 8-23-85 ENTERED MODE 5 0.053 8-26-85 ENTERED MODE 4 0.030 11-21-85 ENTERED MODE 5 0.030

SONGS 1 1988 ILRT TEST REPORT PAGE 12 DATE DESCRIPTION LEAKAGE (%/DAY) 7-3-86 ENTERED MODE 4 0.005 9-7-86 ENTERED MODE 5 0.006 9-28-86 ENTERED MODE 4 0.008 5-11-87 ENTERED MODE 5 0.010 6-26-87 ENTERED MODE 4 0.006 2-16-88 ENTERED MODE 5 0.007

SONGS 1 1988 ILRT TEST REPORT PAGE 13 ATTACHMENT 1 Southern California Edison Company San Onofre Nuclear Generating Station UNIT 1 LOCAL LEAK RATE TEST RESULTS OF PENETRATIONS WHICH CAUSED THE TOTAL LEAKAGE FOR ALL PENETRATIONS TO EXCEED 0.6 La (0.090 %/DAY)

SONGS 1 1988 ILRT TEST REPORT PAGE 14 TABLE OF CONTENTS

1.0 INTRODUCTION

1.1 SPHERE EQUALIZING LINE 1.2 PERSONNEL HATCH

SONGS 1 1988 ILRT TEST REPORT PAGE 15

1.0 INTRODUCTION

Leakage Test Results of Penetration Tests which failed to meet the acceptance criteria of 0.6 La (0.090 %/day) are given below. The values given were calculated in accordance with SOl-V-1.12, "Containment Penetration Leak-Rate Testing."

1.1 SPHERE EQUALIZING LINE (S1-CVS-CV-10, S1-CVS-CV-40, AND Sl CVS-CV-116)

On 9-15-84 a Local Leakage Rate Test (LLRT) was performed on the sphere equalizing line.

Test pressure was not achieved because of excessive leakage through valve Sl-CVS-CV-10.

The outboard containment isolation valve is Sl-CVS-CV-10, while S1-CVS-CV-40 and S1-CVS-CV-116 are the inboard containment isolation valves. The leak path was verified by installing a blank flange downstream of S1-CVS-CV-10 and retesting the penetration. Valve Sl-CVS-CV-10 was removed, reworked and then reinstalled. A successful LLRT was performed on 10-11-84 prior to entering a plant mode requiring containment leak integrity.

On 3-19-87 the quarterly LLRT of the sphere equalizing line failed because of excessive leakage through S1-CVS-CV-10.

The Unit was at power in Mode 1.

Valve Sl-CVS-CV-10 failed to stroke completely closed. The leak path was verified by installing a blank flange downstream of S1-CVS CV-10 and retesting the penetration. The stroke of the valve was adjusted with a successful LLRT performed on 3-19 87, approximately two hours after the initial LLRT.

1.2 PERSONNEL HATCH On 9-15-84, prior to entering a plant mode requiring containment integrity, a LLRT of the Personnel Hatch disclosed excessive leakage. The cause was identified as degraded duroseals for the handwheel shafts inside of containment. The seals were replaced. A successful retest was performed on 10-5-84.

On 3-21-86, prior to entering a plant mode requiring containment integrity, a LLRT of the Personnel Hatch showed excessive leakage. The cause was identified as the hatch seals resulting from hatch rebuild performed by the manufacturer, Chicago Bridge and Iron. The seals were replaced. A successful retest was performed on 4-1-86.

Southem California Edison Company SAN ONOFRE NUCLEAR GENERATING STATION P. 0. BOX 128 SAN CLEMENTE, CALIFORNIA 92672 H.E.MORGAN TELEPHONE STATION MANAGER (714) 368-6241 June 2, 1988 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555

Subject:

Docket No. 50-206 Reactor Containment Building Integrated Leak Rate Test San Onofre Nuclear Generating Station, Unit 1 An Integrated Leak Rate Test (ILRT) was performed at San Onofre Unit 1 during March 1988. The test was performed in accordance with the requirements of the Unit 1 Technical Specifications. Both the measured leak rate test and supplemental verification test met the acceptance criteria set forth in the Technical Specifications.

The enclosed ILRT report for San Onofre Unit 1 constitutes our final report and is being submitted pursuant to 10 CFR 50, Appendix J.

If additional information is required, please so advise.

Sincerely, Enclosure cc:

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

F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)