ML20138L206

Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C

ML20138L206
Person / Time
Site:	Millstone
Issue date:	07/31/1985
From:	STONE & WEBSTER ENGINEERING CORP.
To:
Shared Package
ML20138L185	List: B11825, Forwards Reactor Containment Bldg Integrated Leakage Rate Test,Types A,B & C. Potential Changes in Bypass Leakage Paths Resulting from Continuing Design Review Identified ML20138L206
References
NUDOCS 8510310219
Download: ML20138L206 (52)

Text

_ _ _ _ . _ _ . . _ . _ _ . . . - - . = _ __ =

O i

l' REACTOR CONTAINMENT BUILDING

..,IEGRATED LEAKAGE RATE TEST TYPES A, B, AND C i

+

NORTHEAST UTILITIES MILLSTONE NUCLEAR POWER STATION UNIT 3 JULY 1985-Prepared by i STONE & WEBSTER ENGINEERING CORPORATION

' BOSTON, MA

[ { 3-A

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TABLE OF CONTENTS i Section Title Pm LIST OF ATTACHMENTS iii REFERENCES iv 1 PURPOSE 1-1 2

SUMMARY

2-1 2.1 TYPE A TEST ,

2-1 2.1.1 Conclusion 2-2 2.2 LOCAL LEAKAGE RATE TESTS (TYPES B AND C) 2-2 3 TYPE A TEST 3.1-1 J

3.1 EDITED LOG OF EVENTS 3.1-1 3.2 GENERAL TEST'UESCRIPTION 3.2-1

() 3.2.1 3.2.2 Prerequisites Equipment and Instrumentation 3.2-1 3.2-2 3.2.3 Data Acquisition System 3.2-2.

3.2.4 Data Resolution System 3.2-3 3.3 TEST RESULTS 3.3-1 3.3.1 Presentation of Test Results 3.3-1 3.3.2 ILRT Results 3.3-1 3.3.2.1 Mass Point Analysis 3.3-1 3.3.2.2 Total Time Analysis 3.3-2 3.3.2.3 Supplemental Test Results 3.3-2 3.3.2.4 Types B and C Penetration Leakage 3.3-3 4 LOCAL LEAKAGE RATE TESTS (TYPES B AND C) 4-1 t

i O 11 L _. - __ _ _ _ . ___ _

_ _ . _ . _ _ - -_ . . . , , . _...s - . . , . . . . . _ _ _ _ _

t 4

/"'s LIST OF ATTACHMEhu

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Attachment Title 3.2A Instrumentation 4

3.2B ILRT Temperature Detector Locations - Plan View 3.2C ILRT Temperature Detector Locations - Profile View 3.2D ILRT Dewpoint Temperature Sensor Locations -

Plan View 3.2E ILRT Dewpoint Temperature Sensor Locations -

Profile View 3.3A ILRT Reduced Input Variables 3.3B ILRT Absolute Method - Mass Point Analysis Test Results 3.3C ILRT Absolute Method - Total Time Analysis Test Results 3.3D Graph 1 - Leakage Rate and UCL vs. Time, Mass Point

' Analysis 3.3E Graph 2 - Leakage Rate and UCL vs. Time, Total Time Analysis 3.3F Superimposed Leakage Verification Test Absolute Method - Mass Point Analysis Test Results 3.3G Superimposed Leakage Verification Test Absolute Method - Total Time Analysis Test Results 4A Local Leakage Rate Test Data-iii T

i

REFERENCES O~

1. 10CFR50, Appendix J, Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors, October 22, 1980.

2. 3-INT-2002, Integrated Leak Rate (ILRT) and Structural Integrity (SIT) Test.

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

4. ANSI /ANS-56.8, C tainment System Leakage Testing Requirements, February 19, 1981 1

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' 1 This document used only as a guideline and any reference to said document in no way implies compliance.

O iv

SECTION 1 PURPOSE The purpose of this report is to present a description and analysis of the July 1985, Type A Reactor Containment Building Integrated Leakage Rate Test (ILRT), and summary of the Types B and C Local Leakage Rate Tests (LLRT's) conducted on Northeast Utilities' Millstone Nuclear Power Station Unit 3.

Northeast Nuclear Energy Company (NNECo.) acts as the agent for Northeast Utilities and is responsible for the operation, maintenance, and testing of Millstone 3. NNECo. uses the technical support services of Northeast Utilities Service Company (NUSCo.) in engineering, design, procurecient , construction, accounting, planning, and quality assurance activities. NUSCo. and NNECo. are wholly owned subsidiaries of Northeast Utilities.

NNEco, performed the Type A test with test engineering consultation services provided by Stone & Webster Engineering Corporation (SWEC).

This report is submitted as required by 10CFR50, Appendix J, Paragraph V.B. (Reference 1).

i 1-1

i SECTION 2 4

.-e

SUMMARY

2.1 TYPE A TEST

' The Structural Integrity Test (SIT) was successfully completed on July 12, 1985. The containment was opened and an entry was made to repitch the containment air recirculation fan blades and to perform the Type A inspection. The containment fans were secured during the SIT due to high motor amperage.

The valve lineup required for the ILRT had been established for the SIT.

The ILRT valve lineup conservatively vented portions of- systems that were outside of the outboard isolation valve.

Pressurization for the ILRT was started at approximately 1510 hours0.0175 days <br />0.419 hours <br />0.0025 weeks <br />5.74555e-4 months <br /> on July 12, 1985. The compressors were secured at approximately 0200 hours0.00231 days <br />0.0556 hours <br />3.306878e-4 weeks <br />7.61e-5 months <br /> on July 13, 1985 with a peak instantaneous pressure of 56.013 psia.

At 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br /> on July 13, 1985, the procedural temperature stabilization

, - criteria was satisfied. This time was used as the start time for the

! ILRT. Extensive investigations of all penetration areas were conducted throughout the test. These investigations revealed only minor packing leakage, or minor leakage observed through the downstream vent path.

s Initial Type A computer analysis results indicated a very low leakage rate, approximately one-tenth of the 0.75 L,$ or 0.675 percent per day would be obtained. The Type A test duration was twenty four hours. The i preoperational test will serve as a baseline for future surveillance tests which will be performed on a reduced duration basis.

- At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on July 13, 1985, Zone III temperature channel T7 (3LMS-TE20G) was deleted from the ILRT analysis. As shown on Attachment 3.2A, there are four temperature channels that are equally distributed in Zone III. With four channels, the weight factor was 0.06755 for each i channel. Because the T7 channel was erratic and not consistent with the temperature trends of its zone mates, the weight factor for T7 was changed to 0.0, and the weight factor for T5, T8, and T9 was changed to 0.09007.

i At 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on July 14, 1985, Zone A moisture channel D1 (3LMS-ME22A) was deleted from the ILRT analysis. As shown on Attachment 3.2A, there o are two moisture channels that are equally distributed in Zone A. With two channels, the weight factor was 0.27530 for each channel. Because the D1 channel was erratic and not consistent with the moisture trend of D2, the weight factor for D1 was changed to 0.0, and the weight factor

-for D2 was changed to 0.55060.

!O 2-1

The reduced input variables as shown in Attachment 3.3A were recalculated when the weight factors were changed. This deletes the sensors for the entire Type A and superimposed leakage verification test durations. The failed instrument channels, T7 and D1, were still scanned and their data recorded, but were not used in the ILRT analysis.

The Type A test was successfully completed at 0634 hours0.00734 days <br />0.176 hours <br />0.00105 weeks <br />2.41237e-4 months <br /> on July 14, 1985. A superimposed leakage verification. test was successfully completed from 0822 to 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br /> on July 14, 1985.

Depressurization of the containment began on the af terncon of July 14, 1985 and was completed during the early morning hours of July 15, 1985.

2.1.1 Conclusion 1.

The July 1985 Millstone Nuclear Power Staion Unit 3 Type A Test is considered a successful test in that it demonstrated the leak-tightness of the containment boundary. The measured leakage rates were well within the plant's maximum allowable leakage rate.

2.2 LOCAL LEAKAGE RATE TESTS (TYPES B AND C)

The Local Leakage Rate Tests (LLRT's) of containment isolation valves i and other containment penetrations were performed by the methods 1

O described in Station Test Procedure No. T3312 AIM 02, Local Leak Rate Test j - Type B'and T3312 AIM 03, Local Leak Rate Test - Type C.

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.

J.

2-2 t

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SECTION 3 TYPE A TEST 3.1 EDITED LOG OF EVENTS This log was edited from the information contained in the Official Log of Events.

July 12, 1985 1230 - Repositioned fan blades on 3HVU-FNIA, B, and C.

1330 - Commenced final containment inspection.

1400 - Completed final containment inspection, no abnormalities observed.

1510 - Completed the local leakage rate test on the personnel hatch.

- Commenced containment pressurization.

July 13, 1985 0200 - Secured containment pressurization with a peak instantaneous pressure of 56.013 psia.

- Commenced containment stabilization period.

0628 - Completed stabilization, ILRT started.

2300 - Removed failed Temperature Detector 3LMS-TE20G (Channel T7) from program.

July 14, 1985 0500 - Removed failed Moisture Detector 3LMS-ME22A (Channel D1) from program.

0634 - Satisfied 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ILRT criteria.

0700 - Rebalanced Moisture Detector 3LMS-ME22B (Channel D2).

0805 - Commenced superimposed leakage flow.

0822 - Stabilized superimposed leakage rate at 52.57 standard cubic feet per minute.

- Commenced superimposed leakage verification test.

1223 - Satisfied the superimposed leakage verification test.

1300 - Began depressurization.

3 1-1

f~N Q 3.2 GENERAL TEST DESCRIPTION 3.2.1 Prerequisites In accordance with the Millstone Nuclear Power Station Unit 3 ILRT procedure, 3-INT-2002 (Reference 2), the following is a listing of the pertinent prerequisites that were completed and documented prior to containment pressurization:

a. All required Types B and C local leakage rate testing completed. .

b. All required system valve line-ups completed.

c. Controlled access plan in effect.

d. Temporary air compressors and test skid checked out and available for pressurization.

e. All equipment and instrumentation, that could be damaged by test pressure, removed or protected.

f. General inspection of the accessible interior and exterior surfaces of the containment structures and components completed.

O g. Containment air recirculation fans adjusted for continuous

( operation at test pressure (53 psig).

h. The Official Log of Events was established.

1. All compressed gas cylinders removed from containment.

j. All test instrumentation functionally verified within 6 months of the test,

k. The Data Acquaition and Analysis Computers were operational and programed for ILRT functions.

1. Water levels were taken prior to the start of the Type A test.

i O 3.2-1

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

' 3.2.2 Equipment and Instrumentation Pressurization of the containment was achieved by the utilization of ten temporary air compressors.

Air was piped through two af tercoolers in parallel and a refrigerated air dryer. The system included adequate instrumentation and valving to maintain proper monitoring and control of the compressed air quality throughout the pressurization sequence. The total capacity of the pressurization system as installed was rated at approximately 12,000 cubic feet per minute (CFM).

The various containment parameters required to calculate containment leakage during the test were monitored using instrumentation which consisted of multiple resistance. temperature detectors (RTD's), dew point sensors (chilled mirror type) and an absolute pressure quartz manometer. Pertinent data for the test instrumentation is listed in Attachment 3.2A, and the general locations of the temperature and moisture sensors are shown in Attachments 3.2B through 3.2E.

A mass flowmeter was used to perform the superimposed leakage verification test. All test instrumentation with the exception of that used for the superimposed leakage verification test was monitored _by Northeast Utilities' HP 3497A data acquisition unit and portable computer.

O 3.2.3 Data Acquisition System The data acquisition system used for the Millstone Nuclear Power Station Unit 3 ILRT was Northeast Utilities' HP 3497A Data Acquisition Unit, which was linked to the plant computer.

For the ILRT, the HP 3497A monitored the following-instrumentation:

_ Type Containment Temperature Detectors 23 Dew Point Sensors 5 Quartz Manometers 2 The input to the ILRT program was an HP 3497A calculated fif teen minute instantaneous average. Each data set was time stamped. Instantaneous data (e.g. one sampling for each sensor) was also taken every fif teen minutes during the test period.

O 3.2-2

3.2.4 Data Resolution System After the appropriate data had been acquired and averaged, utilizing the HP 3497A, the reduced parameters were input into Northeast Utilities' HP 9836 portable computer for leakage rate calculations.

For the Millstone Nuclear Power Station Unit 3 ILRT, both the Absolute Method of Mass Point Analysis and Absolute Method of Total Time Analysis were used to determine the leakage rate.

Absolute Method of Mass Point Analysis The Absolute Method of Mass Point Analysis consists of calculating the air mass within the containment structure, over the test period, using pressure, temperature, and dew point observations made during the ILRT.

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

M= 144V (P-Pv) (Eq. 1)

RT where:

M = air mass, 1bm P = total pressure, psia Pv = average vapor pressure, psia R = 53.35 ft-lbf/lbm R (for air) d T =averagecontainmenttemperagure, R V = containment free volume, ft The leakage rate is then determined by plotting the 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 <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or symbolically:

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

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 the containment is positive and the units are in percent / day.

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

M = At + B (Eq. 3)

The slope A and the y-intercept B are then used in Equation 2 to determine the leakage rate.

O 3.2-3 L-

s' A 95 percent confidence interval is calculated using a Student's T distribution. The sum of the leakage rate and the 95 percent confidence interval is the upper confidence limit - mass point (UCL-MP). The measured leakage rate may be described as 95 - percent accurate to within 3

the value of the UCL-MP.

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

The . containment air mass is computed using Equation 1. The neasured leakage rate at any time (t) is then determined by subtracting the mass at that time (Mt) from the initial mass (Mi) and dividing by the initial mass. The measured leakage rate is expressed as a percentage of

' containment mass lost in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or symbol $cally:

Measured Leakage Rate = Mi - Mt (2400) (Eq. 4)

Mi ( a t)

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

The. estimated leakage rate is then determined by plotting the measured

-leakage rate as a function of time and then performing a linear O least-squares curve fit of the measured leakage rate values, as follows:

Estimated Leakage Rate = At + B (Eq. 5) where A is the slope and B is the y-intercept of the least-squares curve.

The confidence interval is determined in accordance with the equations of BN-TOP-1, Revision 1, Testing Criteria for Integrated Leakage Rate Testing of Primary Containment Structures for Nuclear Power Plants. The sum of the estimated leakage rate and the 95 percent confidence interval

~

is the upper confidence limit - total time (UCL-TT).

This analysis method was used in conjunction with procedure 3-INT-2002 (Reference 2).

O 3.2-4 t

O O O ATTACHMENT 3.2A INSTRUMENTATION The following instrumentation was calibrated and/or functionally verified within 6 months prior to the performance of this test and in accordance with 10CFR50, Appendix J.

Note: Instruments that were assigned a zero weight factor were not used in the leakage rate calculations.

Weight

' Instrument. Factor Channel Range Zone Elevation Accuracy Sensitivity A. Temperature 3LMS-TE20A 0.06820 T1 0-200 F I 145'-00" +1.0 F +0.02 F 3LMS-TE20B 0.06820 T2 0-200 F I 141'-09" II.0 F I0.02 F 3LMS-TE20C 0.06820 T3 0-200 F I 144'-06" {1.0F 10.02F 3LMS-TE20D 0.05057 T4 0-200 F II 94'-00" +1.0 F +0.02 F 3LMS-TE20F 0.05057 T6 0-200 F II 86'-00" II.0 F- I0.02 F 3LMS-TE20K 0.05057 T10 0-200 F II 70'-00" 11.0F [+0.02F 3LMS-TE20E 0.09007 T5 0-200 F III 88'-00" +1.0 F +0.02 F 3LMS-TE20G 0.00000 T7 0-200 F III 75'-00" II.0 F IO.02 F 3LMS-TE20H 0.09007 T8 0-200 F III 75'-00" II.0 F I0.02 F 3LMS-TE20J 0.09007 T9 0-200 F III 86'-06" 11.0F [+0.02F 3LMS-TE20M 0.03523 T12 0-200 F IV 32'-00" +1.0 F +0.02 F 3LMS-TE20N 0.02826 T13 0-200 F IV 33'-00" II.0 F I0.02 F 3LMS-TE20T 0.03114 T18 0-200 F IV 15'-06" II.0 F IO.02 F 3LMS-TE20U 0.02488 T19 0-200 F IV 15'-06" I_I.0 F

_ T_0.02 F l

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l Page 1 of 2

O O O ATTACHMENT 3.2A (Con't)

INSTRUMENTATION 4

Weight Instrument Factor Channel Range Zone Elevation Accuracy Sensitivity-4 3LMS-TE20L 0.01287 Til 0-200 F V 45'-00" +1.0 F +0.02 F 3LMS-TE20P 0.02210 T14 0-200 F V 26'-00" II.0 F I0.02 F 3LMS-TE20Q 0.02107 TIS 0-200 F V 30'-00" II.0 F IO.02 F 3LMS-TE20R 0.02107 T16 0-200 F V 30'-00" II.0 F IO.02 F 3LMS-TE20S 0.02210 T17 0-200 F V 26'-00" II.0 F I0.02 F

! 3LMS-TE20V 0.03870 T20 0-200 F VI -12'-06" +1.0 F +0.02 F II.0 F 3LMS-TE20W 0.03870 T21 0-200 F VI -16'-00" 70.02 F 3LMS-TE20X 0.03870 T22 0-200 F VI -14'-00" II.0 F I0.02 F 3LMS-TE20Y 0.03870 T23 0-200 F 'VI -16'-00" 11.0F [+0.02F B. Dewpoint 3LMS-ME22A 0.00000 D1 -25 F to 125 F A 145'-00" +0.4 F +0.1 F 3LMS-ME228 0.55060 D2 -25 F to 125 F A 147'-00" IO.4 F I0.1 F 3LMS-ME22C 0.14980 D3 -25 F to 125 F B -16'-00" +0.4 F +0.1 F 3LMS-ME22D 0.14980 D4 -25 F to 125 F B -16'-06" IO.4 F I0.1 F 3LMS-ME22E 0.14980 DS -25 F to 125 F B -16'-00" I0.4 F {0.1F C. Pressure 3LMS-PIT 41 1.0 -

0-100 psia - -

_0.015

+ psia +

_0.001%

3LMS-PIT 42 0.0 -

0-100 psia - -

+

_0.015 psia +

_0.001%

< D. Superimposed Leakage Verification Test Mass Flow Meter 3SAS-FT28 - -

0-150 scfm - -

1% F.S. 0.2% F.S.

Page 2 of 2

l TE-17 l l TE-21 l l TE-4 l /

l TE-1 l g' TE-14 l l TE-18

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l l TE-5 3RCS*SGIO gCS*SGIA l TE-3 fN s

G M TE-22 l

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\ / ] TE 9 l v

N _ ./

l TE-23 TE-Il l 3RCS*SGIC 9 3RCS*SGIB i -u l TE-I3 TE-19 l TE-2 l TE-15 l l TE-8 l PLAN VIEW NOTE:

1. TE-18 3 LMS-TE20 A (TYP)

ATTACHMENT 3.2B INSTRUMENTATION LOCATION RESISTANCE TEMPERATURE DETECTORS (RTD)

MILLSTONE NUCLEAR POWER STATION N UNIT 3 INTEGRATED LEAKAGE RATE TEST

w.

)

a p TE-1 TE-3 -

el. 14 5'-O" TE-2 ZONE 1 p TE-8 TE-5 ' -- ,

p TE-7

~- e l. 10 5'- 7 "

~~~

TE-4 ~

_ C TE-6 [ C TE-lO ZONE E.E el. 51*- 4" T E - 16  %

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T E - 15 T E - 13 o <( o'

_ _ N TE-12 e l. 24*- 6" O TE18

- O ZONE M Y '

' s T E - 19 el. 3,- 8,,

\ TE 14 TE-23 ~ ~

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TE-22 e l. -2 7'- 3"

/ \ l

/ \

TE-21 PROFILE VIEW NOTE:

1.TE-18 3LMS- TE 20A (TYP)

ATTACHMENT 3.2C INSTRUMENTATION LOCATION RESISTANCE TEMPERATURE DETECTORS (RTD)

D MILLSTONE NUCLEAR POWER STATION

( UNIT 3 INTEGRATED LE AK AGE RATE TEST

ME-1)

ME-4 )

O O 3RCS*SGID 3RCS*SGI A

/~\

m Ns N /-

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( ME-3 O O 3RCS*SGIC 3RCS*SGIB ME 5 )

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(ME-2 )

PLAN VIEW NOTE:

1. ME-1

• 3LMS-ME22A(TYP)

ATTACHMENT 3.2D INSTRUMENTATION LOCATION DEW POINT SENSORS

> / MILLSTONE NUCLEAR POWER STATION UNIT 3 INTEGRATED LEAKAGE RATE TEST

O A

ME-1 el. 145'- O" 1

! ZONE A e l. 105'- 7 "

el. 51*-4" 4

^

D

- - e l. 24'-6" ME-5 et,3*.s" 0

ME-3 - ~

4 V ME-4 I

e l. -2 7'- 3" PROFILE VIEW i  :

?

NOTE:

l.ME-1 s 3LMS - ME 22 A (TYP) i 4

ATTACHMENT 3.2E INSTRUMENTATION LOCATION DEW POINT SENSORS i MILLSTONE NUCLEAR POWER STATION l UNIT 3 INTEGRATED LEAKAGE RATE-TEST l

l l

3.3 ~ TEST RESULTS 3.3.1 . Presentation of Test Results

~

The test data for the July 1985 ILRT is based on a .24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period

, starting at 0628 hours0.00727 days <br />0.174 hours <br />0.00104 weeks <br />2.38954e-4 months <br /> on. July 13, 1985. The final test results were

determined using Northeast Utilities' ILRT computer program. The reduced input data, Mass Point Analysis test results, Total Time Analysis test- results, and representative graphs are contained in Attachments 3.3A through 3.3G.

Both the Mass Point and Total Time Analysis test results for the ILRT

s. satisfied the procedural acceptance criteria.

The Type A test instrumentation was verified by the superimposed leakage

. verification test method. Both the Mass Point and Total Time Analysis j test results for the superimposed leakage verification test satisfied 4

-the procedural acceptance criteria.

1 3.3.2' ILRT Results

. The ILRT was conducted in accordance with Millstone Nuclear Power Station Unit 3 station test procedure 3-INT-2002. The results for the ILRT and for the supplemental test are shown below, a 3.3.2.1 Mass Point Analysis Item (Percent / Day) l 1. Lam, leakage rate calculated 0.0669

2. Confidence 1e'.el 0.0023

3. UCL-MP Lam leakage rate plus 0.0692

confidence level (1 & 2) i Results were within the acceptable limit of 0.675 percent / day.

.1 4

O 3.3-1 3, -

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

3.3.2.2 Total Time Analysis Item (Percent / Day)

1. Lam, leakage rate estimated 0.0747

2. Confidence level 0.0313

3. UCL-TT Lam leakage rate plus 0.106 confidence level (1 & 2)

Results were within the acceptable limit of 0.675 percent / day.

3.3.2.3 Supplemental Test Results The Supplemental Verification Test was performed using the Superimposed Leakage Verification Test Method in accordance with station test procedure 3-INT-2002. The results' for the superimposed leakage verification test are shown below.

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

c (L,, + L, - 0.25L,)$ Lc (bam I bo + 0.25 L,)

where: L

= Type A calculated leakage (computer)

(Lam-MP=0.0669%/ day)

}

,/ (Lam-TT=0.0747%/ day)

L = Superimposed leakage rate developed from rotometer (Lo=0.893%/ day)

L = Maximum allowable leakage rate (La=0.9%/ day)

L = Composite leakage (computer)

(Lc-MP=0.955%/ day)

(Lc-TT=0.953%/ day)

a. Mass Point (0.0669 + 0.893 - 0.225) $ 0.955 I (0.0669 + 0.893 + 0.225) 0.7349 I 0.955 I 1.1849 0~J 3.3-2

, b. Total Time (0.0747 + 0.893 - 0.225) I 0.953 I (0'.0747 + 0.893 + 0.225)

O.7427I0.953$1.1927 The Superimposed Leakage Verification Test met the requirements set forth in References 2 and 4.

3.3.2'.4 Calculation of the superimposed leakage rate, L,

a. Calculate Average Flow in scfm:

Time Flow Time Flow Time Flow 25.9 52.57 27.417 53.82 28.917 52.28 26.1 52.95 27.667 52.76 29.1 51.99

, 26.417 52.49 27.917 52.86 29.417 51.67 26.667 53.07 28.1 52.25 29.667 52.02 26.917 52.57 28.417 52.41 29.917 52.64 27.1 53.59 28.667 52.86 260.60 317.24 316.96 Total Flow = 317.24 + 316.96 + 260.60 = 894.8 scfm-Average Flow = 894.8 + 17 data sets = 52.635294 Average Flow = 52.64 scfm = Lo

b. L,= 0.9 (2.305E6)(39.4 + 14.696) = 76362.379 scfd 100 14.696 L,= 53.02943 = 53.03 scfm = 0.9 percent / day

c. Convert L9 to percent / day:

) 52.64 , Lo 53.03 0.9 L, = 0.893386 percent' day use, L, = 0.893 percent / day 2

4 3.3-3

.,_ ATTAClEENT 3.3A INTEGRATED LEAKAGE RATE TEST '

FROM 0628 on 7-13-85 TO 0634 HOURS ON 7-14-85 REDUCED INPUT VARIABLES Air Vapor Absolute Time Pressure Dewgoint Pressure Temperature (hrs) (psia) ( F) (psia) ( R) 0.0 55.3378 65.183 .3081 552.002 0.25 55.3356 65.207 .3083 551.981 0.50 55.3347 65.194 .3082 551.974 0.75 55.3331 65.159 .3078 551.967 1.0 55.3310 65.257 .3089 551.934 1.25 55.3296 65.299 .3093 551.930 1.50 55.3287 65.192 .3082 551.921 1.817 55.3277 65.193 .3082 551.909 2.0 55.3263 65.325 .3096 551.913 2.25 55.3274 65.218 .3085 551.904 2.50 55.3246 65.392 .3103 551.905 2.75 55.3240 65.443 .3109 551.900 3.0 55.3248 65.369 .3101 551.887 3.25 55.3244 65.313 .3095 551.897 3.50 55.3237 65.379 .3102 551.886 3.75 55.3209 65.634 .3130 551.897 4.0 55.3202 65.700 .3137 551.900 4.25 55.3207 65.655 .3132 551.905 4.50 55.3206 65.664 .3133 551.890 4.75 55.3208 65.641 .3130 551.908 5.0 55.3188 65.827- .3151 551.892 5.25 -55.3185 65.855 .3154 551.903 5.50 55.3181 65.893 .3158 551.912 5.75 55.3182 65.888 .3157 551.911 6.0 55.3175 65.945 .3164 551.917 6.25 55.3175 65.947 .3164 551.926 6.50 55.3189 65.915 .3160 551.919 6.75 55.3173 66.056 '

.3176 551.920 7.0 55.3175 66.035 .3174 552.931 7.25 55.3184 66.050 .3175 552.940

-7.50 55.3190 65.994 .3169 552.943 7.75 55.3193 66.061 .3176 552.944 8.0 55.3183 66.145 .3186 552.955 8.25' 55.3199 66.092 .3180 552.948 8.50 55.3195 66.131 .3184 552.966 8.75 55.3210 66.089 .3179 552.970 9.0 55.3180 66.352 .3209 552.975 9.25 55.3206 66.212 .3193 552.983 9.50 55.3192 66.336 .3307 552.977 9.75 55.3201 66.349 .3208 552.994 10.0 55.3211 66.349 .3208 552.993 Page 1 of 3

)

l I

ATTACHMENT 3.3A (Con't) lp . INTEGRATED LEAKAGE RATE TEST FROM 0628 on 7-13-85 TO 0634 HOURS ON 7-14-85 REDUCED INPUT VARIABLES Air Vapor Absolute Time Pressure Dewgoint Pressure Temperature (hrs) (psia) ( F) (psia) ( R) 10.25 55.3199 66.454 .3220 552.007 10.50 55.3227 66.296 .3202 552.010 10.75 55.3224 66.411 .3215 552.024 11.0 55.3213 66.595 .3236 552.032 11.25 55.3219 66.548 .3230 552.032 11.50 55.3230 66.537 .3229 552.040

[

11.75 55.3231 66.620 .3238 552.043 12.0 55.3237 66.652 .3242 552.065 12.25 55.3261 66.525 .3228 552.069 ,

12.50 55.3231 66.791 .3258 552.073 12.75 55.3258 66.647 .3242 552.083 13.0 55.3250 66.806 .3259 552.083 13.25 55.3253 66.865 .3266 552.094 13.50 55 ??64 66.854 .3265 552.110 13.75 55.3249 66.988 .3280 552.112 i

0 14.0 14.25 14.50 55.3251 55.3257 55.3263 67.059 67.095 67.129

.3288

.3292

.3296 552.114 552.124 552.137 14.75 55.3260 67.154 .3299 552.148 15.0 55.3286 67.016 .3283 552.150 15.25 55.3288 67.084 .3291 552.153

-15.50 55.3291 67.153 .3299 552.169

' 15.75 55.3298 67.171 .3301 552.179 16.0 55.3316 67.109 .3294 552.188 16.25 55.3309 67.252 .3310 552.195 16.50 55.3322 67.227 .3307 552.208 16.75 55.3311 67.322 .3318 552.207 17.0 55.3321 67.321 .3318 552.208

- 17.25 55.3332 67.314 .3317 552.221 17.50 55.3336 67.371 .3324 552.225 17.767 55.3336 67.459 .3334 552.238 18.0 55.3344 67.474 .3335 552.247

'18.267 55.3371 67.322 .3318 552.257 18.517 55.3371 67.410 .3328 552.270 18.767 55.3377 67.450 .3333 552.283 19.067 55.3374 67.559 .3345 552.289 19.267 55.3393 67.485 .3337 552.292 19.517 55.3394 67.560 .3345 552.308 19.767 55.3399 67.601 .3350 552.320 20.016 55.3390 67.680 .3359 552.331 20.267 55.3416 67.541 .3343 552.341 i

Page 2 of 3

'f g - - - - - . --- ,- , . , --_.-.n--., _ _ . , -g- - - - - - - - , , , , , . . , , . , , , ,,.,n,-n , - , . , , _ _ mn-, - , , n- . ,,_ , , , . _,- --

ATTACHMENT 3.3A (Con't)

INTEGRATED LEAKAGE RATE TEST FROM 0628 on 7-13-85 TO 0634 HOURS ON 7-14-85 REDUCED INPUT VARIABLES Air Vapor Absolute Time Pressure Pressure Tempegature (hrs) (psia) Deg(F)oint (psia) ( R) 20.517 55.3421 67.588 .3349 552.354 20.767 55.3423 67.658 .3357 552.353 21.016 55.3424 67.735 .3365 552.351 21.267 55.3445 67.641 .3355 552.364 21.517 55.3427 67.886 .3383 552.382 21.767 55.3441 67.851 .3379 552.391 22.016 55.3455 67.811 .3374 552.406 22.267 55.3465 67.815 .3375 552.409 22.517 55.3478 67.789 .3372 552.417 22.767 55.3469 67.954 .3391 552.445 23.283 55.3491 67.937 .3389 552.447 23.300 55.3467 68.143 .3413 552.442 23.567 55.3466 68.233 .3424 552.449 23.850 55.3323 69.510 .3576 552.464 24.100 55.3494 68.163 .3415 552.471 O Page 3 of 3

ATTACHMENT 3.3B

~'

INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS Time Mass Leakage UCL (hrs) (1bm) (pet / day) (pet / day) 0.000 623835 0.0000 0.0000

.250 623834 0.0000 0.0000

.500 623831 .0271 .0.0000

.750 623822 .0650 .1300 1.000 623835 .0184 .0885 1.250 623823 .0290 .0726 1.500 623824 .0279 .0570 1.817 623826 .0222 .0435 2.000 623806 .0385 .0631 2.250 623829 .0258 .0497 2.500 623796 .0408 .0659 2.750 623794 .0487 .0711 3.000 623819 .0398 .0607 3.250 623803 .0396 .0575 3.500 623808 .0369 .0525 3.750 623763 .0493 .0679 O' 4.000.

4.250 623752 623752

.0601

.0669

.0798

.0855 4.500 623767 .0668 .0834 4.750 623750 .0696 .0847 5.000 623745 .0717 .0856 5.250 623730 .0753 .0884 5.500 623715 .0797 .0924 5.750 623717 .0820 .0938 6.000 623703 .0851 .0963 6.250 623692 .0881 .0989 6.500 623716 .0870 .0970 6.750 623697 .0876 .0969 7.000 623686 .0885 .0973 7.250 623686 .0888 .0969

. 7.500 623690 .0881 .0957 i , 7.750 623692 .0869 .0941

. 8.000 623669 .0872 .0941 4

8.250 623695 .0851 .0918 8.500 623669 .0848 .0911 l 8.750 623682 .0833 .0895 9.000 623643 .0842 .0901 ,

9.250 623663 .0834 .0890 9.500 623654 .0829 .0883 9.750 623645 .0827 .0878 10.000 623656 .0817 .0866 i

Page 1 of 3 4

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

ATTACHMENT 3.3B (Con't)

(,) INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS Time Mass Leakage UCL (hrs) (lbm) (pet / day) (pet / day) 10.250 623628 .0819 .0866 10.500 623655 .0805 .0852-10.750 623636 .0800 .0845 11.000 623616 .0802 .0845 11.250 623621 .0799 .0840 11.500 623625 .0793 .0833 11.750 623622 .0786 .0825

'12.000 623605 .0785 .0823 12.250 623628 .0774 .0812 12.500 623589 .0776 .0812 12.750 623608 .0770 .0805 13.000 623599 .0765 .0799 13.250 623591 .0763 .0796 13.500 623586 .0760 .0792

/'~ i 13.750 623566 .0762 .0793 k/s 14.000 623566 .0763 .0792 14.250 623561 .0763 .0792 14.500 623553 .0764 .0792 14.750 623538 .0768 .0795 15.000 623564 .0763 .0790 15.250 623564 .0758 .0784 15.500 623548 .0756 .0781 15.750 623546 .0754 .0778 16.000 623554 .0749 .0773 16.250 623540 .0746 .0770 16.500 623539 .0743 .0776 16.750 623528 .0741 .0763 17.000 623539 .0736 .0759 17.250 623536 .0732 .0754 17.500 623536 .0727 .0749 17.767 623521 .0724 .0745 18.000 623520 .0720 .0742 18.267 623539 .0713 .0735 4

18.517 623525 .0708 .0730 18.767 623516 .0705 .0726 19.067 623507 .0701 .0723 19.267 623524 .0696 .0717 19.517 623508 .0692 .0713 19.767 623500 .0689 .0710 20.016 623478 .0688 .0709 7- 20.267 623495 .0685 .0705 Page 2 of 3

ATTACHMENT 3.3B (Con't)

-~

INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS Time Mass ' Leakage UCL (hrs) (ibm) (pet / day) (pet / day) 20.517 623485 .0683 .0703 20.767 623489 .0680 .0699 21.016 623492 .0676 .0695 21.267 623502 .0670 .0690 21.517 623461 .0670 .0689 21.767 623467 .0668 .0687 22.016 623466 .0666 .0684 22.267 623473 .0663 .0681 22.517 623478 .0658 .0677 22.767 623437 .0659 .0677 23.283 623459 .0655 .0673 23.300 623437 .0655 .0672 23.567 623429 .0654 .0671 23.850 623251 .0671 .0695 24.100 623436 .0669 .0692 7

(

F l

O 1

Pade 3 of 3 i

ATTACHMENT 3.3C INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - TOTAL TIME ANALYSIS Measured Estimated Time Mass Leakage Leakage UCL (hrs) (1bm) (pet / day) (pet / day) (pet / day) 0.000 623835 0.0000 0.0000 0.000

.250 623834 .0139 0.0000 0.000

.500 623831 .0271 .0271 0.000

.750 623822 .0678 .0632 .172

, 1.000 623835 .0006 .0266 .208 1.250 623823 .0366 .0325 .147 1.500 623824 .0277 .0308 .118 1.817 623826 .0193 .0257 .098 h.000 623806 .0560 .0376 .105 2.250 623829 .0096 .0285 .093 2.500 623796 .0605 .0394 .103 2.750 623794 .0569 .0460 .105 3.000 623819 .0209 .0404 .098 3.250 623803 .0374 .0406 .094 3.500 623808 .0299 .0388 .090 Ot 3.750 4.000 623763 623752

.0736

.0793

.0478

.0563

.101

.109 4.250 623752 .0753 .0623 .114 4.500 6237C7 .0577 .0635 .113 4.750 623'50 .0685 .0665 .114 5.000 623745 .0689 .0691 .115 5.250 623730 .0770 .0727 .117 5.500 623715 .0839 .0768 .120 5.750 623717 .0791 .0795 .121 6.000 623703 .0848 .0827 .123 6.250 623692 .0879 .0858 .125 6.500 623716 .0705 .0860 .125 6.750 623697 .0788 .0873 .126 7.000 623686 .0816 .0888 .126 7.250 623686 .0790 .0897 .127 7.500 623690 .0744 .0899 .127 7.750 623692 .0710 .0896 .127 8.000 623669 .0797 .0904 .127 8.250 623695 .0653 .0893 .127 8.500 623669 .0749 .0895 .127 8.750 623682 .0674 .0887 .126 9.000 623643 .0820 .0896 .127 9.250 623663 .0717 .0893 .126 9.500 623654 .0734 .0892 .126 9.750 623645 .0750 .0892 .126 10.000 623656 .0687 .0887 .125 Page 1 of 3

ATTACHMENT 3.3C (Con't) in) s./ INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - TOTAL TIME ANALYSIS Measured Estimated Time Mass Leakage Leakage UCL (hrs) (ibm) (pet / day) (pet / day) (pet / day) 10.250 623628 .0776 .0889 .125 10.500 623655 .0658 .0881 .125 10.750 623636 .0710 .0878 .124 11.000 623616 .0767 .0879 .124

-11.250 623621 .0731 .0878 .124 11.500 623625 .0703 .0874 .124 11.750 623622 .0696 .0870 .123 12.000 623605 .0738 .0869 .123 12.250 623628 .0649 .0861 .122 12.500 623589 .0756 .0862 .122 12.750 623608 .0684 .0858 .122 13.000 623599 .0697 .0854 .121 13.250 623591 .0709 .0852 .121 13.500 623586 .0711 .0849 .121 g- s

() 13.750 14.000 623566 623566

.0753

.0739

.0850

.0850

.120

.120 14.250' 623561 20733 .0850 .120 14.500 623553 0748 .0850 .120 14.750 623538 0775 .0852 .120 15.000 623564 .0694 .0848 .119 15.250 623564 .0684 .0844 .119 15.500 623548 .0712 .0842 .118 15.750 623546 .0706 .0840 .118 16.000 623554 .0675 .0836 .118 16.250 623540 .0699 .0833 .117 16.500 623539 .0690 .0830 .117 16.750 623528 .0704 .0828 .117 17.000 623539 .0670 .0824 .116 17.250 623536 .0666 .0820 .116 17.500 623536 .0658 .0815 .115 17.767 623521 .0680 .0813 .115 18.000 623520 .0673 .0810 .114 18.267 623539 .0623 .0804 .114 18.517 623525 .0645 .0800 .113 18.767 623516 .0654 .0796 .113 19.067 623507 .0661 .0793 .113 19.267 623524 .0620 .0787 .112 19.517 623508 .0644 .0784 .112 19.767 623500 .0652 .0780 .111

/~' 20.016 623478 .0687 .0779 .111

(,,T/ 20.267 623495 .0645 .0776 .111 Page 2 of 3

l ATTACHMENT 3.3C (Con't)

INTEGRATED LEAKAGE RATE TEST FROM 0628 ON 7-13-85 TO 0634 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - TOTAL TIME ANALYSIS l Measured Estimated Time Mass Leakage Leakage UCL (hrs) (lbm) (pet / day) (pet / day) _(pet / day) 20.517 623485- .0655 .0773 .110 20.767 623489 .0640 .0769 .110 21.016 623492 .0627 .0766 .109 21.267 623502 .0602 .0761 .109 21.517 623461 .0668 .0759 .108 21.767 623467 .0651 .0757 .108 22.016 623466 .0645 .0754 .108 22.267 623473 .0625 .0751 .107 22.517 623478 .0609 .0747 .107 22.767 623437 .0673 .0746 .107 23.283 623459 .0620 .0744 .106 23.300 623437 .0656 .0741 .106 23.567 623429 .0662 .0739 .106 23.850 623251 .0941 .0750 .107 24.100 623436 .0636 .0747 .106 O Page 3 of 3

O O O i

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i i i i i i l 60 0 1000 1400 1800 2200 200 l

TIME j ATTACHMENT 3.3D

! UCL C LAM VS. TIME I MILLSTONE NUCLEAR POWER STATION UNIT 3 INTEGRATED LEAKAGE RATE TEST 1

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! 60 0 1000 1400 ~1800 2200 200 i

i TIME l ATTACHMENT 3.3E i UCL E LAM VS. TIME l MILLSTONE NUCLEAR POWER STATION l UNIT 3 l

INTEGRATED LEAKAGE RATE TEST i

I i __ _ __ _ _ _ _ _ _ _ _ _ -

, f) V-ATTACHMENT 3.3F INTEGRATED LEAKAGE RATE TEST SUPERIMPOSED LEAKAGE VERIFICATION TEST FROM 0822 HOURS TO 1223 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - MASS POINT ANALYSIS Time Mass Leakage UCL (hrs) (1bm) (pet / day) (pet / day) t 0.00 623341 0.000 0.0

. .200 623265 0.000 0.0

.517 623231 .823 0.0

.767 623195 .712 1.0 1.017 623093 .857 1.1 1.200 623036 .903 1.06 1.517 622977 .920 1.03 1.767 622771- 1.11 1.34 2.017 622873 1.03 1.23 2.200 622831 .962 1.13 2.517 622729 .954 1.09 2.767 622682 .940 1.05 3.017 622632 .927 1.02 3.200 622585 .912 .996 0 3.517 3.767 4.017 622482 622309 622370

.919

.963

.955

.992 1.04 1.02 O Page 1 of 1 e+,.-c --r-, ,w. -,. - - - -

ATTACHMENT 3.3G SUPE IMP D VERF T TEST FROM 0822 HOURS TO 1223 HOURS ON 7-14-85 ABSOLUTE TEST METHOD - TOTAL TIME ANALYSIS 4

Estimated Time Ma ss Leakage UCL (hrs) (1bm) (pet / day) (pet / day) 1 0.000 623341 0.0000 0.00

.200 623265 0.0000 0.00

.517 623231 0.820 0.00

.767 623195 .698 1.42 1.017 623093 .810 1.67 1.200 623036 .857 1.45 1.517 622977 .881 1.34 1.767 622771 1.04 1.57 2.017 622873 .998 1.48 2.200 622831 .958 1.40 2.517 622729 .954 1.35 2.767 622682 .944 1.31 3.017 622632 .934 1.28.

1 3.200 622585 .922 1.24 3.517 622482 .926 1.23 s_,/

3.767 622309 .957 1.25 4.017 622370 .953 1.23 b

1 j

O Page 1 of 1

- - ~ * %r , w-r - - - . - -- ---. =

[ SECTION 4

\

LOCAL LEAKAGE RATE TESTS (TYPES B AND C)

Attachment 4A summarizes the Local Leakage Rate Tests (LLRT's) data that was established to support the overall containment leakage testing program. These LLRT's were performed by pressurizing the listed penetrations with air or nitrogen and either measuring leakage across the containment isolation valves (Type C) or across the resilient seals (Type B). Each penetrations leakage rate can be obtained from site reference material.

Containment isolation valves and other leakage barriers that are in the bypass leakage program are designated "BP" under TYPE TEST.

The acceptance criteria for Types B and C testing is in accordance with 10CFR50, Appendix J. The combined leakage rate for all penetrations and valves, subject to Types B and C tests, is well below the acceptable leakage rate of 0.6 L,.

The total leakage rates for all containment isolation valves and leakage barriers subject to Types B, C, and Type B and C Bypass Leakage tests are 2697.4 SCCM, 39,625.9 SCCM, and 2817.8 SCCM, respectively.

The Attachment for this section is:

k"- Attachment No. Title 4A Local Leakage Rate Test Data 4-1

.-..,-,4---. ,+,n-, , , . . . _ , , , _ _ , , _ . , _ , , , _ , _ _ _ , _ , _ _ , , , _ , _ _ _ _

~ . --

ATTACHMENT 4A LOCAL LEAKAGE RATE TEST DATA i

TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) _ REMARKS i

12A - Reactor Coolant Hot C 3SSR*CTV26 (IC) 5.0 Legs Sample C 3SSR*CTV27 (OC) 5.0 12B - Pressurizer Liquid Sample C 3SSR*CTV22 (IC) 5.0 C 3SSR*CTV23 (OC) 5.0 12C - Pressurizer Vapor Space C 3SSR*CTV20 (IC) .5.0 Sample , C 3SSR*CTV21 (OC) 18.9 12D - Pressurizer Relief Tank C 3SSR*CTV8026 (IC) 28.6

(PRT) Gas Sample C 3SSR*CTV8025 (OC) 5.0 13A - Reactor Coolant Cold C 3SSR*CTV29 (IC) 5.0 Legs Sample C 3SSR*CTV30 (OC) 5.0

, 13B - Safety Injection C 3SSR*CTV32 (IC) 68.7 Accumulators Sample C 3SSR*CTV33 (OC) 28.9 t 14 -N 2 to Safety Injection C,BP 3SIL*CV8968 (IC) 45.7 Note 2 Accumulators 3SIL*CV8880 (OC)

15 - Primary Grade Water C,BP 3PGS*CV8046 (IC) 192.0 to PRT C,BP 3PGS*CV8028 (OC) 492.2 Page 1 of 10

g- s g-l k \ kj i ,

i i

!- ATTACHHENT 4A (Con't) 1 LOCAL LEAKAGE RATE TEST DATA-l TYPE VALVES / EQUIPMENT LEAKAGE  ;

l PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS i

16 - Seal Water Injection C 3CHS*V394 (IC) 5.0 i to Reactor Coolant Pumps C 3CHS*MV8109A (OC) 37.8 17 - Seal Water Injection C 3CHS*V434 (IC) 43.8 to Reactor Coolant Pumps C 3CHS*MV8109B (OC)' 67.6.

18 - Seal Water Injection C 3CHS*V467 (IC) 154.4 4

to Reactor Coolant Pumps C 3CHS*MV8109C (OC) 151.7 19 - Seal Water Injection C 3CHS*V501 (IC) 62.9 to Reactor Coolant Pumps C 3CHS*MV8109D (OC) 5.0  ;

23 - Seal Water Return from C 3CHS*MV8112 (IC) 95.3 Reactor Coolant Pumps C 3CHS*MV8100 (OC) 5.0 Note 2 i 3CHS*RV8113 (IC) j 24 - Reactor Coolant Letdown C 3CHS*CV8160 (IC) 105.6 Note 3 l I 4 3CHS*RV8117 (IC)

! 3CHS*CV8152 (OC) 26 - Reactor Coolant Charging C 3CHS*V58 (IC) 38.5

, C 3CHSMTV8105 (OC) 257.9 i

a f

I i

t j Page 2 of 10 i 1

.f ('%

O 4 kJ ATTACHMENT 4A (Con't)

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST- TESTED (NOTE 1) (SCCM) REMARKS 27 - PRT & Containment Drains C 3DCS*CTV24 (IC) 67.2 Note 2 Transfer Pumps Discharge 3DGS*CTV25 (OC) 28 - Containment Drains Sump C,BP 3DAS*CTV24 (IC) 5.0 Pump Discharge C,BP 3DAS*CTV25 (OC) 28.9 29 - PRT & Containment Drains C,BP 3VRS*CTV20 (IC) 5.0 Transfer Tank Vent C,BP 3VRS*CTV21 (OC) 123.1 32 - Containment Atmosphere C 3 CMS *CTV20 (OC) 414.2 Monitor Suction C 3 CMS *CTV21 (OC) 790.7 35 - Containment Vacuum C,BP 3CVS*CTV20A (OC) 86.1 Pump Suction C BP 3CVS*CTV21A (OC) 66.5 36 - Containment Vacuum C.BP 3CVS*CTV20B (OC) 28.7 Pump Suction C,BP 3CVS*CTV21B (OC) 67.0 37 - Containment Vacuum C,BP 3CVS*A0V23 (IC) 459.2 Ejector Suction C,BP 3CVS*V20 (OC) 47.9 Page 3 of 10

-7

( ,

w.Y N, ATTACHMENT 4A (Con't)

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS 38 - Chilled Water Supply C,BP 3CDS*CTV91A (IC) 5.0 C,BP 3CDS*CTV38A (OC) 5.0 39 - Reactor Plant Component C 3CCP*MOV45A (OC) 76.7 Cooling Supply Header 40 - Reactor Plant Component C 3CCP*MOV45B (OC) 220.5 Cooling Supply Header 41 - Reactor Plant Component C 3CCP*MOV49A (OC) 5.0 Cooling Return Header 42 - Reactor Plant Component C 3CCP*MOV49B (OC) 5.0 Cooling Return Header 45 - Chilled Water Return C,BP 3CDS*CTV40B (IC) 38.1 C,BP 3CDS*CTV39B (OC) 57.1 51 - High Pressure Boron C 3SIH*CV8843 (IC) 5.0 Injection to Cold Legs C 3SIH*V5 (IC) 763.1 C 3SIH*MV8801A (OC) 5.0 Note 2 3SIH*MV8801B (OC) 52 - Service Air C,BP 3SAS*V875 (IC) 19.0 C,BP 3SAS*V50 (OC) 19.0 54 - Instrument Air C,BP 31AS*MOV72 (IC) 19.2 Note 2 3IAS*PV15 (OC)

Page 4 of 10

O O O ATTACHMENT 4A (Con't)

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS 56 - Fire Protection C,BP 3FPW*CTV49 (IC) 5.0 Note 2 3FPW*V661 (IC)

C,BP 3FPW*CTV48 (OC) 5.0 Note 2 3FPW*V666 (OC) 59 - Refueling Cavity C 3SFC*V991 (IC) 67.4 Purfication Inlet C 3SFC*V992 (OC) 57.4 60 - Refueling Casity C 3SFC*V990 (IC) 1212.3 Purification Outlet _C 3SFC*V989 (OC) 76.5 62 - Reactor Coolant Loop Fill C 3CHS*V372 (IC) 5.0 C 3CHS*V371 (OC) 5.0 63 - Containment Atmoshere C 3 CMS *MOV24 (IC) 28.5 Monitor Discharge C 3 CMS *CTV23 (OC) 1317.9 70 - Demineralized Water C,BP 3CCP*V886 (IC) 5.0 Supply Inside Containment C,BP 3CCP*V887 (OC) 29.3 72 - Chilled Water Supply C,BP 3CDS*CTV91B (IC) 231.1 C,BP 3CDS*CTV38B (OC) 229.1 85 - Containment Purge Air C,BP 3HVU*CTV33B (IC) 95.7 Note 2 Supply 3HVU*CTV32B (OC)

Page 5 of 10

y ,e x .

On U ATTACHMENT 4A (Con't)

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS 86 - Containment Purge C,BP 3HVU*33A (IC) 382.9 Note 3 Air Exhaust 3HVU*32A (OC) 3HVU*V5 91 - RHS Pumps Suction from C 3RHS*MV8701A (IC) 5.0 Hot Legs C 3RHS*MV8701B (OC) 114.3 Note 2 3RHS*RV8708A (IC) 92 - RHS Pumps Suction From C 3RHS*MV8702B (IC) 5.0 Hot Legs C 3RHS*MV8702A (OC) 5.0 Note 2 3RHS*RV8708B (IC) 93 - RHS Pumps Discharge to C 3SIL*V6 (IC) 1071.53 Cold Legs C 3SIL*CV8890A (IC) 5.0 C 3SIL*V7 (IC) 268.3 C 3SIL*MV8809A(OC) 276.9 94 - RHS Pumps Discharge to C 3SIL*V12 (IC) 1541.3 Cold Legs C 3SIL*CV8890B (IC) 84.7 ,

C 3SIL*V13 (IC) 4400.0 C 3SIL*MV8809B (OC) 344.4 95 - RHS Pumps Discharge to C 3SIL*V26 (IC) 1251.4 Hot Legs C 3SIL*CV8825 (IC) 38.4 C 3SIL*V28 (IC) 378.8 C 3SIL*Mv8840 (OC) 230.5 l

i j

j Page 6 of 10

ATTACHMENT 4A'(Con't)-

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS 96 - Safety Injection Pumps C 3SIL*V29 (IC) 341.3 Discharge to Hot Legs .C 3SIL*V27 (IC) 1251.1 C 3SIH*CV8881 (IC) 94.5 C 3SIH*MV8802A (OC) 170.6 97 - Safety Injection Pumps C 3SIL*V112 (IC) 28.7 Discharge to Hot Legs C 3SIH*CV8824 (IC) 67.0 C 3SIL*V110 (IC) 5.0 C 3SIH*MV8802B (OC) 5.0 98 - Safety Injection Pumps C 3SIH*V22 (IC) 268.3 Discharge to Cold Legs C 3SIH*V28 (IC) 1056.0 C 3SIH*CV8823 (IC) 76.4 C 3SIH*V24 (IC) 4400.0 C 3SIH*V26 (IC) 1541.3 C 3SIH*MV8835 (OC) 1936.0 99 - Safety Injection Test and C 3SIH*CV8871 (IC) 5.0 NE Accumulator Fill Line C 3SIH*CV8964 (OC) 48.1 Note 2 3SIH*CV8888 (OC) 100 - Quench Spray Pumps Discharge C 3QSS*V4 (IC) 265.2 C 3QSS*MOV34A (OC) 262.6 101 - Quench Spray Pumps Discharge C 3QSS*V8 (IC) 418.9 C 3QSS*MOV34B (OC) 192.5 Page 7 of 10

i ATTACHMENT 4A (Con't)'

LOCAL LEAKAGE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKAGE PENETRATION NO. - SYSTEM TEST _ TESTED (NOTE 1) (SCCM) REMARKS 102 - Containment Recire. C 3RSS*MOV23A (OC) 5.0 Pump Suction 103 - Containment Recire. C 3RSS*MOV23C (OC) 306.2 Pump Suction 104 - Containment Recire. C 3RSS*MOV23B (OC) 76.6 Pump Suction 105 - Containment Recire. C 3RSS*MOV23D (OC) 96.0 Pump Suction 107 - Containment Recire. C 3RSS*V3 (IC) 1235.2 Pump Discharge C 3RSS*MOV20D (OC) 767.0 108 - Containment Recire. C 3RSS*V6 (IC) 720.7 Pump Discharge C 3RSS*MOV20B (OC) 5.0 109 - Containment Recire. C 3RSS*V9 (IC) 2310.0 Pump Discharge C -3RSS*MOV20C (OC) 114.8 110 - Containment Recire. C 3RSS*V12 (IC) 67.4 Pump Discharge _C 3RSS*MOV20A (OC) 29.0 111.- DBA Hydrogen Recombiner C 3HCS*V2 (OC) 229.1 Suction C 3HCS*V3 (OC) 228.8 Page 8 of 10

,-s .

A 'k \j ATTACHMENT 4A (Con't)

LOCAL LEAKACE RATE TEST DATA TYPE VALVES / EQUIPMENT LEAKACE PENETRATION NO. - SYSTEM TEST TESTED (NOTE 1) (SCCM) REMARKS 112 - DBA Hydrogen Recombiner C 3HCS*V9 (OC) 5.0 Suction C 3HCS*V10 (OC) 5.0

]

113 - DBA Hydrogen Recombiner C 3HCS*V7 (IC) 1265.4 i Discharge C 3HCS*V6 (OC) 5.0 i

114 - DBA Hydrogen Recombiner C 3HCS*V14 (IC) 85.8 Discharge C 3HCS*V13 (OC) 5.0 115 - Post Accident Sample C 3 SSP *CTV7 (IC) 38.0 C 3 SSP *V13 (OC) 18.9 I

116 - Chilled Water Return C,BP 3CDS*CIV40A (IC) 5.0 C,3P 3CDS*CTV39A (OC) 5.0

120 - Post Accident Sample C 3 SSP *CTV8 (IC) 142.5 Return C 3 SSP *V14 (OC) 47.7

)

121 - Containment Vacuum Pump C 3CVS*MOV25 (IC) 140.1 Jl Discharge C 3CVS*V13 (OC) 5.0 l

l 124 - Nitrogen Supply Header C 3GSN*CTV105 (IC) 76.9 Note 2 1

3CSN*CV8033 (OC)

I l Personnel Air Lock B O-ring 2268.29 i Equipment Hatch B,BP O-ring 5.0 5.0 Equipment Hatch Manway B BP O-ring Fuel Transfer Tube B.BP O-ring 5.0 l Electrical Penetrations B O-ring 414.11 Note 4 i

i Page 9 of 10

ATTAC10ENT 4A (Con't)

LOCAL LEAKAGE RATE TEST DATA NOTES

1. The local leakage rate test program commmenced approximately 6 acnths prior to the Type A test.

2. Combination of two valves.

3. Combination of three valves.

4. All (80) electrical penetrations were tested prior to the performance of the ILRT with a combined total leakage of 414.11 SCCM.

Page 10 of 10