Text

Reactor Containment Bldg Integrated Leak Rate Test. W/
	ML20012C467
Person / Time
Site:	Beaver Valley
Issue date:	03/05/1990
From:	Lacey W, Manko R, Zyra T; DUQUESNE LIGHT CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9003210370
	Download: ML20012C467 (90)
	v • d • e

Beaver V:ioy Power $tation Shippmgport. F A 15077 00D4

, Pr so o Ne me,Geoup i

March 9, 1990 U.

S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Reactor Containment Building Integrated Leakage Rate Report Gentlemen:

Enclosed is the Beaver Valley Unit No. 1 Reactor Containment Building Integrated Leakage Rate Report submitted in accordance with Appendix J

of 10CFR Part 50.

The report provides a summary of the results of all Local Leakage Rate Testing performed since the previous Integrated Leakage Rate Test.

Very truly yours, k,1 by' D. Sieber l

Vice President Nuclear Group Attachment l

cc:

Mr. J.

Beall, Sr. Resident Inspector Mr.

P.

Tam, Sr. Project Manager l

Mr. R.

Saunders (VEPCO) l

.Ow 9003230370 900305 ADOCK0"'00g4 ppg P

i l

REACTOR CONTAINMENT BUILDING INTEGRATED LEAKAGE RATE TEST DUQUESNE LIGHT COMPANY BEAVER VALLEY POWER STATION UNIT NO. 1 DECEMBER 1989 Prepared By:

b[ M

}

Date:

A-9-90 R. J. ilanko Test Engineer Reviewed By m-Date: 2 -/ S -'lO l

'f. 0 ?M l

Director Testing and Plant Performance LW Date: E'0V"$0 jW.'S.[ Lacey General Man er clear ops Support Services Date:

d K. D. Grada Nuclear Safety Manager

[d Approved By: -

Date:

~

T. P. Noohan General Manager Nuclear Operations i

TABLE OF CONTENTS Section Title Eggg TABLE OF CONTENTS 11 LIST OF ATTACHMENTS iii REFERENCES iv 1

PURPOSE 1-1 2

SUMMARY

2.1 TYPE A ILRT 2.1 1 2.1.1 Test Summary 2.1 1 g

2.2 1hCAL LEAKAGE RATE TESTS (TYPES B & C) 2.2-1

[

3 INTEGRATED LEAKAGE RATE TEST 3.1 EDITED LOG OF EVENTS 3.1-1 q

3.2 GENERAL 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 A

3.3.1 Presentation of Test Results 3.3-1 3.3.2 54.7 PSIA ILRT Results 3.3 3 3.3.2.1 ILRT Results - Mass Point Analysis 3.3 3 3.3.2.2 Supplemental Test Results 3.3 4 3.3.2.3 Leakage Penalties added to ILRT Leakage 3.3 5 3.3.2.4 As Found Containment Condition LLRT Improvements 3.3-7 3.3.3 Conclusion 3.3 9 4

LOCAL LEAFAGE RATE TESTS (TYPES B AND C) 41 ii

LIST OF ATTACRMENTS f

ATTACHMENT TITLE 2.1A Graph 1 Containment Mass vs Time 3.2A Instrumentation List 3.3A ILRT Reduced Input Variables 3.3B ILRT Absolute Test Method Mass Point Analysis Test Results 3.3C Graph 2 Containment Air Mass vs Time 3.3D Graph 3 Leakage Rate and UCL vs Time, Mass Point Analysis 3.3E Superimposed Leakage Verification Test Reduced Input Variables.

3.3F Superimposed Leakage Verification Test, Absolute Test Method - Mass Point Analysis 3.3G Mechanical Seal Arrangement for Outside Recirculation Spray Pumps 4.1A Sixth Refueling Local Leakage Rate Test Data 4.1B Sixth Refueling Local Leakage Rate Repairs 4.1C Seventh Refueling Local Leakage Rate Test Data-4.1D Seventh Refueling Local Leakage Rate Repairs-4.1E Sixth and Seventh Fuel Cycle Local Leakage Rate Data l

iii

REFERENCES

1. 10CTR50, Appendix J Primary Reactor Containment Leakage Testing For Vater Cooled Power Reactors, January 1, 1989 2.1BVT 1.47.2, Containment Integrated Leakage Rate Test, Beaver Valley Power Station Unit No.1, Issue 2, Revision 3, September 8 1989.

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

4. ANSI /ANS 56.8, Containment System Leakage Testing Requirements, January 20, 1987.1 IThis document used only as a guideline and any reference to said document in no way implies compliance.

iv

SECTION 1 PURPOSE The purpc.se of this report is to present a description and analysis of the December 1989 Type A Containment Integrated Leakage Rate T6st (ILRT), and a summary of Type B and C Local Laakage Rate Tests (LLRT's) performed since the last periodic ILRT (August 1986) at Duquesne Light Company's Beaver Valley Power Station Unit No.1 (BVPS 1).

Stone & Webster Engineering Corporation (SWEC) provided test engineering consultation services to Duquesne Light Company during the performance of the 1989 ILRT.

This report is submitted as required by 10CFR50. Appendix J. Paragraph V.B.

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SECTION 2

SUMMARY

2.1 TYPE A Ii.RT 2.1.1 Test Summary Upon-completion of all II.RT prerequisites and initial conditions.

containment pressurization started at 2246 hours0.026 days 0.624 hours 0.00371 weeks 8.54603e-4 months on November 29, 1989 at a fairly constant pressurization rate of 3.8 psi per hour. The compressors were secured at 1010 hours0.0117 days 0.281 hours 0.00167 weeks 3.84305e-4 months on November 30, 1989 with a peak instantaneous pressure of 56.217 PSIA.

At 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on November 30, 1989, the temperature stabilization criteria

(<

0.5 'R/Hr) was satisfied. The II.RT start time was declared to be 1500 hours0.0174 days 0.417 hours 0.00248 weeks 5.7075e-4 months on November 30, 1989.

Initial mass trends indicated an unacceptable leakage rate of approximately 45 lbm/hr.

Penetration area leakage investigations identified a seal leak on outside Recirculation Spray Pump (RS P 2B).

At 1742 hours0.0202 days 0.484 hours 0.00288 weeks 6.62831e-4 months on November 30, 1989 (RS P 2B) was isolated by closing pump discharge and suction isolation valves [MOV RS 155B).and (MOV RS 156B).

The ILRT start time was moved to 1800 hours0.0208 days 0.5 hours 0.00298 weeks 6.849e-4 months on November 30., 1989.

The mass trend after isolation of [RS P 2B) still indicated an unacceptable.

leakage rate of approximately 22 lbm/hr.

At 1015 hours0.0117 days 0.282 hours 0.00168 weeks 3.862075e-4 months on December 1, 1989 air was found bubbling from the Fuel Transfer Tube Gate Valve [nt 1) in the Fuel Building Upender Canal..The canal water level was approximately six feet above the gate valve, with the gate valve closed.

Cate valve (FH 1) was opened to relieve accumulated pressure in the Fuel Transfer Tube at 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on December-1, 1989.

2.1-1

Air continued to bubble through the water, indicating a significant leakage path existed through the Fuel Transfer Tube. The mass. trend after openin6 of gate valve

[FH 1) indicated an unacceptable leakage rate of approximately 75 lbm/hr..1A shows how the mass trend was affected by these two leakage paths.

At 1520 hours0.0176 days 0.422 hours 0.00251 weeks 5.7836e-4 months on December 1,

1989 preparations for containment depressurization were started, due to the magnitude of the Fuel Transfer Tube leakage

rate, while extensive leakage investigations of all penetration areas found no other significant leakage paths. Containment depressurization was started at 1918 hours0.0222 days 0.533 hours 0.00317 weeks 7.29799e-4 months on December 1, 1989, and was completed at 0306 hours0.00354 days 0.085 hours 5.059524e-4 weeks 1.16433e-4 months on December 2, 1989.

Determination of the Fuel Transfer Tube, and Outside Recirculation Spray Pump

[RS P 2B) shaft seal leakage paths were started after containment depressurization.

A Type B Icak test of the Fuel Transfer Tube Blind Flange was performed prior to the ILRT, and agian when containment depressurization was completed to verify flange integrity.

Both tests measured an acceptable leakage rate of 0.47 SCF/D.

Inspection and testing of the Fuel Transfer Tube found-that one of the two concentric flexicallic gaskets used to seal-the blind flange-to the Fuel Transfer Tube had dislodged during installation. The gasket had dislodged preventing the flange from sealing completely, and blocked the Type B test port, preventing test gas from pressurizing between the gaskets.

The inner and outer flexitallic gaskets on the Fuel Transfer Tube-Blind Flange were replaced, and the flange was reinstalled.

The-Type B test performed after flange reinstallation-measured a leakage rate of 56.94 SCF/D.

To ensure full thread engagement, and uniform flange compression each blind flange bolt was removed individually, and lubricated.

The threads on one bolt were chased. The blind flange bolts were retorqued, and the Type B test was repeated with a measured leakage rate of 0.47 SCP/D.

2.1 2

The inner and outer mechanical pump seals for [RS P 2B) were cleaned and rebuilt with the existing parts prior to the ILRT because of a slight seal leak found during pump performance testing. Repairs after the first ILRT found the outer mechanical pump seal had inadequate seal face preload.

The inner and outer mechanical seals, and also the shaft sleeve shaft o ring were replaced.

The Seal Water Accumulator was refilled after repairs using a temporary standpipe.

Within approximately five minutes the high level alarm extinguished, while no visible change in the standpipe level could be observed.

This condition was indicative of a defective Seal Water Accumulator diaphragm.

Disassembly of the accumulator verified a defective -diaphragm.

The diaphragm was replaced.

After all maintenance on [RS P 28) was completed, the pump casing was -

pressurized to 42 PSIC to inspect for any seal leakage. No detectable seal leakage was observed.

Upon completion or reverification of all ILRT prerequisites and initial conditions, containment pressurization started at 0248 hours0.00287 days 0.0689 hours 4.100529e-4 weeks 9.4364e-5 months on Decimber 5,

1989 with a fairly constant pressurization rate of 3.2 psi pe nour.

The compressors were secured at 1542 hours0.0178 days 0.428 hours 0.00255 weeks 5.86731e-4 months on December 5,1989 with a peak instantaneous pressura of 56.520 PSIA.

During the second ILRT the Fuel Transfer Tube Gate Valve [FH 1) was open, with the canal water level just above the gate valve.

The water in the canal provided visual indication of any leakage from the Fuel Transfer Tube.

Outside Recirculation Spray Pump [RS P 2B) was aligned with the pump isolation valves [MOV RS 155B) and [MOV RS 156B) open.

At 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months on December 5, 1989, the temperature stabilization criteria was satisfied.

Initial mass trends indicated an acceptable leakage rate of approximately 7 lbm/hr.

Leakage inspections of all penetration areas found no significant leakage paths.

2.1 3

The ILRT start time was declared to be 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months on December 5, 1989.

Temperature,

dewpoint, and pressure data was collected at 15 minute intervals throughout the test period.

The ILRT was successfully completed at 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months on December 6, 1989 with Mass Point Analysis Upper Confidence Limit of 0.031005 percent / day (See a

Section 3.3, Test Results). This leakage rate was well below the 0.75 La acceptance criteria of 0.075 percent / day.

The Superimposed Leakage Verification Test was started at 2045 hours0.0237 days 0.568 hours 0.00338 weeks 7.781225e-4 months on December 6,

1989 when the stability of all the containment parameter trends had recovered from the imposed leakage rate perturbation.

The Superimposed Leakage Verification Test was successfully completed at 0045 hours5.208333e-4 days 0.0125 hours 7.440476e-5 weeks 1.71225e-5 months on December 7, 1989. (See Section 3.3, Test Results)

After review of all ILRT test data, containment depressurization started at 0158 hours0.00183 days 0.0439 hours 2.612434e-4 weeks 6.0119e-5 months and was completed at 1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months on December 7, 1989.

2.1-4

)

r 2.2 IDCAL LEAKAGE KATE TESTS (TYPES B AND C)

The. Local Leakage Rate Tests (LLRT's) of the containment isolation valves-and other containment penetrations were conducted as described in the Beaver Valley Power Station Unit No. 1 surveillance test procedures for

. Type B and C tests.

t e

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.

i a

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5

?

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2.2-1

l J

BEAVER VALLEY POWER STATION UNIT' NO.1-DECEMBER 1989 CONTAINMENT !LRf -

ATTACHMENT 2.1 A - CNMT AIR MASS vs TIME.

y MASS _ (LBM) 498.900 S

498.800 F

M

~

498,700 F

498,600 ;

OPENED [FH--1]

498.500 f.

498.400

~-

ISOLATED [RS-P-28]

498,300 F

498,200 F

'498,500 q

~ 498,000 F

~

O-497,900 F

497,800 b"'""'"""~"'"""""""'"'"""""""'"""'""' " " " ' ' ' ' ' ' ' '

3 q'ND 0

s0 5p0 \\p0 D

0030 o73 ho0 0

0 o@D[o@D sO3 h@D g00 g@D g@D~

D 30 LTiME. (HOURS) -

11/29/89..@.:1430-.TOf :;12/1/89"@[1915L 1

+

h 4.-

, +e o, N'NN -m o wNw-lw w-

SECTION 3 INTEGRATED LEAKAGE RATE TEST 3.1 EDITED LOG OF EVENTS This log was edited from information contained in the ILRT test Log.

November 29. 1989 2109 - Secured the containment personnel airlock and successfully completed Type B test of door seals.

Secured containment lighting.

2246 - Commenced ILRT pressurization.

Initial containment pressure @

14.42 PSIA.

2358 - Containment pressure @ 17.62 PSIA.

November 30. 1989 0245 - Completed walkdown of all' penetration areas, no problems were detected.

Containment pressure @ 28.04 PSIA.

0321 - Noted slight increase on _ pressure gauge installed at Penetration No. 90, Containment Purge Exhaust.

NOTE:

Motor operated dampers inside containment for Penetration 90 and 91 were rotated 180' in response to NRC information Notice 88-73 during the refueling outage prior to the ILRT.

3.1-1

0345 - Received Low Level Seal Water Accumulator alarm for Outside Recirculation Spray Pump

[RS-P 28).

Containment pressure @

31.87 PSIA.

0530 - Operations attempted to refill (RS P 2B) accumulator, but where unable due to air pressure in the accumulator.

0547 - External leakage detected at (RS P-2B) seal.

Containment pressure @ 39.41 PSIA.

1010 - Secured containment pressurization with a peak instantaneous-pressure of 56.217 PSIA.

1030 - Commenced ILRT stabilization period.

1105 - Noted pressure gauge installed at Penetration No.

91, Containment Purge Supply increased to 2 PSIG.

1430 - Satisfied temperature stabilization criteria (< 0.5 'R/Hr).

1500 - Declared start of ILRT.

1505 -

Penetration No.

90 and 91 pressures are still increasing at a slow rate.

Penetration No. 90 at 29.9 PSIC, and Penetration l

No. 91 at 34.6 PSIC.

1738 - Based on 2

1/2 hours of data analysis mass trend is approximately 45 lbm/hr with no signs of improvement. Decided to isolate [RS-P-2B) by closing [MOV-RS-155B) and [MOV-RS-156B) to assess impact of seal leak.

1742 - Closed [MOV-RS-155B] and [MOV-RS-156B).

1750 - Based on closing [MOV-RS 155B) and [MOV-RS-156B] the ILRT will be restarted at 1800.

3.1-2

December 1. 1989-0322 -

Completed walkdown of penetration areas with only several minor packing leaks identified.

Casing of [RS-P 2B) is cressurized to 22.4 PSIG.

0559 - Depressurized (RS-P 28)

casing, and verified isolation valves are leaking by at a rate of approximately 37 SCF/H (leakage measured by a rotameter on vent valve after depressurizing pump casing).

Mass trend since isolating (RS-P 2B) is approximately 22 lbm/hr.

Removed flexible ductwork outboard of outside containment isolation valves on Penetrations No. 90 and 91.

Detected minimal leakage on both valve discs.

0800 -

Isolated Recirculation Spray Heat Exchat.ger (RS E 1A & 1B]

river water inlet and outlet lines by closing [MOV-RW 104A & B) and [MOV RW-105A & B). to assess the possibility of a leakage path through these heat exchangers.

0910 -

Isolated Recirculation Spray Heat Exchanger

[RS-E-lC- & 1D) river water inlet and outlet lines by closing [MOV-RW-104C & D) and [MOV RW 105C & D).

Very slight mass change observed since isolation of [RS-E-1A & IB).

1006 - Unisolated (R3-E-1C & 1D) by opening [MOV-RW-104C & D) and-

[MOV RW-105C & D].

[RS-E 1A & IB) will remain isolated to monitor for any pressure increase on river water lines.

1015 - Operator inspecting for leakage from fuel pool weir gate to upender canal reported that water standing in upender canal i=

ripplin6-1035 -

Possible leakage path from Fuel Transfer Tube, air bubbling through water in canal.

Need to get better lighting in ccnal to determine source of leakage.

3.1-3

1100 - Verified with Refueling Group that air line to fuel handling equipment in upender canal is isolated.

Air appears to be bubbling from packing and valve disc of Fuel Transfer Tube Gate Valve

[FH-1).

(canal water level approximately six feet above gate valve) 1250 - Partially open Fuel Transfer Tube Gate Valve [FH-1); large rush of air was observed. Reclosed gate valve.

1430 - Open gate valve [FH-1) to vent accumulated air pressure in Fuel Transfer Tube to verify continuing leakage. With [FH 1) fully open air continues to stream from Fuel Transfer Tube. Mass trend has increased to approximately 75 lbm/hr.

1520 - Based on the identified leakage paths and their magnitude, the General Manager Nuclear Opcrations has direc: J to terminate the ILRT and prepare for containment depressurization.

1638 - Unisolated

[RS-E-1B) by opening

[MOV-RW-104B]

and

[MOV-RW 105B).

1918 - Commenced containment depressurization.

December 2. 1989 0306 - Completed containment depressurization.

0500 - Containment open, performed fuel transfer blind flange Type B ulch a measured leakage of 0.47 SCF/D. Water was observed flowing from the Ftel Transfer Tube into refueling cavity.

0640 - Completed containment walkdown, no damage observed.

1330 - Setting up for freon leak check of [RS-E-1A & IB).

3.1-4 L

1500 -- Maintenance to remove blind flange from Fuel Transfer Tube, 1530 - Type B test line verified unobstructed by passing flow through line with blind flange removed.

December 3. 1989 0310 - Freon leak test of [RS-E-1A & IB) satisfactorily completed, including all flanges and mechanical joints.

0420 - Maintenance working on placing a temporary flange' on Fuel Transfer Tube in containment to support a pressure test of the

tube, 0900 - Seals and shaft sleeve o ring on [RS-P-2B) were replaced; however, Maintenance believes diaphragm in seal pot accumulator may be defective.

Seal pot accumulator will be disassembled to inspect.

1730 - Completed pressure test of Fuel Transfer Tube. No leakage could be detected in containment.

1950 - Permanent blind flange will be reinstalled on Fuel Transfer Tube and Type B tested.

If Type B test is satisfactory, then fuel building upender canal will be refilled with water above-Sate valve

[FH 1) so Fuel Transfer Tube can be inspected for water leakage in containment.

2140 - Started reverification of containment penetration alignments for repeat of ILRT.

3.1-5

December 4. 1989 0610 - Performed Type B test on-Fuel Transfer Tube Blind Flange after reinstallation. Measured a leakage rate of 56.94 SCF/D.

0800 - Maintenance will inspect blind flange bolt threads, and chase if necessary to ensure full bolt thread engagement, and uniform flange compression.

i 1245 - Performed Type B test on Fuel Transfer Tube Blind Flange after inspection of blind flange bolt threads, and retorquing.

Measured leakage rate was 0.47 SCF/D.

1500 - Filled fuel building upender canal with water above gate valve

[FH-1].

1705 - Completed visual inspection of Fuel

' Transfer Tube in containment for veter leakage. No leakage detected.

1940 - Completed all containment penetration valve alignments and verifications.

2210 - Completed containment walkdown for ILRT.

Secured containment personnel airlock, and successfully completed Type B of door seals.

December 5. 1989 0120 -

Pressure test of [RS-P-2B]

completed with no detectable seal leakage.

0248 - Commenced ILRT pressurization.

Initial containment pressure @

14.17 PSIA.

'l 3.1-6

0725 s,*eted walkdown of all penetration areas, no problems cted.

[RS P 2B] and Fuel Transfer Tuba show no leakage e

ications.

Fuel Transfer Tube Gate Valve [FH 1) is open with canal ve.ter just above valve.

Containment pressure @ 26.98 PSIA.

1542 - Secured containment pressurization with a peak instantaneous pressure of 56.520 PSIA.

1545 - Commenced ILRT stabilization period.

1945 - Satisified temperature stabilization criteria.

Dec1tred start of ILRT at 1945.

2300 - Completed inspection of all penetration areas, only a fer minor packing leaks identified.

Penetrations 90 and 91 have pressurized to 32.5 and 38.6 PSIG respectively; detected minimal '.eakage on both valve discs for these penetrations.

December 6.

1989 0325 - Completed inspection of oil penetration areas.

Operations isolated ventilation in each area momentarily to permit audible leakage inspection. No significant leakage identified.

0500 - Mass trend is acceptable at approximately 7 lbm/hr. Mass Point Upper Confidence Level of 0.047 percent / day.

1300 - No leakage detected in penetration areas, staging test equipment for Superimposed Leakage Verification Test.

1700 - Containment leakage rate at Mass Point Upper Confidence Level of 0.032 percent / day.

3.1-7

'i 1945 - Completed 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months IIAT test period.

1950 - Established a 4.6 SCF/M leakage flow for Superimposed Leakage Verification Test.

2045 - Commenced the Superimposed Leakage Verification Test.

December 7. 1989 0045 - Completed the Superimposed Leakage Verification. Oest.

0158 - Commenced containment depressurization.

1000 - Completed containment depressurization.

3.1-8 4

3.2 GENERAL TEST DESCRIPTION 3.2.1 Prerequisites In accordance with Beaver Valley Power Station Unit 1 ILRT test procedure 1BVT 1.47.2, the following is a listing of the pertinent prerequisites completed and documented prior to containment pressurization:

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

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

c. All penetration valve alignments completed,

d. All ILRT computer software used for data acquisition,- and data analysis, tested and operational.

e. Temporary air compressors and auxiliary equipment checked out and available for pressurization.

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

g. Portable pressure containing equipment removed C+;a e,atainment.

h. Depressurized and vented pressure vessels located i'aside containment.

1. Completed structural integrity inspection of containment.

3.2-1 i

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3.2.2 Equipment and Instrumentation 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 monitoring and control o# the compressed air quality throughout the pressurization sequence.

The total capacity of the pressurization system was 9900 SCFM.

Air was supplied to containment through the Containment Purge System.

The various containment parameters required to calculate containment leakage were monitored using instrumentation which consisted of 16 resistance temperature detectors, 5 dewpoint detectors, and an absolute 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 the plant process P-250 computer.

For the

ILRT, the plant process computer monitored the following instrumentation:

Iygg No. of Sensors Temperature Detectors 16 Dewpoint Sensors 5

Quartz Manometer 1

3.2-2

Instantaneous readings for each sensor were collected and printed at 15 minute intervals.

Input to the daca analysis program was based on these collections.

Each data set was time stamped.

3.2.4 Data Resolution System j

The recorded data was inputted to Stone & Webster Engineering Corporation's portable computer for data reduction and leakage rate l

calculations.

The Masr Point Analysis Method was 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 thm test period, using

pressure, temperature, and devpoint data obtained during the ILRT.

The air mass is computed using the ideal gas law as follows:

144V(P Pv)

M-RT Where:

l M - air mass, Ibm I

i P - total pressure, psia Pv - average vapor pressure, psia R - 53.35 ft-lbm/lbm 'R (for air)

T - average containment temperature, *R V - containment free volume,. 1,760,000 cu. ft 3.2-3 i

The leakage rate is then determined 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 percentage of the air mass lost in 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or symbolically:

Leakage Rate - A/B( 2400)

Where A is the slope of the least squares 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 A confidence interval is calculated using a Student's T distribution.

The sum of the leakage rate and confidence is the Upper Confidence Level.

s 3.2-4

~ _ _ _ _ _

---.m

ATTACHMENT 3.2A INSTRUMENTATION LIST Weight computer Instrument Factor Addrass Egngg Zong Elevation-A. Temperature TRB-LM100 01 0.039104 YO756A 60-100 'F A

739' TRB LM100 02 0.043137 Y1000A 60-100 'F B

739' TRB LM100 03 0.038487 T1000A 60 100 'F A

739'-

TRB-LM100 04 0.041176 T1001A 60 100 'F B

7448-TRB-LM100-05 0.076695 T1002A 60-100 'F C

799' TRB-LM100-06 0.076246 T1003A-60-100 'F C

799' i

TRB LM100-07 0.076695 T1004A 60 100 'F C

799' TRB-LM100 08 0.000000 T1005A 0-300 'F 799' TRB LM100-09 0.090756 T1006A 60-100 'F D

850' TRB-LM100-10 0.090756 T1007A 60-100 'F D

850' TRB-LM100-11 0.090756 T1008A 60 100 'F D

850' TRB-LM100 12 0.038207 T1009A 60 100 'F F

799' TRB LM100 13 0.094846 T1010A 60-100 'F-E 797'~

TRB-LM100 14-0.000000 T1011A 0-300 'F 799' 6" TRB LM100-15 0.000000 T1012A 0-300 'F.

E 799' TRB-LM100-16 0.000000 T1013A' 0 300 *F G

701' 6" l

TRB-LM100 17 0.051746 T2457A 60-100

'F, G_

701' 6" TRB-LM100-18 0.055108 T2460A 60 100 'F G

701' 6" TRB-LM100-19 0.045490 T2467A 60-100 'F F

740' 10" TRE LM100 20 0.050794 T2477A 60-100 *F G

701' 6"-

Page 1 of 2 m

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l ATTACHMENT 3.2A (continued)

INSTRUMENTATION LIST Weight Computer Instrument Factor Address Range Z2ng Elevation B. Devooint 1

MA-LM100-01 0.125690 T0457A 15-85 'F J

825' MA LM100 02 '

O.125690 T0635A 15-85

'F' J

825' MA-LM100-03 0.249540 T0655A 15-85 'F K

701' MA LM100 04 0.249540 T0661A 15-85 *F K

701' MA LM100-05 0.249540 T0675A 15 85 ' F K

701' C. Pressure Q.M. PIT-LM-102 1.000000 P1003A 0-150 IN HG A I-II 2.1409 B 0.000000 0 100 PSIA D. Suoerimoosed Leakare Verification Test Flow Instrument s

I A-1.553.2 1.000000 0-8 SCFM I A-1.553.3 0.000000 0-8 SCFM

Backup quartz manomet,er,. logged locally at same frequency as primary manometer.

Page 2 of 2

3.3 TEST RESULTS 3.3.1 Presentation of Test Results The initial ILRT was unable to meet the containment leakage rate acceptance criteria of < 0.75 La, requiring reperformance following equipment repairs.

The second ILRT satisfactorily met the containment leakage rate acceptance criteria.

During the initial ILRT two significant leakage paths were identified which caused the unacceptably high containment leakage.

A shaft seal leak was identified on Outside Recirculation Spray Pump

[RS P-2B]

prior to the completion of containment pressurization. The impact of this seal leak could not be assessed until containment conditions stabilized after pressurization.

2 1/2 hours of data cr.rdysis after stabilization indicated containment air mass was trending at approximately 45 lbm/hr which exceeded acceptable leakage rate limits (0.75 La 15.32 lbm/hr).

[RS-P-2B) was isolated from containment by closing the pump discharge and suction MOV's, so that the seal leakage could be quantified.

The containment air mass trend improved to approximately 22 lbm/hr after isolating [RS P-2B) which still exceeded acceptable leakage rate limits.

The

[dS P-2B]

casing was vented, and a rotameter connected to the casing vent to quantify MOV leakage. MOV leakage measured was approximately 37 SC FH,

or equivalent to 2.8 lbm/hr.

[RS-P-2B) discharge and suction MOV's are ASME Section XI Category B valves, and are not subject to leakage testing.

While the isolated [RS P-2B) pump was still a substantial leakage path, it was evident an additional leakage path (s) existed in the containment pressure boundary.

Leakage investigations in the Fuel Building found air bubbling through standing water from the Fuel Transfer Tube Gate Valve [FH-1) in the Fuel Building.

3.3-1 1

l

4he amount of leakage visible is was apparent this leakage path was 14( significant.

Cate valve [FH 1) was opened to vent the Fuel Transfer

Tube, and to verify continuing leakage. After (FH 1) was fully opened the containment air mass trend increased to approximately 75 lbm/hr.

The ILRT was terminated for repairs since no additional leakage paths were identified, and the containment leakage rate was unacceptable.

Following repairs to Outside Recirculation Spray Pump (RS-P 2B), and Fuel Transfer Tube a second ILRT was performed.

The test data for the second ILRT is based on an 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test period starting at 1945 hours0.0225 days 0.54 hours 0.00322 weeks 7.400725e-4 months on December 5,

1989.

The final test results were determined using SWEC's ILRT computer analysis program.

The Reduced Input Data, Mass Point Analysis Test

Results, Superimposed Leakage Verification Test Results, and representative graphs are contained in Attachments 3.3A through 3.3F.

The Mass Point Analysis Test Results for the ILRT satisfied the procedt,ral acceptance criteria.

The ILRT instrumentation was verified by the Superimposed Leakage Verification Test Method.

The Mass Point Results for the Superimposed Leakage Verification Test satisfied the procedural acceptet.ce criteria.

l 3.3-2

i 3.3.2 54.7 PSTA ILRT Results The ILRT was conducted in accordance with Beaver Valley-Power Station Unit No.

1 test procedure 1BVT-1.47.2.

The results for the ILRT and for the Supplemental Test are shown below:

3.3.2.1 ILRT Results - Hass Point Analysis 1133 (Percent / Day)

D

1. Lam, Leakage Rate Calculated

' O.029556

2. Confidence Level 0.001449

3. UCL, Lam Leakage Rate plus Confidence Level 0.031005

4. Corrections for:

(See Section 3.3.2.4)

1. Type B Penalties 0.000157 ii. Type C Penalties 0.000510 111. Water Levels 0.000000 iv. Total Corrections 0.000667

5. Total Reported ILRT Leakage Rate 0.031672 (Items 3 & 4)

Results were within the acceptable limits of < 0.75 La or < 0.075 Percent / Day t

3.3-3 ww-

,4 e

--,, - rw s

,-(-w 6<r'~

w ww-v

-+--y

+

~

3.3.2.2 Supplemental Test Results I

The Supplemental verification Test was performed using the Superimposed Leakage Verification Test Method in accordance with test procedure 1BVT 1.47.2.

The results for the Superimposed Leakage Verification Test are shown below.

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

I (Lam + Lo - 0.25La) s Lc 5 (Lam + Lo + 0.25La)

Where:

Lam - Type A calculated leakage (computer)

- 0.029556 Percent / Day Lo - Superimposed leakage rate developed from rotameter

- 0.100043 Percent / Day Lc - Composite leakage (computer)

- 0.107675

a. Mass Point (0.029556 + 0.100043 - 0.025) s 0.107675 s (0.029556 + 0.100043 + 0.025)

(0.104599) s 0.107675 s (0.154599)

The Superimposed Leakage Verification Test was within the allowable limits.

3.3-4 i

l

3.3,2.3 Leakage Penalties Added to ILRT Leakage Penetration leakaEe to be added since these 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. Tvoe B Penalties Descriotion Leakare (SCP/D)

Electrical Canisters 10.30 Penetrations Total Type B Leakage - 10.30 SCF/D Total Type B Leakage - 0.000157 Percent / Day

11. Tyne C Penalties Descriotion Leakare (SCF/D)

Pent #1 Component Cooling Water System 0.47 Pent #2 Component Cooling Water System 0.47 Pent #4 Component Cooling Water System 1.18 Pent #5 Component Cooling Water System 0.47 Pent #8 Component Cooling Water System 0.47 Pent #9 Component Cooling Water System 4.69 Pent #11 Chilled Water System 0.49 Pent #13 Fire Protection System 0.47 Pent #14 Chilled Water System 0.47 Pent #16 Component Cooling Water System 0.47 Pent #17 Component Cooling Water System 1.88 Pent #18 Component Cooling Water System 2.59 Pent #24 RHR System to RWST 0.47 Pent #25 Component Cooling Water System 2.08 Pent #26 Component Cooling Water System 3.84 Pent #27 Component Cooling Water System 9.61 Pent #28 RCS Letdown 0.47 3.3-5 I

l

11. Tvoe C Penalties (continued)-

Pont #31 Fire Protection System 0.47 Pent #32 Fire Protection System 0.47 Pent e55 2.

Leakage Monitoring System 0.47 Pent #58 Component Cooling System 0.47 Pent e97 Reactor Plant Sample System 0.47 Pent #110 1 Pressurizer Dead Weight Tester 0.47 Total Type _C Leakage - 33.41 SCF/D Total Type C Leakage - 0.000510 Percent / Day 111. Water Level Corrections Descriotion-Leakare (SCF/D)

-Rx-Vessel-0.0 Cnet Sump 0.0 Total Water Level Corrections - 0.0 SCF/D Total Water Level Corrections - 0.0 Percent / Day i

-l l

l i

3.3-6

3.3.2.4 As Found Containment Condition LLRT Improvements In order to account for the affect of Local Leakage Rate Test (LLRT) repairs (made prior to the ILRT) on the "as found" condition of containment, an analysis of LLRT results was performed.

The "as found" minimum pathway leakage rate is reviewed against the "as left" minimum pathway leakage rate for each LLRT penetration.

If the a

penetration minimum pathway leakage rate is reduced because of repairs, maintenance, design changes, etc.,

then the leakage rate improvement is noted.

The total of all these leakage rate improvements is the adjustment to the "as found" containment condition.

The minimum pathway leakage rate for the following LLRT penetrations was reduced as a result of repairs:

AS FOUND MINIMUM AS LEFT MINIMUM LEAKAGE PATHWAY LEAKAGE PATHWAY LEAKAGE DIFFERENCE PENT NO.

(SCF/D)

(SCP/D)

(SCF/D) 4 2.44 1.18 1.26 l

25 5.16 2.08 3.08 38 51.70 0.47 51.23 56 2 0.48 0.47 0.01 64 35.91 0.47 35.44 90 16.15 14.60 3.55 94 25.78 16.89 8.S9 10 A 0.46 0.10 0.36 11-A 0.32 0.10 0.21 15-B 0.20 0.10 0.10 Total Minimum Pathway Leakage Rate Improvement - 104.13 SCF/D Total Minimum Pathway Leakage Rate Improvement - 0.001589 Percent / Day 3.3 7 l

4 l

4

I Adding this "as found8. containment adjustment to the reported IIRT results yields the following results:

11RB (Percent /Davi-

l. Total Reported ILRT Leakage Rate 0.031672 (See Section 3.3.2.1)

2. As Found Containment Adjustment -

0.001589

3. Total Containment Leakage Rate 0.033261 4

y l

3.3 8 j

I

3.3.3 Conclusion The Fuel Transfer Tube leakage path was caused by improper gasket compression of the blind flange af ter the completion of refueling.

The design of the Fuel Transfer Tube Blind Flange incorporates two concentric flexicallic gaskets to form the seal on the Fuel Transfer Tube.

These gaskets are held in place during installation by flange compression, and grooves machined into the blind flange.

The area between the gaskets is machined slightly below the flange surface to provide a means of leak testing (Type B) by pressurizing between the gaskets after installation.

It is speculated that while lowering the blind flange into position that of the flexitallic gaskets was struck by the Fuel Transfer Tube mating one flange and dislodged from its recessed groove.

Compression of the other flexicallic gasket was not achieved due to the dislodged gasket interference.

The Type B test port which pressurizes the annulus area between the gaskets was blocked by the dislodged gasket.

This blockage prohibited the test from identifying the improper gasket position, and provided satisfactory test resulto.

The Fuel Transfer Tube Blind Flange is located in a confined area. Access around the blind flange is very limited due to the proximity of the refueling cavity liner fuel transfer cart drive mechanism, and cart rails.

These tight quarters make visual inspection of the entire flange very difficult, if not impossible. Additionally, radiological conditions in this area require extensive personnel protective equipment, and limit stay time.

A redesign of the Fuel Transfer Tube Blind Flange will be considered to reduce the probability of dislodging the flexitallic gaskets (s).

Possibly a temporary installation clip, or a blind flange modification may be incorporated.

Additional consideration will be given to the installation of a pressure port in the blind flange, offset from the existing test port.

l l

3.3 9

y

+

l During.~ the Type B of the blind flange, a temporary pressure gauge:wouldebe Linstalled at the offset pressure port. This gauge.would provide positive indication that the annulus area-between the gaskets is pressurized.-

~

-The BVPS No.

1-containment isj designed to normally, operate at-a

~

subatmospheric pressure of approximately 9.5' PSIA.

Due_to.the magnitude of -the Fuel Transfer Tube. leakage path, and'the subatmospheric~ containment

design, it is_h'ighly improbable that the. improperly installed blind flange would.

not have: been detected.--

Air inlealdt.ge would increase' the containment pressure indicating a leakage path in the containment prosaure boundary.

The Outside. Recirculation Spray Pump-[RS.p.2B) leakage path was. caused by inadequate seal face preload on-the outer pump seal, and a leaking shaft sleeve

o. ring.

The pump is designed with a tandem mechanical seal arrangement as shown. on Attachment 3.30.

The tandem mechanical seal arrangement provides a positive seal against_ pump icakage, with adequate-lubrication-and cooling for' the seals.

Seal water accumulator level alarms provide control room -annunciation that adequate seal water is available, and indicate failure of either seal.

The seal arrangement consists of.two-mechanical face seals.(#2 6 #7),_

arranged to enclose domineralized seal water.

When the pump is operating,'.

the pressure. between the seals, is maintained; higher than the_ pressure outside either seal by-the seal water accumulator (#5) with a weight loaded diaphragm.

The seal water-accumulator is equipped with high and low level alarms (#9),

which annunciate.in the control room.- The seal l

water is cooled by being pumped by the-pumping ring-(#6) through the air-cooler (#4).

During pump' performance testing a slight seal leak was identified'at the- -

outer pump seal.

The rotating seal face bellows for the outer'se'al had taken a set, which caused-the seal faces to be slightly misaligned, j

1

~!

3.3-10

~!

z

t I

The inner' and outer mechanical pump seals were cicaned,-and rebuilt with-the' existing-parts prior-to _ the first ILRT.

Seal water' accumulator level was lost during containment pressurization for the - first ILRT. Air leakage from the [RS-P 28).outside pump-seal was identified shortly after the seal water accumulator level went' low.

-[RS P 2B) was isolated from containment. in an attempt ;to. reduce.

containment leakage to an acceptable rate.

-After pump isolation the resulting change-in Leontainment air mass-loss was significantly reduced, If [RS-P 28) was the only major. leakage path in the containment _ pressure

boundary, it is very probable that.the ILRT Icakage rate would have been-within acceptable limits _with [RS P 2B) isolated.-

After containment depressurization -from the first ILRT, both inner.and outer mechanical seals were replaced.

The outer -seal preload.was determined to =have been inadequate to maintain proper seal' face contact.

The preload was inadvertently altered when a stripped preload adjustment set screw was replaced during reassembly prior to the first ILRT, Also the shaft sleeve o ring was replaced.

While refilling the seal' water accumulator using a standpipe, accumulator' level was lost, with no-corresponding loss of-standpipe level.

A ruptured diaphragm was suspected, and confirmed by accumulator disassembly.

After completion of all

[RS P 2B) maintenance, the pump casing was pressurized to 42 PSIC with.

no external leakage detected, or lost of seal water accumulator-level.

Most probably the seal water accumulator diaphragm ruptured after water level was lost due the higher than normal differential-pressure across the diaphragm.

The leakage path-would have ' developed when the diaphragm

ruptured, providing a path from containment through.the pump' casing, accumulator, and passed the outer seal.

An additional leakage path existed because of the leaking shaft sleeve o-ring, allowing-leakage between the shaft and shaft sleeve.

l l

4 3.3 11 l

l

The leakage of (RS P 2B) mechanical seal, shaft sleeve o ring, and the ruptured seal water accumulator diaphragm would not have gone undetected.

The seal water accumulator would have continued to give a control room low level alarm annunciation due to loss of level, or sinking of the diaphragm.

Air inleakge would have detected the defective shaft sleeve o ring, since the pump casing is exposed to containment subatmospheric conditions.

To ensure integrity of the external loop for Outside Recirculation Spray Pumps (RS-P 2A & B) a periodic surveillance test will be developed to pressurize each pump casing for leakage inspection.

This test would be performed on a refueling frequency.

t l

l l

3.3 12 i

i ATTACHMENT 3.3A INTECRATED LEAKACE RATE TEST FROM 19:45 HOURS ON 12/5/89 TO 19:45 HOURS ON 12/6/89 REDUCED INPUT VARIABLES ABS.

VAP.

ABS.

TIME PRES PRES TEMP DEWPOINT MASS (KR)

(PSIA)

(PSI)

(*R)

('F)

(LBM) 0.000 56.165 0.1965 526.484 52.678 505007.13 0.250 56.160 0.1974 526.471 52.798 504971.83 0.500 56.157 0.1964 526.434 52.660 504985.35 0.750 56.153 0.1974 526.389 52.809 504983.83 1.000 56.149 0.1958 526.364 52.586 504986.51 1.250 56.146 0.1964 526.340 52.659 504973.63 l

1.500 56.143 0.1954 526.298 52.526 504996.37 1.750 56.140 0.1952 526.266 52.504 505001.93 2.000 56.137 0.1954 526.253 52.528 504985.85 2.250 56.134 0.1965 526.240 52.677 504962.55 2.500 56.131 0.1967 526.228 52.701 504949.92 2.750 56.129 0.1957 526.202 52.572 504961.22 3.000 56.126 0.1954 526.171 52.527 504971.56 3.250 56.125 0.1955 526.168 52.535 504956.19 3.500 56.122 0.1964 526.156 52.661 504933.44 3.750 56.120 0.1950 526.144 52.469 504938.86 4.000 56.118 0.1949 526.109 52.454 504955.66 4.250 56.116 0.1947 526.090 52.424 504958.78 4.500 56.114 0.1944 526.084 52.393 504948.89 4.750 56.113 0.1950 526.067 52.474 504950.54 5.000 56.110 0.1948 526,049 52.448 504943.55 5.250 56.108 0.1931 526.035 52.208 504954.17 5.500 56.106 0.1942

.526.036 52.353 504931.21 5.750 56.104 0.1937 526.022 52.286 504925.95 6.000 56.103 0.1942 526.020 52.361 504914.61 6.250 56.102 0.1946 525.997 52.408 504925.08 Page 1 of 4

ATTACHMENT 3.3A (continued)

INTEGRATED LEAKACE RATE TEST FROM 19:45 HOURS ON 12/5/89 TO 19:45 HOURS ON 12/6/89 REDUCED INPUT VARIABLES l

ABS.

VAP.

ABS.

1 l

TIME PRES PRES TEMP DEVPOINT MASS (HR)

(PSIA)

(PSI)

('R)

('F)

(LBM) 6.500 56.100 0.1944 525.976 52.389 504932.93 l

6.750 56.099 0.1940 525.986 52.335 504913.07 7.000 56.098 0.1942 525.956 52.359 504926.99 7.250 56.097 0.1938 525.956 52.296 504922.78 7.500 56.096 0.1948 525.928 52.439 504931.26 7.750 56.094 0.1945 525.925 52.396 504923.84 l

8.000 56.093 0.1932 525.925 52.219 504922.18 8.250 56.091 0.1924 525.897 52,099 504942.94 8.500 56.091 0.1923 525.890 52.090 504945.49 8.750 56.090 0.1935 525.895 52.261 504921.07 9.000 56.089 0.1928 525.909 52.162 504909.57 9.250 56.088 0.1926 525.891 52.132 504919.91 9.500 56.088 0.1925 525.898 52.116 504909.64 9.750 56.087 0.1939 525.884 52.317 504901.70 10.000 56.086 0.1935 525.857 52.266 504921.66 10.250 56,084 0.1937 525.868 52.289 504896.36 l

10.500 56.083 0.1933 525.845 52.239 504912.82 10.750 56.083 0.1943 525.864 52.380 504881.15 11.000 56.081 0.1929 525.840 52.170 504904.72 11.250 56.080 0.1930 525.842 52.188 504892.66 11.500 56.079 0.1929 525.827 52.180 504894.10 11.750 56.078 0.1921 525.820 52.060 504899.89.

12.000 56.077 0.1921 525.806 52.057 504904.42 12.250 56.076 0.1928 525.802 52.158 504892.82 12.500 56.075 0.1923 525.797 52.090 504893.41 12.750 56.073 0.1931 525.788 52.206 504880.85 Page 2 of 4

ATTACHMENT 3.3A (continued)

INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/5/89 TO 19:45 HOURS ON 12/6/89 REDUCED INPUT VARIABLES l

ABS.

VAP.

ABS.

TIME PRES PRES TEMP DEWPOINT MASS (HR)

(PSIA)

(PSI)

(*R)

('F)

(LBM) 13.000 56.073 0.1910 525.771 51.903 504912.41 13.250 56.072 0.1914 525.770 51.968 504900.46 13.500 56.071 0.1916 525.767 51.988 5C4892.62 13.750

!6.070 0.1916 525.748 51.987 504907.23 l

14.000 56.070 0.1931 525.754 52.206 504878.66 14.250 56.069 0.1914 525.742 51.970 504896.01 14.500 56.068 0.1920 525.730 52.054 504893.32 14.750 56.067 0.1925 525.728 52.118 504882.35 3

15.000 56.066 0.1925 525.737 52.115 504864.63 15.250 56.065 0.1917 525.723 52.007 504880,56 15.500 56.064 0.1919 525.718 52.032 504875.54 15.750 56.063 0.1925 525.701 52.117 504873.12 16.000 56.062 0.1915 525.692 51.976 504886.07 16.250 56.062 0.1928 525.692 52.156 504869.66 16.500 56.061 0.1923 525.682 52.087 504874.81 16,750 56.060 0.1920 525.690 52.055 504860.56 17.000 56.059 0.1922 525.679 52.083 504864.97 17.250 56.059 0.1919 525.686 52.042 504856.39 17.500 56.058 0.1918 525.661 52.024 504872.35 17.750 56.057 0.1910 525.663 51.911 504873.80 18.000 56.057 0.1923 525.659 52.098 504860.72 18.250 56.056 0.1920 525.660 52.047 504854.11 18.500 56.055 0.1908 525.644 51.877 504876.53 18.750 56.055 0.1910 525.647 51.907 504867.34 19.000 56.054 0.1906 525.633 51.848 504875.60 19.250 56.053 0.1914 525.637 51.965 504840.34 Page 3 of 4

ATTACHMENT 3.3A (continued)

INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/5/89 TO 19:45 HOURS ON 12/6/89 REDUCED INPUT VARIABLES ABS.

VAP.

ABS.

TIME PRES PRES TEMP DEWPOINT MASS (RR)

(PSIA)

(PSI)

(*R)

(*F)

(LBM) 19.500 56.053 0.1918 525.634 52.028 504854.25 19,750 56.052 0.1904 525.620 51.828 504871.36 20.000 56,051 0.1911 525.623 51.921 504857.92 20.250 56.051 0.1900 525.631-51.764 504855.75 20.500 56.050 0.1910 525.617 51.910 504851.04 20.750 56.049 0.1913 525.604 51.947 504856.72 21.000 56.049 0.1920 525.596 52.048 504853.43 21.250 56.048 0.1925 525.600 52.118 504840.63 21.500 56.048 0.1920 525.592 52.048 504848.76 22.750 56.047 0.1906 525.606 51.852 504843.15 22.000 56.046 0.1909 525.603 51.897 504834.01 22.250 56.046 0.1922 525.584 52.083 504840.61 22.500 56.046 0.1915 525.597 51.978 504834.70 22.750 56.046 0.1926 525.598 52.130 504819.97 23.000 56.045 0.1907 525.570 51.865 504854.74 23.250 56.045 0.1912 525.576 51.934 504844.93 23.500 56.044 0.1905 525.570 51.837 50481-7.25 23.750 56.044 0.1909 525.558 51.891 504855.43-24.000 56.043 0.1923 525.567 52.095 504825.07 Page 4 of 4

ATTACHMENT 3.3B INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/05/89 TO 19:45 HOURS ON 12/06/89 ABSOLUTE TEST METHOD, MASS POINT ANALYSIS TEST RESULTS L

TIME MASS LEAKAGE CONFIDENCE UCL (HR)

(LBM)

(PCT / DAY)

(PCT / DAY) 0.000 505007.13 0.000000 0.000000 0.000000 0.250 504971.83 0.000000 0.000000 0.000000 0.500 504985.35 0.206992 2.292464 2.499456 0.750 504983.83 0.107199 0.391202 0.498401 1.000 504986.51 0.055601 0.193882 0.249483 1.250 504973.63 0.067888 0.115909 0.183797 1.500 504996.37 0.018689 0.096320 0.115009 1.750 505001.93 0.012178 0.077412 0.065233 2.000 504985.85 0.005392 0.058933 0.053541 2.250 504962.55 0.022522 0.055021 0.077543 2.500 504949.92 0.047631 0.051647 0.099278 2.750 504961.22 0.052028 0.042737 0.094766 3.000 504971.56 0.046490 0.036247 0.082737 3.250 504956.19 0.050028 0.031019 0.081047 3.500 504933.44 0.061889 0.029318 0.091207 3.750 504938.86 0.066186 0.025870 0.092056 4.000 504955.68 0.061570 0.023184 0.084754 4.250 504958.78 0.056216 0.021213 0.077429 4.500 504948.89 0.054464 0.018987 0.073451 4.750 504950.54 0.051961 0.017213 0.069173 5.000 504943.55 0.051158 0.015546 0.066704 5.250 504954.17 0.047555 0.014543 0.062097 5.500 504931.21 0.049041 0.013327 0.062369 5.750 504925.95 0.050696 0.012299 0.062995 6.000 504914.61 0.053506 0.011629 0.065135 6.250 504925.08 0.053556 0.010715 0.064270 6.500 504932.93 0.051986 0.010024 0,062010 Page 1 of 4

ATTACHMENT 3.35 (continued)

INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/05/89 TO 19:45 HOURS ON 12/06/89 ABSOLUTE TEST METHOD. MASS POINT ANALYSIS TEST RESULTS TIME MASS LEAKAGE CONFIDENCE UCL (HR)

(LBM)

(PCT / DAY)

(PCT / DAY) 6.750 504913.07 0.053136 0.009362 0.062498 7.000 504926.99 0.051872 0.008792 0.060664 7.250 504922.78 0.051026 0.008237 0.059263 7.500 504931.26 0.049050 0.007936 0.056986 7.750 504923.84 0.047945 0.007510 0.055455 8.000 504922.18 0.046942 0.007115 0.054057 8.250 504942.94 0.043878 0.007330 0.051209 8.500 504945.49 0.040871 0.007504 0.048375 8.750 504921.07 0.040246 0.007107 0.047353 9.000 504909.57 0.040477 0.006721 0.047198 9.250 504919.91 0.039714 0.006406 0.046120 9.500 504909.64 0.039661 0.006073 0.045733 9.750 504901.70 0.040022 0.005776 0.045798 10.000 504921.66 0.038871 0.005603 0.044475 10.250 504896.36 0.039347 0.005353 0.044700 l

10.500 504912.82 0.038642 0.005147 0.043788 10.750 504881.15 0.039735 0.005024 0.044759 11.000 504904.72 0.039276 0.004818 0.044094 l

11.250 504892.66 0.039401 0.004608 0.044009 11.500 504894.10 0.039333 0.004410 0.043743 l

11.750 504899.89 0.038892 0.004246 0.043138 12.000 504904.42 0.038197 0.004126 0.042323 l

12.250 504892.82 0.038011 0.003964 0.041975 l

12.500 504893.41 0.037735 0.003816 0.041551 i

12.750 504880.85 0.037927 0.003672 0.041599 13.000 504912.41 0.036761 0.003708 0.040469 Page 2 of 4 l

l

ATTACHMENT 3.38 (continued)

INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/05/89 TO 19:45 HOURS ON 12/06/89 ABSOLUTE TEST METHOD MASS POINT ANALYSIS TEST RESULTS TIME MASS LEAKAGE CONFIDENCE UCL (HR)

(LBM)

(PCT / DAY)

(PCT / DAY) 13.250 504900.46 0.036104 0.003626 0.039729 13.500 504892.62 0.035736 0.003511 0.039247 13.750 504907.23 0.034818 0.003499 0.038316 14.000 504878.66 0.034915 0.003376 0.038290 14.250 504896.01 0.034362 0.003302 0.037664 14.500 504893.32 0.033893 0.003221 0.037114 14.750 504882.35 0.033755 0.003116 0.036871 15.000 504864.63 0.034112 0.003032 0.037144 15.250 504880.56 0.033917 0.002939 0.036856 15.500 504875.54 0.033832 0.002847 0.036678 15.750 504873.12 0.033772 0.002758 0.036529 16.000 504886.07 0.033326 0.002706 0.036032 16.250 504869.66 0.033297 0.002624 0.035921 16.500 504874.81 0.033098 0.002552 0.035650 16.750 504860.56 0.033220 0.002479 0.035699 17.000 504864.97 0.033187 0.002407 0.035594 17.250 504856.39 0.033313 0.002341 0.035654 17.500 504872.35 0.033033 0.002290 0.035324 17.750 504873.80 0.032707 0.002248 0.034956 18.000 504860.72 0.032647 0.002187 0.034834 18.250 504854.11 0.032693 0.002128 0.034821 18.500 504876.53 0.032251 0.002114 0.034365 18.750 504867.34 0.031990 0.002073 0.'54063 19.000 504875.60 0.031559 0.002061 0.033621 19.250 504840.34 0.031783 0.002019 0.033803 19.500 504854.25 0.031709 0.001969 0.033679 19.750 504871.36 0.031310 0.001958 0.033268 Page 3 of 4 E

ATTACHMENT 3.3B (cantinued)

INTEGRATED LEAKAGE RATE TEST FROM 19:45 HOURS ON 12/05/89 TO 19:45 HOURS ON 12/06/89 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS TEST RESULTS TIME MASS LEAKAGE CONFIDENCE UCL (HR)

(LBM)

(PCT / DAY)

(PCT / DAY) 20.000 504857.92 0.031142 0.001916 0.033058 20.250 504855.75 0.030996 0.001874 0.032870 20.500 504851.04 0.030910 0.001831 0.032740 20.750 504856.72 0.030713 0.001797 0.032510 21.000 504853.43 0.030556 0.001761 0.032317 21.250 504840.63 0.030580 0.001720 0.032300 21.500 504848.76 0.030458 0.001684 0.032142 21.750 504843.15 0.030402 0.001646 0.032048 22.000 504834.01 0.030457 0.001610 0.032067 22.250 504840.61 0.030394 0.001575 0.031969 22.500 504834.70 0.030394 0.001540 0.031935 22.750 504819.97 0.030569 0.001516 0.032085 23.000 504854.74 0.030259 0.001513 0.031772 23.250 504844.93 0.030073 0.001491 0.031564 23.500 504847.25 0.029849 0.001475 0.031325 23.750 504855.43 0.029520 0.001479 0.030999 24.000 504825.07 0.029556 0.001448 0.031005 i

l l

Page 4 of 4 i

l l

fl BEAVER VALLEY POWER STATION UNIT NO. '1 INTEGRATED LEAKAGE RATE TEST ATTACHMENT 3.3C - CNMT AIR MASS vs TIME MASS (LBM)

'505,000 504,980 an=2 c==

504,960 504.940 504.920 504.900 h

504,880 504.860 504.840 504.820 504.800

'"'""'""'"'"'"'"'"'"'"'"i...'"'i...'......

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ATTACKMENT'3.3E SUPERIMPOSED LEAKAGE VERIFICATION TEST FROM 20:45 HOURS ON 12/6/89 TO 00:45 HOURS ON 12/7/89 REDUCED INPUT VARIABLES

ABS, VAP.

ABS.

TIME PRES PRES TEMP DEWPOINT MASS-(HR)

(PSIA)

(PSI)

('R)

(*F)

(LBM) 0.000 56.040 0.1912 525.562 51.936 504813'.91 0.250 56.039 0.1898 525.549 51.743 504829.46 0.500 56.039 0.1914 525.549 51.970 504810.22 0.750 56.038 0.1914 525.546 51.970 504804.55 1.000 56.037 0.1900 525.536 51.766 504818.16 1.250 56.036 0.1914 525.548

'51.958 504785.85 1.500 56.034 0.1907-525.540 51.859 504786,29 1.750 56.034 0.1917 525.532 52.003 504785.14 2.000 56.033 0.1907 525.527 51.860 504790.29 2.250 56.032 0.1901 525.513 51.776 504794.83 2.500 56.030 0.1890 525.529 51.618 504776.19 2.750 56.030 0.1907 525.530 51.861 504760.67-3.000 56.029 0.1915 525.522 51.986

-504751.01' 3.250 56.029 0.1903 525.500 51.803 504779.74 3.500 56.028 0.1911 525.518 51,916 504746.51 3.750 56.027 0.1909 525.508 51.889 504752.53 4.000 56.023 0.1927 525.504 52.151 504700.-07 l

I-l l

Page 1 of 1

ATTACHMENT 3.3F SUPERIMPOSED LEAXAGE VERIFICATION TEST FROM 20:45 HOURS ON 12/6/89 TO 00:45 HOURS ON 12/7/89 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS TEST RESULTS TIME MASS LEAKACE CONFIDENCE UCL (HR)

(LBM)

(PCT / DAY)

(PCT / DAY) 0.000 504813.91 0.000000 0.000000 0.000000 0.250 504829.46 0.000000 0.000000 0.000000 0.500 504810.22 0.035063 1.633559 1.668622 0.750 504804.55 0.090010 0.268006 0.358016 1.000 504818,16 0.031212 0.147385 0.178597 1.250 504785.85 0.097730 0.119725 0.217455 1.500 504786.29 0.110115 0.081306 0.191421 1.750 504785.14 0.107924 0.058493 0.166418 2.000 504790.29 0.093179-0.047029 0.140208 2.250 504794.83 0.075886 0.041239 0.117125 2.500 504776.19 0.079114 0.033368 0.112482 2.750 504760.67 0.089286 0.029443 0.118729 3.000 504751,01 0.098544 0.026459 0.125002 3.250 504779.74 0.085936 0.025960 0.111897 3.500 504746.51 0.091392 0.023025 0.114417 3.750 504752.53 0.090501 0.020046 0.110547 4.000 504700.07 0.107675 0.024734 0.132410 Page 1 of 1

l ATTACHMENT 3.3G i

l

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WPING RIN 7 INNER SE AL AS$tW.LY

. CONNECTION TO PROCEls Slot PRESSURE 9 LEYEL INDICATOR AL ARM TO WAIN CONTROL #00W

.I TANDEM MECHANICAL SE AL ARR ANGEM ENT FOR RECIRCUL ATION PUMPS

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SECTION 4 LOCAL LEAKACE RATE TESTS (TYPES B AND C)

Local Leak Rate Testing (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 #1 Technical Specifications.

These LLRT's are performed by pressurizing the required penetrations with air or nitrogen and either measuring leakage across 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 La, at a minimum test pressure of Pa.

Additionally LLRT's (Total Volume Type B) are performed for each containment airlock at 6 month intervals in accordance with 10 CFR 50 Appendix J, and Beaver Valley Power Station #1 Technical Specifications.

This attachments for this section are:

l Attnehment No.

Title 4.1A Sixth Refueling (12/87 - 2/88) LLRT Data 4.1B Sixth Refueling (9/89 12/89) LLRT Repairs d

4.1C Seventh Refueling (9/89 - 12/89) LLRT Data 4.1D Seventh Refueling (9/89 - 12/89) LLRT Repairs 4.1E Sixth and Seventh Fuel Cycle LLRT Data 41 m

ATTACHMENT 4.1A (ctntinued)

SIXTH 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 LEAVACE LEAKAGE LEAYAGE IN OUT (SCF/D)

(SCP/D)

MOV CC 112A2 X

01 23 88 0.46 0.47 1

0.56 CCR 247 X

01 11 88 0.56 0.56 MOV CC 112B3 X

01 26 88 0.56 0.47 2

0.56 CCR 252 X

01 08 88 561.3 0.56 MOV CC 112A3 X

01 25 88 3.10

8. $7 4

179.8 CCR 251 X

01 11 88 179.8 179.8 MOV CC 112B2 X

01-26 88 0.46 9.33 5

9.33 CCR 248 X

01 06-88 7,87 7,87 TV CC 107D1 X

0.46 0.46 8

12-23 87 0.56 TV CC 107D2 X

0.56 0.56 TV-CC 111D1 X

8.75 8.75 9

12-16 87 8.75 TV CC 111D2 X

3.46 3.46 TV CC 110D X

0.46 0.46 11 TV CC-110F1 X

01 11 88 0.49 0.49 0.49 TV-CC-110F2 X

FP 827 X

01 07-88 0.46 0.46 13 0.47 TV-FP-107 X

01 23 88 230.4 0.47 TV CC-110E3 X

0.46 0.46 14 01-08 88 0.46 TV-CC-110E2 X

0.46 0.46 TV-CC 111A2 X

45.32 45.32 16 01-07-88 45.32 TV CC-111A1 X

1.40 1.40 TV-CC 103B1 X

0.74 0.74 17 01-11 88 11.18 TV CC 103B X

11.18 11.18 TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 257.48 Page 1 of 10

ATTACHMENT 4.1A (continu3d)

SIXTH 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 LEAKACE LEAYACE LEAYAGE IN OUT (SCP/D)

(SCF/D)

(SCP/D)

TV CC 103C1 X

7.46 7.46 18 01 20 88 62.21 TV-CC-103C X

62.21 62.21 MOV CH 378 X

24.09 24.09 19 CH-369

-X 12-22 87 24.09 MOV CH 381 X

0.46 0.46 SI 42 X

0.61 0.61 20 02 02 88 0. 6,'.

SI 41 X

0.46 0.46 l

RH

^.4 X

0.85 0.85 1

24 RH 16 X

01 14 88 0.75 0.75 1.60 RH 15 X

0.75 0.75 TV CC 105D1 X

11.95 11.95 25 12-16 87 11,95

)

TV-CC 105D2 X

6.69 6.69

{

i TV-CC-107El X

69.57 69.57 26 12-24 87 69.57-TV CC 107E2 X

0.56' O.56 TV CC 105El X

01-21-88 193.5 31.69 27 31.69 TV CC 105E2 X

01-11 88 15.66 15.66

'l TV CH-200A X

TV CH 200B X

0.75 0.75 l

I TV-CH-2000 X

28 01 05-88 RV CH 203 X

2.38 2.38 54.43 i

MOV CH 142 X

51.30 51.30 i

TV-CH 204 X

1.91 1.91 TOTAL PENETRATION LEAKAGE SHEET 2 (SCP/D) 256.15 i

Page 2 of 10

ATTACHMENT 4.1A (ccntinued)

SIXTH 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 LEAKACE LEAKAGE LEAYACE IN OUT (SCF/D)

(SCF/D)

TV-DG 108A X

11.67 11.67 29 01-16 88 11.67 TV DG 108B X

9.80 9.80 FP 804 X

0.46 0.46 31 12 21 87 4.39 TV FP 105 X

4.39 4.39 FP 800 X

12 19 87 0.46 0.46 32 19.91 TV FP 106 X

12-21 87 19,91 19,91 TV DA-100A X

168.9 83.88 38 01 23-88 83.88 TV DA 100B X

304.9 24.23 SA 15 X

1.87 1.87 42 12-16 87 1.87 SA 14 X

1.12 1.12 TV CV 102 1 X

02-01-88 238.1 6.03 43 6.03 TV CV 102 X

12-15-87 0,46 0.46 TV CV 101A X

69.63 6.94 44 12-17-87 6.94 TV CV-101B X

64.99 3.89 RC-72 X

10.64 10.64 45 12-18-87 10.64 TV-RC-519 X

1.25 1.25 IA-91 X

28.41 28.41 47 12-15 87 28.41 IA-90 X

11.90 11.90 TV DG 109A2 X

0.46 0.46 48 12-22-87 2.78 TV DG-109Al X

2.78 2.78

.RC 68 X

41.01 41.01 49 12 18-87 41.01 TV RC-101 X

3.59 3.59 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 217.53 Page 3 of 10

t ATTACHMENT 4.1A (continuid)

SIXTH REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED I

PENT VALVF DATE VALVE VALVE PENETRATION NO.

MARK NO.

TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D)

(SCF/D)

TV SI 101 2 X

11.37 11.37 53 01 18 88 11.37 TV SI 101 1 X

6.64 6.64 TV SS 109Al X

0.46 0.46 55 1 12-22 87 0.46 TV SS 109A2 X

0.46 0.46 TV 15 100A1 X

0.46 0.46 55 2 12 14 87 0.46 NOTE 1 TV LM 100A2 X

0.46 0.46 TV SS 111A1 X

0.46 0.46 55 4 12 22 87 0.46 TV-SS-111A2 X

0.46 0.46 TV SS-100A1 X

0.46 0.46 56 1 12-22 87 0.46 TV-SS 100A2 X

0.46 0.46 TV SS-102A1 X

0.47 0.47 56 2 01 27-88 0.47 TV SS-102A2 X

0.47 0.47 TV-SS 105A1 X

0.47 0.47 56 3 01 27 88 0.47 TV-SS 105A2 X

0.47 0.47 TV 1& l01A X

9.72 9.72 57-3 12 18-87 9.72 CV 35 X

9.72 9.72 TV LM 101B X

4.07 4.07 57-4 12 18 87 4.07 CV 36 X

3.94 3.94 TV-CC-103Al X

0.75 0.75 58 01 15-88 2.17 TV CC 103A X

2.17 2.17 QS 4 X

0.75 0.75 63 01 13 88 0.75 MOV-QS-101B X

0.75 0.75 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 30.86 NOTE 1 INCLUDES PENETRATIONS 57-1,57 2, AND 97-3 WHICH ALSO SHARE THESE CNMT IS01ATION VALVES THROUGH A COMMON 4-VAY VALVE.

Page 4 of 10

ATTACHMENT 4.1A (ctntinu;d)

SIXTH 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 LEAVACE IN OUT (SCF/D)

(SCF/D)

QS 3 X

32.59 32.59 64 01 13 88 42.49 MOV-QS 101A X

42.49 42.49 70 RS-101 X

01-21-88 18.66 18.66 18.66 71 RS 100 X

12 23-87 5.57 5.57 5.57 HY-197 X

1.55 1.55 87 01 15 88 1.92 NY 111 X

1.92 1.92 KY 196 X

17.14 8.44 88 01-15 88 8.44 HY 110 X

0.47 1.92 AS-278 X

10.16 10.16 89 12 19 87 10.16 TV SV 100A X

4.16 4.16 VS-D 5 3B X

90 02 08 88 370.7 0,46 0.46 VS D 5 3A X

VS D 5 5B X

91 VS-D 5 5A X

01 27 88 176.1 1.25 1.25 VS D 5 6 X

TV-CV-150C X

6.56 6.56 HY-102 92 01-14-88 17.81 TV VC 150D X

17.81 17.81 HY-104 TV-CV-150B X

0.75 0.75 HY-101 93 01-14 88 2.16 TV-CV 150A X

2.16 2.16 HY-103 TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 108.92 Page 5 of 10

i~

l ATTACHMENT 4.lA (centinu:d)

SIXTH 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 (SCP/D)

(SCP/D)

(SCF/D)'

HCV CV 151 X

13.89 1.58 94 01 04-88 1,58 HCV VC 151 1 X

0.46 0,46 SOV HY 102B1 X

0.46 0.46 95 64 12 19 87 0.46 SOV NY 102B2 X

0.46 0.46 i

SOV HY-103B1 X

0.46 0.46 95 69 12 19 87 0.46 SOV HY-103B2 X

0.46 0.46 SOV HY 104B1 X

0.46 0.46 95-72 12-19 87 0.46 SOV-HY-104B2 X

0.46 0.46 TV SS 104A1 X

0.75 0,75 97 1 01-15 88 0.75 TV-SS 104A2 X

0,75 0.75 TV SS 103Al X

0.75 0.75 97-2 01 15 88 0.75 TV SS-103A2 X

0.75 0.75 PC 38 X

18.52 18.52 103 12-17 87 18.52 PC 37 X

10.18 10,18 PC 9 X

0.46 0.46 104 12-17-87 0.46 PC-10 X

0.46 0.46 TV-SS 112A1 X

13,90 0.75 105 2 01 15-88 4.69 TV-SS-112A2 X

4.64 4,69 MOV-SI-842 X

0,46 0.46 106 12 19 87 0.46 TV-SI 889 X

0,46 0.46 S0V-KY-102A1 X

0.46 0.46 109-44 12-19-87 0.46 SOV HY 102A2 X

0.46 0.46 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 29,05 Page 6 of 10

ATTACHMENT 4.1A (continued)

SIXTH 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 (SCF/D)

(SCP/D)

(SCF/D)

SOV HY 103Al X

0.46 0.46 109 49 12 19 87 0.46 SOV HY-103A2 X

0.46 0.46 SOV HY 104A1 X

0.46 0.46 109 52 12 19 87 0.46 SOV HY 104A2 X

0.46 0.46 RC 277 X

0.46 0.46 110 1 01 15 88 0.46 RC 278 X

0.46 0.46 VS-169 X

0.75 0.75 VS-170 X

0.75 0.75 P. A. L.

01 15 88 (NOTE 2)

VS-167 X

0.75 0.75 VS 168 X

0.75 0.75 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 1.38 NOTE 2 - THE ASSIGNED PENETRATION LEAKAGE FOR THESE VALVES IS ADDED WITH THE PERSONNEL AIRLOCK OVERALL TYPE B LEAKAGE, AND NOT INCLUDED IN THE TYPE C

TOTAL, P.A,L. - PERSONNEL AIRLOCK TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 257.48 TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/D) 256.15 TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 217.53 i

TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 30.86-TOTAL PENETRATION LEAKAGE SHEET 5 (SCF/D) 108.92 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 29.05 TOTAL PENETRATION LEAKAGE SHEET 7 (SCP/D) 1.38 TOTAL CONTAINMENT TYPE C LEAKAGE - SUM OF SHEETS 1 THRU 7 (SCF/D) 901.37 Page 7 of 10

ATTACRMENT 4.1A (c ntinusd)

CIXTH REFUELING LOCAL LEAKAGE RATE TEST DATA i

TYPE B TESTS PENT LEAKAGE PENT LEAYAGE NO 0 RING SEAL / CANISTER NO O RING SEAL / CANISTER (SCCM)

(SCCM) 1B 2.0

/

2.0 7E 2.0

/

2.0 1-D 2.0

/

2.0 7F 2,0

/

2.0 1.F 2.0/2.0 * /

N/A 7G N/A ** /

2.0 2B 2.0

/

2.0 8A 2.0

/

2.0 2-D 2.0

/

2.0 8B 2.0

/

2.0 2F 2.0

/

2.0 8C 2.0

/

2.0 1

3A

.2.0'

/

2.0 8D 2.0

/

2.0 3-B 2.0

/

2.0 8-E 2,0

/

2.0 3C 2.0

/

2.0 8F 2.0/2.0 * /

N/A 3D 2.0

/

2.0 8-G-2.0

/

2.0 3E 2.0

/

2.0 9A 2.0

/

2.0 3F 2.0

/

2.0 9B 2.0

/

2.0 3G 2.0/2.0 * /

N/A 9C 2.0

/

2.0 4A 2.0

/

2.0 9-D 2.0-

/

2.0 4-B 2.0

/

2.0 9E 2.0

/

2.0 i

4C 2.0

/

2.0

.9 F.

2.0

/

2.0 j

4D 2.0

/

2.0 90 2.0

/

2.0 4E 2.0

/

2.0 10 A 2.0.

/

2.0 4F 2.0

/

2.0 10 B 2.0

/

6.0 4-G 2.0

/

2.0 10 0 2.0

/

2.0 5-A 2.0

/

2.0 10 D 2.0

/

2.0 5B 2.0

/

2.0 10 E 2.0-

/

'2.0 5C 2.0

/

2.0 10 F 2.0

/

2.0 5D 2.0

/

2.0 10 G 2.0

/

5.8 5E 2.0

/

2.0 11 A 2.0-

'/

4.2 5F 2.0

/

2.0 11-B

'2.0

/

2.0 5G 2.0

/

2.0 11 C 2.0/2.0 * /

N/A 6A 2.0

/

2.0 11 D 2.0

/

2.0 6B 2.0/2.0 * /

N/A 11-E 2.0

/

9.3 6C 2.0

/

2.0 11-F 2.0

./

2.0 l

6D 2.0

/

2.0 11-G 2.0

/

2.0 6E 2.0

/

2.0 12 A 2.0

/

2.0 6F 2.0

/

2.0 12 B 2.0

/

2.0 6G 2.0

/

2.0 12-C 2,0

/

2.0 7A 2.0/3.2 * /

N/A 12 D 2.0

/

2.0 7-B 2.0

/

2.0 12-E 2.0

/

4.2 7-C 2.0

/

2.0 12-F 2.0

/

2.0 7-D 2.0

/

2.0 12 0 2.0

/

2.0 i

i.

TOTALS 3

f 85.2 68,0 78.0 91.5 i

i SHT 1

SPARE PENETRATION INSIDE/0UTSIDE CONTAINMENT

- CONAX ELECTRICAL PENETRATION INSTALLED AT 6R, 0 RINGS j

AND FEED THROUGHS TESTED SIMULTANEOUSLY l

Page 8 of 10 l

2

.I

ATTACHMENT 4.1A (c:ntinu;d)

SIXTH REFUELING LOCAL LEAFAGE RATE TEST DATA TYPE B TESTS PENT LEAKAGE PENT LEAKAGE NO 0 RING SEAL / CANISTER NO 0 RING SEAL / CANISTER (SCCM)

(SCCM) 13 A 2.0/2.0 * /

N/A 15 E 2.0

/

2.0 13 B N/A ** /

2.0 15 F 2.0

/

2.0 13 C 2.0

/

2.0 15 G 2.0

/

2.0 13 D 2.0/2.0 * /

N/A 16 A 2.0

/

2.0 13 E 2.0

/

2.0 16 B 2.0

/

2.0 j

33 F 2.0

/

5.9 16 C 2.0

/

2.0 13 0 2.0

/

2.0 16 D 2.0

/

2.0 14 A 2.0

/

2.0 16 E 2.0

/

2.0 14 B 2.0

'/

2.0 16 F 2.0

/

2.0 14 C 2.0

/

2.0 16-G 2.0/2.0 * /

N/A 14 D 2.0

/

2.0 17 B 2,0

/

2.0 l

14 E 2.0

/

2.0 17 D 2,0/2.0 * /

N/A 14 F 2.0

/

2.0 17 F 2.0/2.0 * /

N/A 14 G 2.0

/

2.0 18 B 2.0

/

2.37 15 A 2.0

/

2.0 18-D 2.0

/

2.0 15 B 2.0

/

2.0 18 F 2.0/2.0 * /

N/A 15 C 2.0

/

2.0 FB 1 2.0

/

2.0 15 D 2.0

/

2.0 TOTALS i

38.0 35.9 42.0 26.0 SHT 2 1

SPARE PENETRATION INSIDE/0UTSIDE CONTAINMENT l

- CONAX ELECTRICAL PENETRATION INSTALLED AT 6R, 0 RINGS l

AND FEED THROUGHS TESTED SIMULTANEOUSLY LEAKAGE h

TOTALS 0 RING SEAL / CANISTER i

(SCCM) i SHT 1 163.2

/

159.5 SHT 2 80.0

/

61.9 TOTAL LEAKAGE 243.2

/

221.4

.{

(SCCM)

TOTAL LEAKAGE 12.4

/

11.2 (SCF/D) i Page 9 of 10

ATTACRMENT 4.1A (etntinu:d)

SIXTH REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE B TESTS AS FOUND AS LEFT ASSICNED PENETRATION DATE LEAKAGE LEAKAGE PENETRATION TESTED (SCF/D)-

(SCF/D)

LEAKACE Fuel Transfer Tube 2 10 88 0.46 0.46 0.46 Penetration alli 12 30 87 1.67 1.11 1.11 Penetration #112 12 30 87 0.47 0.46 0.46 Equipment Hatch Outer Flange 2 16 88 0.46 0.46 0.46~

Equipment Hatch Inner Flange 2-17-88 0.46 0.48 0.48 1

1 Personnel Airlock 1-12 88 4.98 3.46 3.46 Equipment Hatch Airlock 2 17 88 0.46 0.47 0.47 Summary of 'ivae B and C Leakane Rates As Left As Found Total Type B Leakage 30.50 SCF/D 39.22 SCF/D i

Total Type C Leakage 901.37 SCF/D 679.34 SCF/D Total Type B and C Leakage

931.87 SCF/D 718.56 SCF/D 1

Acceptance Criteria < 60% La

(< 3,893 SCF/D )

Maximum pathway leakage rate.

wa Minimum pathway leakage rate.

1Pa - 38.3 PSIG.

Page 10 of 10 1

ATTACKMENT 4.18 SIXTH RE!VELINC LOCAL LEAKACE RATE TEST REPAIRS Tyne B Repair,g The following electrical petaetrations required maintenance due to high leak rates, or physical damage:

PENT NO.

Mk'R NO.

AS FOUND LEAPAGE AS LEFT LEAPACE (SCCM)

(SCCM) 4 D Canister 875278 65.0 2.0 10 B canister 875281-37.5 7.5 10 C Canister 875282 11.2 2.0 10 0 Canister 8752bs 18.5 5.8 12 E Canister 875277 2.0 4.2 13 F Canister 875276 8.1 5.9 15 E Canister 875275 8.3 2.0 The high leak rate on the 4 D penetration was duc to a leaking canister pressure gauge.

The gauge was replaced, and the canister was satisfactorily retested.

The high leak rate on the 10 B penetration was due to a tubing leak near the canister test isolation valve.

The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The high leak rate on the 10 C penetration was due to a tubing leak near the canister test isolation valve.

The tubing was repaired with hi h shear 6

strength adhesive, and the canister was satisfactorily retested.

l Page 1 of 8 l

ATTACKMENT 4.1B (continued)

SIXTH REFUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe B Reoairs (continued)

The high leak rate on the 10 0 penetration was due to a tubing leck where its connects to the canister test isolation valve.

The connection was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The canister pressure gauge and test isolation valve assembly for 12 E penetration was accidently broken off during work in the penetration area.

The assembly was revelded onto the penetration canister, and was satisfactorily retested.

The high leak rate on the 13 F penetration was due to a tubing leak where its connects to the canister test isolation valve.

The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The high leak rate on the 13 F penetration was due to a tubing leak where its connects to the canister test isolation valve.

The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

The high leak rate on the 15 E penetration was due to a tubing leak where its connects to the canister test isolation valve.

The tubing was repaired with high shear strength adhesive, and the canister was satisfactorily retested.

Two new electrical penetrations were installed per DCP 800 during the Sixth Refueling at locations 7 C and 13 B replacing the existing blank flanges.

Both new electrical penetrations were satisfactorily tested.

Page 2 of 8

. -i I

ATTACKMENT 4.1B (c ntinu:d)

SIXTH REFUELING LOCAL LEAKACE RATE TEST REPAIRS Tyne B Reenirs (continued)

Personnel Airlock IPH P 11 Inner and outer door o rings were replaced.

Door bearings on outer door were replaces, and the door was balanced.

Work was per Maintenance Work Request 878123.

Tyne C Renairs Egngtration No. 1 The initial leak test was performed January 11, 1988.

Due to EQ Requirements, the limit switch and torque switch for valve MOV CC 112A2 were replaced per Maintenance Work Request 882052.

Following the replacement, the Type C retest was performed on January 23, 1988, with a leakage of 0.47 SCF/D.

Penetration No. 2 The initial leak test was performed January 7, 1988. Valve CCR 252 leaked at 561.3 SCF/D.

The high leakage rate was due to the valve being closed beyond its optimum seating position (butterfly valve). The valve j

was recycled and the retest performed on January 8,1988, with a leakage of 0.56 SCF/D.

The valve stop was adjusted to ensure the valve would not over travel its optimum seating position.

Due to EQ Requirements, the limit switch and torque switch for valve MOV CC 11283 were replaced per Maintenance Work Request 882055.

Following the replacement, the Type C retest was performed on January 26, 1988, with a leakage of 0.47 SCF/D.

Page 3 of 8 i

ATTACRMENT 4.1B (Otntinu;d)

SIXTH REFUELINC 1hCAL LEAYACE RATE TEST REPAIRS Tvoc C Reoairs (continued)

Penetration No. 4 The initial leak test was performed January 11, 1988.

Due to EQ Requirements, the limit switch and torque switch for valve MOV CC 112A3 were replaced per Maintenance Work Request 882053.

Following the replacement, the Type C retest was performed on January 25, 1988, with a leakage of 8.37 SCF/D.

Penetration No. $

The initial leak test was performed January 6,

1988.

Due to EQ Requirements, the limit switch and torque switch for valve MOV CC 112B2 were replaced per Maintenance Work Request 882054 Following the replacement, the Type C retest was performed on January 26, 1988, with a leakage of 9.33 SCF/D.

Penetration No. 13 The initial leak test was performed January 7,1988. Valve TV FP 107 leaked at 230.4 SCF/D.

The valve was rebuilt per Maintenance Work Request 878106 and Design Change 833.

The valve trim was replaced with a later design, soft seat trim.

The Type C-retest was performed on January 23, 1988, with a leakage of 0.47 SCP/D.

Penetration No. 27 The initial leak test was performed January 11, 1988. Valve TV CC 105El leaked at 193.5 SCF/D.

Maintenance Work Request 882502 was initiated.

The valve plug was machined to remove indications.

The valve seat was machined to remove raised metal.

The Type C retest was performed on January 21, 1988, with a leakage of 31.69 SCF/D.

Page 4 of 8

ATTACRMENT 4.1B (ctntinu;d)

SIXTH REFUELING LDCAL LEAKACE RATE TEST REPAIRS Tvoc c Repairs (continued)

Penetration No. 38 The initial leak test was performed January 15, 1988. Valve TV DA 100A leaked at 168.9 SCF/D, and valve TV.DA 100B leaked at 304.9 SCF/D.

Maintenance Work Requests 882509 for TV DA 100A, and 882510 for TV DA 1008 were initiated.

The seat ring and seat was replaced on valve TV DA 100A, and the seat lapped.

The Type C retest was performed on January 23, 1988, with a leakage of 83.88 SCF/D.

The seat and plug of valve TV DA 100B was cleaned of debris, and the valve re assembled.

The Type C retest was performed on January 23, 1988, with a leakage of 24.23 SCF/D.

Penetration No. 43 The initial leak test waa performed December 15, 1987. Valve TV CV 102 1 leaked at 238.1 SCF/D.

The valve was rotated in the system per Design Change 666 to permit leak testing the valve on top of the valve seat, rather than from under the valve seat.

The Type C retest was performed on February 1, 1988, with a leakage of 6.03 SCF/D.

Penetration No. 44 The initial leak test was performed December 14, 1987. Valve TV CV 101A leaked at 69.63 SCF/D, and valve TV CV 1018 leaked at 64.99 SCF/D.

Since no air leakage was detected at the downstream vent for either valve, i

Maintenance Work Request 879156 was initiated for the inboard penetration boundary valve CV 14.

Corrosion was removed from the seat and disc of valve CV 14.

The Type C retest was performed on December 17, 1987, with a leakage of 6.94 SCF/D for TV CV-101A, and 3.89 SCF/D for TV CV 101B.

1 I

I Page 5 of 8

l ATTACHMENT 4.1B (c:ntinu;d)

SIXTH RF. FUELING LOCAL LEAYACE RATE TEST REPAIRS I

Tvoc C Repairs (continued)

)

Penetration No. 63 l

The initial leak test was performed January 13, 1988.

Valve QS 4 leaked at 0.47 SCT/D.

Maintenance Work Request 882506 was initiated due to binding when QS 4 was cycled.

The valve shaft was lubricated to eliminate the binding.

A Type C retest was not performed, since the seating surfaces of the valve were not affected.

Penetration No. 70 The initial leak test was performed December 23, 1987. Valve RS 101 leaked at 0.46 SCF/D.

Maintenance Work Request 879160 was initiated due to binding when RS+101 was cycled.

The valve shaft was lubricated to eliminate the binding.

A Type C retest was not to be performed, since the seating surface of the valve was not affected; however, it was discovered that the downstream piping was not properly vented during the initial leak test, due to water in Recirculation Spray Pump RS P 2B casing.

The Type C retest was performed on January 21, 1988, with a leakage of 18.66 SCP/D.

Penetration No. 71 The initial leak test was performed December 23, 1987. Valve RS-100 leaked at 5.57 SCF/D. Maintenance Work Request 879161 was initiated due to binding when RS 100 was cycled.

The valve shaft was lubricated to eliminate the binding.

A Type C retest was not performed, since the t

seating surface of the valve was not affected.

Penetration No. 88 The initial leak test was performed January 12, 1988. Valve HY 196 leaked at 17.14 SCF/D, and valve NY 110 leaked at 0.47 SCP/D.

Maintenance Work Request 882511 was initiated for penetration boundary valve NY 119 shaft leakage.

Page 6 of 8 l

1 I

l l

s ATTACHMENT 4.1B (c ntinusd)

SIXTH REPUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe C Repairs (continued)

The internals of valve HY 119 had been removed during the 5th Refueling Outage.

The valve shaft was removed and the opening temporarily plugged.

The Type C retest was performed on January 15, 1988, with a leakage of 8.44 SCF/D for HY 196, and 1.64 SCF/D for HY 110.

Penetration No. 90 The initial leak test was performed January 18, 1988.

Valves VS D 5 3A and VS D 5 3B leaked at 370.7 SCF/D (pressurized between CIV's).

Maintenance Work Request 882319 was initiated for a packing leak on valve VS D 5 3A, and Maintenance Work Request 882313 was initiated for a packing leak on VS D 5 3b.

The old packing was removed, and both valves repacked.

The Type C retest was performed on February 8, 1988, with a leakage of 0.46 SCF/D.

Penetration No. 91 The initial leak test was performed January 18, 1988.

Valves VS D 5 5A and VS D 5 5B, and VS D 5 6 leaked at 176.1 SCF/D (pressurized between CIV's).

Maintenance Work Request 875577 was initiated to inspect the seat and repack valve VS D 5 5A.

Maintenance Work Request 875439 was initiated for a crack on the Motor Operator of VS D 5 5A.

The seat was inspected satisfactorily, the valve repacked, and the motor operator replaced on valve VS D 5 5A.

The Type C retest was performed on January 27, 1988, with a leakage of 1.25 SCF/D.

Penetration No. 94 The initial leak test was performed December 21, 1987. Valve HCV CV 151 leaked at 13.89 SCP/D.

Maintenance Work Request 879158 was initiated.

Page 7 of 8

ATTACHMENT 4.18 (centinusd)

SIXTH REFUELING LOCAL LEAKACE RATE TEST REPAIRS Tvoe C Renairs (continued)

Prior to any work being performed by Maintenance, it was discovered that valve HCV.CV 151 had not gone fully closed to the mechanical stop (chain operated valve).

The Type C retest was performed on January 4, 1988, with a leakage of 1.58 SCF/D.

Maintenance Work Request 879158 was voided.

Penetration No. 105 2 The initial leak test was performed December 22, 1987.

Valve TV SS 112A1 leaked at 13.90 SCF/D.

Since no air leakage was detected at the downstream vent, Maintenance Work Request 879167 was initiated for inboard penetration boundary valve TV SS 110.

The packing for valve TV SS 110 was adj us ted.

The Type C retest was performed on January 15, 1988, with a leakage of 0.47 SCP/D.

t l

l l

Page 8 of 8

I ATTACKMENT 4.1C SEVENTH REFUELINC LOCAL LEAKACE RATE TEST DATA j

TYPE C TESTS l

i CONTAINMENT AS FOUND AS LEFT ASSIGNED f

PENT VALVE DATE VALVE VALVE PENETRATION NO.

MARK NO.

TESTED LEAKAGE LEAKAGE LEAKAGE l

IN OUT (SCF/D)

(SCP/D)

(SCF/D) l MOV CC 112A2 X

09 29 89 0.47 0.47 1

2.83 CCR 247 X

09 29 89 2.83 2.83 MOV CC 112B3 X

09 25 89 0.47 0.47 2

10.78 CCR 252 X

09 25 89 1988.6 10.78 MOV CC 112A3 X

10 19 89 2.44 1.18

{

4 14.16 CCR 251 X

09 29 89 14.16 14.16 MOV CC 11282 X

09 25 89 0.47 0.47 5

6.25 CCR 248 X

09 25 89 6.25 6.25.

t TV CC 107D1 X

09 29 89 1.50 1.50 8

1.50 TV CC 107D2 X

09 29 89 0.47 0.47 TV CC 111D1 X

11 11 89 2.81 43.88 9

43.88 TV CC 111D2 X

09 08 89 4.69 4.69

+

TV CC-110D X

09 13 89 2.34 2.34 11 TV CC 110F1 X

2.34 09 13 89 0.49 0.49 TV CC 110F2 X

FP 827 X

09 28 89 0.47 0.47' 13 0.47 TV FP 107 X

09 28 89 0.47 0.47 TV CC 110E3 X

09 13 89 1.31 1.31 14 1.31 TV CC-110E2 X

09 13 89 0.47 0.47 TV CC-111A2 X

09 11-89 0.47 0.47 16 62.38 TV CC 111A1 X

09 11 89 62.38 62.38 TV CC 103B1 X

10 02 89 1.88 1.88 17 22.71 TV CC 1038 X

10 02 89 22.71 22.71 TOTAL PENETRATION LEAKACE SHEET 1 (SCF/D) 168.61-1 r

l Page 1 of 10 l

ATTACHMENT 4.1C (esntinued)

SEVENTH REFUELING lhCAL 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)

TV CC.103C1 X

10 03 89 2.59 2.59 18 52.27 TV.CC.103C X

10 03 89 52.27 52.27 MOV.CH 378 X

10 06 89 25.38 30.08 19 CH.369 X

30.08 MOV.CH 381 X

10 06 89 0.47 0.47 SI.42 X

09 06 89 1,41 1.41 20 1.41 S1 41 X

09 06 89 1.13 1.13 RH 14 X

09 25 89 0.47 0.47 24 RH.16 X

09 25 89 0.47 0.47 0.94 RH.15 X

09 25 89 0.47 0.47 TV.CC.105D1 X

11 10 89 13.62 2,08 25 5.16 TV.CC.105D2 X

09 08 89 5.16 5.16 TV.CC 107El X

09 09 89 60,87 60.87 26 60.87 TV.CC.107E2 X

09 09 89 3.84 3.84 TV.CC.105El X

03 09 89 16.86 16.86 27 16.86 TV.CC 10$E2 X

09 09 89 9.61 9.61 TV.CH 200A X

TV.CH 2005 X

10 11 89 1.32 1.32 TV.CH 2000 X

28 RV.CH.203 X

10 11 89 0.47 0.47 48.79 MOV.CH 142 X

10 11 89 84.68 47.00 TV.CH 204 X

09 23 89 0.47 0.47 TOTAL PENETRATION LEAXAGE SHEET 2 (SCF/D) 216.38 Page 2 of 10 I

(

l

)

ATTACHMENT 6.1C (centinued)

SEVENTH RETUELING 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 LEAKACE j

IN OUT (SCF/D)

(Scr/D)

(SCP/D)

TV.DG 108A X

09 28 89 10.30 10.30 29 10.30 TV.DG 108B X

09 28 89 8.40 8.40 j

TP.804 X

09 29 89 0.47 0.47 31 0.47 TV.FP.105 X

09 28 89 2.44 0.47 i

TP.800 X

09 30 89 0.47 0.47 32 0.47 TV.FP 106 X

09 30 89 13.14 0.47 TV.DA.100A X

10 26 89 51.70 51.70 38 51.70 TV.DA 1008 X

10 26 89 220.90 0.47 SA 15 X

09 05 89 10.47 37.39 42 37.39 SA.14 X

11 03 89 0.71 0.71 TV.CV.102 1 X

09 12 89 0.47 0.47 43 0.47 TV.CV 102 X

09 12 89 0.47 0.47 TV.CV 101A X

09 11 89 3.53 3.53 44 3.53 TV.CV 101B X

09 11 89 1.88 1.88 RC.72 X

09 05 89 20.58 20.58 45 20.58 TV.RC 519 X

09 06 89 0.47 0,47 IA 91 X

09 06 89 9.36 9.36 47 9.36 IA.90 X

09 06 89 3.27 3.27 TV.DC.109A2 X

09 11 89 3.02 3.02 48 6.13 TV.DG 109Al X

09 11 89 6.13 6.13' RC 68 X

09 11 89 56.46 56.46 49 56.46 TV.RC 101 X

09 11 89 2.82 2.82 i

TOTAL PENETRATION LEAKAGE SHEET 3 (SCF/D) 196.86 Page 3 of 10 L

l

ATTACKMENT 4.1C (centinu;d)

SEVENTH RETUELING LOCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS TOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO.

MARK NO.

TESTED LEAKAGE LEAKAGE LEAKAGE IN OUT (SCF/D)

(SCF/D)

TV.SI.101 2 X

09 23 89 0.47 0.47 53 0.47 TV.SI.101 1 X

09 23 89 0.47 0.47 TV SS 109Al X

09 23 89 0.47 0.47 55 1 0.47 TV.SS.109A2 X

09 23 89 0.47 0.47 TV.LM.100A1 X

09 05 89 0.47 0.47

$$.2 0.47 NOTE 1 TV.LM 100A2 X

09 05 89 0.47 0.47 TV.SS.111A1 X

09 23 89 3.30 3.30 55 4 3,30 TV.SS.111A2 X

09 23 89 3,30 3.30 TV SS.100A1 X

09 23 89 0.47-0.47 56 1 0.47 TV.SS.100A2 X

09 23 89 0.47 0.47 TV SS.102A1 X

11 28 89 0.48 0.47 56 2 0.48 TV.SS 102A2 X

11 03 89 0.48 0.48 TV.SS 105A1 X

09 27 89 0.56 0.56 i

56 3 0.56 TV SS 10$A2 X

09 27 89 0.47 0.47 TV.LM 101A X

09 08 89 8.06 8.06 This pent was 57 3 spared by l

CV.35 X

09 08 89 8.06 8.06 DCP 819 l

TV LM 1018 X

09 11 89 4.71 4.71 This pent was l

57 4 spared by CV.36 X

09 11 89 3.53 3.53 DCP 819 i

TV.CC.103Al X

10 03 89 0.47 0.47 58 3.52 TV.CC.103A X

10 03 89 3.52 3.52 i

QS.4 X

10 25 89 0.47 0.47 63 70.70 MOV.QS.1018 X

10 25 89 205.09 70.70 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 80.44 NOTE 1 INCLUDES PENETRATIONS 57 1,57 2, AND 97 3 WHICH ALSO SHARE THESE CNMT ISOLATION VALVES THROUGH A COMMON 4.WAY VALVE.

l Page 4 of 10

ATTACHMENT 4.1C (c ntinu;d)

SEVENTH REFUELING IhCAL LEAKACE 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)

QS 3.

X 11 02 89 35.91 11.30 64 11.30 MOV-QS 101A X

11 02 89 40.66 0.47 70 RS 101 X

09 15 89 3.06 3.06 3.06 71 RS 100 X

09 1$ 89 34.31 34.31 34.31 HY 197 X

09 13 89 2.67 2.67 87 3.38 HY 111 X

09 13 89 3.38 3.38 HY 196 X

09 13 89 0.66 0.66 88 0.66 HY 110 X

09 13 89 0.56 0.56

~~

AS 278 X

09 16 89 42.42 15.08 89 15.08 TV SV 100A X

09 15 89 4.71 4.71 VS D 5 3B X

90 11 07 89 36.29 29.20 29.20 VS D 5 3A X

VS D 5 5B X

91 VS D 5 5A X

11 26 89 70.70 79.75 79.75 VS D 5 6 X

TV CV 150C X

09 14 89 6.12 6.12 HY 102 X

09 14 89 6.12 6.12 92 24.48 TV CV 150D X

09 14 89 17.42 17.42 HY 104 X

09 14 89 7.06 7.06 TV-CV 150B X

09 14-89 0.47 0.47 HY 101 X

09 14 89 3.53 3.53 93 7.25 TV CV 150A X

09 14 89 3.72 3.72 HY 103 X

09-14 89 0.66 0.66 TOTAL PENETRATION LEAKACE SHEET 5 (SCF/D) 208.47 Page 5 of 10

ATTACHMENT 4.1C (centinu d)

SEVENTH REFUELINC LDCAL LEAKAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO.

MARK NO.

TESTED LEAKACE LEAYAGE LEAYAGE IN OUT (SCF/D)

(SCF/D)

HCV CV 151 X

09 27 89 25.78 23.93 94 23.93 HCV VC 151 1 X

09 27 89

>2400 16.89

$0V HY 102B1 X

09 09 89 0.47 0.47 95 64 0.47 SOV HY 102B2 X

09 09 89 0.47 0.47 SOV HY 103B1 X

09 09 89 0.47 0.47 95 69 0.47-SOV HY 103B2 X

09 09 89 0.47 0.47 i

SOV HY 10481 X

09 09 89 0.47 0,47 95 72 0.47 SOV HY 104B2 X

09 09 89 0.47 0.47 TV SS 104A1 X

09 23 89 0.47 0.47 97 1 0.47 TV SS 104A2 X

09 23 89 0.47 0.47

(

TV SS 103Al X

09 26 89 0.47 0.47 l

97 2 0.47 TV SS 103A2 X

09 26 89 0.47 0.47 I

PC 38 X

09 08 89 0.48 0.48 103 0.48 PC 37 X

09 08 89 0.48 0.48 PC 9 X

09 08 89 1.28 1.28 104 1.28 PC 10 X

09 08 89 0.48 0.48 l

TV SS 112A1 X

09 26 89 0.47 0.47 105 2 4.69 TV SS 112A2 X

09 26 89 4.69 4.69 MOV SI 842 X

09 12 89 0.66 0.66-106 0.90 TV SI 889 X

09 12 89 0.90 0.90 SOV NY 102A1 X

09 09 89 0.47 0.47 109 44 0.47 SOV NY 102A2 X

09 09 89 0.47 0.47 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 34.10 i

Page 6 of 10

I ATTACHMENT 4.1C (centinued)

SEVENTH RETVELING LOCAL LEAYAGE RATE TEST DATA TYPE C TESTS CONTAINMENT AS FOUND AS LEFT ASSIGNED PENT VALVE DATE VALVE VALVE PENETRATION NO.

MARK NO.

TESTED LEAKAGE LEA}%CE LEA)%CE IN OUT (SCF/D)

(SCF/D)

(SCP/D)

$0V.HY.103Al X

09 09 89 0.47 0.47 109 49 0.47 SOV HY 103A2 X

09 09 89 0.47 0.47

$0V.HY.104A1 X

09 09 89 0.47 0.47 109 52 0.47 SOV.HY 104A2 X

09 09 89 0.47 0.47 RC.277 X

09 14 89 0.47 0.47 110 1 0.47 RC 278 X

09 14 89 0.47 0.47 VS.169 X

09 12 89 0,47 0.47 VS.170 X

09 12 89 0.47 0.47 P.A.L.

(NOTE 2)

VS.167 X

09 12 89 0.47 0.47 VS.168 X

09 12 89 0.47 0.47 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 1.41 NOTE 2. THE ASSIGNED PENETRATION LEAKAGE FOR THESE VALVES IS ADDED WITH THE PERSONNEL AIR 14CK OVERALL TYPE B LEAKAGE, AND NOT INCLUDED IN THE TYPE C

TOTAL, P.A.L. - PERSONNEL AIRLOCK TOTAL PENETRATION LEAKAGE SHEET 1 (SCF/D) 168.61 TOTAL PENETRATION LEAKAGE SHEET 2 (SCF/0) 216.38 T0h.L PENETRATION LEAKAGE SHEET 3 (SCF/D) 196.86 TOTAL PENETRATION LEAKAGE SHEET 4 (SCF/D) 80.44 TOTAL PENETRATION LEAYAGE SHEET 5 (SCF/D) 208.47 TOTAL PENETRATION LEAKAGE SHEET 6 (SCF/D) 34.10 TOTAL PENETRATION LEAKAGE SHEET 7 (SCF/D) 1,41 TOTAL CONTAINMENT TYPE C LEAKAGE. SUM OF SHEETS 1 THRU 7 (SCF/D) 906.27 l

Page 7 of 10

ATTACRMENT 4.1C (c:ntinued)

SEVENTH REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE B TESTS PENT LEAF. ACE PENT LEAYACE NO

0. RING SEAL / CANISTER NO 0 RING SEAL / CANISTER (SCCM)

(SCCM) 1.B 2.0

/

2.0 7.E 2.0

/

2.0 1.D 2.0

/

2.0 7F 2.0

/

2.0 1.F 2.0/2.0 * /

N/A 7.C N/A ** /

2.0 25 2.0

/

2.0 8.A 2.0

/

2.0 2D 2.0

/

2.0 8B 2.0

/

2.0 2F 2.0

/

2.0 B.C 2.0

/

2.0 3.A 2.0

/

2.0 8.D 2.0

/

2.0 35 2.0

/

2.0 8.E 2.0

/

2.0 3.C 2.0

/. 2.0 8.F 2.0/2.0 * /

N/A 3.D 2.0

/

2.0 8.C 2.0

/

2.0 3E 2.0

/

2.0 9.A 2.0

/

2.0 3F 2,0

/

2.0 9.B 2.0

/

2.0 30 2.0/2.0 * /

N/A 9.C 2.0

/

2.0 4.A 2.0

/

2.0 9D 2.0

/

2.0 48 2.0

/

2.0 9.E 2.0

/

2.0 4C 2.0

/

2.0 9.F 2.0

/

2.0 4.D 2.0

/

2.0 9.G 2.0

/

2.0 4.E 2.0

/

2.0 10 A 2.0

/

2.0 4F 2.0

/

2.0 10 B 2.0

/

6.0 40 2.0

/

2.0 10.C 2.0

/

2.0 5.A 2.0

/

2.0 10 D 2.0

/

2.0 58 2.0

/

2.0 10.E 2.0

/

2.0 50 2.0

/

2.0 10 F 2.0

/

2.0 5.D 2.0

/

2.0 10 0-2.0

/

2.0 5.E 2.0

/

2.0 11.A 2.0

/

2.0 5F 2.0

/

2.0 11 8 2.0

/

2.0 50 2.0

/

2.0 11.C 2.0/2.0 * /

N/A 6.A 2.0

/

2.0 11.D 2.0

/

2,0 68 2.0/2.0 * /

N/A 11.E 2.0

/

2.0 6.C 2.0

/

2.0 11.F 2.0

/

2.0 6.D 2.0

/

2.0 11.C 2.0

/

2.0 6.E 2.0

/

2.0 12.A 2.0

/

2.0 6.F 2.0

/

2.0 12.B 2.0

/

2.0 60 2.0

/

2.0 12.C 2.0

/

2.0 7.A 2.0/2.2* /

N/A 12 D 2.0

/

2.0 75 2.0

/

2.0 12.E 2.0

/

2.0 7.C 2.0

/

'2.0 12 F 2.0

/

2.0 7.D.

2.0

/

2.0 12 0 2.0

/.

2.0 TOTALS 84.2 68.0 78.0 76.0 SHT 1

SPARE PENETRATION INSIDE/0UTSIDE CONTAINMENT

- CONAX ELECTRICAL PENETRATION INSTALLED AT 6R

0. RINGS-AND FEED THROUGHS TESTED SINULTANEOUSLY Page 8 of 10

ATTACHMENT 4.1C (c:ntinued)

SEVENTH REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE B TESTS PENT LEAKAGE PENT LEAKAGE NO 0 RING SEAL / CANISTER NO 0-RING SEAL / CANISTER (SCCM)

(SCCM) 13.A 2.0/2.0 * /

N/A 15.E 2.0

/

2.0 13 8 N/A ** /

2.0 15.F 2.0

/

2.0 13.C 2.0

/

2.0 15 0 2.0

/

2.0 13.D 2.0/2.0 * /

N/A 16 A 2.0

/

2.0 13 E 2.0

/

2.0 16 8 2.0

/

2.0 13 F 2.0

/

2.0 16.C 2.0

/

2.0 13 0 2.0

/

2.0 16 D 2.0

/

2.0 14 A 2.0

/

2.0 16.E 2.0

/

2.0 14 B 2.0

/

2.0 16.F 2.0

/

2.0 14.C 2.0

/

2.0 16 0-2.0/2.0 * /

N/A 14 D 2.0

/

2.0 17.B 2.0

/

2.0 14 E 2.0

/

2.0 17.D 2.0/2.0 * /

N/A 14 F 2.0

/

2.0 17 F 2.0/2.0 * /

N/A 14 0 2.0

/

2.0 18 8 2.0

/

2.0 15 A 2.0

/

1.0 18.D 2.0

/

2.0 15 B 2,0

/

2.0 18.F 2.0/2.0 * /

N/A 15 C 2.0

/

2.0 FB 1 2.0

/

2.0 15 D 2.0

/

2.0 TOTALS 38,0 32.0 42.0 26.0 SHT 2

SPARE PENETRATION INSIDE/0UTSIDE CONTAINMENT

- CONAX ELECTRICAL PENETRATION INSTALLED AT 6R. 0 RINGS AND FEED THROUGHS TESTED SIMULTANEOUSLY LEAKAGE TOTALS 0 RING SEAL / CANISTER (SCCM)

SHT 1 162.2

/

144.0 SHT 2 80.0

/_

58.0 TOTAL LEAKAGE 242.2

/

202.0 (SCCM)

TOTAL LEAKAGE 12.3

/

10.3 (SCF/D) 4 Page 9 of 10

ATTACHMENT 4.1C (c:ntinued)

SEVENTH REFUELING LOCAL LEAKAGE RATE TEST DATA TYPE B TESTS AS FOUND AS LEFT ASSIGNED PENETRATION DATE LEAKACE LEAKAGE PENETRATION TESTED (SCF/D)

(SCP/D)

LEAKAGE Fuel Transfer Tube 12 04 89 0.47 0.47 0.47 Penetration alli 09 04 89 0,47 0.47 0.47 Penetration #112 09 04 89 0.47 0.47 0.47 Equipment Hatch Outer Flange 11 21 89 0.47 0.47 0.47 Equipment Hatch Inner Flange 11 24 89 0.48 0.48 0.48 Personnel Airlock 11 28 80 105.3 105.3 105.3 Equipment Hatch Airlock 11 24 89 3.25 3,25 3,25 Sn== mrv of Tvoe B and C Leakane Rates As left w

As Found-we Total Type B Leakage 133.51 SCF/D 134.28 SCF/D Total Type C Leakage 906.27 SCF/D 295.58 SCF/D Total Type B and C Leakage

1039.78 SCF/D 429.86 SCF/D I

Acceptance Criteria < 606 La

(< 3,929 SCF/D )

w Maximum pathway leakage rate,

== Minimum pathway leakage rate.

I Pa - 40 PSIG Page 10 of 10 1

ATTACRMEh"7 4.1D SEVENTH RETVELING LOCAL LEAKACE RATE TEST REPAIRS Tvoe B Recairs The following electrical penetrations required maintenance due to high leak rates or physical damage:

PENT NO.

MVR NO.

AS POtJND LEAKAGE AS LEPT LEAKAGE (SCCM)

(SCCM) 6 A 0 Ring 893727 7.4 2.0 10 A Canister 893730 9.0 2.0 10 B Canister 894564 2.0 6.0 11 A Canister 893728 6.2 2.0 15 B Canister 893729 4.0 2.0 The high leak rate on the 6 A penetration was due to a leak on the tubing to pressurize the 0 Rings.

The tubing was brazed to repair the leak and the 0 Rings were satisfactorily retested.

The high leak rate on the 10 A penetration was due to a leak on the tubing connection to pressurize the Canister.

When the penetration was repressurized to mark the exact location of the leak prior to repair, no leakage could be detected.

The MVR was voided and the Canister was satisfactorily retested.

During the repair of the 10 A penetration it was noted that the canister pressure gage connection for 10 B had been damaged.

Possibly during the erection of the scaffolding for the repair of the 10 A penetration.

A MVR was written to repair the damaged-gage connection.

The gage connection was unable to be repaired by brazing so a new gage connection and gage were installed.

The Canister was retested following the repair with a leakage rate of 6.0 SCCM measured. No external leakage could be detected following the repair.

Page 1 of 8

ATTACKMENT 4.1D (c ntinu:d)

SEVENTH RETUELING LDCAL LEAKAGE RATE TEST REPAIRS Tvoc B Repairs (continued)

The high leak rate on the 11 A penetration was due to a leak on the tubing to pressurize the Canister.

The tubing was brated to repair the leak and the Canister was satisfactorily retested.

The high leak rate on the 15 B penetration was due to a leak on the tubing to pressurize the Canister. The tubing was brated to repair the leak and the Canister was satisfactorily retested.

Personnel Airlock IPH.P 11 Inner and outer door o rings were replaced, and upgraded to material less susceptible to compression set.

Breech rings for inner and outer doors were adjusted.

Tvoc C Repairs Penetration No. 2 The "As Found" leak test was performed September 25, 1989.

Valve CCR 252 leaked at 1988.60 SCP/D.

The high leakage rate was due to the valve being closed beyond its optimum seating position (butterfly valve).

The valve was recycled and an " As Le f t" leak test performed on September 25, 1989, with a leakage of 10.78 SCF/D measured.

The valve stop was adjusted and its lock nut secured to ensure the valve would not over travel its optimum seating position in the future.

Penetration No. 4 The "As Found" leak test was performed September 29, 1989.

Due to EQ Requirements, the torque switch for valve MOV CC 112A3 was replaced per Maintenance Work Request 892752.

Following the replacement, an "As Lef t" leak test was performed on October 19, 1989, with a leakage of 1.18 SCF/D measured.

I l

Page 2 of 8 I

I

ATTACRMENT 4.1D (c ntinutd)

SEVENTH REFUELING LOCAL LEAKACE RATE TEST REPAIRS Tyne C Renairs (continued)

Penetration No. 9 The "As Found" leak test was performed September 8, 1989.

Due to previous difficulty in repairing the existing actuator on valve TV CC 111D1, a new smaller actuator was installed per DCP 666.

An "As Left" leak test was

)

performed on November 11, 1989, with a leakage of 43.88 SCF/D measured.

Penetration No. 19 The "As Found" leak test was performed September 13, 1989.

Due to EQ Requirements, the torque switch for valve MOV CH 378 was replaced per Maintenance Work Request 892769.

Following the replacement, an "As Left" leak test was performed on October 6, 1989, with a leakage of 30.08 SCF/D measured.

Due to EQ Requirements, the torque switch for valve MOV CH 381 was replaced per Maintenance Work Request 892770.

Following the replacement, an

" As Le f t" leak test was performed on October 6, 1989, with a leakage of 0.47 SCP/D measured.

Due to dual indication for valve position, the torque switch and limit switches for valve MOV-CH 381 were adj us ted per Maintenance Wock Request 891487.

Following the adjustment, an "As Le f t" leak test was performed on November 27, 1989, with a leakage of 0.47 SCF/D measured.

Penetration No. 25 The "As Found" leak test was performed September 8, 1989. Due to previous difficulty in repairing the existing actuator on valve TV CC 105D1, a new smaller actuator was installed per DCP 666. An "As Lef t" leak test was performed on November 10, 1989, with a leakage of 2,08 SCF/D measured.

Page 3 of 8

ATTACHMENT 4.1D (centinu;d)

SEVENTH REFUELING LOCAL LE.AKACE RATE TEST REPAIRS Tvoe C Reenirs (continued)

Penetration No. 28 The As Found" leak test was performed September 23, 1989.

Due to excessive seat leakage, Maintenance Vork Request 890994 was initiated for valve MOV.CH 142.

The clamp which connected the valve actuator to the valve stem was repaired to allow the valve to close completely.

An "As Left" leak test was performed on October 10, 1989, with a leakage of 47.00 SCF/D measured.

Relief Valve RV.CH.203 was removed for In Service Testing per Maintenance Work Request 883184.

Following the rsinstallation, an "As Left" leak test was performed on October 11, 1989, with a leakage of 0.47 SCF/D measured.

Penetration No. 31 The "As Found" leak test was performed September 22, 1989.

Due to a misapplication of valve TV.FP 105, the valve trim was replaced with a later

design, soft cent trim, per DCP 833.

An "As.Lef t leak test was performed on September 29, 1989, with a leakage of 0.47 SCP/D measured.

Due to binding when Check Valve FP 804 was cycled, Maintenance Work Request 893732 was initiated.

The valve shaft was lubricated to eliminate the binding.

An "As Left" leak test was performed on September 29, 1989, with a leakage of 0.47 SCF/D measured.

Penetration No. 32 The "As Found" leak test was performed September 22, 1989.

Due to a misapplication of valve TV FP 106, the valve trim was replaced with a later

design, soft seat trim, per DCP 833. An " As Le f t" leak test was performed on September 30, 1989, with a leakage of 0.47 SCF/D measured.

Page 4 of 8

ATTACRMENT 4.1D (continu:d)

SEVENTH REWELING LOCAL LEAFACE RATE TEST REPAIRS Tvoc C Renairs (continued) l

{

Due to binding when Check Valve FP.800 was cycled, Maintenance Work Request 893733 was initiated.

The valve shaft was lubricated to eliminate the j

binding.

An "As Left" leak test was performed on September 30, 1989, with i

a leakage of 0.47 SCF/D measured.

Eenetration No.'38 The "As.Found" leak test was performed September 26, 1989.

Due to excessive leakage, Maintenance Work Request 893731 was initiated for valve TV DA.1008.

The valve seat and plug were cleaned and new seat and bonnet gaskets installed.

An " As.Le f t" leak test was performed on October 26, 1989, with a leakage of 0.47 SCF/D measured.

Penetration No. 42 The "As.Found" leak cest was performed September 5, 1989.

Due to excessive seat and bonnet leakage, Maintenanco Work Request 893719 was initiated for valve SA 15.

The valve seat and flapper were cleaned and lapped and the valve reassembled.

An " As Le f t" leak test was performed on November 3, 1989, with a leakage of 37.39 SCF/D measured.

Penetration No. 56 2 The "As Found" leak test was performed November 3, 1989.

Due to dual indication for valve TV.SS 102A1, the valve switch assembly was replaced per Maintenance Work Request 880966.

Following the replacement, an "As Left" leak test was performed on November 27, 1989, with a leakage of 0.47 SCF/D measured.

I Page 5 of 8 1

ATTACHMENT 6.1D (etntinu;d)

SEVENTH RETUELING LOCAL LEAKAGE RATE TEST REPAIRS Tvec C Reemirs (continued)

Penetration No. 57 3 and $7 4 These penetrations were spared per DCP 819.

Penetration No. 63 The "As Founda leak test was performed September 7,

1989.

Due to recommendations from the valve vendor, check valve QS 4 was modified per Maintenance Work Request 893244.

Following the modification, an "As Left leak test was performed on October 25, 1989, with a leakage of 0.47 SCF/D measured.

Due to excessive seat leakage, Maintenance Work Request 893720 was initiated for MOV-QS 101B.

During the "As Left" leak test of valve QS 4, l

valve MOV-QS 101B was stroked and an "As Le f t" leak test performed on October 25, 1989, with a leakage of 70.70 SCP/D measured.

Maintenance Work i

Request 893720 was voided.

Penetration No. 64 The "As Found" leak test was performed September 7,

1989.

Due to recommendations from the valve vendor, check valve QS 3 was modified per Maintenance Work Request 893243.

Following the modification, an "As Lef t" leak test was performed on October 30, 1989, with a leakage of 11.30 SCF/D measured.

During the inspection of valve MOV-QS 101A per Maintenance Work Request 892628, bad grease was detected in the valve operator.

The operator was completely disassembled, the old grease removed, the new grease installed, and the operator reassembled.

Page 6 of 8

ATTACRMENT 4.1D (ccntinu d)

SEVENTH REfVELING LOCAL LEAKACE RATE TEST REPAIRS Tvoe C Renairs (continued)

An "As Le f t" leak test was performed on October 27, 1989 with excessive seat leakage measured.

The closing torque was increased to the operator's maximum allowable value.

An "As Lef t" leak test was performed on October 30, 1989 with exceasive packing leakage detected.

The valve's packing was adjusted two flats by mechanical maintenance and an "As Left" leak test performed on October 31, 1989.

Due to excessive packing leakage selli being detected, Maintenance Work Request 894565 was initiated to repack the valve.

Following the completion of Maintenance Work Request 894565, an "As Le f t" leak test was performed on November 2, 1989, with a leakage of 0.47 SCF/D measured.

Penetration No. 89 The "As Found" leak test was performed September 15, 1989.

Due to excessive seat leakage, the flapper of check valve AS 278 was cleaned of dirt and debris by testing personnel (the flapper can be reached through the valve's outlet). An " As Le f t" leak test was performed on September 16, 1989, with a leakage of 15.08 SCF/D measured.

Penetration No. 90 The "As Found" leak test was performed September 11, 1989.

Due to the information supplied by NRC Information Notice 88 73, valve VS D 5 3B was rotated to provide a more conservative leak test.

Following the completion i

of Maintenance Work Request 892327, which rotated the valve, an "As Left" leak test was performed on November 7, 1989, with a leakage of 29.20 SCF/D measured.

Page 7 of 8

ATTACHMENT 4.1D (c ntinued)

SEVENTH REIVELING LOCAL LEAKAGE RATE TEST REPAIRS Tvoe C Repairs (continued)

Penetration No. 91 The "As Found" leak test was performed September 12, 1989.

Due to the information supplied by NRC Information Notice 88 73, valve VS D 5 5B was rotated to provide a more conservative leak test.

Following the completion of Maintenance Work Request 892328, which rotated the valve, an "As Left" leak test was performed on November 26, 1989, with a leakage of 79.75 SCF/D measured.

Penetration No. 94 The "As Found" leak test was parformed September 13, 1989.

Due to the external stop being bent for valve HCV CV 151 1, the valve closed beyond its optimum seating position (butterfly valve).

Maintenance Work Request 893723 was written to repair the stop.

An " As Le f t" leak test was performed on September 27, 1989, with a leakage of 16.89 SCF/D measured.

Page 8 of 8 i

i ATTACHMENT 6.1E SIXTH AND SEVENTH FUEL CYCLE LOCAL LEAKAGE RATE TEST DATA

1. Sixth fuel Cvele LLRT Data A. Type B Tests

1. Airlock Total Volume Type B Tests

a. Personnel Airlock [PH P.1) (01 28 87) -

15.80 SCF/D Corrective Action (s)

Per Maintenance Work Request 875404; replaced o rings for outer door, and outer door escape hatch.

Outer door breech ring limit switch adjusted to permit additional travel in the closed

position,

b. Equipment Hatch Airlock [PH P.2) (01 27 87)... -

5.06 SCF/D Corrective Action (s)

None.

c. Personnel Airlock [PH.P 1) (07 22 87) 3.86 SCP/D Corrective Action (s)

Per Maintenance Work Request 875688; replaced o rings for outer door, and adjusted outer door breech ring,

d. Equipment Hatch Airlock [PH P 2] (07 21 87) -

0.46 SCF/D Corrective Action (s)

None, i

B. Type C Tests l

None l

l l

Page 1 of 3

ATTACHMENT 6.1E SIXTH AND SEVENTH TUEL CYCLE LOCAL LEAKAGE RATE TEST DATA II. Seventh ruel Cvele LLRT Data l

A. Type B Tests

1. Airlock Total Volume Type B Tests Personnel Airlock [PH P 1) (08 02 88) 166.35 SCP/D a.

Corrective Action (s). Per Maintenance Work Request 883255; interlocking pin limit required a minor adj us tment so that the closing hydraulic pump motor would shut off properly.

b. Equipment Hatch Airlock [PH.P 2) (08 03 88).....

0.46 SCF/D Corrective Action (s)

None.

l

c. Personnel Airlock [PH.P.1) (01 25 89)........

225.13 SCF/D Corrective Action (s)

Per Maintenance Work Request 892202; l

replaced

o. rings for inner and outer door.

Adjusted inner door breech ring, t

d. Personnel Airlock [PH.P 1) (01 30 89) 71.32 SCP/D Corrective Action (s)

Inner door o. rings were replaced due to OST 1.47.1,

" Personnel Airlock Door (s)

Seal Test" not passin6 the inner door seal test.

The Overall Type B of the airlock was performed after

o. ring replacement with no problems, i

Page 2 of 3

9 ATTACHMENT 4.lE SIXTH AND SEVENTH FUEL CYCLE IDCAL LEAKAGE RATE TEST DATA

1. Airlock Total Volume Type B Tests (continued)

e. Equipment Hatch Airlock [PH P 2) (01 25 89) - - -

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

f. Personnel Airlock [PH.P 1) (07-24 89) 70.49 SCF/D Corrective Action (s) - None.

1 l

i

g. Equipment Hatch Airlock [FH.P 2) (07 25 89) -----

23.22 SCF/D l

Corrective Action (s)

None.

l B. Type C Tests None l

l Note:

BVPS #1 administratively limits Type B leakage of each airlock to St La (327 SCF/D).

Total Type B and C leakage (excluding airlocks) ir administratively limited to 50% La to account for airlock ratests.

Page 3 of 3 4

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