ML20029A136

Reactor Containment Bldg Integrated Leakage Rate Test.

ML20029A136
Person / Time
Site:	Beaver Valley
Issue date:	11/30/1990
From:	Manko R, Noonan T, Zyra T DUQUESNE LIGHT CO.
To:
Shared Package
ML20029A133	List: ML20029A132 ML20029A136
References
NUDOCS 9102040203
Download: ML20029A136 (83)

Text

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REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST DUQUESNE LIGilT COMPANY BEAVER VALLEY PO'JER STATION UNIT No. 2 NOVEMBER 1990 Prepared By: k # Date: 'l

• 4 7 ' 'IO R. J.W anko Test Enginee Reviewed By: .

44> Date: l-7-91 T 'G . 7y a Director s ing and Plant Performance Mh Date: '

I D. E. Spoet9y \ '

General Manager Nuclear Operation Services Date: [ [/

N. R. Tonet [/'

Manager Nuclear Safety Approved By: s Date: k T. P. NoonAn General Manager Nuclear Operations 9102040203 910123 ,

PDR ADOCK0500ge P

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3 TABLE OF CONTENTS l

Section Title Engg TABLE OF CONTENTS 1i .

LIST OF ATTACitMENTS 111 REFERENCES iv

, 1 PURPOSE 11 2-

SUMMARY

2.1 TYPE A ILRT 2.1-1 2.1,1 Test Summary 2.1 1 2.2 LOCAL LEAKAGE RATE TESTS (TYPES B & C) 2.2 1 3 INTEGRATED LEAKAGE RATE TEST 3.1 EDITED LOC OF EVENTS 3.1 3.2 CENERAL TEST DESCRIPTION 3.2 1 3 . 2 '.1 Prerequisites 3.2 1 3.2.2 Equipment and Instrumentation 3.2 2 3,2,3 Data Acquisition 3.2-2 3.2.4 Data Resolution System 3.2 3 3.3 TEST RESULTS 3.3 1 3.3.1 Presentation of Test Results 3.3 1 3.3.2 59.4 PSIA-ILRT Results 3,3-2 3.3,2.1 ILRT Results Total Time Analysis 3.3 2 3.3.2.2 ILRT Results Mass Point Analysis 3.3-3 3.3.2.3 Supplemental Test Results _ 3.3 3 3.3.2;4 Leakage Penalties added to ILRT Leakage 3.3 5 3.3.3 ' Concluc ion 3.3~9' 4 LOCAL LEAKAGE RATE TESTS (TYPES B AND C) 41 11 1:

' LIST OF ATTACMMENTS ATTACHMENT TITLE 2.1A Graph 1 Containment Air Mass vs Time 3.2A Instrumentation List 3.2B Instrumentation Selection Guide 3.3A ILRT Reduced Input Variables 3.3B ILRT Absolute Test Method Total Time Analysis Test Results 3.3C ILRT Absolute Test Method Mass Point Analysis Test Results 3.3D Graph 2 Containment Air Mass vs Time 3.3E Graph 3 Leakage Rate and UCL vs Time, Total Time Analysis 3.3F Craph 4 - Leakage Race and UCL vs Time, Mass 3.30 -Superimposed Leakage Verification Test Reduced Input Variables.

3.3H Superimposed Leakage-Vorification Test. Absolute

-Test Method Total Time Analysis 3.3I Superimposed Leakage Verification Test. Absolute Test Method Mass Point Analysis 4.1A First Refueling Local Leakage Rate 1 Test Data 4.1B First Refueling Local Leakage Rate Repairs 4.1C Second Refaeling Local Leakage Rate Test Data 4.1D Second Refueling Local Leakage Rate Repairs 4.1E First and Second Fuel' Cycle Local Leakage Rate Data-1 111

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4 REFERENCES 1.10CFR50, Appendix J, Primary Reactor Containment Leakage Testing f or Water Cooled Power Reactors, January 1, 1989,

2. 2BVT 1.47.2,- Contain:uont Integrated Leakage Rate Test, Beaver Valley Power Station Unit No. 2 Issue 2, Revision 0, August 16, 1990.

3. ANSI N45.4, American National Standard, Leakage Ra e Testing of Containment Structures for Nuclear Reactors, March 16, 1972.

4.-ANSI /ANS-56.8, Containment System Leakage Testing Requirements, January 20, 1987.1

5. Bechtel Topical. Report BN TOP 1, Testing Criteria for Integrated Lenkage Rate Testing of Primary Containment Structures for Nuclear

' Power Plants, November 1, 1972.

6. I&E. Inspection Procedure 70313 " Containment Integrated Leak Test Surveillance", October 3,1985.

I This document used only as a guidelir,e and any reference to said document in no way implies compliance, iv l

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_r SECTION 1 URPOSE 4

The purpose.of this report is to present a description and analysis of the November 1990 Type A Containment Integrated Leakage Rate Test (ILRT), and a -summary of Type B and C Local Leakage Rate Tests (LLRT's) performed since the pre-opertional ILRT (February 1987) at-Duquesne Light Company's

+? .Boaver Valley Power Station Unit No. 2 (BVPS 2).

Stone & Webster Engineering Corporation (SWEC) provided test engineering consultation services to Duquesne Light Company during the performance of

-th e 1990 ILRT, This - report is. submitted as required by 10CFR50, Appendix - J , Paragraph V.B.

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1 11

SECTION 2

SUMMARY

2.1 TYPE A ILRT 2.1.1 Test Summary Prior to ILRT performance, seal maintenance for Recirculation Spray Pump 2RSS*P21D was not completed. The alignment for this pump was revised to isolate it from containment by closing the respective suction and discharge valves. Af ter completion of the ILRT the pump would be tested locally, and the measured leakage added to the ILRT results (see Reference.

6).

Upon completion of all ILRT prerequisites and initial conditions, containment pressurization started.at 1417 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.391685e-4 months <br /> on October 24, 1990. The compressors were secured at 0416 hours0.00481 days <br />0.116 hours <br />6.878307e-4 weeks <br />1.58288e-4 months <br /> on October 25, 1990 with a peak instantaneous pressure of 60,990 PSIA.

At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on October 25, 1990, the temperature stabilization criteria

(< 0.5 'R/Last 2 Hrs) was satisfied. The ILRT was started at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on October 25, 1990, Af ter 1 1/2 hours of data analysis, the initially high mass trend of approximately 46 lbm/hr had shown signs of stabilizing at approximately 24 lbm/hr (acceptable mass trend is < 16 lbm/hr). The ILRT was restarted at 1100.

Extensive containment penetration . area leakage investigations since pressurization did not identify any si nificant 6 leakago paths. Temporary pressure gauges connected between the containment isolation valves indicated that the containment purge and supply penetrations (No.'s 90 &

91) wer.e slowly pressurizing. Minor leakage was also detected at 2RSS 101 (Recire Spray pump dominerialized water fill header vent).

2.1 1 l

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on October 25 1990 the mass trend was unacceptable at an approximate leakage rate of 27 lbm/hr. At 1540 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.8597e-4 months <br /> on October 25, 1990 the leakage from 2RSS 101 was isolated to assess the significance'of this leakage path. After approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> no noticeable change in the containment mass trend was observed.

Quench Spray Pump 21B discharge containment isolation valve 2QSS*MOV101B was closed at 1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br /> on October 25, 1990 to assess the possibility of this penetration as a leakage path. Penetration No. 64 ("B" Train Quench Spray) consists of a weighted arm check valve 2QSS*3 inside containment, and a motor operated valve 2QSS*MOV101B outside containment. 2QSS*MOV101B is NSA open, and also opened for the I LRT. Any leakage through 2QSS*3 would be to the Refueling Water Storage Tank (RWST), and not detectable by local inspection.

The containment mass trend did not improve as of 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on October 25, 1990. Isolation of the opposite train of Quench Spray was performed by closing Quench Spray Pump 21A discharge containment isolation valve 2QSS*MOV101A at 1903 hours0.022 days <br />0.529 hours <br />0.00315 weeks <br />7.240915e-4 months <br /> on October 25, 1990 to assess the possibility of this penetration as a leakage path. Penetration No. 63 ("A" Train Quench Spray) arrangement is the same as Penetration No. 64, except the inside containment isolation is 2QSS*4. By 2146 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.16553e-4 months <br /> on October 25, 1990 it was apparent that neither Quench Spray penetration contributed any improvement to the containment mass - trend; thus eliminating these penetrations as possible leahage paths.

The Fuel Transfer Tube was investigated as a potential leakage path . At 2151 ~ hours on October 25, 1990 the water level in the Fuel Building Uponder Canal was raised above the Fuel Trans fe r Tube. No leakage (bubbling water) was observed from the Fuel Transfer-Tube.

The possibility of -leakage into the steam generator secondary side was investigated due - to unexplained steam generator level instrumentation fluctuations. To assess this potential leakage path the steam generator secondary side was pressurized with air (air blocked) to slightly less 2.1-2

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than containment pressure. The air block reduces the differential pressure across the pressure boundary,_ and consequently reduces the magnitude ~ of any r otential leakage. Maintaining the air block pressure below containment pressure prevents inleakage into containment.

At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on October 25, 1990 pressurization of "C" Steam Generator was started. The mass trend improved to approximately 16 lbm/hr after "C" Steam Generator pressurization had been in progress for two hours.

Pressurization of "C" Steam Generator was co:::ple ted at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on October 26, 1990, The steam generator secondary side pressure was increased to within 0.2 psi of containment pressure.

At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on October 26, 1990 - pressurization of "A" Steam Generator was started. An _ improvement in the mass trend was noted, less than '16 lbm/hr, was observed after the start of "A" Steam Generator pressurization, Based on the improved mass trend, data collection was restarted at 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> on October 26, 1990, At 0720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> on October 26, 1990_ the air block pressure in "C" Steam Generator was reduced from 0.2 to 0.5 psi below containment pressure, data collection was restarted at 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br /> on October-26, 1990 based on the pressure reduction. At 0927 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.527235e-4 months <br /> on October 26, 1990 pressurization of "A" Steam Cenerator was completed at a pressure 0.5 psi below containment pressure.

At 1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br /> on October 26, 1990 data collection was restarted based on completing the air blocks on "A" and "C" Steam Generators, "B" Steam Generator was not air blocked. At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on October - 26, 1990 mass trend has been approximately 7 lbm/hr over last 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />, and calculated leakage rate is 0,04211 %/ Day (Total Time) and 0,04954 %/ Day (Mass Point).

Station. management elected to terminate the- 11.RT using the air blocks due to concerns that this condition may not yield valid testing, or achievable retesting, At 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br /> on October 26, 1990 the 11.RT was terminated. A steam generator pressure test would be performed after containment depressurization to identify leakage paths, and the ILRT reperformed after repairs to the steam generators, 2.1-3 l

At 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> on October 27, 1990 containment depressurization commenced.

At 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> on October 27, 1990 preparations were in progress to perform a pressure test of "A", * !!" , and "C" Steam Generators. At 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> on October 27, 1990 containment depressurization was completed.

Prior to pressurizing each steam generator a complete alignment verification of all valves located inside containment was successfully performed. No valves were found out of alignment on any steam generator.

Insulation was removed where necessary to permit access to steam generator manways, handholes, and root isolation valves. At 2029 hours0.0235 days <br />0.564 hours <br />0.00335 weeks <br />7.720345e-4 months <br /> on October 27, 1990 the steam Benerator pressure test commenced. The secondary side of each steam generator was maintained at approximately 50 psig while leakage inspections were performed inside containment.

At 0620 hours0.00718 days <br />0.172 hours <br />0.00103 weeks <br />2.3591e-4 months <br /> on October 28, 1990 the pressure test of all three steam generators was completed. Several packing leaks were detected on each steam generator and repaired. Two feedwater level transmitters on the "A" Steam Generator (2FWS*LT474 and 2FWS*LT476) were found leaking at the transmitter vent connection, and repaired. No quantification of the detected leakage paths could be performed.

Prior to containment pressurization for the ILRT, seal repair work on outside Recirculation Spray Pump 2RSS*P21D was completed. A local pressure test was satisfactorily completed. The pump was -unisolated f rom containment and aligned to NSA for the ILRT.

Upon completion of reverification of all ILRT prerequisites and - initial

. conditions, containment pressurization started at 1641 hours0.019 days <br />0.456 hours <br />0.00271 weeks <br />6.244005e-4 months <br /> on October 28, 1990. The compressors were secured at 1043 hours0.0121 days <br />0.29 hours <br />0.00172 weeks <br />3.968615e-4 months <br /> on-October 29, 1990 with a peak instantaneous pressure of 61.006 PSIA.

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> - on October 29, 1990 the temperature stabilization criteria was satisfied, The ILRT was started at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on October 29, 1990.

2.1 4

At 1709 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.502745e-4 months <br /> on October 29, 1990 the containment temperature trend indicates temperature is still stabilizing. The mass trend is being influenced ' by temperature which is still trending downward. Containment penetration area inspections have found no significant leakage paths.

At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on October 29, 1990 the ILRT was restarted based on the improved stability of containment temperature. At 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> on October 30, 1990 mass trend is approximately 10 lbm/hr, and calculated leakage rate is 0.08867 %/ Day (Total Time) and 0.060060 %/ Day (Mass Point).

The ILRT was completed at 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br /> on October 30, 1990 with a Total Time i Upper Confidence Level of 0.05888 t/ Day and a Mass Point Upper Confidence Level of 0.04533 t/ Day. This leakage rate is below the 0.75 La acceptance criteria of 0.075 t/ Day.

The Superimposed Leakage Verification Test was started at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on October 30, 1990 when the stability of all containment partmeter trends had recovered from the imposed leakage rate perturbation. The Superimposed Leakage Verifi ition Test was completed at 1515 on October 31, 1990 using Mass Point analysis; however, the Total Time analysis was just outside of 0.25 La limit. Correspondence with Duquesne Light Company Licensing Department provided interpretation that the wording of the BVPS #2 Technical Specifications did not permit for the use of the Mass Point Analysis regardless of its endorsement in 10CFR50, Appendix J.

The actual containment leakage rate was assumed to have been initially over influenced by temperature stabilization during the ILRT. The re fo re the ILRT was restarted at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on October 31, 1990 due to the improved stability of containment conditions. The ILRT was completed at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on November 1, 1990 with a BN TOP-1 Total Time Upper Confidence Limit of 0.06923 %/ Day, and a Mass Point Upper Confidence Limit of 0.02298

%/ Day (See Section 3.3, Test Results). This leakage rate is below the 0.75 La acceptance criteria of 0.075 %/ day.

2.1 5

The Superimposed Leakage Verification Test was started at 0915 hours0.0106 days <br />0.254 hours <br />0.00151 weeks <br />3.481575e-4 months <br /> on November 1,-1990 when the stability of all containment' parameter trends had recovered from the - imposed leakage rate perturbation. The Superimposed Leakage Verification Test was successfully completed at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> on November 1, 1989 (See Section 3.3, Test Results).

After review of all ILRT test data, containment depressurization started at 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br /> on November 1, 1990 and was completed at 0018 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> on November 2, 1990.

I 2.1 6

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a 2.2 LOCAL LEAYAGE RATE TESTS (TYPES B AND C) i The Local Leakage Rate Tests (LLRT's) of the containment ! solation valves and other containment penetrations were conducted as described in the Beaver Valley Power Station Unit No. 2 surveillance test procedures for Type B and C tests.

In accordance with Appendix J to 10CFR50, Paragraph V.B, data for the Local Leakage Rate Tests are summarized in Section 4 of this report.

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SECTION 3-INTECRATED LEAVACE RATE TEST 3.1 EDITED LOC OF EVENTS This log was edited from information contained in the ILRT test Log.

October 23. 1990 2000 - Revised alignment for Recirculation Spray Pump 2RSS*P210 - to isolate from c on tainmen t by closing suction and discharge valves'2RSS*MOV155D & 156D.

October 24. 1990 1230 - Verified all p r e re quis ites and initial conditions are satisfactory.

1245 - Secured the containment Personnel Airlock and success fully completed Type B test of door seals. Secured containment lighting.

1417 - Commenced ILRT pressurization. Initial containment pressure @

14.304-PSIA.

1800 - Containment pressure @ 25.690 PSIA- ,

2025 - Completed inspection of all containment penetration areas, no leakage detected.

3.1 1

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4-

-October 24. 1990 (continued)

NOTE: Hotor operated dampers inside containment for Penetration 90 and 91 were rotated 180' in response to NRC Information Notice 88 73 prior to ILRT performance.

2115 - Noted slight increase on pressure gauge installed at Penetration No. 90, Containment Purge Exhaust, 2300 - Containment pressure @ 42.834 PSIA.

October 25. 1990 0050 - Completed walkdown of all penetration areas, no problems were detected.

0200 - Containment pressure @ 53,335 PSIA.

0416 - Secured containment pressurization with -a peak instantaneous pressure of 60.990 PSIA.

'0430 - Commenced ILRT stabilization period.

0556 - Completed walkdown of all penetration areas, small amount of leakage noted from 2RSS 101 (Recire Spray Pump deminertalized water fill header vent).

0825 - Satisfied -temperature --stabilization criteria (< 0.5 'R/Last 2 l Hrs).

0825 - Will declare start of ILRT at 0830.

j; 0830 - Declared start of ILRT.

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October 25. 1990 (continued)-

1015 - Based on 1 1/2 hours of data analysis initial mass trend was initially high, but showing signs of settling down.

1050 - Based on the stabilization of mass since 1015 the ILRT will be restarted at 1100.

1115 - Pressure gauge installed at Penetration No. 91, Containment Purge Supply increased to 4.28 PSIC.

1400 - Control Room reported that RCS temperature had drifted from their target over the last hour. RCS temperature is now back in spec.

1505 - Mass change over last hour was 27-lbm.

1515,- Penetration No. 90 and 91 pressures are still increasing at a slow rate, renetration No. 90 at 3.20 PSIC, and Penetration No. 91 at 6.02 PSIC.

1540 - Isolated leakage from 2RSS 101 to assess impact.

1620 - No noticeable change in -leak rate due to the isolation of 2RSS 101, 1707 - Closed quench Spray outside containment isolation valve 2QSS*MOV101B to determine if inside containment valve 2QSS*3 may be-leaking through to the RWST.

1900 - Hass trend has not improved since the isolation of 2QSS*MOV101B. Will isolate 2QSS*MOV101A to determined .if 2QSS*4 may be leaking through to the RWST.

3.1 3

4 October-25. 1990 (continued) 2146'- Isolation of 2QSS*MOV101A & B did not appear to have any impact  ;

on the containment leak rate.

2151 - Inspected for leakage from the fuel transfer tube by filling upender canal with water above fuel tube gate valve. No indications of leakage observed.

2300 - Started to pressurize the "C" Steam Generator secondary side with air to determine if this could be a leakage path. '

October 26. 1990 0406 - "C" Steam Generator at approximately 45 PSIC. Setting up to pressurize A Steam Generator. .

0514 - "A' Steam Generator is approximately 12 PSIG. Mr.ns trend has improved.

0521 - Based on the improved containment leak rate the ILRT will be restarted at 0530. Also valves 2QSS*MOV101A & B will be reopened.

0720 - Vill restart ILRT-at-0730 based on lowering air block pressure i in "C" Steam Generator from 46.1 to 45.6 PSIG. '

0927 - Completed prossurizing "A" Steam Generator to 45.6 PSIC.

1040 - Will restart ILRT at 1045 based on data- collected since-completing air block on "A" and "C" Steam Generators. "A" Steam Generator appears to have made a contribution to the leak

~ rate improvement. "B" Steam Generator will not be air blocked at this time.

3.1-4 4

y - , , - - . ,

4.A a,. - - - a 2 m' N- - . ,a-ew + , _ :4 ~Ma. :A,. sp_-4 4 .a 2Le ,,LJmL. L e - -s A ---4L-s- LP- Ji - 4 48 m s- w 6A n,aksa October 26. 199Q (continued) 1300 - Containment leak rate has been trending down steadily. Mass change for last hour is 15 lbm.

1840 - Management has decided to terminate II.RT and depressuri::e containment for repairs. This decision is based on the possible -difficulty in quantifying leakage from the air blocked steam Benerators, h2sb3.r 2L.1990 0005 - Commenced containment depressurization.

0350

• Preparations in progress to pressurize each steam generator once containment access is established.

0930 - Coupleted containment depressurization.

1700 4 operators completed verification of valve alignments for each steam generator in containment. No valves were found out of alignment.

= 2029 - Starting-pressure test of steam generators.

October 28. 1990 0620 - Completed pressure test of steam generators. Several packing leaks were -identified and repaired. Also two steam generator

- level transmitters were found leaking at the transmitter = and repaired.

3.1-5

t October 28. 1990 (continued) ,

0700 - S tarting - to reve rify valve alignments for reperformance of ILRT. No containment penetrations have been realigned since. .

containment depressurization.

0900 - Recirculation spray pump 2RSS*P21D seal repair is complete and pump will be valved in for ILRT if the- local pressure test is satisfactory. >

1015 - Starting to reverify prerequisites and initial c:anditions for IIRT reperformance.

1500 - Pressure test of 2RRS*P21D satisfactorily completed. Pump isolation valves will be opened as soon as clearar.co is removed from suction and discharge valves.

1600 - Completed containment closcout and walkdown. Tested Personnel Airlock door seals. All prerequisites and initial conditions were verified satisfactory.

- 1641 - Commenced pressurization of cont ainme nt , Initial containment t -

pressure was 14.397 PSIA.

2115 - Containment pressure at 25.592 PSIA.

l l 2230 - Completed inspection of all c'antainment penetration areas, no significant leakage fourcl.

l

- october 29'. 1990 0830 - Containment pressure at 55.096 PSIAi 1043 - Completed containment pressurization with a peak instantaneous pressure of 61.006 PSIA.

3.1 6

. . . . . . . . ~ _ . . - _ . . - - . -- . -

J

. Oetober 29. 1990 (continued) 1045 - Commenced 1LRT stabilization period.

1425 - Completed inspection of all containment penetration . ire n s , no significant leakage found. Penetration No. 90 and 91 pressures are increasing at a slow rate. Penetration No. 90 at 1.70 PSIG, and Punetration No. 91 at 3.20 PSIG.

1500 - Satisticd tssperature sc Ailization criteria. Declared start of IIRT at 1500, 1709 - Appears that containment temperature to still trending downward, and has not fully stabilized.

2200 - -Containment comperature appears s tab' e . Will restart II.RT a t 2215.

2215 - Restarted ILRT.

October 30. 1990 0600 - Containment leak rate trending downward. Upper confidence level is abcte 0.0/5 %/ Day (Total Time), and 0.057 %/ Day (Mass

' Point).

0730 - A short duration ILRT does not seem likely due to the choppy data which is causing confidence to trend down-slowl 1000 - Planning on a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> IIRT, and should complete at 221.5.

1730 - Containment leak rate trending downward. Upper confidence level is 0.064 t/ Day (Total Time), and 0.049 i/ Day (Mass Point).

3.1 7

l Qstober 30. 1990 (continuad) 2118'- Preparing for superimposed leak test.

2221 - Completed ILRT vith a UCL leak rate of 0.058 t/ Day (Total Time), and 0.045 t/ Day (Mass Point).

2300 - Started superimpoaed leak test.

October 31. 1990 0118 - Superimposed leak test in progress, data is acceptable.

0305 - Superimposed leak test is now just outside of acceptable limits, 0604 - Superimposed leak test still outside of acceptable limits, will continue to record data.

1515 - Superimposed leak test came in acceptable limits for Mass Point.

1700 - According to Duquesne Light Company Licensing and Compliance Department, the wording of BVPS #2 technical specifications will not permit the Mass Point Analysis method as an acceptable method for IIRT performance, f

2105 - Superimposed leak isolated. Suspect actual containment leak rate is much less than measured and was over influenced by the comperature stab 111ation of the containment building.

2200:- Restarted the ILRT.

2332 - Containment leak rate is trending toward the -value measured at the end of the superimposed leak test.

3.1-8

{

1

I 1

November 1. 101Q 0330 - Contat raent leak rate is 0.021 t/ Day (Total Time), and 0.027 t/ Day (Mass 1olnt). Upper confidence level is 0.09, t/ Day '

i (Total Tin.e), and 0.033 t/ Day (Mass Point).

0815 - Containment leak rate is 0.016 t/ Day (Total '1:me), and 0.020 t/ Day (Mass Point). Upper confidence level is 0.060 t/ Day (Total Timo), and 0.023 t/ Day (hass Point). Tctal Time analysis is ' accordance with BN TOP 1, 0819 Initiated superimposed 1 tak.

0915 Started superireposed leak test.

1430 Completed superimposed leak test.

1550 - Commenced containment depressurization.

November 2. 1990 0018 - Completed containment depressuritation.

v u

3.1 9

e 3.2 CENERAL TEST DESCRIPTION 3.2.1 Prerequisiten In O 3rdance with Beaver Valley Power Station, Unit ! ILRT test procedure 2tVT 1.47.2, the following is a 1! sting of the pertinent prerequisites completed and docu: tented prior to ,ontainment pressurization:

a. All Type B and C Local Leakage Rate Testing completed.

b A11. test instrumentation calibrated or functionally verified within 6 months of ILRT.

c. o 4 penetration valve aligraents completed, d._All ILRT __ computer software used for data acquisition, and data.

analysis, tested and operational.

e. Tamporary air compressors and auxiliary equipment (.hecked out and

i. . 11able for preasurir.atic.n.

f. All equipment that could be damaged by test pressure, removed or protected.

g. Portable pressure containing equipment removed from containment.

h. Depressurized and vented pressure vessels located inside containment.

\.

1. Completed structural integrity inspection of containment.

3.2-1 s

. _ - - _. ._ __. m________ _ . _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . _ _ _ . _ _ . _ _ _

i 4

3.2.2 Equipment and Instrumentation l

Pressurization of the containment was achieved by the utilization of a temporary system consisting of eleven diesel driven oil free air  !

compressors, a water cooled aftercooler, and a refrigerant air dryer. The  !

system included adequate instrumentation and valving to maintain proper L

monitoring and control of the compressed air quality throughout the '

pressurization sequence. The total c.apacity of the pressurization system

was 9900 SCIM. Air was supplied to containment through the containme -

Purge System.

The various co ntainment parameters required to calculate containment leakage were monitored using instrumentation which consisted of 17 resistance temperature detectors, 5 dewpoint detectors, and an absolute h-pressure quartz manometer. Pertinent data for the test instrumentation is ,

listed in Attachment 3.2A.

A test panel consisting of a rotameter, pressure gauge, and a thermometer  ;

was used to perform the Superimposed Leakage Verification Test.

3.2.3 Data Acquisition System The data acquisition system used for ILRT was a tamputer controlled logging system which provided ins:...taneous raw sensor data.

For the ILRT, the data acquisition system monitored the following instrumentation:

Tygg No. of Sensors Temperature Detectors 17 Dewpoint Sensors 5 Quartz Manometer i 3.2 2

~ ,-,..._.--,.w+.m--.y, , ,-c,--,w,,,,,-we,,,..,,-,, _.

9 w, , - - . , , . ,. ...--+m,-_...r- yy. ,ww ,w y ...,-.c ym,- % ,,,yw, -y.

Instantaneous readings for each sensor were collected and printed at 15 minute intervals. Input to the data analysis program was based on these collections. Each data set was time stamped.

3.2.4 Data Resolation System The recorded data was inputted to Stone & k'eb s t e r EngineerinE Corporation's computer program for data reduction and leakage rate calculations. The Total Time and Mass Point Analysis Methods were used to determine the containment leakage rate.

Absolute Method of Mass Point Analysis The Absolute Method of Mass Point Analysis consists of calculating the air mass within the containment structure, over the test period, using pressure, temperature, and dewpoint data obtained during the ILRT. The air mass, is computed using the ideal gas law as follows:

144V(P Pv)

M- (Eq. 1)

RT k'he re :

M - air mass, Ibm P - total pressure, psia Py - average vapor pressure, psia R - $3.35 ft lbm/lbm *R (for airj T - average containment temperature, 'R V - containment free volume, 1,716,633 cu. ft 323

1 The leakago rate is then determinec' by plotting air mass as a function of time, using a least squares fit to determine the slope, A - dM/dT. The leakage rate is expressed as a parcentage of the air reass lost in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> l

or symbolically:

Leakage Rate - A/B( 2400) (Eq. 2/

1

'a'here A is the slope of the least squarts curve and B is the y intercept.

, The sign convention is such that the leakage out of containment is positive, and the units are in percent / day.

The air mass is calculated and the result is correlated as a function of time by means of a least squares curve fit of the form:

M - At + B (Eq. 3)

A confidence interval is calculated using a Student's T distribution.- The sum of the leakage rate and confidence is the Upper Confidence Level.

Absolute Method of Total Time Analysis The Absolute Method of Total Time Analysis consists of calculating air lost from. the containment, using pressure, temperature, and dewpoint observations made during the ILRT.

The containtnent air mass is computed using Equation 1. The measured leakage rate at any time (c) is then determined by substracting the mass at that time (Mt) from the initial mass (M1) and dividing by the initial mass. The measured leakage rate is expressed as a percentage of containtnent mass lost in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or symbolically:

Heasured Leakage Rate - Mi - Mt (2400) (Eq. 4)

Hi ( t) 3.2 4

. . . _ . . . _ . _ -_- .._. _ _ _ _ _ _ . - _ _ _ . . -.____.__m_.

i i

'Th e sign convention is such that leakage out of the containment is l pocitive, and the units are in percent / day.

l The calculated leakage rate is then determined by plotting the measured l leakage rate as a function of time and then performing a least squares

! curve fit of the measured leakage rate values as follows:

1 d

Calculated Leakage Rate - At + B (Eq. 5) .

where, A is the slope and B is the y intercept of the least squares curve, The sum of the calculated leakage rate the confidence interval is the 4-Upper Confidence Level.

, i f'

l-l i

j i

c 4

i I

9 I

l 3.2 5

(

'.l l i

I 1

-A .

ATTACHMENT 3.2A INSTRUMENTATION LIST k'e i ght Instrument Eatter Rante Z2ng Elevation A. Temperature 2LMS TE100 1 0.05810 60 100 'F II 781' 2LMS TE100 2 0.06915 60 100 'F III 801' 6" 2LMS TE100 3 0.05550 60 100 'T V 701' 6" 2LMS TE100 4 0.05570 60 100 'T IV 745' 6" 2LMS TE100 5 0.07440 60 - 100 *F I 865' 2LMS TE100 6 0.06915 60 - 100 'T III 791' 2LMS TE100 '. 0.05810 60 - 100 'F II' 781' 2LMS TE100 8 0.02340 60 - 100 'T IV 743' 2LMS TE100 9 0,03880 60 - 100 'F V 701' 6" 2LMS TE100 10 0.07440 60 100 'F I 865' 2LMS TE100 11 0.04690 60 100 *F IV 730' 2LMS TE100 12 0.06915 60 - 100 'F III 794' 2LMS TE100 13 0.06915 60 100 *F III 802' 2LMS TE100 14 .0.06680 60 100 *F V 701' 6" 2LMS TE10015 0.05810 60 100 'T 11 777' 6" 2LMS TE100 16 0.03880 60 100 *F V 701' 6" 2LMS TE100 7 0.07440 60 100 'F I 865' 2LMS TE100 18 0.00000 60 100 'F IV 726' 6" Fage 1 of 2 a

I

._. . = -.. . . _ --- ~_~. - - . . . . . . .- .. - -.-. _ . _ . - . - - . . . . - . . -- .- _..... _ ,

l ATTACHMENT 3.2A (continued)

INSTRUMENTATION LIST Veight l Ins t rutne nt Tactor Range lang Elevntion

, B. Devooint l 20!S ME100 1 0.111624 58 122 'F I 848' 20!S ME100 2 0.111624 -58 122 'F I 848' 2LMS ME100 3 0.258917 58 122 'F II 701' 2LMS ME100 4- 0.?$8917 -58 122 'T II 701'  ;

2LMS ME100 5 0.258918 58 122 'F II 701' C. Pressurg I II-2.1409 B 1.000000 0 100 PSIA s 1 II 2.1399 B 0.000000 0 100 PSIA D. Superimnosed leakage Verif tention Test Flow Instrume,nt I A 1.553.2 0.000000 0 8 SCFM I-A 1.553.3 1.000000 0 8 SCFM P

1. Backup quartz manometer, logged locally at same frequency as- primary I

canometer.

l.

Page 2 of 2 i

r

.. ,e,..- y ,--...

ATTACHMENT 3.211 INSTRUMENTATION SELECTION CUIDE l

l The Instrumentation Selection Cuide (150) formula is used to deterreine the ability of an instrumentation systern to measure the integrated lenhage of j the reactor containment systern. Instrumentation errors are combined using l a root sum square formula. The ISC is not added to the value of the calculated leakage rate, bus. is used for instrument selection and loss of sensor criteria only. Measurement system sensitivity values are used in the 150 formula since it is the change in the containment air mass, not the absolute value in mass, that is used to cortpute leakage. Complete th( ,

following information for the 11.RT instrumentation system and calculate i the 150.

Quartz Chilled Mirror Platinum Manometer Hverometer RTD Sensor Manufacturer Mensor General Eastern Pyco Mumber of Sensors (n) 1 5 17 Parameter Measured Total Pressure, Dew Point, *F Temperature PSIA (p) (pv) 'R (T)

Absolute Value 59.4 PSIA 60 'F 530 'R Page 1 of 3

ATTACllMENT 3 2B (continued)

INSTRUMENTATION SELECTION CUIDE NOTE: From the Steam Tables, at a dew point temperature of 60 'r the equivalent water vapor pressure change is 0.0092 PSIA /'F. Convert Sensor Sensitivity (E), and Repeatability and Resolution (C) for the

}{ygrometer's to PSIA prior to calculating the total system error (e).

Quartr Chilled Mirror Platinum Manometer Hygrometer RTD Sensor Sensitivity (E) 0.001 0.11 0.1 Repeatability and Resolution of System Excluding Senser (C) 0 0,1 0.05 Total System Error (e) 0.001 6.114443E 04 2.7116307E.02 2

e - ((E 2 + C )/n]1/2 Use the following equation to calculate the ISG:

1/2

-2 -

-2 -

-2 2400 e p e py eT ISC - 2 -

+2 +2 C P p T where: t - test duration , llours e

p system error for pressure, PSIA e - system error for dew point, 'F SyT - system error for temperature. 'R Page 2 of 3

t 0

ATTACl! MENT 3.2B (continued)

INSTRUMENTATION SELECTION CUIDE Calculate the ISC (24 lirs) as follows:

1/2

-2 -

_2 _

-2 2400 0.001 6.1164434E 04 2.7116397E 02 150 - 2 +2 +2 24 59.4 59.4 530 2400 - -

1/2 ISO - $.668355BE 10 a + 5.2352730E 09

.24. -

ISC a 0.00776 _,_ Pet / Day (Maximum allowable ISG - 0.025 Pet / Day Solve for t at the maximum ISC as follows:

2400 -

1/2 t- $.6683558E 10- + 2.1205810E 10 + , M 12730E 09 0.025 -

t_-- 7.44 llours Page 3 of 3 hii.q.ru .

k

. O e, l 3,3 TEST RESULTS '

i  ;

3.3.1 Presentation of Test Results t

The test data for the November 1990 ILRT is based on an 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> 15 minute l- tant period starting at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> on October 31, 1990. The final test results were determined using Stone & Webster Engineering corporation's  ;

2 IIRT computer program, The Reduced Input Data, BN TOP 1 Total Time c '

Analysis . Test Results, Mass Point Analysis Test Results, Superittposed Leakage Verification Test Results, and representative graphs are contained [

in Attachments 3.3A through 3,31.

r Both the Total Time and Mass Point Analysis Test Results for the 11RT satisfied the procedural acceptance criteria.

The ILRT- instrumentation was verified by the Superimposed Leakage Verification Test Method, Both the Total Time and Mass Point Analysis Test Results for the Superimposed LeakaBe Ver.11 cation Test satisfied the f

procedural acceptance criteria, f

a 4

3.3 1

_. _. - a.,~.._. _ . _ . . - _ . a ..-. _ . ~ . _ _ . . . . _ _ . _ . _ - _ - . - _ _ . _ . _ _ . _ _ _ _ _ _ _ . _ . - - , . _ _ - _

i i

3.3.2 59.4 PSIA ILRT Results 1

The ILRT was conducted in accordance with Beaver Valley Power Station Unic No. 2 test procedure 2BVT 1.47.2. The results for the ILRT and for the Supplemental Test are shown below:

I 3.3.2.1 ILRT Results BN TOP 1 Total Time Analysis

• j 1'

1123 (Percent /Dav) l

1. Lam, Leekage Rate Calculated 0.016762

2. Confidence Level 0.052465

'3. UCL, Lam Leakage Rate plus Confidence Level 0.069227

4. Corrections for:

(See Section 3.3.2.4)

1. Type B Penalties 0.000012

11. Type C Penalties 0.001193 111. Water-Levels 0,000000 iv. Total Corrections 0.001205

5. Total Reported ILRT Leakage Rate 0.070432 (Items 3 & 4) a Results were within the acceptable-limits of < 0.75 La or < 0.075 Pe* cent / Day Total Time Analysis: performed in -accordance with ~Bechtel Topical Report BN TOP 1, 3.3 2

. ,_._.__....c..._. .._ . . . . _ _ . , _ _ . , _ - - - , - -. _ . . _ . , _ _ . - . .._.___.u..

3.3.2.2 ILRT Results Mass Point Analysis JJ.f.ID (Pereent/Dayi

1. Lam, Leakage Rate Calculated 0.020203

2. Confidence Level 0.002775

3. UCL, Lam Leakage Rate plus Confidence Level 0.022977

4. Corrections for:

(See Section 3.3.2.4) l

1. Type B Penalties 0.000012 l

11. Type C Penalties 0.001193 111. Water Levels 0.000000 iv. Total Corrections 0.001205 1

5. Total Reported ILRT Leakage Rate 0.024182 l

(Items 3 & 4)

Results were within the acceptable limits of < 0.75 La or < 0.075 Percent / Day 3.3.2.3 Supplemental Tert Results The Supplemental Verification Test was performed using the Superimposed Leakage Verification Test Method in accordance with test procedure 2BVT 1.47.2. The results for the Superimposed Leakage Verification Test are shown below.

1. The Superimposed Leakage Verification Test is acceptable provided Lc falls within the following range:

(Lam + Lo 0.25La) s Le 5 (Lam + Lo + 0.25La) 3.3-3

4 1 .

a

\

p k'he re : *. am - Type A calculated leakage (computer)

[ = 0.016762 Percent / Day (Total Time)

[ - 0.020203 Percent / Day (Mass Point) i Lo - Superimposed leakage rate developed from rotameter )

j. l j - 0.101410 Percent / Day l

j .. Le - Composite leakage (cortputer) 4

- 0.103952 Percent / Day (Total Tirte)

- 0.103081 Percent / Day (Mass Point) i.

a. Total Time I-I (0.101410 + 0.016762 0.025) s 0.103952 s (0.101410 + 0.016762 + 0.025) i 4

(0.093172) 5 0.103952 s (0.143172)

I

b. Mass Point I

T (0.101410 4 0,020203 0.025) s 0.103081 s (0.101410 + 0.020203 + 0.025)

(0.096613) s 0.103081 s (0.146613) l' s The Superimposed Leakago Verification Test was' within the allowable limits

,_ for both Total Time and Ma 4t.

i I.'

(

L h

1 3.3 4 ,

e 3.3.2.4 Leakage Penalties Added to ILRT Leakage Penetration leakage to be added since thtae penetrations were isolated or could not be vented and drained during the ILRT. The leakage assigned is the recorded value for minimum pathway leakage.

1. Type B Penn1tieg Decerletion Ltaknre (SCF/D)

Electrical "0" Rings 8.55 Penetrations Total Type B Leakage - 8.55 SCF/D Total Type B Leakage - 0,000012 Percent / Day

11. Iyre C Pennitics Description Lenkage (SCF/D)

Pent #1 Component Cooling Water System 8.78 Pent #2 Component Cooling Water System 34.07 Pent #4 Component Cooling Water System 0.49 Pont #5 Component Cooling Water System 24.80 Pent #14 Chilled Vater System 0.48 Pent #21 Chilled Water System 0.48 Pent #24 RHS System to RWST 0.49 Pent #25 Chilled Vater System 0.48 Pent #27 Chilled Water System 0.48 Pont #28 RCS Letdown 0.49 Pent #56 2 RCS Sample System 0.49 Pent #97 1 RHS Sample System 0.49 Pent #99 Fire Protection 0.49 L Pont #101 Fire Protection 1.07 L Pont #116 Fire Protection 0.49 Pent #117 Fire Protection 8.75 Total Type C Leakage - 82.82 SCF/D Total Type C Leakage - 0.001193 Percent / Day i

3.3 5

_ _ _ _ . . . , . , . _ . . . . . .. . . . ___ ____.___.m-___....... .- . . _ . . __ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ .

5 4

iii Vater Level Corrections

. Description Lenkare (SCF/D)

A Rx Vessel 0.0  :

Cnmt Sump 0.0 t- 1 Total Water Level Corrections - 0.0 SCP/D l Total Water 1.evel Corrections - 0.0 Percent / Day i

i l

8 J

't d

j 4

N 6 3,3 6 P

ww.,,,,--vw---w,,_.-,e erv ., pe .y y.r,--%<s-ow-,,,m-.

3.3.3 Conclusion During the first and second runs of the ILRT, temperature stabilization appears to have overwhelmed the actual containment leakage rate initially. The containment building is extremely temperature sensitive without the use of any forced ventilation to aid stabilization.

Steam generator leakage paths identified during the first ILRT run provided the containment leakage rate improvement af ter establishing air blocks in the "A" and "C" Steam Generators. The leakage rate contribution of "A" Steam Generator appeared significantly greater than the contribution of "C" Steam Cenerator. This also corruponds to the leaks detected during the steam generator pressure test performed after the first ILRT run.

No significant leakage pat.hs were identified during the second ILRT run.

The measured containment leakage rate appears to have been over influenced initially by temperature stabilization durin6 the first half of the leakage rate measurement period. This caused the final ILRT measured leakage rate to be artificially highsr than the actual Icakage rate, but still acceptable. The Superimposed Leakage Verification Test however was impacted by the luproved temperature stabilization.

During the Superimposed Leakage Verification Test a leak of approximately La (0.1 t/ Day) is imposed onto containment. Leakage rate measurements are restarted after allowing approximately one hour for stabilization. The resulting measured leakage rate (composite leakage rate) must equal the final measured ILRT leakage rate plus the imposed leakage rate within a margin of i 0,025 t/ Day to be acceptable.

Since the final ILRT measured leakage rate used for the verification test was actually greater than the actual containment leakage rate, the resulting composite leakage rate was biased. Subsequent data analysis during the verification test yielded a composite leakage rate which reflected the actual containment leakage rate which was not biased. The 3.3 7 m m._--..s___ __ .-...___.

- . -. ~ - - -. ---- --. .. . - - - . ~ . - - .. - - --- . .. -

N 6

resulting composite leakage rate remain just below the lower verification test acceptance limit.

The third ILRT run was started since the actual containment leakage rate ,

was assumed to have been initially over influenced by temperature stabilization during the second ILRT run. During the third ILRT run the measured Icakage rate trended very quickly to a value less less than half of that measured during the second ILRT run. The ILRT was completed with )

~

an acceptable leakage rate. i l

The Superimposed Leakage Verification Test performed af ter the third ILRT 1

- run was within acceptable limits.

Containment temperature stabilization in both the first and second ILRT runs - significantly influenced the mass trend, which directly affected the containment leakage rate. Without the assista. o of forced ventilation, stabilization the containment building appears to take much longer than previously assumed. No ventilation equipment was operated during the BVPS

1. 2 ILRT.

Consideration for future ILRT's will be given to possibly tightening the temperature stabilization guideline criteria from the present <. 5 'R over last 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to a more stringent criteria.- Additionally the use of forced ventilation will be evaluated to determined if existing ventilation could be used to aid stabilization. One possibility might involve operation of one or more Containment Air Recirculation Fans during pressurization to promote stabilization. These fans could then be isolated either prior to, or shortly after completing pressurization.

J 3.3 8 y

l ATTACHMENT 3.3A INTEGRATED LEAKAGE RATE TEST FROM 22:00 HOURS ON 10/31/90 TO 08:15 HOURS ON 11/01/90 REDUCED INPUT VARIABLES ABS. VAP. ABS.

TIME PRES PRES TEMP DE'a' POI NT MASS (HR) (PSIA) (PSI) (*R) ('F) (LBM) 22:00 60.482 0.2256 533.516 56.469 523312.51 22:15 60.482 0.2265 533.517 36.577 523303.80 22:30 60.482 0.2261 533.507 56.529 523316.56 22:45 60.482 0.2266 533.518 56.593 523301.64 23:00 60.482 0.2267 533.512 56.605 523306.89 23:15 60.482 0.2268 533.514 56.615 523303.66 23:30 60.482 0.2265 533.518 56.579 $23302.79 23:45 60.482 0.2268 533.530 56.616 523287.89 00:00 60,484 0.2264 533.530 56.562 523309.11 00:15 60.484 0.2266 533.538 56.587 523299.92 00:30 60.484 0.2267 533.539 56.599 523297.62 00:45 60.485 0.2270 533.545 56.631 523298.22 01:00 60.485 0.2263 533.552 56.547 523297.98 01:15 60.485 0.2264 533.555 56.562 523293.30 01:30 60.485 0.2267 533.562 56.606 523283.92 01:45 60.486 0.2267 533.572 56.599 523282.58 02:00 60,486 0.2270 $33.573 56.634 523279.16 02:15 60.486 0.2271 533.578 $6.644 523274.17 02:30 60,488 0.2270 533.575 56.635 523295.29 02:45 60.488 0.2273 533.577 56.675 523290.44 03:00 60.487 0.2273 533.577 56.674 523281.00 03:15 60.487 0.2275 533.578 56.697 523278.45 03:30 60.487 0.2277 533.574 56.724 523280.73 03:45 60,487 0.2274 533.584 $6.691 523273.55 04:00 60.488 0.2268 533.579 56,613 523293.00 04: 15 60.488 0.2276 533.590 56.712 523274.17 04:30 60.488 0.2276 533.590 56.708 523275.24 04:45 60.488 0.2274 533.598 56.690 523268.77 05:00 60.488 0.2276 533.595 56.708 523270.53 05:15 60.488 0.2279 533.593 56.749 523268.92 05:30 60.489 0.2274 533.595 56.682 523281.07 05:45 60.489 0.2275 533.600 $6.692 523275.24 06:00 60.489 0.2280 533.609 56.763 523260.66 06:15 60.490 0.2276 533.611 56.711 523271.25 06:30 60.490 0.2280 533.611 56.755 523268.49 06:45 60.490 0.2263 533.609 56.547 523284.93 07:00 60.490 0.2275 533.616 56.692 523267.71 07:15 60.490 0.2278 533.616 56.729 523265.60 07:30 60.491 0.2279 $33.618 56.744 523271.26 i 07:45 60.491 0,2280 533.619 56.754 523269.21 08:00 60.491 0.2283 533.621 56.794 523264.06 08:15 60.491 0.2284 533.619 56.803 523266.28 Page 1 of 1 l

_ . _ . . . _ . _ _ _ _ .... _ . _ _ _ _ . _ . _ _ _ _ _ _ _ . _ - .~ _ _ _ _ . _ .

a r

ATTACHMENT 3.3B INTEGRATED LEAXACE RATE TEST 3 PROM 22:00 HOURS ON 10/31/90 TO 08:15 HOURS ON 11/01/90 ABSOLUTE TEST METHOD, TOTAL TIME ANALYSIS TEST METHOD j TIME MASS MEAS LEAK CALC LEAK CONFIDENCE UCL (HR)

(LBM) (PCT / DAY) (PCT / DAY) (PCT / DAY) (PCT / DAY)

J 22:00 523312.51 0.000000 0.000000 0.000000 0.000000 L 22:15 533303.80

' 0.159701 0.000000 0.000000 0.000000 i 22:30 523316.56 0.037145 0.000000 0.000000 0.000000 22:45 523301.64 0.066426 0.016357 1.188127 1.204483 23:00 $23306.89 0.025750 0.008941 0.448953 0.457893 1 23:15 523303.66 0.032465 0.011124 0.292829 0.303953 4

23:30 523302.79 0.029711 0.011738 0.224763 0.236501 4

23:45 523287.89 0.064518 0.028868 0.195792 0.224660 00:00 523309.11 0.007795 0,016217 0.168470 0.184686 00:15 523299.92 0.025663 0.014908 0.149613 0.164521 00:30 523297.62 0.027319 0.014819 0.135805 0.150624 00:45 523298.22 0.023827 0.013836 0.124848 0.138684 01:00 523297.98 0.022212 0.012796 0.116023 0.128818 01:15 523293.30 0.027098 0.013486 0.109112 0.122599 01:30 523283.92 0.037460 -0.016794 0.104101 0.120894 01:45 523282.58 0.036598 0.019266 0.099463 0.118729 02:00 523279.16 0.038236 0.021675 0.095391 0.117066 02:15 523274.17 0.041372 0.024349 0.091875 0.116225 02:30 523295.29 0.017542 0.021698 0.088122 0.109820 02:45 523290.44 0.021311 0.020276 0.084739 0.105014 03:00 523281.00 0.028902 0.020532 0.081850 0.102382

[ 03:15 523278.45 0.029755 0.020930 0.079257 0.100187 i 03:30 523280.73 0.026497 0.020742 0.076811 0.097553 p 03:45 523273.55 0.031073 0.021352 0.074693 0.096045 04:00 523293.00 0.014913 0.019366 0.072612 0.091979 04: 15 523274.17 0.028134 0.019660. 0.070786 0.090446 04: 30 523275.24 0.026296 0.019658 0.069048 0.088716 04:45 523268.77 0.029714 0,020171 0.067513 0.087684 05:00 $23270.53 0.027504 0.020331 0.066019 0.086350 05:15 523268.92 0.027570 0.020495 0.064621 0.085116 l 05:30 523281.07 0.019222 0.019594 0.063235 0.082829 05:45 523275.24 0,022054 0.019151 0.061944 0.081095 06:00 523260.66- 0.029720 0.019681 -0.060863 0.080544 06:15 523271.25 0.022935 0.019382 0.059718 0.079100 p 06:30 523268,49 0.023751 0.019214 0.058646 0.077860 06:45 523284.93 0.01445? 0.018054 0.057620 0.075673

. 07:00 523267.71 0.012825 0.017904- 0.056660 0.074564 07:15 523265.60. 0.023256 0.017822 0.055755 0.073577

, 07:30 523271.26 0,019914 0.017417 0.054864 0.072280 07:45 523269.21 0.020364 0.017099 0.054019 0,071118 -

08:00 $23264.06 0.022219 0.016995 0.053232 0.070227 08:15 523266.28 0.020683 0.016762 0.052465 0.069227 L

i Page 1 of 1

. _ - _ . - _ , . . ~ _ _ _ . _ _ . - _ . _ _ - -_- _ _ _ _ . _ .. . ~ . ._.

4 ATTACHMENT 3.3C INTEGRATED LEAKAGE RATE TEST FROM 22:00 HOURS ON 10/31/90 TO 08:15 HOURS ON 11/01/90 ABSOLUTE TEST METHOD, MASS POINT ANALYSIS TE"T METHOD TIME Mass LEAKACE CONFIDENCE UCL (HR) (LBM) (PCT / DAY) (PCT / DAY) (PCT / DAY) 22:00 523312.51 0.000000 0.000000 0.000000

, 22:15 523303.80 0.000030 0.000000 0.000000 22:30 523316.56 0.037145 0.972357 0.935212 22:45 523301.64 0.036385 0.194842 0.231227 23:00 523306.89 0.024558 0.091448 0.116005 23:15 523303.66 0.026145 0.054238 0.080384 23:30 523302.79 0.025619 0.036256 0.061875 23:45 523287.89 0.046045 0.034702 0.060747 00:00 523309.11 0.026556 0.033783 0.060340 00:15 523299.92 0.024383 0.026554 0.050938 00:30 523297.62 0.024008 0.021377 0.045386 00:45 523298.22 0.022442 0.017663 0.040105 01:00 523297,98 0.020903 0.014877 0.035780 01:15- 523293.30 0.021787 0.012676 0.0'4463 3

01:30 $23283.92 0.026121 0.011774 0.037895 01:45- 523282.58 0.028986 0.010646 0.039632 02:00 523279.16 0.031615 0.009716 0.041332 02:15 523274.17 0.034512 0.009080 0.043592 02:30 523295.29 0.029921 0.009314 0.039235 02:45 523290.44 0.027422 0.008720 0.036142 03:00 523281.00 0.027465 0.007865 0.035330 03:15 523278.45- 0.027726 0.007135 0.034861 03:30 523280.73 0.027168 0.006522 0.033690 03:45 523273.55 0.027784 0.005996 0.033781 04:00 523293.00 0.024714 0.006288 0.031002 04:15 523274.17 0.025041 0.005802 0.030844 04: 30 523275.24 0.024946 0.005364 0.030310 04:45 523268.77 0.025562 0.005010 0.030572 05:00 523270.53 0.025661 0.004659 0.030319 05:15 523268.92 0.025765 0.004343 0.030108 05:30 523281,07 0.024347 0.004290 0.028637 05:45 523275.24 0,023648 0.004075 0.027723-06:00 $23260.66 0.024372 0.003889 0.028261 06:15 523271,25 0.023874 0.003689 0.027563 06:30 523268.49- 0.023584 0.003486 0.027070 06:45- 523284.93 0.021874 0.003689 0.025563 07:00 523267,71 0.021682 0.003492 0.025173 07:15 -523265.60 0.021588 0.003306 0.024894 07:30 523271.26 0.021025 0.003182 0.024207 07:45 -523269.21 0.020603 0.003049 0.023652 08:00 523264.06 0.020497 0.002900 0.023397 08:15 523266.28 0.020203 0.002775 0.022977 Page 1 of 1

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ATTACRMENT 3.30 SUPERIMPOSED LEAKAGE VERITICATION TEST TROM 09:15 HOURS TO 14: 30 HOURS ON 11/01/90 REDUCED INPUT VARIABLES ABS. VAP. ABS.

TIME PRES PRES TEMP DEk' POINT KASS (HR) (PSIA) (PSI) (*R) ('F) (LBM) 09:15 60.490 0.2283 533.631 56.797 523246.14 09:30 60.490 0.2285 '533.633 $6.822 523242.15 09:45 60.488 0.2276 533.632 56.708 523234.23 10:00 60.487 0.2285 533.630 56.820 523219.33 10:15 60.487 0.2287 533.630 56.839 523217.30 10:30 60.487 0.2286 533.626 56.836 3232?1.65 10:45 60.485 0.2289 533.624 56.869 5'i3204.05 11:00 60.485 0.2282 533.624 $6.778 523210.35 11:15 60.484 0.2284 533.626 56.803 523198,38 11:30 60.484 0.2289 $33.621 56.864 523198.21 11:45 60.482 0.2284 533.630 56.810 523176.16 12:00' 60.482 0.2290 533.623 56.879 $23178.37 12:15 60.481 0.2290 533.620 $5.876 523172.92 12:30 60.481 0.2289 533.619 56.864 523174.52 12:45 60.480 0.2283 533.61) 56.799 523174.04 13:00 60.478 0.2288 533.614 56.851 523154.83 13:15' 60.478 0.2290 533.608 56.879 523158.61 13:30 60.478 0.2292 533.615 56.902 523150.04 13:45 60.477 0.2293 533.619 56.910 523136.17 14:00 60.477 0.2292 533.617 56.899 523138.87 14:15 50.477 0.2295 533.620 56.936 523134.01 14:30 60.477 0.2296 533.629 56.948 523123.80 Page 1 of 1

7.-_..-_..._.___

l-ATTACHMENT 3.3H 4 SUPERIMPOSED LEAKAGE VERIFICATION TEST TROM 09:15 HOURS TO 14:30 HOURS ON 11/01/90 i ABSOLUTE TEST METHOD, TOTAL TIME ANALYSIS TEST METHOD TIME MASS MEAS LEAK CALC LEAK CONFIDENCE UCL (HR) (LBM) (PCT / DAY) (PCT /DAV) (PCP/DAT) (PCT / DAY) i 09:15 523246.14 0.000000 0.000000 0.000000 0.000000 09:30 523242.15 0.073127 0.000000 0.000000 0.000000 09:45 523234.23 0.109266 0.000000 0.000000 0.000000 10:00 523219.33 0.163953 0.160862 0.115894 0.276756 10:15 523217.30 0.132273 0.154473 0.108511 0.262985 -

10:30 523221.65 0.089866 0.124994 0.089916 0.214910 10:45 523204.05 0.128699 0.129624 0.055748 0.185372 11:00 523210.35 0.093793 0.115865 0.041978 0.157844 11:15 523198,38 0.109534 0.113785 0.031003 0.144788 11:30 523198.21 0.097713 0.107931 0.024213 0.132144 11:45 523176.16 0.128397 0.114513 0.019727 0.134240 12:00 523178.37 0.113026 0.114320 0.016084 0.130404 i 12:15 523172.92 0.111949 0.113850 0.013378 0.127228 12:30 $23174.52 0.101080 0.110502 0,011416 0.121918 12:45 523174.04 0.094482 0.106229 0.009920 0.116149 P 13:00 523154.83 0.111687 0.107048 0.008613 0,115661 13:15 523158 61 0.100370 0.105135 0.007552 0.112687 13:30 523150.04' 0,103708 0.104324 0.006664 0.110988

! 13:45 523136.17 0.112093 0.105391 0.005950 0.111341 14:00 $231~38.87 0.103583 0.104629 0.005325 0.109954 14:15 523134.01 0.102859 0.103868 0,004795 0.108663 14!;0 523123.80 0.106880 0.103952 0.004343 0.108295-L i

Page 1.of 1 1

3a-,,-.-.,~,.,..,,...u--..._..-..~...._.,_-~_._.-~,__.--..___.

o ATTACKtENT 3.3I SUPERIMPOSED LEAKAGE' VERIFICATION TEST FROM 09:15 HOURS TO 14:30 HOURS ON 11/01/90 ABSOLUTE TEST METHOD. MASS POINT ANALYSIS TEST METHOD 1 .

TIME Mass LEAKACE CONFIDENCE UCL (HR) (LBM) (PCT / DAY) (PCT / DAY) (PCT / DAY) 09:15 523246.14 0.000000 0.000000 0.000000

. 09:30 523242.15 0.000000 0.000000 0.000000 09:45 523234.23 0.109266 0.178514 0.287779 10:00 523219.33 0.162098 0.093851 0.255949 10:15 523217.30 0.147691 0.047580 0.195271 10:30 523221.65 0.111082 0.053157 0.164239 10:45 523204.05 0.120698 0.037247 0.157945 11:00 523210.35 0.105010 0.032040 0.137050 11:15 523198.38 0.105336 0.024201 -0.129537 11:30 523198.21 0.099928 0.019818 0.119747 11:45 523176.16 0.110825 0.019684 0.130508 12:00 523178.37 0.111284 0.016200 0.127484 12:15 523172.92 0.111193 0.016 67 0.124760 12 :50 523174.52 0.107121 0.012268 0.119389 12:45- 523174.04 0.102013 0.011778 0.113791 r 13:00 523154.83 0.104122 0.010465 0.114588 13:15. 523158.61 0.102168 0.009397 0.111565 13:30 523150.04 0.101760 0.008325 0.110086 13:45 523136.17 0.103882 0.007720 0.111602

.14:00 523138.87 0.103236 0.00U,54 0.110189 14:15 523134.01 0.102574 0.006307 0.108880 14:30 523123.80 0.103081 0.005740 0.108821 1

Page 1 of 1

- ---- - - - - - - - - ~ -- -

SECTION 4 LDCAL LEAKAGE RATE TESTS (TYPES B AND C)

Local Leak Rate TestinS (LLRT) of containment penetrations is performed on a periodic basis (normally each refueling, but not exceeding 24 months),

in accordance with 10 CFR 50 Appendix J and Beaver Valley Power Station No. 2 Technical Specifications. These LLRT's are performed by '"

pressurizing the required penetrations with air or nitrogen and either measuring leakage a:ross the containment isolation valves boundary (Type C), or across the resilient seals (Type B). The combined leakage rate of containment penetrations subject to LLRT's shall be less than 60 percent *y La, at a minimum test pressure of Pa.

Additionally LLRT's (Total Volume Type B) are performed for each containment airlock at 6 month inte rvals in accordance -4th 10 CFR 50 Appendix J, and Beaver Valley Power Station No. 2 Technical Specifications.

This attachments for this section are:

Attachment No. Title 4.lA First Refueling (3/89 5/89) LLRT Data 4.1B First Refueling (3/89 - 5/89) LLRT Repairs 4.lC Second Refueling (9/90 11/90) LLRT Data 4.lD Second Refueling (9/90 - 11/90) LLRT Repairs 4.lE First and Second Fuel Cycle LLRT Data 41 l

l l

, ATTACHMENT 4,1A '

FIRST REFUELING LOCAL LEAKACE RATE TEST DATA

) TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT- VALVE DATE VALVE VALVE PENETPATION NO. MARK NO. TESTED LEAYACE LEAYACE LEAKACE IN OUT (SCP/D) (SCP/D)- (SCP/D) 2CCP*MOV157-2 X 04 15 89 58.63 13.73 4

1 2CCP*RV105 X PARALLEL WITH 20 '*MOV157-2 19.54 2CCP*MOV157 1 X 04 13 89 19.54 19.54 2CCP*MOV150 2 X 04 21 89 97.45 0.49 2 2CCP*RV102 X PARALLEL WITH 2CCP*MOV150 2 0.49 2CCP*MOV150 1 X 04 09 89 0.49 0.49 2CCP*MOV151 2 X 04 16-89 63.52 63.76 4 2CCP*RV103 X PARALLEL WITH 2CCP*MOV151 2 83.06 2CCP*MOV151 1 X 04 13 89 83.06 83.06 2CCP*MOV156 2 K 04 09 89 0.49 4.88 5 2CCP*RV104 X PARALLEL WITH 2CCP*MOV156 2 4,88 2CCP*MOV156 1 X 04 09 89 0.49 4.88

,7 2IAC*MOV133 X 03-28 89 46.77 11.67 11 11.67 2IAC*MOV134 X 03-28-89 16.57 7.78 2SWS*MOV153-2 X 04 24-89 48.02 2.34 14 2SWS*MOV153 1 X 04-24 89 68.60 0,49 2.34 2SWS*RV153 X PARALLEL WITH 2SWS*MOV153 1 2CHS*MOV378 X 04 08-89 5.26 -5.26 19 2CHS*473 X PARALLEL WITH 2CHS*MOV378 5.26 2CHS*MOV381 X 04 08 89 2,44 2.44 2 SIS *42 X 04 15 09 > 1925 0,49 0,49 20 2 SIS *41 -X 04-15-89 0.49 0.49 2 SIS *RV130 X PARALLEL WITH 2 SIS *41 TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 127.73 Page 1 of 9

1 ATTACHMENT 4.1A (continued)

FIRST REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAXACE LEAYAGE IN OUT (SCF/D) (SCF/D) (SCF/D) 2SWS*Mov155 2 X 04 24 89 0.49 0.98 21 2SWS*MOV155 1 X 04 27-89 0.49 0.49 0.98 2SWS*RV155 X PARALLEL WITH 2SWS*MOV155 1 2PJIS*107 X 03 2P-89 0.49 1.95 24 2RHS*15 X 03 2S 89 0.73 0.73 1.95 2RHS*RV100 X PARALLEL WITH 2RHS*15 2SWS*MOV154 2 X- 03 21-89 0.48 0.48 25 2SWS*MOV154 1 X 04-25 89 4.75 0.49 0,49 2SWS*RV154 X PARALLEL WITH 2SWS*MOV154 1 2SWS*MOV152 2 X 04-24 89 4.86 0.49 27 2SWS*MOV152 1 X 04 24 89 0.48 0.73 0.73 2SWS*RV152 X PARALLEL WITH 2SWS*MOV152 1 2CHS*A0V200A X 04 12 89 0.49 0.49 2CHS*A0V200B X PARALLEL WITH 2CHS*A0V200A 2CHS*A0V2000 X PARALLEL WITH 2CHS*A0V200A 28 2.45 2CllS*llCV142 X 04 15 89 > 1925 1.47 2CHS*RV203 X 04-12-89 0.49 0.49 2CHS*A0V204 X 04-12 89 0.49 0.49 2DCS*A0V108A X 04-05-89 0.49 0.49 29 2DGS*A0V108B X 04 05 89 0.49 0.49 0.49 2DCS*RV115 X PARALLEL WITil 2DCS*A0V108B TOTAL PENETRATION LEAKAGE SHEET-2 (SCF/D) 7.09 Page 2 of 9

.------.--.----,-----------------------.-.,.----r------------------,-----------------------w- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ----

c ATTACHMENT 4.lA (continued)

FIRST REFUELING LOCAL LEAVAGE PATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED ,

PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAVACE IN OUT (SCP/D) (SCP/D) (SCP/D) 2DAS*A0V100A X 04 04 89 0.49 0.49 38 2DAS*A0V100B X 04-15 89 0.96 0.49 0.49 2DAS*RV110 X PARALLEL WITH 2DAS*A0V100B 2SAS*15 X 03 20 89 1.77 1.77 42 8.85 2SAS*14 X 03 20 89 8.85 8.85 2CVS*91 X 03 25-89 9.75 9.75 43 9.75 2CVS*A0V102- X 03 25 89 0.49 0.49 2CVS*SOV153B X 03 25-C9 9.26 9.26 44 39.95 2CVS*S0V153A X 03 25-89 39.95 39.95 2RCS*72 X 04 14 89 0.49 0.49 45 2RCS*A0V519 X 04 08-89 2.92 0.49 0.49 2kCS*RV100 X PARALLEL WITH 2RCS*A0V519 2VRS*A0V109A 2 X 04 05 89 0.49 0.49

, 48 0.49 2VRS*A0V109A 1 X 04 05 89 0.49 0.49 2RCS*68 X 04 07 89 0.49 0.49 49 0.49 2RCS*A0V101 X 04 07-89 0.49 0.49 2CNS*A0V101-2 X 04-08 89 0.49 0.49 53 0.49 2GNS*A0V101 1 X 04-08 89 0.49 0.49 2SSR*A0V109A-1 X 03-24-89 7.80 7.80 55-1 2SSR*A0V109A 2 X 04-10 89 8.78 1.76 7.80 2SSR*RVil7 X PARALLEL WITH 2SSR*A0V109A 2 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 68.80 Page 3 of 9

l ATTACHMENT 4 lA (continued)

IRST REfVELING LOCAL LEAKAGE P. ATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO, TESTED LEAKAGE LEAYAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCP/0) '

2SSR*SOV130A 1 X 03 27 89 5.34 5.34 55 2 5.34 2SSR*SOV130A 2 X 03-27 89 0.49 0,49 2HCS*SOV136A X 04-07 89 0.49 0.49 55-3 0,49 2HCS*SOV136B X 04 07-89 0,49 0.49 2SSR*A0V102A-1 X 03 24 89 0.49 0.49 56 1 2SSR*A0V102A 2 X 03 24-89 0.49 0.49 0.49 2SSR*RV118 X PARALLEL WITH 2SSR*A0V102A 2 2SSR*SOV128A-1 X 04 05-89 0.49 0.49 56 2 2SSR*SOV128A 2 X 04 27 89 0.49 4,89 4.89 2SSR*RV120 X PARt.LLEL WITH 2SSR*A0V128A-2 2SSR*A0V100A- i- 03 24 89 0.49 0.49 56 3 2SSR*A0V100A . X 03 24 89 0.49 0.49 0.49 2SSR*RV119 X PARALLEL WIT) .SSR*A0V100A 2 2SSR*A0Vil2A 1 X 03 25 89 b,49 0.49-

$7 1 2SSR*A0V112A 2 X 03 25 89 0.49 0.49 0.49 2SSR*RV121 X PARALLEL WITH 2SSR*A0Vll2A 2 2HCS*SOV135A X 04 07-89 0,84 0.84 57 2 0.84 2HCS*SOV135B X 04 07-89 0.84 0.84 2IAC*22 X- 03-23 89 0.49 0.49 59 0.49 21AC*MOV130 X 04 10 89 1,27 0.49 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 13,52 Page 4 of 9

ATTACHMENT 4.1A (continued)

FIRST REFUELING LOCAL LEAFACE PATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE -DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAXACE LEAVACE IN OUT (SCF/D) (SCF/D) (SCF/D) 2QSS*4 . X 03 22-89 0.48 0.48 63 2QSS*MOV101A X 04 04 89 0.48 8.28 8.28 2QSS*RV101A X PAPALLEL WITH 2QSS*MOV101A 2QSS*3 X 03 22-89 0.97 C.97 64 2QSS*MOV101B X 04 06 89 0.49 0.49 0.97 2QSS*RV101B X PARALLEL WITH 2QSS*MOV101B 2HCS*111 X 04 11 89 15.64 15.64 87 15.64 2HCS*MOV117 X 04 11 89 15.15 15.15 2HCS*110 X 04 11-89 0.49 0.49 88 0.49 2HCS*MOV116 X 04-14 89 0.49 0.49 2HVR* MOD 23B X 90 03 25 89 0.25 0.49 0.49 2HVR* MOD 23A X 2HVR* MOD 25B X 91 2HVR* MOD 25A X 03 25 89 6.81 13.62 13.62 2HVR*DMP206 X 211CS*SOV114B X 04-13-89 0.49 0.49 2HCS*SOV115B X 04 13 89 0.49 0.49 92 27.90 2CVS*SOV151B X 04-13-89 0.49 0.49 2CVS*SOV1528 X 04 13 89 27.41 27.41 2HCS*SOV114A X 04 14-89 0.49 0.49 2HCS*SOV115A X 04 14-89 0.49 0.49 93 12.72 2CVS*SOV151A X 04-13 89 12.23 12.23 2CVS*SOV152A X 04 13 89 7.34 7.34 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 80.I1 PaSe 5 of 9 1

ATTACHMENT 4.'lA (continued)

FIRST REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE

• IN OUT (SCF/D) (SCP/D) (SCP/D) 2CVS*151 X 03 23-89 19.47 19.47 94 19.47 2CVS*151 1 X 04 05 89 730 0.49 2SSR*SOV129A 1 X 04 27 89 1119 2.93 97 1 2SSR*SOV129A 2 X 04 18 89 77.88 0.49 2.93 2SSR*RV122 X PARALLEL VITH 2SSR*A0V129A 2 2HCS*SOV133B X 04 07 89 0.49 0.49 97-2 0.49 2HCS*S0V134B X 04 07-89 0.49 0.49

\

2 FPS *761 X 04-06 89 0.49 0.49 99 26.80 e 2 FPS *A0V206 X 04-06 89 26.80 26.80 2 FPS *753 X 04-06-89 2.92 2.92 101 --

4.14 2 FPS *A0V205 X 04-06-89 4.14 4.14 2FNC*121 X 03 27-89 0.49 0.49 103 0.87 2FNC*38 X 03-27-89 0.87 0.87 2FNC*122 X 03 21 89 0.48 0.48 104 0.48 2FNC*9 X 03 21-89 0.48 0,48 2HCS*SOV133A X 04-07 89 3.40 3.40 105-1 3.40 2HCS*SOV134A X 04 07-89 0,49 0.49 2 PAS *SOV105Al X 04 03-89 0.49 0.49 105 2 0.49 2 PAS *SOV105A2 X 04-03 89 0.49 0.49 2WS*51 X 03 24 89 0.49 0.49 105 3 0.49 2mS*52 X 03 24-89 0.49 0.49 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 59.56 Page 6 of 9

ATTACHMENT 4.1A (continued)

FIRST REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAYAGE IN OUT (SCP/D) (SCF/D) (SCF/D) 2 SIS *MOV842 X 04 22 89 0.49 0.49 106 2SIA*A0V889 X 04 22-89 25.34 0.49 0.49 2 SIS *RV175 X PARALLEL WITH 2 SIS *A0V889 2FPW*388 X 03 27-89 0.49 0.49 116 0.49 2 FPS *A0V221 X 03-27-89 0.49 0.49 2FPW*382 X 03 27 89 8.27 8.27 117 24.32 2 FPS *A0V204 X 03 27-89 24.32 24.32 2QSS*267 X 03 28 89 0.49 0.49

'.18 2QSS*SOV100A X 03 28 89 0.49 0.49 0.49

.2QSS*SOV100B X PARALLEL WITH 2QSS*S0V100B TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 25.79 TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 127.73 TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/D) 7.09 TOTAL PENETRATION LEAKAGE SHEET 3 (SCP/D) 68.80 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 13.52 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) $0.11 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 59.56 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 25.79 TOTAL CONTAINMENT TYPE C LEAKAGE - SUM 0F SHEETS 1 THRU 7 (SCF/D) 382.60 r-Page 7 of 9

{ l l

1

ATTACHMENT 4.lA (continued)

FIRST REFVELING LOCAL LEAKAGE RATE TEST DATA TYPE B TESTS TYPE B TEST - CONTAINMENT ELECTRICAL PENETRATIONS PENT LEAK PENT LEAK PENT LEAK PENT RATE PENT RATE PENT RATE NO (SCCM) NO (SCCM) NO (SCCM) 2RCP*02C 2.0 2RCP 09A 2.0 2RCP*14E 2.0 2RCP 02D 2.0 2RCP 09B 2.0 ** Ell 2.0 2RCP*02E 2.0 2RCP 09C 2.0 2RCP 15C 2.0 2RCP*03A 2.0 2RCP 09D 2.0 2RCP-15D 2.0 2RCP*03B 2.0 2RCP-09E 2.0 2RCP*15E 2.0 2RCP-03C 2.0 2RCP*10A 2.0 2RCP*16C 2.0 2RCP*03D 2.0 2RCP*10B 2.0 2RCP*16D 2.0 2RCP*04A 2.0 2RCP*10C 2.0 2RCP*16E 2.0

• • B4 2.0 2RCP*10D 2.0 2RCP 17A 2.0 2RCP 04C 2.0 2RCP*10E 2.0 2RCP-17B 2.0 2RCP-04D 2.0 2RCP llA 2.0 2RCP-17C 2.0 2RCP-04E 2.0 2RCP llB 2.0 2RCP-17D 2.0 2RCP*05A 2.0 2RCP* llc 2.0 2RCP 17E 2.0 2P.CP*05 B 2.0 2RCP*llD 2.0 2RCP-18A 2.0 2RCP 05C 2.0 2RCP 11E 2.0 2RCP 18B 2.0 2RCP 05D 2.0 2RCP 12A 2.0 2RCP 18C 2.0 2RCP 05E 2.0 2RCP 12B 2.0 2RCP 18D 2.0 2RCP*06A 2.0 2RCP 12C 2.0 2RCP-18E 2.0 2RCP*06B 2.0 2RCP*12D 2.0 2RCP*19C 2.0 2RCP*06C 2.0 2RCP 13A 2.0 2RCP*19D 2.0 2RCP*06D 2,0 2RCP-13B 2.0 2RCP*19E 2.0 2RCP*06E 2.0 2RCP-13C 2.0 2RCP*20C 2.0 2RCP 07C 2.0 2RCP*13D 2.0 2RCP*20D 2.0 2RCP 08A 2.0 2RCP 13E 2.0 2RCP*20E 2.0 2RCP-08B 2.0 2RCP*14A 2.0 2RCP*21C 2.0 1RCP 08C 2.0 2RCP*14 B 2.0 2RCP*21D 2.0

• • D8 2.0 2RCP*14C 2.0 2RCP*21E 2.0 2RCP*08E 2.0 2RCP*14D 2.0 2RCP FL1 2.0

• • Spare electrical penetrations.

Total Type B Electrical Penetration Leakage - 168 SCCM or 8.55 SCFD Parje 8 of 9 j

ATTACHMENT 4.lA (continued)

FIRST REFUELING LOCAL LEAKACE RATE TEST DATA TYPE B TESTS AS FOUND AS LEFT ASSICNED PENETRATION DATE LEAKAGE LEAKAGE PENETRATION TESTED (SCP/D) (SCF/D) LEAKAGE Fuel Transfer Tube 04 28 90 0.49 0.49 0.49 Equipment Hatch Outer Flange 05 02 90 0.49 0.49 0.49 Equipment Hatch Inner Flange 05 03 90 0.50 0.50 0.50 Personnel Airlock 04 28 89 0.49 0.49 0.49 Equipment Hatch Airlock 05 03 89 0.50 0.50 0.50 Summary of Tvve B and C Leakage Rates  %

As Left # As Found n#

Total Type B Leakage 11.02 SCP/D 11.02 SCF/D Total Type C Leakage 382.60 SCP/D 332.d5 3CF/D s

Total Type B and C Leakage

• 393.62 SCF/D 343.87 SCF/D

• Acceptance Criteria < 60% La (< 4,160 SCF/D1 ]

1. Maximum pathway leakage rate.

1. 1. Minimum pathway leakage rate.

1 Fa - 59.4 PSIA Page 9 of 9

ATTACHMENT 4.1B FIRST REFUELING LOCAL LEAKAGE RATE TEST REPAIRS Igp.g_B Repairs None Tyra C Reesirs Penetration No. 1 The initial leak test was performed April 13, 1989. Due to EQ Requirements, the torque switch for valve 2CCP*MOV157 2 was replaced per Maintenance Work Requcst 898046. Following the replacement, the Type C retest was performed on April 15, 1989, with a measured leakage of 13.73 SCF/D.

Penetration No. 2 The initial leak test was performed April 3,1989. Due to EQ Requirements, the torque switch for valve 2CCP*MOV150 2 was replaced per Maintenance Work-Request 898002. Following the replacoment, the Type C retest was performed on April 9, 1989,-with a measured leakage of 390.15 SCF/D. The valve was removed anc returned .to the vendor to have the seat . replaced per Maintenance Work Request 898384. Following the repair, the Type C retest was performer' on April 21, 1989, with a measured leakage of 0.49 SCF/D.

Penetration No. 4 The initial leak test was performed April- 13, 1989. Due to EQ Requirements, the torque switch for valve 2CCP*MOV151 2 was replaced per Maintenance Work Request 898001. Following the replacement,- the Type-C retest was performed on April 16, 1989, with a measured leakage of 63.76 P- SCF/D, Paga 1 of 7

i o.

ATTACHMENT 4.1B (continued)

FIRST REFUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe C Reonirs (continued) e Penetration No. 11 The initial leak test. was performed March 23, 1989. Due to vendor recommendations, the connection between the valve stem and the valve operator for valves 2IAC*MOV133 and 2IAC*MOV134 was modified per Maintenance Work Requests 889916 and 889915 respectively. Following the modification, the Type C retest was performed on March 28, 1989, with a measured leakage of 11.67 SCF/D for 2IAC*MOV133 and 7.78 SCF/D for 2IAC*MOV134.

Penetration No. 14 The initial leak test was performed April 11, 1989, Due to EQ Requirements, the torque switch for valve 2SWS*MOV153-2 was replaced per Maintenance Work Request 898043, Following the replacement, the Type C retest was pe rformed on April 24, 1989, with a measured leakage of 2.34  !

SCP/D.

L Relief valveE 2SWS*RV153 was removed for In Service Testing per Maintenance Work Request 898375. Following the reinstallation, the Type C retest was performed on April 24, 1989, with a measured leakage of 0.49 SCP/D.

l Penetration No. 20 The initial leak test was perfvrmed April 13,1989. Due to excessive body to bonnet leakage, Maintenance Work Request 895410 was initiated forc 2 SIS *42. The bonnet gasket and disc seat were replaced. The Type C retest L was performed on April 15, 1989, with a measured leakage of u0.49 SCF/D.

y-L i

L

!' Page 2 of 7 L

o ATTACHKENT 4.1B (continued)'

- FIRST REFUELING LOCAL LEAKACE RATE TEST REPAIRS Tvoe C Repairs (continued)

Relief- valve 2 SIS *RV130 was removed for In Service Testing per Maintenance Work Request 898182. Following the reinstallation, the Type C retest was performed on April 15, 1989, with a measured leakage of 0.49 SCP/D.

Penetration No. 21 The initial leak test was performed April 12, 1989. Due to EQ Requirements, the torque switch for valve 2SWS*MOV155 2 was replaced per

, Maintenance Work Request 898044. Following the replacement, the Type C ratest was performed on April 24, 1989, with a measured leakage of 0.98 SCP/D.

Relief valve 2SWS*RV155 was removed for In Service Testing per Maintenance Work Request 898876. Following the reinstallation, the Type C retest was performed on April 27, 1989, with a measured' leakage of 0.49 SCP/D.

Penetration No. 24 The int.ial leak test was performed March 24, 1989. Due to excessive packing leakage Maintenance Work Roquest 895366 was initiated for

2 RHR*107. The valve .was repacked and the Type C rotest was performed on March 128,-1989, with a measured leakage of 0.49 SCP/D.

-Penetration No. 25

.The . initial leak test was performed March- 21, 1989, Relief valve 2SWS*RV154 was removed for In Service Testing per Maintenance Work Request 898875. Following .the reinstallation, the Type C retest was_ performed on

. April 25, 1989, with a measui cd leakage of 0.49 SCF/D.

Page 3 of 7

D ATTACHMENT 4.1B (continued)

FIRST REFUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe C Repairs (continued)

Penetration No. 27 The initial leak test was performed March 21, 1989. Due to EQ Requirements, the torque swntch for valve 2SWs*Movi52 2 was replaced per Maintenance Work- Request 898924. Following the replacement, the Type C retest was performed on April 24, 1989, with a measured leakage of 0.49 SCF/D.

Relief valve 2SWS*RV152 was removed for In Service Testing per Maintenance Work Request 889392. Following the reinstallation, the Type C retest was performed on April 24, 1989, with a measured leakage of 0.73 SCF/D.

Penetrr.cion No. 28

~The initial leak test was performed April 12, 1989. Due to excessive seat leakage, Maintenance Work Request 898859 was initiated for 2CHS*HCV142.

The valve actuator was adjusted to permit the valve to close completely.

The . Type C retest was performed on April 15, 1989, with a measured leakage of 1.47 SCP/D.

Penetration No. 38 The initial leak test was performed April 4, 1989. Relief valve 2DAS*RV110 was removed for In Service Testing per Maintenance Work Request 889377.

Following the reinstallation, the Typo C retest was performed on April 15, 1989, with a measured leakage of 0.49 SCF/D.

Penetration No. 45 The initini leak test was performed March 22, 1989. Relief valve 2RCS*RV100 was removed for In-Service Testing per Maintenance Work Request 889373. Following the reinstallation, the Type C retest was performed on April 8,1989, with a measured leakage of 0.49 SCF/D.

Page 4 of 7 f

, y. ___. , .._ _ _ _ . . _ . _- - _ . _ _ _ _ _ _ _ _ _ . _ . _ , . _ .. ._ _

ATTACHMENT 4,1B (continued)

FIRST REIVELING LOCAL LEAKACE RATE TEST REPAIRS Iyne C Repairg (continued)

Maintenance Work Request 898382 was initiated for repair of 2RCS*72 which lifted at an extremely low pressure during the performance of 2BVT 1.47.3.

The valve soft seat dise was replaced. The Type C retest was performed on April 14, 1989 with a measured leakage of 0.49 SCP/D.

Penetration No. 55 1 The initial leak test was performed March 24, 1989. Relief valve 2SSR*RV117 was removed for In Service Testing per Maintenance Work Request 889382. Following the reinstallation, the Type C retest was performed on April 10, 1989,-with a measured leakage of 1.76 SCF/D.

Penetration No. 56 2 The initial leak test was performed April 5, 1989, Relief valve 2SSR*RV120 was removed =for In Service Testing per Maintenance Work Request 889383.

Following -the reinstallation, the Type C retest was performed on April 27, 1989, with a measured leakage of 4.89 SCF/D, Penetration No. 59 y The initial leak test was performed March 23, 1989. Due to vendor

- recommendations, the connection between the valve stem and the valve operator ~ for valves 2IAC*MOV130 was modified per Maintenance Work Requests 889914. Following the modification, the Type C retest was performed on

"_ March 28, 1989, with excessive leakage measured, Maintenance Work Request 898371 was 'nitiated to repair the valve, The valve motor operator was adj us ted to permit the valve to close completely. The Type C retest wes performed on April 10, 1989 with a measured leakage of 0.49 SCF/D.

Page 5 of 7

l ATTACRMENT 4.1B (continued)

.FIRST REFUELING LOCAL LEAY. ACE RATE TEST REPAIRS Iyne C Penairs (continued) b netration No. 63 The initial leak test was performed March 22, 1989. Relief valve 2QSS*RV101A was removed for In Service Testing per Maintenance Work Request 889381. Following the reinstallation, the Type C retest was performed on April 4, 1989, with a measured leakage of 8.28 SCF/D.

Penetration No. 63 The initial leak test was performed March 22, 1989. Relief valve 2QSS*RV101B was removed for a previously reported coupling leak per Maintenance Work Requent 878276. Following the reinstallation, the Type C retest was performed on April 6, 1989, with a measured leakage of.0.49 SCP/D.

Penetration No. 94 The initial leak test was performed March 23, 1989. Due to excessive seat leakage,- Maintenance Work Request 898355 was initiated for 2CVS*151-1. The valve seat was replaced. The Type C retest was performed on April 5. 1989, with a measured leakage of 0.49 SCF/D.

Penetration No. 97-1 The initial leak test was performed April 5, 1989. Due to excessive seat 1,2 leakage, Maintenance Work Request 898379 was initiated for 2SSR*SOV129A 1.

The valve plug was replaced, and the seat lapped. The Type C retest was performed on April 27, 1989, with a measured leakage of 2.93 SCF/D.

Relief valve 2SSR*RV122 was removed for a previously reported coupling 1aak per Maintenance Work Request 871946. Following the reinstallation, the Type C retest was performed on April 18, 1989, with a measured leakage of.

0.49 SCP/D.

Page 6 of 7

- -- - .. ... . .. . . . .. .. ~ _ - . . ._ .. . . - _. - -._. - . __. _ - - - - _ ~ .

9 ATTACHMENT 4.1B (continued)

FIRST REFUELINC LOCAL LEAY, AGE RATE TEST REFAIRS Ivoo C Reonirs (continued)

Penetration No. 103 The initial leak test was performed March 21, 1989. Due to excessive boundary valve leakage, Maintenance Work Request 898180 was initiated for 2FNC 39. Following the repair of 2FNC 39, the Type C retest was satisfactorily performed on March 27, 1989.

Penetration No. 106 The initial leak test was performed April 4, 1989. Due to excessive packing leakage, Maintenance Work Requeat 895357 was initiated for 2 SIS *MOV842. The valve packing was adj us ted. The Type C retest was performed on April 22, 1989, with a measured leakage of 0.49 SCF/D.

Page 7 of 7

l

, ATTACHMENT 4.1C BVPS UNIT #2 SPCOND REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D) (SCF/D) (SCF/D) 2CCP*MOV157-2 X 09 22 90 15.55 15.55 1 2CCP*RV105 X 09 22 90 19.43 19.43 34.98 2CCP*MOV157-1 X 09 22 90 8.78 8.78 2CCP*MOV150 2 X 09 26 90 27.26 27.26 2 2CCP*RV102 X 09 26 90 10.70 10.70 37.96 2CCP*MOV150 1 X 09 26 90 34.07 34.07 2CCP*MOV151 2 X 09 22 90 0.49 0.49 4 2CCP*RV103 X 09-23 90 4.88 2.38 2.87 2CCP*MOV151 1 X 09 22-90 0.49 0.49 2CCP*MOV156 2 X 09 25-90 16.05 16.05 5 2CCP*RV104 X 09 25-90 8.75 8.75 27.23 2CCP*MOV156 1 X 09 25 90 27.23 27.23 2IAC*MOV133 X 09 11-90 2.42 2.42 11 2.42 2IAC*MOV134 X 09-11 90 1.45 1.45 ,

2SWS*MOV153 2 X 09 08-90 0.48 0.48 14- 2SWS*MOV153 1 X 09 12-90 0.48 0.48 0.48 2SWS*RV153 X PARALLEL WITH 2SWS*MOV153-1 2CHS*MOV378 X 09 28-90 0,49 0.49 19 2CHS*473 X PARALLEL WITH 2CHS*MOV378 0.49 2CHS*MOV381 X 09 28 90 0.49 0.49 2 SIS *42 X 10 21-90 11.66 0.49 0.49 20 2 SIS *41 X 10 04 90 2.72 0.49 2 SIS *RVl30 X PARALLEL WITH 2 SIS *41 TOTAL PENETRATION LEAKACE SHEET 1 (SCF/D) 106.92 Page 1 of 9 1

ATTACHMENT 4.1C (continued)

.BVPS UNIT #2 SECOND REFUELING LOCAL LEAKAGE RATE TEST DATA TY1'E C TESTS CONTAINMENT .AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAY. ACE LEAKACE LEAKAGE IN OUT (SCF/D) (SCP/D) (SCF/D) 25WS*MOV155 2 X 09-08 90 0.77 0.77 21 2SWS*MOV155 1 X 09 17 90 0.77 0.48 0.77 25WS*RV155 X PARALLEL WITH 2SWS*MOV155 1 2RHS*107 X 09 23 90 3.40 3.40 24 2RHS*15 X 09 23 90 0.49 0.49 3.40 2RHS*RV100 X PARALLEL WITH 2RHS*15 2SWS*MOV154 2 'X 09 09 90 0.48 0.48 25 2SWS*MOV154 1 X 09-09-90 0.48 0.48 0.48 2SWS*RV154 X PARALLEL WITH 2SWS*MO '154-1 2SWS*MOV152 2 X 09 09 90 0.48 0.48 27 2SWS*H0V152 1 X 09 12 90 0.48 0.48 0.48 2SWS*RV152 X PARALLEL WITH 2SWS*MOV1521 2CHS*A0V200A X 10-15-90 0.49 0.49 2CHS*A0V200B X PARALLEL WITH 2CHS*A0V200A 2CHS*A0V200C X PARALLEL WITH 2CHS*A0V200A 28 1.47 2CHS*HCV142 X 10 15 90 0.49 0.49 2CHS*RV203 X 10-15-90 0.49 9.49 2CHS*A0V204 X 10-15 90 0.49 0.49 2DGS*A0V108A X 09-25-90 0.49 0.49 29 2DCS*A0V108B X 09 28 90 0.49 0.49 0.49 2DGS*RV115 X PARALLEL WITH 2DCS*A0V108B TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/D) 7.09 Page 2 of 9

ATTACHMENT 4.1C (continued)

BVPS UNIT #2 SECOND REFUELING LOCAL LEAKACE RATE TEST DATA TYPE C TESTS CONTAINMENT AS TOUND ! AS LEFT . ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKACE LEAKAGE LEAKAGE -

IN OUT (SCP/D) (SCP/D) (SCP/D) 2DAS*A0V100A X 10 06 90 262 0.49 38 2DAS*A0V100B X 10 01-90 3.50 3.50 3.50 2DAS*RV110 X PARALLEL WITH 2DAS*A0V100B 2SAS*15 X 09 06 90 15.84 15.84 42 15.84 2SAS*14 X 09 06 90 4.95 4.95 2CVS*93 X 09 21 90 5.90 5.90 43 5.90 2CVS*A0V102 X 09 21 90 0.49 0.49 2CVS*SOV153B X 09 21-90 17.12 17.12 44 48.91 2CVS*SOV153A X 09 21 90 48.91 48.91 2RCS*72 X 09 09 90 0.48 0.48 45 2RCS*A0V519 X 09 09 90 C.48 0.48 0.48 2RCS*RV100 X PARALLEL WITH 2RCS*A0V519 2VRS*A0V109A 2 X 09 27-90 0.49 1.12 48 1.51 2VRS*A0V109A 1 X 09 27-90 34.27 1,51 2RCS*6P X 09 19 90 5.37 5.37 49 5.37 2RCS*A0V101 X 09 19 90 5.37 5.37 2CNS*A0V101 2 X 09-23 90 0.50 0.50 53 0.50 2CNS*A0V101-1 X 09 30 90 0.50 0,49 2SSR*A0V109A 1 X 09 27 90 0.49 0.49 55 1 2SSR*A0V109A 2 X 09-27 90 0.49 0.49 0.49.

2SSR*RV117- X PARALLEL WITH 2SSR*A0V109A 2 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 82.50 4

Page 3 of 9 l

ATTACILMENT 4.10 (continued)

BVPS UNIT #2 SECOND REFUELING LOCAL LEAYAGE PATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCP/D) (SCF/D) (SCF/D) 2SSR*SOV130A 1 X 09-29 90 5.36 5.36 55-2 5.36 2SSR*SOV130A 2 X 09 29 90 5.36 5.36 2}iCS*SOV136A X 09 12-90 0.48 0.48 i 55 3 0.48 211CS*SOV136B X 09 12 90 0.48 0.48 2SSR*A0V102A-1 X 09-11-90 1.11 1.11 56-1 2SSR*A0V102A 2 X 09-23 90 1.11 0.49 1.11 2SSR*RV118 X PARALLEL WITil 2SSR*A0V102A-2 2SSR*SOV128A 1 X 09-24-90 0.49 0.49 56 2 2SSR*SOV128A 2 X 0.49 0.49 0.49 09-2490l 2SSR*RV120 X PARALLEL WITil 2SSR*A0V128A-2 2SSR*A0V100A-1 X 09 27-90 0.49 0.49 56-3 2SSR*A0V100A 2 X 09-27-90 0.49 0.49 0.49 2SSR*RV119 X PARALLEL WITil 2SSR*A0V100A 2 2SSR*A0V112A 1 X 09-11 90 0.48 0.48 57 1 2SSR*A0V112A 2 X 10 01 90 0.48 0,48 0.48 2SSR*RV121 X PARALLEL WITil 2SSR*A0Vll2A 2 211CS*SOV135 A X 09-12 90 0.48 0.48 57-2 0.48 2HCS*SOV135B X 09 12 90 0.48 0.48 2IAC*22 X 09 11-90 0.48 0.48 59 0.48 2IAC*MOV130 X 09-11 90 0.48 0.48 TOTAL PENETRATION LEAKAGE SilEET 4 (SCF/D) 9.37 i

Page 4 of 9

ATTACHMENT 4.1C (continued)

BVPS UNIT #2 SECOND REFUELIllC LOCAL LEAYJGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAKAGE LEAVACL LEAKAGE IN OUT (SCP/D) (SCF/0) (SCF/D) 2QSS*4 X 09 10 90 0.48 0.48 63 2QSS*MOV101A X 09 10 90 8.20 8.20 8.20 -

g 2QSS*RV101A X PARALLEL WITH 2QSS*MOV101A 2QSS*3 X 09-10 90 0.48 0.48 64- 2QSS*MOV101B X 09 20 90 0.48 0.49 0.49 2QSS*RV101B X PARALLEL WITH 2QSS*MOV101B 2HCS*111 X 09 13 90 10.17 10.17 87 10.17 2HCS*MOV117 X 09 13 90 10,17 10.17 2HCS*110 X 09 13 90 0.48 0.48 88 0.48 2HCS*MOV116 X 09-13 90 0.48 0.48 2HVR* MOD 23B X 90 10 22 90 62.80 68.21 68.21 2HVR* MOD 23A X 2HVR* MOD 25B X 91 2HVR* MOD 25A X 10 23 90 86.90 97.40 97.40 2HVR*DMP206 X 2HCS*S0V114B X 09 18 90 0.49 0.49 2HCS*S0V115B X 09 18 90 0.49 0.49 92 15.09 2CVS*SOV151B X 09 18 90 0.49 0.49 2CVS*SOV152B X 09-18 90 14.60 .14.60 2HCS*S0V114A X 09-13 90 5.31 5.31 2HCS*SOV115A X 09 13 90 4.06 4.06 93 11.11 2CVS*SOV151A X 09 13 90 5.80 5.80 2CVS*SOV152A X 09 13-90 2.22 2.22 TOTAL PENETRATION LEAKACE SHEET 5 (SCF/D) 211.15 Page 5 of 9

ATTACHMENT 4.1C (continued)

BVPS UNIT #2 SECOND REFUELING IDCAL LEAYACE PATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO. MARK NO. TESTED LEAFACE LEAKACE LEAVACE IN OUT (SCF/D) (SCF/D) (SCF/D) 2CVS*151 X 09 26 90 3.89 3.89 94 3,89 2CVS*151 1 X 10 02 90 > 2864 0.49

^

2SSR*SOV129A-1 X 10 21 90 > 2864 0.49 97 1 2SSR*SOV129A 2 X 10 22 90 1.07 0.49 0.49 2SSR*RV122 X PARALLEL WITH 2SSR*A0V129A 2 2HCS*SOV133B X 09 12 90 0.48 0.48 97 2 0.48 2HCS*SOV134B X 09 12 90 0.48 0.48 2 FPS *761 X 10-06 90 0.49 0.49 99 3.89 2 FPS *A0V206 X 10 06 90 3.89 3.89 2 FPS *753- X 09-26-90 1.07 1.07 101 5.35 2 FPS *A0V205 X 09 26 90 5.35 5.35

?FNC*121 X- 09 07 90 0.78 0.78 103 9.73 2FNC*38 X 09 07-90 9.73 9.73 2 FNC*122 X 09 07 90 0.78 0.78 104- 0.78 2FNC*9 X 09 07-90 0.78 0,78 2HCS*SOV133A X 09 13-90 3.-29 3.29 10541 3.29 2HCS*SOV134A X 09 13-90 0.49 0.49 2 PAS *SOV105A1 X 09-20-90 1.07 1.07 105 2 1.07 2 PAS *S0V105A2 X 09 20-90 0.49 0.49 2LMS*S1 X 09 21 90 0.49 0.49 105 3 0.49 2 LMS*S2 X 09 21-90 0.49 0.49 TOTAL PENETRATION LEAKACE SHEET 6 (SCP/D) 29.46 Page 6 of 9

P ATTACHMENT 4.1C (continued)

BVPS UNIT #2 SECOND REFUELINO LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETPATION NO. MARK No. TESTED LEAKAGE LEAYAGE LEAKAGE IN OUT (SCF/D) (SCP/D) (SCF/D) 2 SIS *Mov842 X 09 11 90 0,48 0.48 106 2SIA*A0V889 X 10 03 90 2.95 0.49 0.49 2 SIS *RV175 X PARALLEL WITH 2 SIS *A0V889 2FPW*388 X 09 24 90 0.49 0.49 116 0.49 2 FPS *A0V221 X 09 24 90 0.49 0.49 2FPW*382 X 09 24 90 8.75 8.75 117 12.16 2 FPS *A0V204 X 09 24 90 12.16 12.16

-2QSS*267 X 10 21 90 > 2864 0.49 118 2QSS*SOV100A X 10 22 90 2864 18.48 18.4P 2QSS*SOV100B X PARALLEL WITH 2QSS*SOV100B TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 31.62 TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 106.92 TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/D) 7.09 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 82.50 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) -9.37 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 211.15 TOTAL PENETRATION LEAKAGE SHEET 6 (SCP/D) 29.46 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 31.62 TOTAL CONTAINMENT TYPE C LEAKAGE SUM OF SHEETS 1 THRU 7 (SCF/D) 478.11

.g Page 7-of 9 1

e ATTACRMENT 4.1C (continued)

BVPS UNIT #2 SECOND REFUELINC LOCAL LEAKACE RATE TEST DATA TYPE B TESTS TYPE B TEST CONTAINMENT ELECTRICAL PENETRATIONS PENT LEAK PENT LEAK PENT LEAK PENT RATE PENT RATE PENT RATE NO (SCCM) NO (SCCM) NO (SCCM) 2RCP*02C 2.0 2RCP 09A 2.0 2RCP*14E 2.0 2RCP 02D 2.0 2RCP+09B 2.0 ** Ell 2.0 2RCP*02E 2.0 2RCP-09C 2.0 2RCP-15C 2.0 W 2RCP*03A 2.0 2RCP 09D 2.0 2RCP 15D 2.0 2RCP*03B 2.0 2RCP 09E 2.0 2RCP*15E 2.0 2RCP 03C 2.0 2RCP*10A 2.0 2RCP*16C 2.0 2RCP*03D 2.0 2RCP*10B 2.0 2RCP*16D 2.0 2RCP*04A 2.0 2RCP*10C 2.0 2RCP*16E 2.0

• • B4 2.0 2RCP*10D 2.0 2RCP 17A 2.0 2RCP 04C 2,0 2RCP*10E 2.0 2RCP-17B 2.0 2RCP 04D 2.0 2RCP 11A 2.0 2RCP 17C 2.0 2RCP-04E 2.0 2RCP-11B 2.0 2RCP 17D 2.0 2RCP*05A 2.0 2RCP*11C 2.0 2RCP 17E 2.0 2RCP*05B 2.0 2RCP*11D 2.0 2RCP 18A 2.0 2RCP 05C 2,0 2RCP-11E 2.0 2RCP 18B 2.0 2RCP-05D 2.0 2RCP 12A 2.0 2RCP 18C 2.0 2RCP-05E 2.0 2RCP-12B 2.0 2RCP 18D 2.0 2RCP*06A 2.0 2RCP 12C 2.0 2RCP-18E 2.0 2RCP*06B 2.0 2RCP*12D 2.0 2RCP*19C 2.0 2RCP*06C 2.0 2RCP 13A 2.0 2RCP*19D 2.0 2RCP*06D 2.0 2RCP 13B 2,0 2RCP*19E 2.0 2RCP*06E 2.0 2RCP-13C 2.0 2RCP*20C 2.0 2RCP 07C 2.0 2RCP*13D 2.0 2RCP*20D 2.0 2RCP 08A 2.0 2RCP-13E 2.0 2RCP*20E 2.0 2RCP-08B 2.0 2RCP*14A 2.0 2RCP*21C 2,0-2RCP 08C 2.0 2RCP*14B 2.0 2RCP*21D 2.0

• • DB 2.0 2RCP*14C 2.0 2RCP*21E 2.0 2RCP*08E 2.0 2RCP*14D 2.0 2RCP FL1 2.0

• • Spare electrical penetrations.

Total Type B Electrical Penetration Leakage - 168 SCCM or 8.55 SCFD Page 8 of 9

t l

ATTACH.4ENT 4.10 (continued)

BVPS UNIT #2 SECOND REFUEL 1NC LOCAL LEAKACE RATE TEST DATA TYPE B TESTS AS FOUND AS LEFT ASSIGNED PENETRATION DATE LEAKAGE LEAKAGE PENETPATION TESTED (SCF/D) (SCP/D) LEAKAGE Fuel Transfe - Tube 10 21 90 0.49 0.49 0.49

. Equipment Hatch Outer Flange 10 23 90 0.48 0.48 0.48 Equipment Hatch inner Flange 10 23 90 0.48 0.48 0.48 Personnel Airlock 10 18-90 29.18 29.18 29.18 Equipment Hatch Airlock 10-23 90 0.49 0.49 0.49

{

1 Summary of Tvoe B and C Leakane Rates As left # As Found un Total Type B Leakage 39.67 SCF/D- 39.67 SCF/D Total Type C LeakaSe 478.11 SCF/D 3098.35 SCF/D l Total Type B and C Leakage

• 517.78 SCP/D 3138.02 SCF/D

• Acceptance Criteria < 60% La [< 4,160 SCF/D1 ]

l

1. Maximum pathway leakage rate,

1. 1. Hinimum pathway leakage rate, j

1 Pa - 59.4 PSIA Page 9 of 9 i l

l l

n I

ATTACHMENT 4.1D BVPS UNIT #2 SECOND REFUELINC LOCAL LEAKACE RATE TEST REPAIRS Tvoe B Renairs None Tyne C Reening Penetration No. 4 The "As Found" leak test was performed September 22, 1990. Relief Valve 2CCP*RV103 was removed for In Service Testing per Maintenance Work Request 908137. Following the reinsta11ation, the "As Left" leak test was performed September 23, 1990, with a leakage of 2.38 SCF/D measured.

Penetration No. 14' The "As Found" leak test was performed September 8, 1990. Relief Valve 2SWS*RV153 was removed for in-Service Testing por Maintenance Work Request 908140. Following the reinstallation, the "As Left" leak test was performed September 12, 1990, with a leakage of 0.48 SCP/D measured.

Penetration No. 20 The "As Found" leak test was performed September 7, 1990. Due to excessive seat -leakage, Maintenance Work Request 909502 was initiated for

• Check -Valve 2 SIS *42, The valve seat was replaced and the "As-Left" leak l

test was performed on October 21, 1990, with a leakage of 0.49 SCF/D measured.

Relief Valve 2 SIS *RV130 was removed for In Service Testing per Maintenance Work Request 908131. Following the reinstallation, the "As-Lef t" leak test was pertormed October 4,1990, with a leakage of 0.49 SCF/D measured.

t Page 1 of 5

i V

ATTACHMENT 4.1D (continued)

BVPS UNIT #2 SECOND REFUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe C Reoatrs (continued)

Penetration No. 21 The "As Found" leak test was performed September 8, 1990. Relief Valve 2SWS*RV155 was removed for In-Service Testing per Maintenance Work Request 908141. Following the re ins tallati?m the "As Left" leak test was performed September 17, 1900, with a leak 'a of 0.48 SCF/D measured.

Penetration No. 27 The "As-Found" leak test was performed September 9, 1990. Relief Valve 2SWS*RV152 was removed for In Service Testing per Maintenance Work Request 899469. Following the reins tal: atien, the "As Left" leak test was

. performed September 12, 1990, with a letkage of 0.48 SCF/D measured.

Penetration No. 29 The "As Found" leak test was performed September 25, 1990. Relief Valve

, 2DGS*RV115 was removed for In Service Testing per Maintenance Work Request 908129. Following -the reinstallation, the "As-Left" leak test was performed September 28, 1990, with a leakage of 0.49 SCF/D measured.

Penetration No. 38 The "As-Found" leak test was perforned October 1, 1990. Due to excessive seat leakage, Maintenance Work Request 908797 was initiated for Valve 2DAS*A0V100A. The valve plug and stem assembly were replaced and the "As-Left" leak test was performed on October 6, 1990, with a leakage of 0,49 SCF/D measured, b

[ Page 2 of 5

ATTACMMENT 4.1D (continued)

BVPS UNIT p2 Sf'COND REFUELING LOCAL LEAKAC.E RATE TEST REPAIRS Iy.Du',,}ppair s (continued)

Penetration No. 48 s

The "A Fourd" leak test was pa-brmed Septembe r 20 1990. Due to

, excessive packing leakage, Maintenance Work Reques: 908782 was initiated for.VrIve 2VR$*A0V109A 2. The valve packing was adjusted and the "As Lef t"

( leak test was performed on September 27, 1990, with a leakage of 1.12 SCF/D for Valve 2VRS*A0V109A 2 and 1.51 SCP/D for Valve 2VRS*A0V109A 1 measured.

Penetration No. 53 The "As Found" leak test was performed September 23, 1990. Valve 2CNS*A0V101 1 was repacked per previously written Maintenance Work Request 896516. FollowinS the repack, the "As Left" leak test was performed 5 Septemver 30, 1990, with_a leakage of 0.49 SCF/D measured.

w -

Penetrition No. $6 1 The "As Found" leak test was performeo September 11, 1990. Relief Valve 2SSR0RV118 was removed for In Service Teating per Maintenance Work Request a

9081re 2. Following the reinstallation, the "As Left" leak test was

{, performed September 23, 1990, with a leakage of 0.49 SCF/D measured.

Penetration No. 57 1 The "As Found" leak test was performed September 11, 1990. Relief Valva 2SSR*RV?.21 was removed for In Service Testing per Maintenance Work Request 908143. Following the reinstallation. the "As Left" leak test was performed October 1, 1990, with a leakage of 0.48 SCP/D measured.

Penetration No. 64 The "As Found" leak tsst was performed September 10, 1990, Relief Valve 2QSS*RV101B was removed for In Service Testing per Maintenance Work Request 908136. Following the reinstallation, the "As Left" leak test was performed September 20, 1990, with a leakage of 0.49 SCF/D measured.

Page 3 of 5 t'

e i

a L -

(TTACHMENT 4.1D (continued) l l

BVFS L' NIT #2 SECOND REFUELING LOCAL LEAKACE RATE TEST REPAIRS l l 1 l

l Tyre C Repairs (continued) l-i Fenetration No. 9Q l

a The "As.Found" leak test was performed September 7, 1990. Due to the

, information supplied by NRC Information Notice 88 73, Valve 2HVR* MOD 23B was rotated to provide a more conservative leak test. Following the completion sf Haintenance Work Request 898153, which rotated the valve, the "As.Left" leak test was performed October 22, 1990, with a leakage of 68.21 SCF/D measuted.

4 i fing,trntion No. 91 l

The "As Found" leak test was performed September 7, 1990. Due to the 1 i information supplied by NRC Information Notice 88 73, Valve 2HVR* MOD 25B was l 4

rotated to provide a more conservative-leak test, Following-the completion -j of Maintenance Work Request 898154, which rotated the <alve, the "As.Left" leak test. was performed October 23, 1990, with a leakage of 97.40 SCP/D measured.

Penetration No. 94 The "As.Found" leak test was performed September 26, 1990. Due to excessive cent leakage, Maintenance Work Request 908786 was initiated for Valve 2CVS*151 1. The valvs seat was replaced'and the "As.Left' leak test was performed on October 2, 1990, with a leakage of 0.49 SCP/D measured.

Penetration No. 97 1 The "As Found" leak test was performed September 24, 1990. Due to excergive seat ' leakage , Maintenance Work Request 908783 was initiated for Valve 2SSR*SOV129A 1. The valve plug o. rings were replaced and_ the "As+Left" leak test was performed on October 21, 1990, with a leakage of 0.49 SCP/D measured.

Page 4 of 5

. _. _ - - . _ . - _ _ . _ _ _ _ _ _ . . ~ _ _ - _ _ . _ _ . . . _ . _ _ _ _ . _ . . _ _ . _ . _ . _ _ . _ . _ _ . -

i i

i i ATTACRMENT 4.1D (continued) I

'j bVn UNIT 82 SECOND REFUELINO LOCAL LEAVACE RATE TEST REPAIRS l

4 Tyre C Rernirs (continued) l 5

' Haintenance Work Request 909509 was initiated for replacement of the Inlet $

riange Casket of Relief Valve 2SSR*RV122. Following the replacement of the l gasket, the "As+Left" leak tes' was performed October 22, 1990 with a leakage of 0.49 Scr/D mea 6ured.

L.

Penetration No. 106 The "As Tound" Itak test was performed September 11 1990. Due to slight i

leakage of Rolief Valve 2 SIS *RV175 during the previous fuel cycle, Maintenance Work Request 898944 was initiated to repair the val a .

Following the renair, the As Le f t" leak test was performed October 3, 1990, with a leakage of 0.49 Scr/D measured.

Penetration No. 118 The "As rov.3d" leak test was performed October 16, 1990. Due to excessive seat leakap, Maintenance Work Requeet 90952S was initiated for Check Valve 2QSS*267. The valve seat was replaced and the "As Left" leak test was performed on October 21, 1990, with a leakage of J.49 Scr/D measured.

Due to excessive seat loakago, Maintenance Work Requ0st 909521 and 909522 were initiated for Valves 2QSS*SOV100A & B respectively. The valve plug

o .-ings were replaced on - both valves and the "As Left" leak . test was performed' on October 22, 1990, with a combined leakage of 18.48 SCF/D i measured.

r Prge 5 of 5 i

+-

e,w. c r -r , , , - . - . ,, , , , , - , _ , n - - - . . . , , . . .n,n.ns-,--, . , , - , .....,-.r,--- .-,-++,.,-.,,e--,r- - , - ,-

ATTAC)! MENT 4.1E FIRST AND SECOND FUEL CYCLE LOCAL LEAKACE PATE TEST DATA

1. Tirst Fuel Cvele LUtT Darn J

A. Type B Tests

1. Airlock Total Volume Type B Tests

a. Personnel Airlock (2PHS* PAL 1] (12 02 87) -

7.27 SCF/D Corrective Action (s) None,

b. Equipment flatch Airlock [2PHS*EAL1] (12 03 87) -

8.14 SCF/D Corrective Action (s) None,

c. Personnel Airlock (2PilS* PAL 1] (05 24 88) -

4.11 SCF/D Corrective Action (s) None.

d. Equipment Hatch Airlock [2PHS*EAL1) (05 25 88) -

0.85 SCP/D Corrective Action (s) None.

c. Personnel Airlock l2PHS* PAL 1] (11 15 88) --

43.69 SCP/D Corrective Action (s) None,

f. Equipment Hatch Airlock [2PHS*EAL1] (11 16 88) -

6.52 SCF/D Corrective Action (s) - None.

B. Type C Tests 1

1. Penetration No. 56 1, RCS Cold Leg Saaple (10 13 87)

a. Valve No. 2SSR*RV118 - Relief valve 2SSR*RV118 was removed for Page 1 of 3 L

ATTACHMENT 4.1E FIRST AND SECOND FUEL CYCLE LOCAL 1r,Ay. ACE RATE TEST DATA setpoint verification per M'a'R 873;03.

No adjusta.ents were necessary. The as found and as left leakage valve Icarage rate was 0.49 SCP/D.

II . Second Puel Cvele LLRT Dnta A. Type B Tests

1. Airlock Total Volume Type B Tests

a. Personnel Airlock [2PHS* PAL 1] (1017 89) - -

47.44 SCF/D Corrective Action (s) None,

b. Equipment Hatch Airlock [2PHS*EAL1] (1018 88) -

5.05 SCF/D Corrective Action (s) None.

c. Personnel Airlock [2PHS* PAL 1] (04 10 90) - -

43.65 SCF/D Corrective Action (s) None.

d. Personnel Airlock [2PHS* PAL 1) (04 11 90) - -- 7.07 SCF/D Corrective Action (s) None.

B. Type C Tests

1. Penetration No. 56 2. RCS Hot Leg Sample (06 27 90)

a. Valve No. 2SSR*RV120 Relief valve 2SSR*RV120 was replaced l 1

due to apparent leakage from discharge l Page 2 of 3 I

.isi-m immiimiim-iin-iissm--

o ATTACllMENT 4.1E FIRST AND SECOND PJEL CYCLE LOCAL LEJJ'JsCE P. ATE ILST DATA of relief valve per tro*R 905631. The as found and as left valve leakage rates were 0.49 SCF/D.

i e

Note: BVPS #2 administratively limics Type B leakage of each airlock to 5% La (347 SCF/D). Total Type B and C leakage (excluding airlocks) is administrative 1y limited to 506 La to account for airlock retests.

Page 3 of 3 0

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