ML20155D493

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Rev 1 to Reactor Containment Bldg Integrated Leak Rate Test,880501
ML20155D493
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 05/20/1988
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML20155D479 List:
References
NUDOCS 8806150211
Download: ML20155D493 (11)
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i ARKANSAS POWER AND LIGHT COMPANY ARKANSAS NUCLEAR ONE, UNIT 2 00CKET NUMBER 50-368 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST MAY 1, 1985 Revision 1 May 20, 1988 Submitted to The United States Nuclear Regulatory Commission Pursuant To Facility Operating Licensing Number NPF-6 SU-082 8806150211 880603 gDR ADOCK0500g3f8 - - - - - - - - -

I. INTRODUCTION-The reactor containment building Integrated Leakage Rate Test (Type A) is performed to demonstrate that leakage through the primary reactor containment and systems and components penetrating primary containment does not exceed allowable leakage rate values as specified in the Plant Technical Specifications. .

A' successful Type-A test was performed at-Arkansas Nuclear One, Unit 2 between 1230 on 4/30/85 and 1230 on 5/1/85. The results were substantiated by the data from the Verif.ication Test acquired between 1630 and 2030 on 5/1/85.

These tests were performed according to the requirements of the Arkansas Nuclear One Technical Specifications and 10CFR50, Appendix J. The Type A test was conducted applying the absolute method defined in ANSI /ANS 56.8-1981 (previously ANSI N274), "Containment System Leakage Testing Requirements."

The leakage rate was calculated by formulas specified in ANSI 45.4-1972,

'"Leakage Rate Testing of Containment Structures for Nuclear Reactors" and

< ANSI /ANS 56.8-1981. A total-time analysis is also_ included as described in ANSI 45.4-1972 and Bechtel _ Topical Report BN-TOP-1, "Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants," as referenced in the ANO-2 Technical Specifications.

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- III. TEST DATA

SUMMARY

A. Plant Information-Owner. Arkansas Power & Light Plant Arkansas Nuclear One, Unit 2 Location 6 Miles NW of Russellville, Arkansas Containment type Prestressed, post-tensioned concrete NSSS, Supplier, Type CE, PWR Docket No. 50-368 License No.- NPF-6 B. Technical Data

1. Containment Net Free Air Volume 1,780,000 cu. ft.
2. Design Pressure 54 psig

.3. Design Temperature _ 288 F

4. Calculated Peak Accident 54 psig Pressure, Pa
5. -Peak Accident Temperature 411 F C. Test Results - Type A Test 1.. Test Method Absolute
2. 0ata Analysis Techniques Mass Point (per ANSI /ANS 56.8-1981)

Total Time-(per ANSI 45.4-1972 and BN-TOP-1)

3. Test Pressure 54.3 psig

, '4. -Maximum Allowable Leakage 0.1%/ day Rate, La

5. 75% of La 9.075%/ day
6. Integrated Leakage Rate Test Leakage Rate, %/ day Results From Regression At Upper 95%

Line (Lam) Confidence Limit

a. Mass Point Analysis 0.022 0.023
b. Total Time Analysis

%/ day Mean of the measured leakage rates = .042 Maximum allowable leakage rate = .100 75% of maximum allowable leakage rate = .075 The upper 95% confidence limit = .020 The calculated leakage rate = .011 SU-082 5

7. Verification Test Imposed 5.85 SCFM Leakage Rate (0.1%/ day)
8. Verification Test Results Leakage Rate T/ day
a. Mass Point Analysis 0.1zu
9. Verification Test Limits Test Limits

%/ day

a. Mass Point Analysis
1) Upper Limit (Lo+ Lam +0.25La) 0.147
2) Lower Limit (Lo+ Lam-0.25La) 0.097
10. Report Printouts The Report Printouts of the Type A and Verification Test summary data and calculations are provided for the Mass Point Analysis and Total Time Analysis (appendices C through H). Stabilization data are also provided (Appendices B and F).

D. Test Results - Type 8 & C Tests Refer to Appendix I for a s nmary of Local Leakage Rate Test results since the last ILRT was performed.

E. Integrated Leakage Rate Measurement System

1. Absolute Pressure (2 channels)

Range: 0-100,000 counts Measurement system error: 0.001 psia Sensor error: 0.005 psig Range: 0-100 psia Repeatability: 0.0005 psia Texas Instruments Model 145-02 Precision Pressure Instrument, Serial Number No. 2861 Bourdon Capsule Ser:al No. 6806 Calibration Date: 4/3/85 Texas Instrument Model 145-02 Precision Pressure Instrument, Serial Number No. 2860 Bourdon Capsule Serial No. 6807 Calibration Date: 4/3/85

2. Drybulb Temperature (18 plus 3 spares)

Range: (-190) - (+200) F Measurement system error: 0.1 F Sensor error: 0.2 F Repeatability: 0.05 F Resistance Temperature Detectors - Leeds & Northrup Thermohm lead, 100 ohm copper Calibration Date: 11/19/84 SU-082 6

IV. ANALYSIS AND INTERPRETATION A. Type A Test Adjustment and Other Penalties The following penetrations were used for the ILRT:

Penetration No. Equipment Leakage Rate 2P-61A 2IA-88 0 accm 2P-61B 2IA-89 2.80 accm 2P-62 ILRT Pressurization Line ~

40.40 accm 43.20 accm B. Valve 2PS-189 at penetration number 2P-66 was hand tightened during the test. However, this does not constitute an adjustment as this penetration is not required to be vented. Therefore, closing this valve was not necessary for succe5sful completion of the test.

C. Type B and C Test Results The total of tested type B and C local leakage rates are: as found 5058.707 accm; as left, 1388.887 accm. The acceptance criterion is that the above total be less than 20,990 accm (.06% per day, 60% of La). The total for type B and C tests for the "as found" condition is within the acceptance criteria.

D. Conclusions The ILRT results for the upper 95% confidence limits at 54 psig (-0 psi, + .3 psi) were:

Mass Point Analysis .023% per day.

Total Time Analysis .020% per day.

These values must be increased by leakage rates in section IV.A above. The total, 43.20 accm (equivalent to 0.00012% per day),

added to the 95% confidence limit results in a value of .023%

per day for Mass Point Analysis, and .020% per day for the Total Time Analysis.

The acceptance criterion is that this value be less than .075%/ day (75% of La). The calculated value is within the acceptance criteria.

The ISG was calculated as 0.011%/ day which is within the acceptance criterion of 5 025 (25% of La).

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LiRT DATA FOR PENETRATIONS USED DURING MAY 1985 ILRT PENETRATION VALVE ACTUAL FOUND ACTUAL LEFT NUMBER NUMBER LEAXAGE (ACCM) LEAKAGE (ACCM) DATE 2P61 2IA88 0 5/6/85 2P61 2IA89 2.80 5/7/85 2P62 Blank Flanges 40.4 '5/7/85 NOTE: 2PS-189 was closed during ILRT to keep the following valves from leaking water. However, these valves are not subject to type C testing and are not required to be vented during ILRT. This leakage is reported for information only.

LLRT CATA FOR VALVES 2SV5633-1 & 2SV5633-2 PENETRATION VALVE ACTUAL FOUND ACTUAL LEFT NUMBER NUMBER LEAKAGE (ACCM) LEAKAGE (ACCM) DATE 2P66 2SV-5633-1 Not Applicable 29.43 5/10/85 2P66 2SV-5633-2 Not Applicable 11.10 5/10/85 NOTE: These valves were within the boundary for ILRT, and were closed

  • during ILRT. These valves are not subject to type C *.esting and are not required to be vented during ILRT. This leakage is reported for information only.

LLRT DATA FOR VALVES 2SV-5634-1 and 2 I PENETRATION VALVE ACTUAL FOUND ACTUAL LEFT NUMBER NUMBER LEAKAGE (ACCM1 LEAKAGE (ACCH) DATE 2P67 2SV-5634-1 Not Applicable 5.51 5/8/85 2P67 2SV-5634-2 Not Applicable 5.54 5/8/85 SU-082 I-2

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TYPE:C TESTS PENETRATION ' VALVE "AS-FOUND" "AS-LEFT"

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NUM3ER SYSTEM LEAKAGE (ACCM)~ LEAKAGE (ACCM),

t 2P-6  : Containment HVAC 29.24' 29.24 2P-B  : Sampling System 57.43 57.43- [

2P-9 Hydrogen'and Nitrogen Addition 13.98 13.98 -

' 2P-14 Chemical and Volume Control 784.12 76447 l 2P-18 Chemical and Volume Control' O.00 0.00-2P Gaseous Radioactive Waste 137.25 38.19' 2P-37 Sampling System -8,56 8.56 ,

2P-39 Reactor Coolant System 0.00 0.00 2P-40 Fire Water System 1827.86 0.00 2P-41 _ Hydrogel,and Nitrogen Addition 124.01 28.62~

4 2P-51 Chilled Water 0.0 0.0 2P-52 Component Cooling Water 82.78 82.78

- 2P-58 Containment HVAC 21.94 21.94 2P-59 Chilled Water 862.84 341.88

- 2P-60 Component Cooling Water 0.0 0.0

. 2P-61 Instrument ' Ai r 7.01 7.01 2P-62 Instrument Air 4.12 4.12-2F-68 Liquid Radioactive Waste 69.24 69.24-2P-69 Boron Management System 421.21 2.31 2V-1 Containment HVAC 568.80 568.80 2V-1 containment HVAC 0.0 0.0 ,

Total 5020.39 1350.57 I

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TYPE B TESTS PENETRATION LEAK RATE (ACCM)

NUMBER SYSTEM "AS-FOUND" "AS LEFT" 2C-1 Equipment Hatch 35.86 35.86

. 2C-2 Escape Lock C.0 0.0 2C-3 Fuel Transfer Tube 0.0 0.0 2C-4 Personnel lock 0.0 0.0 2E-1 Electrical Penetration 2.46 2.46 All Other Electrical Penetrations 0.0 0.0 Total 38.32 38.32 "AS-FOUND" "AS LEFT" TOTAL OF TYPE 8 AND C PENETRATIONS TESTED 5058.707 1388.887 l

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LLRT DATA TAKEN JUST PRIOR TO MAY 1985 ILRT PENET. VALVE- LEAKAGE (ACCM)

NUMBER NUMBER "AS-FOUND "AS-LEFT" COMMENTS 201 Equip. Hatch 35.86 35.86 Performed under 2304.22 control Copy #151 2L2 Barrel 0.00 0.00 Performed under 2304.22 control copy #151 2C2 Inner Saal 0.00 0.00 202 Outer Seal 0.00 0.00 2C3 Fuel Transfer 0.00 0.00 2C4 Inner Seal 0.00 0.00 Performed under 2304.22 control copy #153 2C4 Outer Seal 0.00 0.00 2P6 2SV-8273-1 24.21 24.21 2P6 2SV-8271-2 23.84 23.84 2P6 2CV-8233-1 0.00 0.00 2P6 2SV-8231-2 5.03 5.03 2P8 2SV-5833-1 57.43 57.43 2P8 2SV-5843-2 20.87 20.87 2P9 2CV-6207-2 13.98 13.98 2P14 2CV-4821-1 76.47 76.47 2P14 2CV-4823-2 784.12 60.375 Volume correction 2P18 2CV-4846-1 0.00 0.00 2P18 2CV-4847-2 0.00 0.00 2P31 2CV-2401-1 121.49 26.25

'2P31 2CV-2400-2 137.25 38.19 2P37 ?SV-5878-1 3.38 3.38 2P37 2SV-5876-2 3.75 3.75 2P37 2SV-5871-2 4.81 4.81 2P39 2CV-4690-2 0.00 0.00 2P40 2CV-3200-2 1827.86 0.00 2P41 2CV-6213-2 124.01 28.62 2P51 2CV-3852-1 0.00 0.00 2P52 2CV-5236-1 82.78 82.78 2P58 2SV-8261-2 2.74 2.74 2P58 2SV-8263-2 17.41 17.41 2P58 2CV-8259-1 4.53 4.53 2P58 2SV-8265-1 15.70 15.70 2P59 2CV-3850-2 0.00 0.00 2P59 2CV-3851-1 862.84 341.88 2P60 2CV-5255-1 0.00 0.00 2P61 2IA-88 5.607 5.607 2P61 2IA-89 1.40 1.40 2P62 Blank Flanges 4.12 4.12 2P68 2CV-2061-2 69.24 69.24 2P68 2CV-2060-1 42.45 42.45 2P69 2CV-2201-1 2.31 2.31 2P69 2CV-2201-2 421.21 0.00 2V1 2CV-8284-2 2CV-8289-1 568.80 568.80 2V2 2CV-8286-2 2CV-8291-1 0.00 0.00 SU-082 I-7

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ARKANSAS NUCLEAR ONE - UNIT 2 LEAKAGE RATE (WEIGHT PERCENT / DAY)

TOTAL TIME ANALYSIS

. TIME AND DATE AT START OF TEST: 1230 430 1985 TEST DURATION: 24.00 HOURS TIME TEMP PRESSURE MEASURED (R) (PSIA) LEAKAGE RATE 1230 535.067 68.5868 1245 535.089 68.5876 .284 1300 53D.077 68.5864. .112 1315 535.088 68.5871 .114 1330 535.100 68.5886 .081 1345 535.105 68.5880 .102 1400 535.113 68.5887 .093 1415 535.118 68.5892 .081 1430 535.123 68.'5898 .073 1445 535.128 68.5919 .043 1500 535.120 68.5925 .016 1515 535.130 68.5908 -.052 1530 535.140 68.5913 .056 1545 535.171 68.5922 .085 1600 535.148 68.5921 .050 1615 535.155 68.5917 .060 1630 535.456 68.5947 .030 1645 535.175 68.5929' .064 1700 535.171 68.5961 .032 1715 535.169 68.5948 .038 1730 535.187 68.5945 .054 1745 535.189 68.5935 .059 1800 535.191 68.5915 .071 1815 535.195 68.5960 .043 1830 535.206 68.5973 .043 1845 535.208 68.5950 .055 1900 535.210 68.5958 .050 1915 535.207 68.5970 .040 1930 535.210 68.5976 .038 1945 535.227 68.5965 .052 2000 535.226 68.5991 .037 2015 535.219 68.5979 .038 2030 535.239 68.6029 .026 2045 535.237 68.5980 .045 2100 535.236 68.5986 .041 2115 535.243 68.5999 .038 2130 535.248 68.6000 .039 2145 535.258 68.6001 .042 2000 535.256 68.5998 .041 2215 535.253 68.6002 .037 2230 535.252 68.6015 .031 2245 535.257 68.6036 .026 2300 535.271 68.6030 .033 2315 535.276 68.6030 .034

. 2330 535.271 68.6029 .032 2345 535.290 68.6040 .035 D-1

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0 535.278 68.6037 .031 15, '535.296 68.6047 .034 30 535.288 68.6040 .033 45 335.289 68.6040- .032 100 535.299 68.6065 .028 115 535.294 68.6047 .030 130 535.310 68.6037 .038 145 535.304 68.6044 .034 200 535.323 68.6069 .033 215 535.326 68.6052 .037 230 535.332 68.6055 .008 245 535.324 68.6061. .033 300 535.325 68.6088 .027 315 535.335 68.6061 .036 330 535.326 68.6079 .008 345 535.337 68.6089 .029

. 400- 535.329 68.6072 .030 415 -535.335 68.6088 .027 430 535.336 68.6084 .028 445 535.342 68.6082 .030 500 535.356 68.6094 .030 515 535.356 68.6111 .027 530 535.341 68.6092 .026 545 535.366 68.6102 .030 ,

600 535.350 68.6092 .028 615 535.353 68.6105 .026 630 535.358 68.6111 .025 645 535.357 68.6116 .024 700 535.352 68.6109 .024 I 715 535.346 68.6118 .020 730 535.382 68.6121 .028 745 535.382 68.6110 .029 800 535.374 68.6113 .027 815 535.368 68.6097 .028 830 535.385 68.6109 .029 845 535.371 68.6098 .028 900 535.376 68.6105 .027 915 535.371 68.6109 .025 930 535.566 68.6112 .023 945 535.379 68.6076 .031 1000 535.358 68.6101 .023 1015 535.375 68.6091 .028 l 1030 535.386 68.6084 .031 1045 535.385 68.6094 .029 1100 535.386 o8.6068 .033 1115 535.380 68.6091 .028 1130 535.382 68.6099 .026 1145 535.396 68.6105 .028 1200 535.395 68.6111 .026 i

1215 535.394 68.6158 .019 1230 535.394 68.6089 .029 ,

MEAN OF THE MEASURED LEAKAGE RATES = .042 MAXIMUM ALLOWABLE LEAKAGE RATE = .100 75% OF MAXIMUM ALLOWABLE LEAKAGE RATE = .075 THE UPPER 95% CONFIDEN,CE LIMIT = .020 THE CALCULATED LEAKAGE RATE = 011 D-11 '

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