ML17252A642

Reactor Containment Bldg Integrated Leak Rate Test

ML17252A642
Person / Time
Site:	Dresden
Issue date:	10/06/1986
From:	Eenigenburg E COMMONWEALTH EDISON CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
86-088, 86-88, NUDOCS 8610280087
Download: ML17252A642 (100)

Text

I

. Co~f11onAth Edison Drilsoen Nuclear Power Station R.R. #1 Morris, Illinois 60450 Telephone 815/942-2920 October 6, 1986 EDE LTR: 86-:-088 Mr. Harold Denton Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

Reactor Containment Building Integrated Leak Rate Test, Dresde~ Nuclear Power Station Unit 3~ Docket 050-249, DPR-25

Dear Mr. Denton:

Enclosed, please find. the Reactor Containment Building Integrated Leak Rate Test (ILRT) report for* Dresden Nuclear Power Station Unit 3, conducted July 24~26, 1986.

This report is submit~ed to you in accor-dance with lOCF~ 50, Appendix J,Section V.B.3.

Sincerely,.

er Dresden Nuclear\\Power Station

~~P;E.: ML:: hj b

• Enclosure cc:

J. Keppler (U.S. NRC R III)

M. Ring (U.S. NRC R III)

L. McGregor (U.S. NRC R III)

L. Mariani (Am. Nuc. Ins.).

B. Stephenson

• G. Diederich N. Kalivianakis P. LeBlond J. Wojnarowski R. Bax J. Glover J. Achterberg M. Leahy E. Mendenhall File/NRC File/T.S. File (1600)

File/Numerical

Dresden Unit 3 Reactor Containment Building Integrated. Leak Rate Test I

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July 24-26, 1986

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Abstract The 1986 Dresden Unit 3 primary containment.Integrated Leak Rate Rest (ILRT) was performed in accordance with the requirements of 10CFR 50, Appendix J, Section V.B.3, from July 24 to July 26, 1986.

A "short duration" (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) test was conducted using the me~hods outlined in Bechtel Topical Report BN-TOP-1, Revision 1, dated November 1, 1972.

Total containment leakage upon successful completion of the ILRT was.5874 weight %/day, including local leak rate test results for several systems that were not vented or drained during the ILRT.

The associated 95% upper confi-dence level leak rate was.7407 weight %/day.

A supplemeptal.induced phase verification test was performed in order to prove the accuracy of the computerized measurement system.

The difference between the indu~ed phase cal*culated leak rate and the sum of the measured pha.se calculated leak rate and the superimposed leak rate was 0.0785 weight %/day, which was well below the Technical Specification 4.7.A.2.d.(1). accuracy requirement of 0.4 weight

%/day.

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DRESDEN UNIT 3 1986 ILRT Abstract A.

Introduction A. l Purpose B.

c.

A.2 Test Requirements

.A.3 Summary of Results Test B. l B.2 B.3 B.4 Test C.l C.2 C.3 C.4 C.5 Method Basic Technique Supplementai Verification Test Linear Regression Analysis Short Duration Test Instrumentation and Calibration Types of Sensors Used ILRT Console Data Acquisition System Instrument Calibration Instrument Error Analysis - Application D.

Containment Representation D.l Structural Data D.2 Containment Survey D.3 Instrument Placement D.4 Pressurizat1on System E.

Calculations Performed E.l Volume Weighting Factors E.2 Data Reduction E.3 Measured Leak Rate E.4 Calculated Leak Rate (Least Squares Fit)

E.5 95% Confidence Limits E.6 Computer Program E.7 Leak Rate Compensation for Non-Vented Penetrations F.

Containment Pressurization F.l Preparation F.2 Containment Instrumentation F.3 ILRT Log Entries F.4 Final Calculated Leak Rate G.

Supplemental Verification Test (Induced Phase)

G.l Purpose of Test G.2 Magnitude of Induced Leakage H.

Test Evaluation Appendix A:

Appendix B:

Appendix C:

Type "A" Test Instrument Accuracy Error Analysis Type "A" Test Data Type "B" and "C" Test Results 1

2 3

8 18 26 34 35

A.

INTRODUCTION A.l Purpose of Test The purpose of the Dresden Unit 3 prtmary containment Integrated Leak Rate Test was to measure the primary containment leak rate while at a test pressure equal to that postulated to occur during loss-of-coolant accident (LOCA) conditions.

The system line-ups for the ILRT.are intended to provide the normal isolations that are available under opera-tion to prevent primary containment leakage should such conditions develop.

This report is provided in order to give a detai1ed description o! the test method and the final results.

These results are reported in accordance with 10CFR 50, Appendix J, "Primary Containment Leakage Testing for Water Cooled Power Reactors".

A.2 Test Requirements All leak rate tests performed during the recent refueling outage were done in accordance with schedules and acceptance criteria established by 10CFR 50, Appendix J, American National Standard ANSI N45.4 1972, and by the Dresden Unit 3 Technical Specifications.

The maximum acceptable leak rates, as stated ill: the Technical Specifications are as followi:

Type, "A" test. (ILR"I; @ gJZeater than 48 psig)

I

'~

a.

Measured Phase. :

1. : L ~>wei;g~t %/day.

(La) m~xiin~ni* 'allowable

~ :

/~.

~ >.

f.

!~

.... 2*.

• i. 2 weight. "%/day: *.{Lt}. maximum* oper'a'tional.

\\:.....~.

b.

Supplemental Verification Phase

+/- 0.4 weight %/day (0.25 La)

Type "B" and "C" 't;est§*. (Local Leak Rate Tests)*

a.

Testable penetrations and isolation* valves must have a total.

combined leakage of less than or equal to 60 percent of La except for main steam isolation valves.

b.

Any one air lock.must have a leakage rate of less thah or equal to 3.75 percent of La when pressurized to 10 psig.

c.

Any one main steam isolation valve must have a leakage of less than or equal to 11.5 scfm when pressurized to 25 psig.

r~:.. The Type "A".*test ~~as cond.uct:e'<f* Tn_~!l.cc_ordarite *wfth Tec:q.n;i:c.cil,,?.;.ta(f- _S.l1rveil-

~, ~ ~la'rice*

• * Proced'Jt:e> PTS. 160_0.::..7.* ~Rev. ; ~:.* -*~ 'This"; pr'oc,e_dtite. incorI!.f>.ra:t~s*: au - O~: t;he

~ -

--~'.test-req4irements.

• *.f>...3 ~*:surtnnar.y *o.f Res'ults The* Dres.deri un'it 3 primary.. cori't?i!l:mell:t )eak rate* wa:s fouiig :ta *be O. 5034

• w~ight/%~~,d~~ _*(br :3'.3.i: 3\\s~*fn) 'at:: a -test :"press,uJ::e* of 48 ~p~-ig_ mintmum.:.. T~i't=i' ":~'

• total calculated leak rate includes the 12-hour phase Type A calculated test result and several Type C test results for process lines not drained and vented as required by 10CFR 50, Appendix J.

The associated upper 95%

confidence limit was 0.6567 weight %/day *.

The supplemental test result was 2.1849 *weight %/day.

This result was compared with the sum of the 12-hour phase result of 0.5034 weight %/day and an induced leakage of 1.76 weight %/day.

B.

TEST METHOD B.l Basic Technique The Absolute Method was used to. *perform the Type A test.

The Absolute Method uses the ideal gas law to calculate changes in* dry air mass as a function of pressure and temperature.

Compensation for water vapor pres-*

sure is taken into account when the dry air mass within the containment is calculated.

Leakage of mass (which is assumed to be constant) from the containment during the Type A test interval can be determined by establish-ing the rate of mass loss.

B.2 Supplemental Verification Test The ~erification test (induced leakage) was performed by intentionally inducing a c_ontrolled leak of magnitude approximately equal to the maximum ailowable leakage (110% of La)~ This induced leak was superimpqsed on th~

previously determined leak rate.

The d~gree of detectability ~oJ.~j:}ie:..

combined leakage pr:ovided a basis for resolving any uncertainties associated with the 12-hour phase of the test..

B.3 Linear Regression Analysis Since it is assumed that the* leak rate is constant during the te.sting period, a plot of the measured contained dr:y air mass versus time would ideally yield a straight line with a negative slope (assuming a non-zero leak rate).

Obviously*, sampling techniques and test conditions are not per:Eect and consequently the measured valu~s will deviate from the ideal straight line situation *

. A "least square" statistical analysis was performed to establish a regr~s sion line for the mass versus time parameters after each set of data was obtained.

The slope of the regtession line is called the statistically averaged leak rate.

It was this quantity that was co~pared to the Technic~l Spec~fication l_imit La.

Associate~ with 'the ~tatistical leak rate is the upper 95% confidence

• leak rate.

The c.alculation of. this upper: limit is. based on the standard deviation of ~he regression lines 'and :the one-'-sid.ed Student~ s T-Distribution. func~ion.

A. *procedural requirement.spec,ified that the 95%

confidence limit was to b_e less than }5% of the Technical Specification limit La**

• Both the regression line and the associated confidence limit were calcu-lated after each set of data was obtained.

B.4 Short Duration Test Although in the past it has been customary to conduct Primary Containment Leak Rate Tests for a duration of at least 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at test pressure, this test was conducted for a shorter duration following the methods out-lined in Bechtel Topical Report BN-TOP-1, Revision 1, November, 1972.

The BN-TOP-1 method has been approved by the NRC.

A measured test phase of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> was utilized.

Also, the Supplemental Verification Test was conducted for a period of one-half that of the measured phase, or approximately 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

C.

TEST INSTRUMENTATION AND CALIBRATION C.l Types of Sensors Used Two types of sensors were placed inside of the primary containment during.

the test.

The first type of sensor used was a resistance temperature

.device (RTD) designed to measure dry bulb temperature.

The RTD detects a change in temperature through varying amounts of resistance within a plati-num wire.

The second type of sensor used was designed to measure dewpoint, using a Lithium chloride detector and heating element in conjun~tion with an internal RTD.. *There, were* 32 RTD's and~lO dewcells installed for the ILRT. **At* the start Of the test,. 28 RTD is and 9 dewcells were in use for the test. *No inst*r~ment.'s were {cfe_:(ete_d_dµr~pg' the::ies1: ;'

• C.2 ILRT*Console All the raw test data was digitally displayed on the Volumetrics Console 14627.

LED displays enabled the console operator to visually monitor the raw data as it appeared* at* regu*lar.10-minute intervals or -manually select specific channels for specific data.

This console also printed the data at each scan interval.

The test calculations were performed by an on-site Prime computer system, which received data from the Volumetrics console via permanent cables ins~alled. for this purpose.

The data was ma~ually verified on display terminals in the Technical Support Center before being released for calcu-lations, disk storage and printing.

In addition to the display electronics enclosed in the console, there were 2 *precision pressure.. gages and* 2 clocks.

The.clocks and pressµre gages were.redundant features included within the console to insure *reliability.

. A diagram of the ILRT console and related ele.ctronics is shown in Figure C.2.a.

C.3 Data Acquisition System

.The ILRT Volumetric Console, sensors and multiplexer comprise the ILRT Data Acquisition System which was used to perform.the Type A test qt D_resden.

A description of the ILRT 'cphsole. and':'*s*e.!1_s_9rs* was. -given.-in*

Sections C~l and C.2.

The system also included a multiplexer, which was located within the containment throughout the test.

29 PRIME*

COMPUTER MULTIPLEXER 10 *-----.,.:-.--

DATA ACQUISITION CONSOLE RTD's DEWCELLS REACTOR WATER LEVEL ILRT CONSOLE AND INPUT SYSTEMS FIGURE C.2.a AMBIENT RTD 1 *AMBIENT.

PRESSURE

• w'.

RTD

.. 30A RTD

. 30B I

• 'In order to minimize the number of conductors penetrating the primary containment, the Data Acquisition System instrumentation was subdivided into two major parts.

The multiplexer unit was the focal point for all the RTD' s and the dewcells... This subsystem consisted of the. solid state signal conditioning bridge circuit boards that are used to calibrate the system and the dual redundant electronic scanners which feed the sensor signal through the primary containment to the console outside.

These.components, seen as a whole system, provide a full automatic multi-point data measuring and processing system capable of measuring absolute pressure, dewpoint temperature, dry bulb temperature and test duration.

During the supplemental test, it also monitored the induced leak rate.

(See Fig~re C.3.a for a block diagram of the system interconnections.)

C.4 Instrument Calibration A major portion of the time spent in preparation for the Unit 2 ILRT wa~

devoted to instrument calibration.

All RTD's were calibrated to within

+/- l.0°F of actual temperature by using a water bath and a RTD standard which is traceable to the National Bureau of Standards (NBS).

The dewcells were calibrated to within +/- 5.0°F of actual temperature by using a standard RTD (traceable to NBS) and a water bath which provided various dewpoints.

The prec1s1on pre_ssure gages were calibrated to within +/- 0.015 ps_ig of actual pressure*using a portable standard traceable to NBS.*

The flowmeter used for the induced leakage portion of the ILRT was cali-brated using.a transfer*standarq which was traceable to NBS and accurate to within 1% of ~ull scale.

Table C.4.a shows the specifications for the-instr-umentation utilized in the Type A test.

All of the instruments were calibrated prior to use, as required by ANSI/ ANS-56. 8;_1981.

The quantity of sensors used was based on the cohtaininent s;ize and system error analysis *.

Throughout* the test, ambient atmospheric conditions were monitored.

The

• instrumentation used for this -monitoring was of sufficient accuracy to determine atmbspheric changes for correlation with test.data, had that been necessary.

~

C.5 Instruinentatibil. Error Analysis - Applicatio*n The instrumentation error is used only to illustrate the system's capa-bility.to measure the required parameters that are necessary for calculation of the primary containment leak rate.

The instrumentation

29,RTD's

. 29.RTD SIGNAL CONDITIONERS..

SCANNER 10 DEWCELL SIGNAL

.CONDITIONERS 10.DEWCELLS PPG 1

.:r5tGITAL

• DISPLAY

'ENCODER PPG 2 DIGITAL DISPLAY ENCODER I *.------JI PRIME COMPUTER DATA*~-.: **

--~-----------'--------'*-.:i*:'~'.Acqu1sitf6N*-1-_~.....,.*:,...~--------*-..;.._.~----~

mu_1:*-< :

__ '.*.~ 1--.-~:-***-----------1 * -~~N~~~A I *-. -. -. -. -.

r-------------'9,

. **:REACTOR

. WATER LEVEL r.~

... -"-=-tr~~,'

...,AMB 'PRESS SIGNAL

,CONDITIONER AMB PRESS SENSOR -

AMB.. TEMP

SIGNAL, CONDITIONER.

':.._. J AMB TEMP RTD ILRT SYSTEM BLOCK DIAGRAM Figure C.3.a RTD ll30A & B SIGNAL CONDITIONERS RTD 1130A & B I

°'

I

Table C.4.a INSTRUMENT QUALITY/USAGE RANGE Precision Pressure Gage 2 - Containment Pressure 0-100 psia RTD 28 - Containment Temp.

50-200°F Dewcell 9 - Containment Dewpoint 140°F Flow Meter 1 - Induced Leak Rate 2-20 scfm Ambient Temp. RTD 1

Ambient Temp.

50-200°F Ambient Pressure 1 - Ambient Pressure 0-20 psia Humidigy 1 - Relative Humidity 0-100% R.H.

ACCURACY

+/- o*. 015 psia

+/- 0.96°F

+/- 4.12°F

+/- 0. 2 scfm REPEATABILITY

+/- 0.001 psia

+/- 0.01°F

+/- O.Ol°F

+/- 0.02 scfm I

-..J I

error is always present in the-data and is inco.rpc:i'rated in the 95%

confidence limit in the form of data scatter.

Procedur'es required that the error due to accuracy and r~peatability be less than 0.25 La (0.4 weight %/day).

D.

CONTAINMENT REPRESENTATION D.l Structural Data The Unit 3 primary containment provides a multibarrier pressure suppres-sion containment employing containment-in-depth principles in design.

The containment systems are composed of a primary containment and the pressure suppression system, which when taken together enclosed a total free air space of 288966 ft 3

• The primary containment consists of a drywell, which encloses a reactor vessel, a pressure suppression chamber which stores a large volume of water, a connecting vent system between the dryw.ell and the water pool, isolation valves, containment cooling. systems, and other service equipment. *(See Figure D. 2. a.. )

The performance objectives of the primary containment system are:

1) to provide* a barrier *.which* in th.e.unlikely event of a loss-of-coolant accident, which* will.control* the release of fission products to the secondary contain-ment, and 2) to rapidly reduce the pressure in the containment resulting from the loss-of-coolant accident.

In oider to meet these objectives, the containment was* designed to withstand a design pressure of 62 psig with a leak rate. of 0.5 weight %/day.

To as~ure that the containment could structurally meet these criteria, the drywell was designed using a stee.l pressure vessel with a spherical lower portion and a cylindrical upper portion.

(See Figure D.2.a.)

The steel head and shell of the.drywell are fabricated of SA-212 GRB plate manufactured to A-300 requirements.

The top

.. head closure_ is made,.with a double. tongue and grove seal,. whic;h. will permit periodi~ ch~cks for tightness without pressurizing.the eniire vessel. - The drywell is enclosed in reinforced co~crete for shielding purposes.and to provide additional resistance to deformation a11d buckling of the drywell

• over areas where concrete backs up the steel shell.

An integral par*t of. the containment is the pressure suppression chamber, which is also pressurized during the ILRT.

The pressure suppression

.. chamber is a st.eel pressure vessel in th,e __,shape of a torus below and encirc~~*

ling the* drywell which containsrri2r;2-o?; ft:.,01-~-~~:t:*e( itf its'.7W9.:_ft;-;_, iiiaJB:}~

diameter.

The torus free air volume is 118529 ft 3

• D.2 Containment Survey In order to establish the containment temperature tendencies for regional variations, an area temperature survey was performed.

This survey complied with ANSI/ANS 56.8-1981 and was performed by Technical Staff personnel *. The sensor locations are indicated in Tabie D.2.a (refer to Figure D.2.a for an idealized view of the containment structure and the zoning configuration used.)

• D.3. Instrumentation Placement Figures D.3.a through D.3.g indicate exactly where the RTD's and dewcells were placed within the primary containment.

The dewcell placement is indi-

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• f ss.. -2**. to 589*-111 517 1-011 to 551*-211 Subvolume I. 589*-111 to

. Subvohne 2. Open spac~ between reactor and blologlcal 1hlold Subvoltne 6.

• 515 1-611 to 52$ 1-1t**

Subvolumo 7~ Open space below reactor

. Subvolume 8.

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.*UNIT 3.

• PRESSURE SUPPRE$SION COtffAINHENT SVSTEH

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• Fl GURE D. 2

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1 TABLE D.2.a DRESDEN 0-3 n.RI' SENSOR LJ:CATICNS

~

Sensor Type I

• D. Numl::er Subvolune 7.one Elevation Azilluth N I R1'D R1 1

595' 4"

60° R1'D R2 1

592~ 4".

240° DDl CELL 01 1

594' 225° I,

R1'D R3 2

554' 6" 340°

~* t R1'D R4 2

561 160° R1'D RS 3

573' 270°'

r R1'D R6 3

575 30°

>1'

~ -.

R1'D R7 3

574 150° DE.W CELL 02

• 3 571' 6" 80°

~-

Rl'D RB 4

545 1 9"

320° J;

RI'D R9 4

546' 9"

90°

~

Rl'D RlO 4

J 544' 8"

220°

~*

DEl'l CELL 03 4

544 1 220° RI'D Rll 5

533' ao Rl'D Rl2 5

531' 180° Rl'D Rl3 5

531*'

120°.

l-R1'D Rl4

.5 530' 270° DBi CELL-04 5

529' 270° L

DEW CELL 05 5

533' 90° J'

• ~ Rl'D Rl5 6

521' 180° R1'D Rl6 6

520.'.

60° RI'D R.17 6

520 t. 6"

. 30:0°

}

DE.W CELL 06 6

. 521 t 10" 180° Rl'D Rl8 7

509' 4"

180°

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RI'D 120.

8 509' 10" 230° R1'D R2l 8

509' 10" 140° Rl'D l R22 8

. 510' 4"

50° J.

RI'D R23 8

510' 4"

320° DEl'l.CELL 07 8

509 1 4"

50° DE.W CELL

08.

8 509' 10"..

230° RI'D R24 9

503' 7"

. 300°.

RI'D,

R25 9

503' 8"

240° Rl'D R26

. *9 503' 10" 120° Rl'D R27.

9 503' S"

60° Rl'D R28 9

503' 8".

180° Rl'D R29 9

503' 8" oo DE.W CELL 09 9

502' 1" 300° DE.W CELL 010 9

502' 10" 120° RI'D R30B 10 Ia::ated.in Shutdown COOling - Loop B

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FIGURE D.3.a 1403-1011 1404-10"

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-.. *.*.i,-..*; ; *..-... * *..,,_,...* ~.;... ;~; *.,.~

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EUVATION 509 I*

RID 19

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bryweJ 1 Equip~

men~ Drain S

• FIGURE 0.3.f

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.,..---~J

..._ --- ON!l: 3 toms

~.;,...

~ :**..

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Suppression Otamber R i nq

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Header 1SO1 *2.4" El. 483 I

**~.,.......

• LPCI Pumps 0

0

• cated by the initial D, and the RTD placement is indicated by the initial R.

To avoid local temperature variations, all RTD's and dewcells were placed at least three fee~ away from any pipe, wall, pump, motor, etc.

All sensors were placed in the containment immediately before the ILRT to minimize the possibility of sensor wire or sensor damage due to maintenance and cleanup work.being performed while the containment was open.

A special effort was made to place two RTD's in that subvolume between the reactor and the biological shield.

See Figure D.3.b.

This was done to minimize the transients in test data caused by ~T change in that subvolume due to changes in reactor temperature.

Due to the impra.cticality of installing temperature and humidity sensors inside the vessel (Subvolume 10), several assumptions were made concerning the air space within.

The reactor vessel air space was _assumed to be satu-rated and at an equilibrium temperature with the water.

To measure the reactor water temperature, an ~TD was placed in the shutdown cooling loop between the shutdown cooling pump and the heat exchanger.

This temperature was then used as the drybulb and dewpoint temperature for subvolume 10.

D.4 Pressurization System Primary containment pres~urization was accomplished with a 3000 scfm electric compressor connected to a 4" pressurization line.

The air compressor was located outside the* Reactor Building.

Refer *to Figure D.4.a for a plan view.

E.

CALCULATIONS PERFORMED E.l Volume Weighting Factors

• Due to the size and shape of the primary containment, a mathematical model was developed to account for'.the effects of temperature stratification and locai'*temperature variations.

The 'containment' volume wa? theoretically divided -into ten subvolumes with weighting factors assigned to each.

(The value of the weighting factor is equivalent to the fractional part of the total containment volume occ.upied by the associated'.subvolume.)

The volumes of the larger pieces of.equipment were taken into account when calculating the subvolumes.*. (See Figure D.2.a for a diagram of the idealized containment and zoning configuration used.)

Table E.l.a lists the subvolume 'weighting factors associated with each zone.

E.2. Data Reduction Before the ideal gas law could be applied for obtaining the contained dry air mass, the raw data had to be reduced to a single dry air pressure and temperature.

The total containment absolute pressure was determined by arithmetically averaging the two precision gauges.

The average containment temperature and dewpoint were obt~ined by utilizing the same application of the volume weighting factors.

Like sensors within a subvolume were arith-

UNIT 3 PRIMARY CONTAINMENT UNIT 3 SECONDARY CONTAINMENT

.ELECTRIC:,AIR

.. *coMPRESSOR

[

ELECTRIC AIR COMPRESSOR

-*----------~*---*.

CONTAINMENT PRESSURIZATION SYSTEM -

FIGURE D.4.a 4" Pipe

":'20~*

I*-:*.'/'-

Table E.l.a Temperature and Humidity ~eighting Factors SUB VOLUME VOLUME (FT WEIGHTING FACTOR 11373 0.03936 2

3081 0.01066 3

20281 0.07018 4

23043 0.07974 5

30819 0.10665 6

26363 0.09123 7

7226 0.02501 8

41828 0.14475 9

118529 0.41018 10 6423 0.02223

• metically averaged to determine the mean atmospheric conditions for the subvolume.

Any subvolume void of a sensor type was assumed to have the same average value as the next subvolume in sequence.

The sum. *of :the products of the subvolume averages and respective weighting factors, yielded the average containment temperature and dewpoint.

The dewpoint was then converted to vapor pressure and subtracted from the average total containment pressure, yielding absolute dry air pressure.

The following mathematical expressions summarize the data reduction process.

Average Subvolume Temperature and Dewpoint (All operable RTD's in jth subvolume) oF Tj =

Number of operable RTD's.in the jth subvolume D.P.j (All o.p.erable dewcells in.the.j th.subvolume)

Number of operable dewcells in jth ptibvolume where Tj

= average temperature of the jth subvolume D.P.j = average dewpoint of the jth subvolume Primary Containment Temperature and Dry Air Pressure NVOL T

undefined, then OF L

(VFj)

(Tj)

°F j=l

i:f Tj Tj Tj Tj T (j + 1) for i.s j ~,(NVOL-2)

D.P.

NVOL L

(VFj)

(D.P.j) j=l-EXPON,::: -_ X(A +*. ZX + 'i:X3 )

(D. p. ( °K) 0 + DX)'

OF

• pv* -~ (218A67)

(1'4~.696). PSI (EXPON ln 10) p Pt Pv PSIA T(j - 1) for j NVOL -

1 estimate for j NVOL if D.P.j = undefined, then D.P.j*= D.P(j*+ i) for 1 ~- j ~ (NVOL-2)

D.P.j = D.P(j -

1) for j = NVOL-1 D.P.j = estimate, for j = NVOL Q.P.(~k) =!273~16 + D.P.(°F) ~.*32

. '} * '!.

1. 8 x

A z

c D

0 64].~7~-* D.P-( K) 3.2437814 5.86826 x

1. 1702379

~-* 1878462 10:.:3 x lo-8 x 10-3 W

(28.97)

(144)

(P). ((total volume -

(level -50)

(28.635))__Lbs.

1545.33 (T + 459.69) where NVOL = -number of primary containment subvolumes NFj = volume wrighting factor of the j th subvolume'.. \\

T = volume weighted containment temperature D.P. = volume weighted containment dewpoint X, A, Z, C, D, EXPON = dewpoint to vapor pressure conversion constants and coefficients

-~.....

~.... ----

NOTE:

E.3 Pv = volume weighted containment vapor pressure Pt = total absolute containment pressure P = contained dry air absolute pressure W = contained dry air mass Level = reactor water level The subvolume numbering sequence is from the top to the bottom of the containment.

Measured Leak Rate (Total Time)

From BN-TOP-1 Rev. 1, Section 4.5, the following equation is given for the measured leak rate using the total time procedure:

2400 (1 - ToPi)

(% per day)

H T.P 1 0 where Mi = measured leak rate in weight % per day for the ith data point.

H time interval, in hours, between measurements.

T0, Ti = mean absolute temperature, 0 R, of the containment atmos-phere at the beginning and the end of test interval (H),

respectively.

mean total absolute pressure, psia, of the containment atmosphere at the beginning and end of the test interval (H), respectively.

Using the following relationship derived in ANSI N45.4 *- 1972 Appendix B given below:

w 0

w 0

W.

1 where W, W.

0 1

1 - T P.

0 1

T p i

0 dry air mass "of the containment at the beginning of the test and data point i, respectively.

And substituting in the calculation of the containment dry air mass that corrects for a change in reactor water level gives the following expres-sion for the measured leakage: '

M.

1 2400 H

ToPi (volume - LEVELi -

50) (28.635)))

(1 -

T.P (volume - LEVEL

50) (28.635))

1 0

0 where LEVEL, LEVEL.

0 1

reactor water level in inches at beginning of the test and the data point i, respectively.

E.4 Calculated Leak R~te (Least Squares Fit)

The method of "Least Squares" is a statistical procedure for finding the best fitting regression line for a set of measured data.

The criterion

• for the best fitting line to a set of data points is that the sum of the squares of the deviations of the observed points from the line must be a minimum.

When this criterion is met, a unique best fitting line is obtained based on all of the data points in the ILRT.

The value of the

• leak rate based on the regression is called the statistically average leak rate.

Since it is assumed that the leak rate is constant during the testing period, a plot of the measured contained dry air mass versus time would ideally yield a straight line with a negative slope (assuming a non-zero leak rate).

Obviously, sampling techniques and test conditions are not perfect and consequently the measured values will deviate from the ideal straight line situation.

Based on this statistical process, the calculated leak rate is obtained from the equation:

1. = A+ B x *t.

i i

where tf = time in hours since the beginning of the test to the ith data setpoint.

The values of the constants A and B such that the regression line is best fitting to the ILRT data are B

[ nL( t. )(M.) ] -

[ {Lt.) (Di.) ]

. i i

i i

A = LM. -

B~ ti i

i n

In order to reduce the round-off error in the above calculations, the equations are rearranged such that:

A (Dii) {Lti 2) -

{Lti) CLtiMi) nI,t. 2 -

(Et.) 2 i

i E.5 95% Confidence Limits To determine the value of the confidence limits the following statistical information is required; the variance, standard deviation, and students' T-distribution.

g2 = ~

n-2 where SSQ S2 variance S

standard deviation based (n-2) degrees of freedom.

The standard deviation has more practical significance since computing the standard deviation returns the measure of variability to the original units of measurement.

Additionally, it can be shown that given a normal distribution of measurements, approximately 95% of the measurements will fall within two standard deviations of the mean.

The number of standard deviations either side of the regression line which establish a 95% confidence interval are more accurately determined using a statistical table called a "Table of Percentage Points of the T-Distribution" and provide increased confidence in outcomes for small and large sample sizes.

The table of T-Distribution has been formulized for use by the computer program as follows:

TD 1.95996 + 2.37226 + 2.8225 (n-2)

(n-2) 2 where TD value of T-Distribution for the 95% confidence limit and (n-2) degrees of freedom.

n = number of data points including the ith data point.

The application of the additional factor to the variance formula yields:

6 2 = s2 r1 +..!. +

n l!(t..,,; t) 2

l.

t 2

s [ 1 +..!. + ( p - t) J\\:

n

• E<t. - t) 2

,J.

where t p time after start of test "t-""' Et.

l.

n UCL L. + TD x o

l.

E.6 Computer Program In order to e~pedite the data reduction and statistical computations, the Station Prime computer system was used.

A telephone connection to the.

Prime system at the Corporate Offices was also available had the Station computers become unavailable at any time during the test.

Data was recorded and analyzed at 10 minute intervals.

• The raw test data was printed by the Volumetrics Console, located just outside the drywell.

Each data set was also automatically transferred over cables from the console to the Computer Room, where it was checked on a display terminal against the console printouts before being released for disk storage, calculations, and printing.

Key test parameters were plotted on a color-graphics display screen as the test progressed.

Hard copies of these graphs were also plotted by the computer system.

The computer program was written by off-site Commonwealth Edison Computer Systems personnel.

Its logic was protected by codes intended to prevent unauthorized access.

The program was reviewed and approved at the Station by the same process used for all test procedures and surveillances prior to their use.

E.7 Leak Rate Compensation for Non-Vented Penetrations The actual calculated result of the Type 11A" ILRT as performed was.5034 weight %/day.

The test was performed with the following penetrations not drained and vented.

Included with each penetration listed is the leakage as determined by Type C local leak rate testing.

SYSTEM.DESCRIPTION~

"A11 Rx Feedwater 11B11 Rx Feedwater Shutdown Cooling Standby Liquid Control Rx H2 0 Cleanup Isolation Condenser 11A11 Core Spray Injection 11B" Core Spray Injection 11A11 LPCI llB II LPCI 11A11 LPCI "B II LPCI 11A11 LPCI 11B11 LPCI 11A11 LPCI (Containment Spray)

"B" LPCI (Containment Spray)

HPCI Condensate Return VALVE NUMBERS 229.:..:57A*.& 220...:5sA..

2*20-57A:;&. 220":'62A.

2foi5iB:* &, 220:..;*5s:B:

22o~57B ;,& 22*0..:.6Z'B 1001...,.lA, lB, 2A, 2B

& *2G 11'01...:.1 & 'U;Ol-15 1-1\\01-1 &.* 1101.::.16 ~-

1-2.01_-L; lA, 2, 3:

• lJ.01-3' &" ;1301--4*.

1°402-4A SA 25A *

~. ' .

& 36A.

1402-24A & 25A 14Qi-_4.B,.8B, 25B,

&'.' 36:8*'_ ~..

1402-24:8'& 25B 1501-lSA & 19A lso1-1sJ3* & 19B -.

15'Dl.:...26A &. 15Ql,.,.J8A. **

1501-20B __ & 1:so1...,.3si3*

lsb1-2iA.

• 26.A... & :

~,.

100f-:-5A::

• L'fo'f-2~J\\.\\.1';?01..::?6A'.:

1501-22B***~6B &

),,,

1001:-5B.

1501-25B & "15.0l-26B 1501-27A & 1501-28A 1501-27B & 1501-28B 2301-45 & 2391-74 LEAK RATE SCFH 0.00 0.7178 3.3174 6.01 8. 655

1. 72 0.1078

o. 911 0.310 2.267

'6; 2°96 0.970 0.647 7.998 2.: 3 IO 1.137 0.398 L281 WT. %/DAY 0.00

0. 001.4 0.0006 0.01-17 0. 0168 0.0033 0.0002 0.0018 0.0006 0~0044 0.-0006.

0. 00188 0.00126 0.0156

0. 00.45 0.0022

0. 00077 0.,00~49

• LEAK RATE SYSTEM DESCRIPTION VALVE NUMBERS SCFH WT. %/DAY Primary Sample Drywell CAM 220-44 & 45 9:207A & 9207B*

9208A & 9208B*

0.017

1. 65 2.306 Total 43.026 0.000033*

0.0032 0.004-5 0.0837

• LLRT results for these lines are included because these lines were used during the ILRT for test instrumentation.

The total containment leak rate, including local leak rate test results for. unvented systems as shown in the preceding list, is 0. 5784 weight

%/day.

The associated 95% upper confidence limit is 0.7407 weight %/day.

It should be noted that the CRD cooling water return penetration*; *which was previously reported in the above table, was removed from Unit-3 as a part of this outage.

F.

CONTAINMENT PRESSURIZATION F.l Preparation The following major events wer~ completed prior to containment pressuriza-tion as required by 10CFR Part 50, Appendix J, and ANSI/ANS 56.8-1981.

1.

Satisfactory completion of all Type B and C Leak Rate tests.

2.

Prim_ary containment *temperature survey.

3.

Cali:b.ration qf all instrumeritation.

4.

I;nstrumentatibn, error analysis calculation.

5.

Visual contai~ment inspection.*

6.

Venting of the reactor vessel to the primary containment atmosphere.

Training was provided to all technical personnel involved in the ILRT.

The 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> of training was designed to familiarize personnel with the test instrumentation, computer program, and necessary ~cheduling for the successful completion of the 1986 ILRT *

. -T,wo 3000:- scfig~ elect/~c compre.s_s6rs :w-~re "'bro1,1g!)t o_n site tp supply2cCl~an air to the primary conta-inment through a 4-inch pipe tied into the LPCI system.

These compressors not only served as a source of.oil free air but enabled Dresden personnel to realize 48 psig containment pressure in a minimal amount of time.

F.2 Containment Instrumentation ILRT sensors were placed within the containment shortly before the test.

All sensors were kept at a distance of three feet or farther from any pump, motor, or piece of piping.

This was done so local temperature variations would not overly influence the.real average subvolume tempera-ture recorded by the sensor in that subvolume.

In preparation for the test, special care was taken to keep all sensors out of any airflow which might be caused by the compressor during pres-surization.

• F.3 ILRT-Log Entries The following is a list of significant events taken from the ILRT Log:

DATE TIME 1830 1920 1930 1945 1955 1955 2000 2030 2050 2110 2115 2207 2250 2255 2300 2301 2317 2-329 2330 2325 Late Entry 07-25-86 1700 ILRT LOG Log initiated per DTS 1600-7 Rev. 8, for 1986 Unit 3 ILRT.

Compressor started, not loaded.

Compressors aligned to M03-1501-28B to pressurize it.

M03-1501-28B opened and pressurizing drywell.

1.0 psi -

28B stopped.

Computer "Mover PH" stopped.

M. Moy to start night.

Equalized torus/drywell; Lizalek to secure open 2 sets of vacuum breakers.

McCabe/Sitts still-on torus.-

Two sets (4) of vacuum breakers gagged open.

LPCI 28B valved opened; commenced loading compressor.

Drywell pressure at 6 lbs.

Drywell pressure at 14 lbs.

Drywell pressure at 14 lbs.

Drywell pressure at 15 lbs.

Compressor unloaded; LPCI 28B closed.

B. McCabe found leaking LPCI line.7/25/86 downstream of 22B valve (3-1501-22B (#1500-16B) on torus.

U-3 foreman notified of air leak (Hussein Ata) and dis-patched to torus.

Awaiting status.

Drywell pressure holding at 15 lbs.

Drywell pressure holding at 15 lbs.

On 7-24-86, at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br />, Technical Staff personnel (B. McCabe) discovered leakage coming from a l/4~inch diameter open threaded hole located on the sleeve of piping penetration X-116B.

The leak was discovered during the pressurization phase of the test with the air compressor running and a drywell pressure of approximately 15 psig.

The pipe plug was replaced.

Pressurization* continued and the test was started.

DATE 07-24-86 07-25-86 TIME 1700 (Cont'd) 2345 0015 0030 0045 0050 0~05 0120 ILRT LOG As part of the recirculation pipe replacement work performed during the refueling outage, the line run-ning through penetration X-116B (3-1506-16A) was completely removed and replaced with new piping.

During the installation of the new pipe, contractors performing the work needed to remove a pipe plug installed in the threaded hole that had been found leaking.

The pipe plug had to be removed in order to install the new pipe.

Station Construction Engineer, M. Hogan, gave permission to remove the plug provided the plug was re-installed after the pipe replacement was completed.

The pipe replacement was completed but the plug was not replaced.

The amount of leakage found could not be determined.

The pipe penetration cannot be leak rate tested by Type B or Type C testing methods per 10CFR 50 Appendix J.

The inside of the penetration is not sealed and is open directly to drywell atmosphere.

Leakage of the penetration can only be verified by Type A testing.

A meeting was held between J. Achterberg (Technical Staff Supervisor), J. Kotowski (Unit 3 Operating Engineer), R. Flessner (Superintendent Technical Services), J. Glover, M. Leahy (ILRT Coordinator) and P. LeBlond (Nuclear Licensing Administrator).

As a result of the meeting, it was decided that the replace-ment of the plug should be considered a re-alignment (such as a valve re-alignment) and was not considered a repair or adjustment as described in 10CFR Appendix J.

Therefore, the test was allowed to continue.

(R. Stachniak,,Technical Staff Group Leader).

Drywell pressure at typer is 15 lbs.

Instrument tap plugged; air leak stopped.

(Ata/McCabe/

Bandura)

Ata/McCabe to open LPCI isolation 43,45B and 80,79B to verify water in LPCI lines.

Water verified to be in LPCI lines.

Air leak suspected to be in equalizing valves on upstream side of LPCI 3-1501-25B.

Drywell pressure still at 15 lbs.

.Reviewed leak rate per procedure; no indication of pres-sure decay; will commence pressurization to 65.

Directed NSO to open LPCI 28B; loaded compressor.

DATE 07-25-86 07/25/86* TIME ILRT LOG 0132 Drywell pressure 18 lbs.

0144 Drywell pressure 20 lbs.

0235 Reactor wat~r temperature 145°F.*

0235 RBCCW valved into a SDC Hx to control water tempera-ture.

0318 DN Pressure:

35lb Rx H2 0 Level:

50.25 0338 DN Temperature:

112.14 Torus Water Temperature:

87° Torus Water Level:

14" DAS 1139 Rx Level:

49.91 (F 309) 53 (F 380)

Drywell Temperature:

112.55 Torus Temperature:

87 Level:

13.6/14 Torus Level:

14 0355 Rx Water Temperature:. 140°F.

0358 Drywell Pressure:

411/

Rx Level:

49.63/53 Druwell Temperature:

112.55 Torus Temperature:

87.

Torus Level:

14/13.6 0410 Rx Water Temperature:

37°F.

0420 0450 (4:48)

Secured a SDC.

Rx Water Temperature 35°F.

Drywell Pressure:

481/

Drywell Temperature:

112.549 Rx H2 0 Level:

49.48/52 - Stable Torus Water Level:

14 - Stable Torus Water Temperature:

87 - Stable r* -

0450 Maintenance (Bandura/Shift [Ata]) notified of drywell pressure and preparation for drywell spray header installation of blind flange.

0500 Compressor tripped on high temperature.

Drywell pressure to 471/.

0504 NSO directed to open 28B valve to continue pressuri-zation.

DATE 07-25-86 TIME 0518 0520 0530 0540 0550 0554 0630 0640 0650 0710 ILRT LOG Rx Water Temperature:

Drywell Pressure:

49#

Compressor tripped on high H2 0 temperature.

LPCI 28B closed.

Service H2 0 discharge header pressure = 98#.

Circulating water temperature 83.9/84.6.

2nd (Front) compressor started; continuing to pres-surize; 28B valve opened.

Drywell Pressure:

51 Rx Water Level:

49.71/52 Rx Temperature:

112.023 28B valve closed:

Stabilization commencing; data set 542.

2nd (Front) compressor unloaded.

H. Ata notified shift to hang outage fan 28B valve in preparation for installation of blind flange.

Breaker fan air.compressors racked out.

Rx Pressure:

51 Rx Level:

49.19/52 Rx Temperature:

111.349 Torus Level:

14/13.6 Torus Temperature:

87 Maintenance not to install blind. flange until after 0700.

Rx Water Temperature:

137°F and steady.

J. Kotowski wants 24-hour watch on console due to station cleaning in the area.

Ron Jackson sent to watch console.

Phone extension at console is 732.

Console must remain in attendance by T. S. Person.

Shift turned over to Leahy.

Temperature stabilization 7:42 to 9:42 = 0.226°F/hr, data set at 9:52 not signi-ficantly different from 9:42, so data set #87 at 10:02 (DAS time) will start test - Bechtel test will be performed.

1130 Notified by NRC resident inspector that 3-2301-28 is out of position.

1400 Found out that valve cannot be closed.

Open is conser-vative position, so TPC 86-7-463 written to cover posi-tion change.

DATE TIME ILRT LOG Late Entry 07-25-86 1255 Valve A0-3-2301-28 was found open by Beth Hare (NRC) while performing an inspection of the Control Room panels.

Attempts were made to close the valve from the control room and locally by the Unit 3 Operating.

Foreman, but all were unsuccessful.

After preliminary review of the valve, it is believed that the solenoid to the air operator on the valve failed some time during the test.

The valve had been verified closed by the Unit 3 NSO and the Technical Staff prior to conducting the test.

The valve fails open on loss of air and could provide a leakage path from the torus 07-26-86 Late Entry if other valves in series with AS-23-1-28 were to leak.

Leaving the valve open for the remainder of the test was considered conservative since leaving the valve open could only induce leakage *. (R. Stachniak, Technical Staff Group Leader) 2000 Shift turned over to M. Moy.

2250 Completed leakage phase of test at data set #161.

Calculated leak rate = 0.5034 %/day+ 0.5874 %/day.

2300 Notified J. Red for air sample.

0025 Rad/Chem took 8-minute air sample.

0042 Rad/Chem takes 2nd sample; results ready 0200 Rad/Chem air samples in.

0.0 Ioane l.2E-11 B

5. 2E-12 B. Causen ok to vent to Rx Bldg.

0200.

0213 Flowmeter set at induced leak of 14.0 scfm.

Data set

1. 185 will be first data set @

2:22.

07-26-86 1300 At approximately 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on 7-25-86, shortly before the end of the leakage phase of the test, the Unit 3 Operating Foreman discovered that valves M0-3-1501-32A and 3-1501-66A had not been opened during the test.

The valves were to have been opened prior to starting the test, after Mechanical Maintenance had removed the temporary flange from the containment spray line.

A review of the valves remaining closed shows that this did not jeopardize the test results.

Closure of valve 1501-66A isolated any flow from the ECCS jockey pump and could not have isolated any leakage path.

Valve M0-3-1501-32A is a crosstie isolation valve between the A and B LPCI loops.

Closing this valve did not

DATE TIME ILRT LOG isolate any vent or leakage path.

Closure of M0-3-1501-32A only affected LPCI system operability which was not required by the Technical Specifica-tions.

The unit was in cold shutdown with no mainte-nance ongoing that could drain the vessel.

0720 Shift turned over to M. Leahy.

0800 Looks like *flow for verification about 1/2 of what was believed, due to 48 psig outlet calibration.

0832 1st Verification phase failed, (data set #222)

[(1.209g + 0.084)-[(0.5034 + 1.74 + 0.084)] = 1.109 wt. %/day.from 14 s~fm flow.

The cause of the failure was determined to be improper operation of the flow meter.

0850 Installing flowmeter outlet passage and throttle valve.

0902 Start stabilization of 2nd verification phase.

1002 Start 2nd verification phase (data set #231).

Late Entry 0955 Temperature stable for 2nd verification phase.

Late Entry 1445 A review of the results from the first verification test had shown that the test had failed.

The cause of failure has been attributed to improper operation of the flow meter used to measure the induced leakage.

In a telephone conversation held between J. Glover (CECo) and H. Jacobine (Fischer Porter) on 7-26-86, at 0845 hrs, it was realized that the flow meter had been cali-brated by Fischer Porter such that the discharge pres-sure of the flow meter outlet was 48 psig.

The flow meter had been installed and operated by CECo such that the discharge pressure of the outlet of the flow meter was (approximately 14.-7 psia) Reactor Building pressure.

Under this condition, a flow rate of 14.0 scfm as measured on the flow meter was actually 6.78 scfm..

Using an induced leakage rate of 6.78 scfm, the differ-ence between the calculated induced leak rate and the actual induced leak rate (equation - page 15 of DTS 1600-7) was.2118 wt. %/day.

This was less than th~

.4 wt. %/day (.25 La) limit necessary to pass the verification test.

Although the verifi~ation test was succe~sful, a flow rate of 6.78 scfm did not meet the minimum induced flow requirement of Technical Specifi-cation 4.7.A.2.

For this reason a second flow verifi-cation test was performed.

Prior to starting the second flow verification test, a calibrated pressure gauge (DTS-31) and throttle valve were placed on the discharge of the flow meter.

DATE TIME ILRT LOG Valves on the inlet and outlet of the flow meter were throttled until a discharge pressure of 48.0 psig and a flow rate of 14.0 scfm were established.

Drywell pressure was approximately 50 psig at the time that the second verification test began and was monitored throughout the test to ensure that the pressure did not fall below 48 psig.

The flow and discharge pressure on the flow meter were monitored throughout the test to ensure that a 14.0 scfm flow and a 48 psig discharge pressure were kept constant at all times.

A review of the first verification test was held on 7-26-86 at 0910 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.46255e-4 months <br /> between J. Achterberg (Technical Staff Supervisor), J. Kotowski (Unit 3 Operating Engineer), and M. Leahy (ILRT Coordinator).

It was concluded that the cause of failure had been identified and corrected as required by 10CFR 50 Appendix J.

A second flow verification test was approved.

(R. Stachniak, Technical Staff Group Leader) 1325 Drywell pressure 48.7 psig.

Calculated induced leakage 2.1532 wt. %/day.

Must fall within 2.25 + 4 wt. %/day.

1510 Data scan received (Leahy and Blauw).

Going to DAS to investigate why data received at this time (not 15:12) 1530 Cause of 15:10+ scan determined to be console watcher (Technical Staff) inadvertently pressing the DAS power switch to "off" - he then re-energized the DAS using the power switch.

The DAS has a memory feature wh.ich enables the DAS to maintain all input levels (lOOmV,

• °F, etc.).

When the DAS was re-energized, a scan was transmitted since the 10-minute interval clock reset to zero. *The subsequent data set.,was transmitted at

• ~520, verifying the retention of the interval set, and all input levels were retained.

The final verifi-cation phase data set is now scheduled to be at *1620; 6:.18 after* the V.erification,.phase** start.

_ _,~.

1630 Final Rad sample taken to be analyzed.

1630 Final (1620) data set accepted.

Difference = 0.0185.

(1620 data set required since test phase was 12:333 hrs long).

1645 Air sample being taken.

1400 Air sample results - 0.0 Iodine 2.3E-ll Beta/Gamma

1. 7E-l l Alpha Ok to depressurize via Rx Building vents per Art Tucker, Rad Protection Foreman.

• DATE TIME ILRT LOG 08-19-86 1330 Procedure sign-off's completed - Log closed.

F.4 Final Calculated Leak Rate The final calculated leak rate was found to be 0.5034 weight %/day.

The upper 95% confidence limit was 0.6567 weight %/day.

Including compensa-tion for non-vented systems, these results are 0.5874 weight %/day and 0.7407 weight %/day, respectively.

(Refer to Section E.7.)

Since these values are well within the Technical Specification Limit of 1.2 weight

%/day for reactor startup, the Unit 3 primary containment integrity remains intact.

G.

SUPPLEMENTAL VERIFICATION TEST (INDUCED PHASE)

The purpose of the induced portion of the ILRT is to verify that the

• results of the 12-hour measured phase are valid.

The supplemental test portion of the ILRT procedure involves inducing a leak from the primary containment through a separate calibrated flow meter.

Concurrently, readings from the computerized ILRT data acquisition system are analyzed to determine the magnitude of the total containment leakage.

If the criteria established by the following equation is satisfied, the ILRT calculated leakage is considered acceptable and the test is terminated.

L (Induced Phase

, : Total Containment;

,c_alc~lated Leak Rate)

[L (12-hour phase +.(Superimposed]

0.25L a calculated.

leak rate) leak rate)~

G.2 Magnitude of Induced Leakage The induced leakage test was b.egun at 0222 hours0.00257 days <br />0.0617 hours <br />3.670635e-4 weeks <br />8.4471e-5 months <br /> on 7-26-86.

A flow believed to be 14 scfm was induce.d from the primary containment.

Because of a misunderstanding in the calibration conditions of the flowmeter, how-ever, the actual flow rate was approximately 7 scfm (see ILRT Log entries, Section F.3).

This induced test passed, but the flow rate was not suffi-cient to meet Technical Specification requirements.

A flow of 14 scfm was then induced, and the induced test re-performed, starting at 1002 on 7~26-86. This flow was converted to weight %/day as follows:

14:0 scfm 1440 Min Day T + 459.69°R 519.69°R 14.696 psia p

where:

T p

VOL Induced phase average containment temperature, 105°F Induced phase average containment pressure, 63.3 psia.

(Includes dry air and vapor)

Free volume of the contain-ment, 288966 Ft 3.

100% = 1.718 weight %/Day Vol

• The induced phase calculated leak rate; as shown by the computerized data.

acquisition system, was 2.1849 weight %/day.

The resulting difference, following the equation of Section G.l, is:

2.1849 -

(0.5034 + 1.76)

<.0.*25 La Since La*.. the maximum allowable containment leak rate is 1. 6 weight %/day,*

2.1849 -

(0.5034 + 1.76)

< 0.4 0.0785 ~ 0.4 Since the difference, as shown above, was well below the 0.4 weight %/day accuracy requirement the ILRT values are considered valid.

H.

TEST EVALUATION Both the statistical leak rate and the upper confidence limit, corrected for process lines not vented or drained, were well within all Technical Specification limits.

Reactor vessel temperature transients were minimized by leaving the shut-down cooling system (B heat exchanger) in steady-state operation throughout the test.

Reactor water temperature was controlled by varying the reactor building closed cooling water (RRCCW) supply flow rate to the heat exchanger.

Remote throttling of the RBCCW discharge valve provided this method for stabilizing reactor water temperature.

APPENDIX A TYPE A TEST INSTRUMENT ACCURACY ERROR ANALYSIS

APPENDIX A

~STRUMENT ACCURACY ERROR ANALYSIS A.I Development of Equations Per Topical Report BN-TOP-1 the measured total ti=ie leak rate (M) in weight percent p~r day is computed using the Absolute Method by the formula where:

M = c ;oo) 24 H

( I)

= total containment atmosphere absolute pressure, in psia, at the start of tes~, corrected for water vapor pressure.

p n = ? n -PVn,.= Total containment atmosphere absolute pressure, in psia, at data point n after start of the~test, corrected for water vapor pr:ssure

• TI, -

= containment mean atmospheri;: temperature in or

l the and data poi::t respectively.

at start at n,

= test interval l.n hours betv;::n time 1 and time

!i

= gas constant.

The change or uncertainty interval in M due to *.:::lcertainties in the measured* >-.Uiables 0 is 0given by-:-

M = 2400 I (d.M

• l dP2 (2) where o is the standard error for each variable.

This formula

• assumes t~at all errors are systematic rather t~an random in character~ Even though the formula is determi:::stic it does, how-ever, all:::r. assessment of figure of merit for *a=ious equipment to be used i:: the measuring system without the ne:i for assembling and calib=ating the system as an entity *

n.

The error in M after differentiating is:

2400 '. (_ Tl eP2\\ 2

+(P2TI e-2 eM = H

)

p I)

(3)

\\

PIT2

- 2 p I T2

-I

+ t p2 er) 2

( P2T I e) 2,

~

+

2 T

I P1!2 PIT2 I

where:

e

=

iS 1

pl pl e

= iS p2 p2 For the purpose 0£ developing a finite number for ~ using equation (3), it is necessa.-~ to assume certain containment conditions made *

1.

For purposes ~f comparison to other tests H = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

Containment :~k rate is essentially zero, that is:

.~ere T is the average volume weighted primary

=~ntainment air temperature ( R) duri~g the test;

.~ere P is the total containment atmospheric

?=essure-(psia);

PV 1 = PV2

-.6ere PV is the partial pressure of water vapor

=- the primary containment; Equation (3) becoimes:

where:

= 2400 H

ep 2

eT 2

2 (

)

+ 2 (

)

p T

= the :~or in pressure which accounts for t~e error in the :~tal pressure measurement system; bot~ total abso-lute ?=essure and water vapor pressure.

+

A.2 inst. accuracy error/ /no. inst.

absolute pressure in psia.

error in total inst. accuracy error/ I no. inst. = error in water vapor pressure (dewpoint) indicator in psia at 80°F~

inst. accuracy error/ I no. inst. = error in temperature, 0 R.

Calculations Instrument RTD (°F)

PPG (PSIA)

DEWCELL (oF)

Range 50-200 0-100 140 Accuracy

+/- 0.96 0.015

+/- 4.12 Repeatability

+/- 0.01 0.001

+/- 0.01°F BN-TOP Computation of Instrument Accur*acy Uncertainty.

1.

eT "Error in temperature"

+/- 0.96 = 0.1814°F

/28

2.

"Error in total absolute pressure in psia" ePT

+/- (0. 015%)

(100)./2

= 0.0106 psia

3.

• Comp~ting "ep" FLOWMETER (SCFM) 2-20 1% (Full Scale) 0.02 Error in water vapor pressure (dewpoint) indicator in psia at a dewpoint of between 85°F and 90°F (assumed), results in an inter-polated conversion factor of 0.02046 psi/°F.

e pv 4.12 (0.02046 psi) = 0.0266 psia OF

'/10*

• 9 Dewcells + 1 RTD as.a:-dewcell. in the* rea.ctor.

4.

Computing "e*"

p ep

+/- [(epT)2 + (epv)2]~

+/- [(0.0106) + (0.02666) 2 ]~

= 0.02869 psia

5.

Computing total instrument accuracy uncertainty "em".

em = +/- 2400 [2 x (~) 2 + 2 x (eT ) 2 -)~

12 65.0 550

+/- 200 [2 x (0.02869) 2 + 2 x 0.1814) 2 ]~

65.0 550

= +/- 0.1558 wt. %/day Computation-.o'f Instrument Repeatibility. _

1.

"e II.

T eT

+/- 0.01

.fi8 0.00189°R

2.

II e II PT ePT 0.001 12

+/- 0.0007 psia.

3.

"e II pv e

+/- 0.01 (0.02046 psi pv OF

.fi-0*

• 9 Dewcells + 1 RTD.

4.

"e e p II p"

5.

"e.-"

m e m

= *+/- 0.0001 psia

+/- [(0.0007) 2 + 0.0001) 2 ]\\

0.0007 psia

+/- 2400 [2 x (0.0007) 2 + 2(0.06189) 2 ]~

12 65 550

f 0.03048 %/day

APPENDIX B TYPE A TEST DATA

12-HOUR TEST PHASE

DRESDEN UNIT 3 13:21:04 WED' 20 AUG 1986

• • • • BECHTEL CALCULATIONS FOR DATA SETS. 87 THRU 161 ****

TEST TAPE

• TEHP DRY AIR WATER HEAS LEAK CALC LEAK 95% UPPER T

DURATION TIHE CR>

PRESSURE LEVEL RATE RATE CONFIDENCE

<HRS>

CPSIA>

<IN>

% I DAY

% I DAY LI HIT 87 0.000000 10:02:14 565.89087 63.54987 52.57000 0.0000 0.0000 0.0000 88 0.166016 1o:i2:12 565.85144 63.53759 52.20000

' 1.2568 1.0459 0.0000 89 0.333008 10:22:13 565.80432 63.52508 51.89000 1.2248 1.0385 0.0000 90 0.500000 10:32:14 565.76477 63.51613 51.63000 1.0316 1.0310 1.6961 91 0.666016 10:42:12 ' 565.71619 63.50240 51.41000 1.1660 1.0236 1.5873 92

'0.833008

• 10:52: 13 565.66931 63.49256 51.24001 1.0915 1.0162 1.3881 93 1.000000 11:02:14 565.62158 63.48088 51.04999 1.1029 1.0087 1.3185 94 1.166016 11:i2:12 565.59143 63.47242 51.06001 1.1119 1.0013 1.2884 95 1.333008 11:22:13 565.54431 63.46334 51.08999 1.0860 0.9939 1.2524 96 1.500000 11: 32: 14 565.50952 63.45395 51.06001 1.0983 0.9864 1.2363

,97 1.666016 11:42:12 565.48743 63.44778 51.04001

' 1.0699 0.9790 1.2113 98 1.833008 11:52:13 565.44849 63.43967 51.02001 1.0472 0.9716 1.1850 99 2.000000 12:02:14 565.42102 63.43367 51.06001 1.0194 0.9642 1.1573 100 2.166016 12:i2:12 565.40283 63.42761 50.99000 1.0039 0.9567 1.1318 101 2.333008 12:22:13 565.38733 63.42310 ' 51.02999 0.9807 0.9493 1.1062 102

' 2.500000 12!32!14 565.36780 ' 63.41817 51.04999 0.9586 0.9419 i.0809 103 2.666016 '...._12!42!12 565.35242 63.41405*

51.04001 0.9320

o. 9345 1.0551 104 2.833008 1.2:52: 13

'565.32764 63.40986 50.99998 0.8925 0.9270 1.0274 105 3.000000' 13:02:14 565.31103 63+40656 51.00999 0.8619 0.9196 (l. 9993

'106 3.166016 13:12:12 565.29724 63.40025 51.06001 0.8773 0+9122.

0.9769

'107 3.333008 13:22: 13 565.28430 63.39705 50.99998.

0.8489 0.9047 0.9531 108 3.500000 13!32!14 565.27600 63.39536 51.0200C

• 0*8179 0.8973 0+9281 9 '

3.666016 13:42:12 565.26233 63.39185* ' 50.99998 0.8000 0.8899 0.9040 0

3.833008 13!52!13 565.26587 63.38924 51.02999 0.7966 0.8824 0.8826 111

• 4,000000

.14!02!14 565.24951 ' 63.38712*

51.02001 0.7656 0.8750 0.8596 112 4.166016 14:'12:12 ' 565.24451 63.38367 50.99000

.0.7595 0.8676

' 0.8389 113 4.333008 14!22!13 565.24414 63;37885 50.99000 '

0.7720 0.8601.

0+8240

-114 4.500000 14!32:14 565.23779 63.37452' 50.93999 0.7712 0.8527 '

0.8122

'115

' 4.666016 14:42!12 565.23352 63.37241 50.93999 0.7570 0.8453 0.8001 116 4.833008 14!52!13 565.23645 I 63.36967 50.99000 0.7573 0.8378*

0.7907 117

• *5.oooooo

-.*15:02:14 565.23584 63.36564 50.99000 o.7619 0.8304 0.7850

• n0

- 5.166'016 c

'~15:12:12* ~

• 565.'23584 - 63.36338 *.

50.93999 --

0.7516

-o.0*230 o.7786 119 5.333008' 15:22: 13

• 565.22754 63.36237 50.97999 o.7304 0.8155 0.7693 120 51500000 '

15!32:14 565.22912 63.35935 50.97000 0.7298 0.8081

.o. 7620 121 5.666016 15:42:12 565.23254 63.35718 50.91999 0.7234 0.0007 *

o. 7552 '

122 5.833008 15:52:13 565.22876 63.35496 50.95998 0.7160 0.7932 0.7484 123 6.000000 16!02:14 565.23157 63.35349 50.91999 o.7057 0.7858 0.7412 124 6.166016 16:12:12 565.22876 63.35139 50.89999 0.6968 0.7784 0.7340 125 6.333008 16:22:13 565.23401 63.34745 50.86999 o.7044 0.7709

o. 7296 126 6.500000' ' 16!32:14 565.23535 63.34762 50.91999 0.6880 0.7635 0.7233 127 6.666016 16!42!12 565.24170 63.34455 50.89999 0.6916 o.7561 0.7191 128 6+833008 16: 52:13 565.23364 63.34224 50.88000

' 0.6818 0+7486 0.7140 129 7+000000 17:02:14 565.24939 63.34131 50.86999 0.6797 0.7412 0.7097 130 7.166016 17:12:12 565.25366 63.33906 50.88998 0.6791 0.7338 0.7063 131 7.333008 17:22:13 565.25732 63.33504 50.88000

' 0.6861 o.7263 0.7049 7.500000 17:32! 14 565.26221 63.33500 50.67999 0.6674 0.7189 0.7010 7.666016 17:42:12 565.26221 63.33317 50.58001 0.6590 0.7115 0.6967 7.833008 17!52!13 565.27124 63.32838 50.34999 0.6660 0.7040 0.6942

DATA TEST TAPE TEHP DRY AIR WATER HEAS LEAK CALC LEAK 95% UPPER SET DURATION TIHE CR>

PRESSURE LEVEL.

RATE RATE CONFIDENCE

<HRS>

<PSIA>

(IN>

% I DAY

% I DAY LIHIT a.000000 18:02:14 565.27173 63.32527 50.18000 0.6620 0.6966 0.6917 8.166016 10:12:i2 565.27258 63.32196 50.05999 0.6608 0.6892 0.6897 137

• .8.333008 18:22:13 565.26684 63.31924 49.90001 0.6524 0.6817 0.6870 138 0.500000 18!32:14 565.26050 63.31731 49.68001 0.6389 0.6743 0.6829 139 8.666016 19:42:12 565.25561 63.31029 49.57001 0.6519 0.6669 0.6814 140

. 8.833008 10:52:13 565.25586 63.30952 49.46999 0.6403 0.6594 0*6786 141 9.000000 19:02:14 565.25256 63.30133 49.30998 0.6570 0.6520 0.6787 142 9.166016 19:12:12 *.

565.24805 63.30075 49.12000 0.6405 0.6446 0.6768 143 9.333008 19:22:13 565.24036

.63.29526 48.95998 0.6438 0.6371 0.6757 144 9.500000

. 19:32:14 565.23682 63.29145 48.84000 0.6431.

0.6297 0.6749 145 9.666016 19:42:12 565.22473 63.28669 48.66000 0.6409 0.6223 0.6741 146 9.833008 19:52:13 565.21570 63.28389 48.54001

. 0.6340 0.6148 0.6727 147 10.000000 20:02:14 565.20972 63.27858 48.36000 0.6367 0.6074 0.6720 148 10.166016 20:12:12 565.19922 63.27404 48.23999 0.6361 0.6000 0.6715 149 10.333008 20:22:13 565.19299 63.27070 48.07000 0.6316 0.5925 0.6706 150.

10.500000 20:32:14 565.18750 63.26817 47.90999 0.6248 0.5851 0.6692 151 10.666016 20:42:12 565.17041 63.26138 47.81000 0.6302.

0.5777 0.6688 152 10.833008 20:52:13 565.16052 63.25829 47.66999 0.6243 0.5703 0.6678 153.. 11

• 000000 21:02:14. 565.14148 63.25376 47*.52000 0.6198 0.5628 0.6666 154 11.166016*

?1:12:12 565.14014 63.24976 47.39000 0.6209 0.5554

. 0.6658 155 11.333008 21:22:13 5p5.12073

.63.24503 47.28000 0.6180 0.5480 o.t.648 156 11*.500000 21:32:14 565.11011 63.24109.

47.20000 0.6164 o.5405 0.6639 157 11.666016 21!42i12 565.09778 63.23765 47.02998 0.6109 0.5331.

o.6627 158

. 11.833008 21:52:13 565.09228. 63.23402 46.89999 0.6093 0.5257'.

0.6615 159 12.000000 22,:02: 14 565.06799 63*22980 46.82000*

0.6039 0.5182 0.6600 12.166016 22: 12: 12

. 565.04553 63.22501 46.67001 0.5'199 0.5108 0.6584 12.333008 22:22:13 565.03882 63.22223 46.63999 0.5974:

0.5034 0.6567

. i*.. _,.

0 ID DRESDEN ONTAINMENT ORY AIR PRESSURE~vs TIME UNIT

~"T"T'"T"T'"1rT"T-r-r-rh....-.-T"T'"1rT'"T,-+-T"T"1....,.....-r-r-T"""rl.......... -.-.-..-.--.-r-r+-r-..-.--.-r-r-r-r-rl1-r-r-r-r-~-r+...-.-,....,_,....,......---,.-;f-r-,.~..-.--.-r-r+-r-..-.--.-.-r-r-r-r+.....-.--.-.-~-r+~~~......-<h-.~~....-.-+-.-~~~-h-~~~...+-

~H-t-t-t-t-HH-+-tt-t-H-t-t-+-HH-+-t-t-t-HH-+-tt-t-HH-+-tt-t-H-++++-t-H-++++-t-H-++-tt-t-H-++++-t-+-1-+++-HH-+-t-+t-HH-+++-t-H-++++-t-H-++++-t-+-1-++++-t-+-1-+++-HH-+++-t-H-+t-+-HH-+++-H-t-++++-H-t--I

~H-t-++t-HH-+-tt-t-H-++++-H-+++-t-HH-+++-t-H-++++-t-H-++++-t-H-++++-t-H-++++-t-H-++++-H-1-+t-++-H-+-t-+t-HH-+++t-H-++++H-t-++++t-H-++++-H-+-+++-H-++++-t-H-+++-H-++++H-t-++++-H-H

~"tt-t-HH-+++-H-t-++t-HH-+-tt-t-H-++++-t-H-++++-t-H-++++-t-+-1-++++-t-H-++++-t-H-++++-H-+-t-+-t-HH-+++-t-H-++++-t-+-t-++++-t-+-1-++++-H-+-t-+-++-H-+++-t-HH-+++-t-H-+++-HH-+++-t-H-++++-H-+-++++

~t++-++M--i-++++-1-H-++++-H-+++++-IH-+++++-IH-+++t-H-++++t-HH-+++t-H-++++-t-H-++++-t-H-++++-H-+-++t-H-++++t-H-++++t-HH-+++t-H-++++-H-+-++t-H-++++t-H-++++-H-+-++t-H-++++-~

w~-++t-H-++--H-+-++++-IH-+++t-H-++++-t-H-++++-t-H-+-+++-t-H-+-+++-H-1-++++-t-H-++++-H-+-+++-HH-+++t-H-++++-H-t-++++-t-H-++++-t-H-++++-H-+-++t-H-++++-t-H-++++-H-+++t-H-++++-t-H-++++-

• ~~t-t-t-H-+-H~++l-+-l++++H-t+++-HH-t-H-+-HH-++++-HH-++++-HH-++++-H-+++++-H-++++1-+-1-++++-1-H++++-11-H+++-HH-++++-H-++++1-+-1-++++-1-+-1+++-H-++++1-+-1-++++-1-H++++-1-++++H-H

..J o~H-t-++t-HH-+++"1rt-t-++++-H-+-++t-HH-+-++t-H-++++t-HH-+++-t-HH-+++-t-H-++++-t-H-+-+++-t-+-1-++++-H-+-++t-HH-+++-+-HH-+++t-H-++++t-+-1-++++-t-H-+++-HH-+++t-+-1-++++-H-+++-H-t-+-+++-H-H

(/)~ ~~~tt~~~tt~~~tt~~~ttt~~~ttt~~~!tt~~j!tt~~~ttt~~tttt~jttt~~jttt~~ttt~~j!tt~~jttt~~ttt~~jttt~~t!t~~j!t~~j!tt~jttt~jttt~t::t:

a). t++-++++-1-++++t-+-t....+++-H-+++++-1-++++++-1-++++t-H-++++t-H-++++t-H-++++-t-H-++++-H-t-++++-H-+-++t-HH-+++t-HH-+++t-H-++++-H-t-++++-H-+-+-l'-t-HH-+++-t-H-++++-H-+++t-H-++++-H-H

~~"'H-t-HH-+-t-t-H-t-++~lcH-++-t-HH-+-tt-t-H-++-t-t-t-+-t-++++-t+-t-++++-t+-t-++++-t-+-1-++++-H-+-++t-HH-+++t-H-++-t-t-t-H-++++-t-+-t-++++-H-+-++++-H-+++-++-IH-+++-t-H-+++-HH-+++t-H-++++-H-+++-++-

~t+i-++++-it++-H-+-H-++++t+++++-Ht++-H-+-HH-++++-HH-++++-HH-++++-H-+++++-H-++++-1-+-1-++++-1-H++++H-+++++-IH-++++-H-++++-+-H-R-'"'=l-l-+-l+++-HH-++++-H-++++-1-+++++-H-++++-H+

Nt+i-+++t-11++-H-+-H-+++t-t+++++-HH-t-H-+-HH-++++-HH-t-l-++-HH-++++-HH-++++-H-++++-l-+-l-++++-1-H++++-1H-++++-HH-++++-H-+++++-H-++++-P+...i+r++il-+++++-H-++++-H-++++-H-++++-l+H

~-t-t-t-HH-+-t-+-t-H-+++-HH-+++-t-H-++++-t-H-++++-H-1-++++-H-1-++++-t-H-++++-H-t-++++-H-+-+++-H-++++-t-H-++++t-H-++++-H-t-++++-H-t-++++-H-+-++t-HR--.!-+-l-t-H-++++-H-+++-t-H-++++-H-+-+++-H

~o.oo I. 00 2.00 J.oc 4-0C s.oo s.oc

?.oo s.oo g.oc 10.oc i I. 00 12.00 iJ.QO 14.0C TEST DURATION (HOURSl

VERIFICATION PHASE I

.\\!

\\m!..mt.t; u":i: i *:/

I.)Tv %......

'ft.'b"f 'Z.V 1'ftnf y )"00'

• • • • BECHTEL CALCULATIONS FOR DATA SETS 185 THRU 222 ****

DATA TEST TAPE TEHP DRY AIR WATER HEAS LEAK CALC LEAK

• 95% UPPER SET DURATION TIME

<R>

PRESSURE LEVEL RATE RATE CONFIDENCE

<HRS>

<PSIA>

<IN>

% I DAY

% I DAY LI HIT 0.000000 02:22:13 564.76111 63.12099 45.13000 0.0000 0.0000 0.0000 186 0.166992 02:32:14 564.75647 63.11516 45.16001 1.2509 1.2560 0.0000 187 0.333008 02!42!12 564.74438 63.10774 45.20000 1.3491 1.2547 0.0000

. 188 o.500000 02:52: 13 564.72937 63.10061 45.16001

• 1.2954 1.2534 1.9224 189 0.666992 03:02:14 564.71374 63.09387 45.13000 1.2450 1.2521 1.5656 190.

o.833008 03:12:12 564.70532 63.08637 45.22000 1.3215 1.2508 1.4988 191 1.000000 03:22:13 564.69690 63.08074 45.20998 1.2769 1.2496 1.4425 192 1.166992 03:32!14 564.68396 63.07425 45.22000 1.2601 1.2483 1.4044 193 1.333008 03:42:12 564.67200 63.07000 45.20998 1.1851 1.2470 1.3718 194 1.500000 03:52:13 564.67346 63.06207 45.20998 1.2583 1.2457 1.3609 195 1.666992 04:02: 14.

564.65967 63.05742 45.20998 1.20.33.

1.2444 1.3332 196 1.833008 04: 12:12 564.66162. 63.05206 45.20998 1.2096 1.2432 1.3136 197 2.000000 04!22!13 564.65832 63.04625 45.24000 1.2161

'1.2419 1.3014 198 2.1669'7'2 04!32:14 564.65210 63.04047 45.27999 1.2155

. 1.2406 1.2921 199 2.333008 04!42!12 564.64868 63.03415 45.22999 1.2206 1.2393 1.2871 200 2.500000 04!52!13 564.64123 63.02647 45.29001 1.2494 1.2380 1.2950 201 2.666992 05!02!14 564.64831 63.02298

45. 1699'1

. 1.2214 1.2368 1.2902 202 2;833008

,05*:12:12

.564.64416 63.01745

. 45. 13000

.. 1.2147 1.2355 1.2844 203 3.000000 05!22!13 564.63476 63.01167 45.00999 1.1973 1.2342 1.2756 204 3.1M992

. 05!32!14 564.63647 63.00504 44.92999 1.2103 1.2329 1.2713 205 3.333008 05!42!12 564.63220 62.99831 44.70001 1.2048 1.2316*

1.2665 206 3.500000 05: ~j2: 13 564.62500 62.98997

. 44 t 54000 1.2185 1.2304*

1.2660 207 3.666992 06!02!14 564.61572 62.98267 44.32000 1.2136 1.2291 1.2643 3,. 833008.

. %! 12: 12 564.60364 62.* 97575 44.17001.

1.2071 1.2278

• 1,2614 4.000000 06!22:13 564.59289 62.96863 44.02Q01 1.2042 1.2265 1.2583 4.166992 06!32! 14. 564.58301 62.96211 ' 43. 97999 1.2032

.1.2252.

1.2555 211 4.333008 06!42!12 564.57361 62 *. 95320 44.02999 1.2288 1.2240 1.2590 212 4.500000 06!52!13 564.57153 62.94795 44.10000 1.2292

-1 +2227 1.2618

. 213 4.666992 07:02:14 564.56128 62.94040 44.02999 1.2339 1.2214.

1.2652 214 4.833008 07:12! 12 564.55505 62.93561 44.04999 1.2249 1.2201 1.2661 215 5,000000 07!22:13 564.54700 62.92968 44.06999 1.2231 1.2188 1.2665 216

5. 166992 07!32!14 564.54578 62.92191 44.08999 1.2406 1.2175 1.2703

',.;,-,.211 -. *'5,'333008.... 07! 42H2... -.: :*564. 5394*3 °, 62. 91743 -- 44.08999 ° --

-1*.2290

... 1.2163

• - -.. 1. 2712.

218 5.5000!)0 07!52!13 564.53540 62.91122 44.08000 1.2310 1.2150 1.2723 219

• 5.666992 08!02!14 564.53809 62.90759

.44t10000 1.2221 1.2137 1.2718 220 5.833008 08!12! 12 564.54004 62.90173. 44~ 10000 1*2269 1.2124.

1.2720 221.

6.000000 00:22:13 564.54407 62.89621 44.13001 1.2318 1.2111 1.2729 222

6. 1.66992 08!32!14 564.54980 62.88943 44.13999 i*2445 1.2099 1.2757

DRESDEN BECHT.EL LEAK RATE VS TIME

~:

__ UN I T 3.

95::i'. LJPPER CONFIDENCE: LIMIT MEASURED LEAK RATE CALCULATED lEAK RATE gl+H-+-H-H-H-++H-++-H-++-H-++-+++++-1H-++++++-H-++-H-++-+++++-1H-++++++-+-++++-1-++-H-++-H-++-+++++-1H-++++++-+-++++-1-++-H-+++-IH-++++++-1+-+++++++-1-+++++++-1-+++++++-+-+++++-++-1 dHH-+++++-IH-+++++HH-++++++-+-++++-1++-H-++-H-+++++++-+-++++-1-++-H-++-H-+++++-H-IH-++++++-H-+-++-1++-H-++-H-++-+++++-1+-++++-1++-+-+++H-++-+-+++-H-+++-+++-H-++-+-+++-H-++-+-+++-H

~Hr++++++-+-++++-1++-1-++++-1-++-H-+++-i-++-H-++-H-+++++++-+-++++-1-++-+-+++-H-+++++-H-IH-++++-++-+-++++-1-++-H-++-H-++-+++++-1-++++-1-++-+-++++-1-++++++-HH-+++++-HH-+++++-HH-+++++-H C'JHtt--t-+-t-H-H-t--t-+-t-H-H-t--t-+-t-++-H-+++-t-++-H-++-HH-t-+++++-H-+++-t-++-H-++-H-++++++HH-++++++-H-+-t-+-t-++-H-+++-t-++-+++++-H-+++t-++-+-+++-H-+++-+++-HH-++-+++-H-+++-++-H-1-+++-+++-H gt-++++t-++-H-+++t++-H-+++t-++-H-+++t++-H-++-H-+++++++-H-+++-1-++-H-++-H-+++++-H-IH-+-+++++-H-+++-l-t-+-H-++-H-++-+++++-11-+++++-++-+-+++H-++-t+++-H-++++++-H-+++-+++-H-++-+-+++H

~NH-t-++t-H-H-+++t-H-H-+++t-H-H-+++t-++-H-++-H-++++++HH-+++t-t-+-H-++-H-++t+++HH-+-+++++-H-t-++-1-t-+-H-++-H-++-+-++-H-IH-++++-++-+-+++H-++-+-+++-H-+++-+++-H-++-t+++-H-+++-++++r 0

a::

~o

~~~+~~+t~+t~+t~+t~+t~+t~+t~+t~+t~~+t~+t~+t~+t~+t~~+~~+~~+t~+t~+t~+t~+t~~+~~+t~+t~+t~+t~+t~+t~+t~+t~+t~+t~+t~

1-z i.JJ u l~~~~~~~~~~~~~~~~~!!I~~~~~~~~~~~~~~~~~ii~~attfl~~~~~~~~~~~~il a:::o UJC'J

~-~t-++++t-++-H-t-++t-++-H-+++t,-t-H-t-++t-++-H-++-H-+++++++-IH-+-t-+-t++-H-++-H-++t++-H-1H-+-+++++-H-+++t-H-H-++-H-+++-+++HH-++++-++-+-+++-H-+++-+++-H-+++-+++-H-+++-+++-H-++H-++-H OH-++-H++-H-++-H-t-+-H-++-H-t-+-H-++H-++-H-++-HH-+-+++-++-+-+++H-+++-+++-HH-+-+++++-1-+++++-H-H-++H-++-t++-H-IH-+-+++-++-+-+++H-++-+-+++-H-+++-+++-H-+++-+++-H-+++-+++H-+++-+++H 0 0.00 C-.30

l. 00

l. 50 2.00 2.so 3.00 3.so 4.00

4. '.50 s.oo 5.50 6.QQ 5.so 7.00 TEST DURATION (HOURSl

. ~.

VERIFICATION PHASE II

&.1 1\\l-W&.'l-1'1 \\in l '( ~

r:rnt:n~

\\1"f 'r:'f:I 'Pft:lo' y )"oo'

• • • • BECHTEL.CALCULATIONS FOR DATA SETS 231 THRU 269 ****

DATA TEST TAPE TEHP DRY AIR WATER HEAS LEAK CALC LEAK 95% UPPER SET DURATION TIHE (R)

PRESSURE LEVEL RATE RATE CONFIDENCE

<HRS>

<PSIA>

<IN>

% I DAY

% I DAY LI HIT 0.000000 10:02:14 564.59570. 62.82247 44.21000 0.0000 0.0000 0.0000 232 0.166016 10: 12:12 564.60779 62.81403 44.24001

. 2.2951 2.1493 3.0000 233 0.333008 10!22:13 564.62158 62.80503 44.06999 2.2307.

2.1503 3.0000 234 0.500000 10 :32 :14 564.62610 62.79601 43.93001 2.1471 2.1513 2.2267 235 0.666016 10:42:12 564.62537 62.78667 43.71999 2.0681 2.1522 2.1033 236 0.833008 10: 52:13 564.63379 62.77564 43.* 53000 2.1483 2.1532 2.3058 237 1.000000 11 :02:14 564.64209 62.76752 43.38000

. 2.0991 2.1542 2.2497 238 1.166016 1i:12:12 564.63782 62.75829 43.25001 2.0604 2.1551 2.1946 239 1.333008 1i:22: 13 564.63721 62.74601 43.10999

. 2.1273 2.1561 2.2244 240 1.500000 11: 32:14 564.64294 62.73582 43.05999 2.1582 2.1571 2.2590 241 1.666016 11:42! 12 564.63769 62.72626 42.94000 2.1321 2.1580 2.2563 242 1.833008.

11:52:13 56.4.63696 62.71612 42.85999 2.1371 2.1590 2.2551 243 2.000000 12:02:14 564.63330 62.70591 42.75999 2.1343 2.1600 2.2515 244 2.166016 12:12:12.

564.63904*

62.69520 42.70999 2.1654 2.1609 2.2614 245 2.333008 12:22:13 564.63672 62.68302 42.61999 2.1964 2.1619 2.2805 246 2.500000 12!32!14 564.63721 62.67564 42.50000

2. 1516

.2t1628 2.2763 247 2.6t..6016 12!42!12 564.63318 62.66508 42.45000

2. 1582 2.1638 2.2742 248 2*833008..

12!52!13 564;62976 62.65337. 42.37999 2.1780 2t1648 2.2777 249 3.000000 l.3!02!14 564.62805 62.64412 42.26000 2.1630 2.1657 2.2757 250 3.166016 13:12:12 564.62305 62.63173 42t13999 2.1832 2~1667 2.2787 251 3.333008 13!22!13 564.62341 62.62231 42.06000.

2.1764 2+1677 2.2789

• • r.-.

.::._._IL 3.500000 13:32! 14 564.61706 62.61157 42.10000 2.1850 2.1686 2.2806 25.3 3.666016 13!42!12 564.61670 62.60186 42.06998 2.1849

.. 2.1696 2.2816 41 3.833008 13!52!13 564.62830 62.59404 42.10000..

. 2+ 1825 2.1706 2+2816 4.000000 14:02:14 564.63196 62.58494 42.12000

. 2.1834' 2+1715 2.2815.

4. 166016 14!12!12 564.63757. 62. 57658 42.11001 2; 1781

2. 1725 2.2803 257 4.333008 1.4!22!13 564.64319 62.56697 42.12000

2. 1849 2.1.734 2+2801 258 4.500000 14!32!14 564.647.83 62.56046 42.13999 2.1645 2.1744 2.2770 259 4.666016 14!42!12 564.65552 62.54952. 42+15999

. *. 2.1851

. 2+ 1754 2+2769 260 4.833008

. 14!52:t3 564.67517 62.54172 42.15999

2. 1885 2.1763 2+2770 261

. 5.000000.

• 15:02: 14 564.67981 62.53369 42.15000 2+1802.

2.1773.

2.2760 262.

5.144531 15!10!54 564.69311 62.52751 42.13999 2.1754 2.1781.

2+2742

. - _,,. :,*263-::.:_ 5.-311523 ' ~-*15: 20: 56' ~ -: 564 ~ 70508-- -. 62. 52096 -- '" 42 + 19998

'-c.2,,-1661 *

._ 2.1791 '

2+2717-264 5.478516 15!30!57. 564. 71667. 62.50980. 42.18999 2+ 1865 2+1801 2.2716

.~,.,.

265 5.644531 15!40!54 564.72803 62.50138 42.17999 2+ 1872 2.1810 2+2714 2.1796.

2+1820 2.2704 266 5.811523 15!50!56 564.74060 62~49419 42.15000 267 5.978516 16:00:57 564.75305 62*48560 42.18999 2.1840 2.1830 2.2698 268 6.144531 16:10!54 564.75378 62.4.7789 42.15000 2+1720 2.1839 2+2681 269 6 t 311523 16:20!56 564.78210 62.47124 42+15999 2+1739 2.1849 2+2667

0 rJ DRESDEN. *-

BECHTEL LEAK RATE VS TIME.

UNIT 3

~5% 0PPER CONFIDENCE LIMIT MEASURED LEAK RATE CALCULATED LEAK RATE

~t-tt+-H-t+t+t-+++++++-H++-H-t+-H-t-++t+t-H-t+t-H-t+t-H-t++-H-H-t++!H++H-t++-H-t+t+t-++H-t-H-H-+-t+H-t-t+H-t++-H-++HH-++-H-+++-H-H-H-+++t-++++!-++t+t-++1++++11-++++-i Nt-+tt-+-H-++-++-t-++-H-t-++-t-+++-H-++-++-t-++-++-t-++-++-t-++-++-t-++-H-+-+-+-t-++++-it-+++-H-++-++-t-++-++-t-++-++-t-++-H-+-+-+-H-+-++-t-++-++-t-+++-Ht-+++-H-++-++-t-++-H-+++-1-++++-t-++-++-t++-H-++-Hl-++++-t

~H-+it-Ht-++++-t-++-t++-++-H-++-H-++-++-t-++-++-t-++-++-t-++-++-t-++-H-+-++-H-+-++-t-+++-HH-t-++-t-++-++-t-++-++-t-++-++-t++-H-+-++-t-++-++-t-++++-11-1-++-Ht-++++-t-++-++-t-++-t-++++-1-++-++-t++-H-+-++-1-++++1 NH-++r'H-t-++-t-H-H-t-H-H-++-HH-+++-t-++-++-t-++-++-t-++-++-t-++-H-t++-H-+-++-1-+++-HH-+++-t-++-++-t-++-++-t-++-++-t++-H-+-++-t-++-++-t-+++-HH-++-H-++-++-t-++-++-t-++-H-++-H-++-++-t++-H-t-H-H-+++I C>*~mm*ammnmmam=mnmnttmmmmtnnwmm OH-++-HH-t-++-t-++-t++-++-H-++-HH-+++-t-++-++-t-++-++-t-++-++-t-++-++-t-++-t-++-++-t-+++-HH-++-H-++-++-t-++-++-t-++-++-t-+-+-t-++-+-+-t-++-++-t-++-++-H-++-H-++-++-t-++-++-t-++-t-+++-H-++-++-t-++-t-++-H-1-++++I

>-Nt+t++!H++-H-H-t++-H-H++-H-t++-H-t+t-H-++t-H-t+H-t-t+H-+-t+H-t-t+H++-H-t++-H-t++-H-++t+t-++H-t-t+H-+-t+H-t-t+H-t++!H++H-t++-H-t+H-+-t+H+++!-++t+t-++H-+++t-+++H

<(

.o a:::

woH++-H-+++++-++H++-H-++++t-++tt-t-+++-++-++H-+++-H+++-1-+++-HH-++-H-t+t+t-+++++-++H-+-++H-+++-H+++!H-++HH-++-HH-++-H-+++-H-+++++-++1-+++HH-++-H-+++++++1-+++Ht-+++H Q:.~H-+++-t-++-H-+-++-H-++-H-++-++-t-++-H-t-++-H-+-+-+-t-++-++-t-++-++-H-++-HH-++-H-++-+-H-++-++-t-++-H-t++-t-++-++-t-+++-Ht-+++-HH-++-HH-+++-t-++-++-t-++-t-++-+-+-l-+++-HH-+++-t-++-t-++++-1-+++-HH-+++-f 1-z w u

O:::o WNH-t++!H++-H++t++-H-H++-HH-++-HH-+t-H-++t+t-++t-H-t+t++-H-t++++-H++-HH++-H-t++-H-++++t-H-t+t-t+H-t-t+H-+++-H+++-H++HH-++-H-+++++-t+H++HH-++-H-+++++++++++H Cl...~++-H-t+-HH-+++-t-++-t++-++-H-++-HH-++-H-++-++-t-++-++-t-++-++-t-++-++-t-++-++-t-++-H-++-+-11-+++-Ht-++++-t-++++-t-+-+-++-t-++-++-t-+-+-++-t-+-+-H-+-H-t-+++-Ht-++++-t-++-++-t++-H-++-Ht-++++-t-++-+-+-+-+-+-M-+....

ol++++!H++-H-H-t++++H++-H-t++-H-++t+t-++t+t-++H-t-H-t++++-H-+++-H-++H-t++-H-++t+t-++++t-++t+t-+++++++-H-+++-H+++!H++HH-++-H-+++++-++H++HH-++-H-+++++++++++H

~H-++-HH-+++-t-++-t++-++-t-+++-H-+++-H-++-++-t-++-++-t-++-++-t-++-H-+-++-H-+-++-H-++-HH-+++-t-+++++-++-++-t-++-++-t-+-+-H-+-+-+-1-++-++-1-++++-il-+++-Ht-++++-t-++-++-t-+-+-H-++-Ht-++++-t-++-t-++++-t-++++1 OH-++-HH-t-++-t-++-t++-++-H-++-HH-t-++-t-++-+-+-t-++-++-t-++-++-t-++-H-+-+-+-H-++-Ht-+++-H'-++++-t-++-++-t-++-++-t-++-++-t-++-H-+-+-+-H-+-+-+-H-++-HH-++-H-++-++-t-++-++-t-+-+-H-+++-1-++-++-t-++-+-+-+-++-1-++++1 oH-t+HH++-H+++++++-H++-H-t++-H-++t+t-++t+t-H-H-t++H-++++-++++-H++-HH++-H-t++-H-++++t-++t+t-++H-+-++H-+++-H-+++-H+++!H-++-H-+++++-++++++HH-++-H-+++++++++++H

~ 1-+-++-H-++-++-t-++-H-+-++-t-+++-H-++++-t-++++-t-+-+-++-t-+-+-++-t-++-H-+-+-+-H-+-++-t-+++-HH-++-H-+++-H-++++-t-+-+-++-t-+-+-++-t-+-+-++-t++-H-+-+-+-t-++++-it-++++-t-++-++-t-++-t-++++-it-++++-t-++-++-t-+-+-M-+++I ot++++!H++-H++H-t+t-H++-H-t++-H-++t+t-++t+t-+++++++++++++++++-H-++-HH++-H-+++-H-+++++-+++++-++++++++++++-+++++-+++++.t-+++-H-++-+-H++++++HH-++-H-+++++++++++++

0 0.00 o.:to I. CJO I. 'jQ

.' 2. 'jQ

• J DO.

3. ~>0..

. 4. 00.

.4. '.iO 5 00

'j.'jO 1;.00 1.00 T E S T DUR AT I 0 N. ( H 0 UR S l

APPENDIX C TYPE "B" AND "C" TEST RESULTS UNIT 3 1986 REFUELING OUTAGE

1985-1986 UNIT 3 OUTAGE

y

}->~,,JY<-

D. yatt TO:

SUBJECT:

Unit 3 *Primary Containment Local Leak Rate Testing During the 1985-1986 Refueling Outage Unit 3 entered its 1985-1986 refueling*outage with a total initial or "as found" leak rate from the primary* containment of 3878.590 SCFH for Type B and C. testing which excee'ds the Technical Spe,:ification -limit of 493.116 SCFH (493.116 SCFH = 60% La).

The final or "as left" leak rate from all the Type B and C testable penetrations, isolation-valves, and double gasketed seals is 408.549 SCFH, which is 82.85% of the Technical Specification limit.

The Type A containment leak prior to startup is 60.24% of the Technical Specification allowable operational containment leak rate, Lam (616.39 SCFH =.75 La).

The Type A "as found" containment leak rate, prior to shutdown, was 454.655 SCFH

. which is.!3.76% of the Technical Specification limit for Lam.

Reportable

• • through* leakage 'for-Type -B *and C testing' is calculated *using Maximum Pathway methods.

Correcting for Type A "as found" and "as left" leakage, the Minimum Pathway method is used.

Maximum Pathway method entails reporting leakage assuming a complete failure of the best valve in the test volume.

Minimum Pathway method entails reporting leakage assuming the leakage is equal to that past the best valve in the test volume.

. *'.. Type. of Test B&C As Found B&C As Left Nonvented Add-Ons Type A As Found Type A As Left TEST RESULTS

• '*Minimum..,-Maximum Pathway (SCFH) 3878.590 408.549 35.724 454.655 371.300 Seven initial local leak rate test results were greater than or equal to the recommended limit of 30.82 SCFH (3.75% of La).

Only one of the seven initial test failures exceeded the Technical Specification limit of 493.116 SCFH for type "B" and "C" testing of all testable penetrations combined.

This test failure was caused by excessive leakage (3026.35 SCFH) past RV-3-8526 in the Nitrogen Makeup line.

Investigation found that teflon tape, used on the threads of the pipe connected to RV-3-8526 had become unwrapped and lodged on the seat of the valve preventing RV-3-8526 from seating properly.

Safety significance was minimal because RV-3-8526 is bounded by primary containment isolation valves A03-1601-57,58 and 59.

These other in-line isolation valves showed no significant leakage during the test.

Therefore, the "through" leakage past these valves was minimal.

The leakage past RV-3-8526 accounted for 78% of the total type "B" and "C" "as found" leakage.

This test failure is documented in Reportable Occurrence 85-021 on Docket #050-249.

• Maintenanc*e ~was--performed on the* equipment involv.e.d *.in. these test failures and the final test results for each individual*local leak rate.test failure and the cause of.the.failure are shown in Table 2.

TEST PROCEDURE

• The drywell:bellows seals were tested using the permanently installed flo~ make-up~stations.

The electrical penetrations were.tested using a flow make-up leak rate monitor~ The remainder of all tests were performed using the pressure decay method.. The local leak rate equipment, including the permanently installed bellow seals flow make-up. stations, were calibrat~d throughout the outage.

LLRT TEST VOLUME CHANGE ASSOCIATED WITH RPR ACTIVITIES During the Unit 3 Pipe Replacement Project, several local leak rate test lines were removed and replaced with new piping.

This resulted in changes to the *calculated test volume of these lines.

The table below outlines the extent of the changes made to the calculated volume of the local leak rate test lines replaced during the ~ipe.replacement project.

Previous New As-SYSTEM Volume Tested Test Volume Built Test (All units in Ft 3 )

Cleanup (1200) 3-1201-1,lA,2&3 37.19 24.75 Isolation Condenser ( 1300) 3-1301-3&4 20.30 29.47 LPCI (A) (1500) 3-1501-25A&26A

.33.50 23.62 LPCI (A) (1500) 3-1501-22A,26A, 1001-5A

41. 866 46.00 Volume LPCI (B) (1500) 3-1501-25B&26B 25.133

24. 05' LPCI (B) (1500) 3-1501-22B,26B &

1001-5B 41.866 47.20

,:_,,:.. _,,,l\\J_so:,

cll\\r~_ng.t)J,e.,._pipe,./epl_acemen~_ proje_ct, the.control rod drive (CRD) return line (including irtboard check valve 3-0301-98) to the reacto~-~e~s~l ~as permanently removed from inside primary containment.

The reactor vessel nozzle was capped at the safe-end and the containment penetration was capped on the in-board side.

Outside primary containment, the pipe was cut and caps were installed on the segment protruding from the containment penetration and on the line down-stream of the outboard check valve 3-0301-95.

This deleted CRD valve 3-0301-98, and isolated CRD valve 3-0301-95 from primary containment.

Therefore, these valves no longer serve as primary containment isolation valves and will no longer be leak tested per Appendix J.

cc:

.J. Brunner J. Achterberg J. Kotowski R. Stachniak B. McCabe File/T.S. File,LLRT Prepared by Technical Staff Engineer Approved by. t);4 ~~

J.Tchterberg Technical Staff Supervisor

.. Appendix A

. )"'*:Dr.eden Unit 3 LLRT Summary* (all. units in SCFH)

As Found As Left

• Back Correction for ILRT Maximum Allowable Leak Rate (La) 1.6 wt.%/Day = 821.857 SCFH 3878.590 408.549 83.355 Allowable Operational Containment Leak Rate (.75La) 1.2 Wt.%/Day -

616.392 SCFH Type B and C Containment Leak Rate (.6 La)

.96 Wt.%/Day = 493.116 SCFH

,Percent of.. Limit,for. Type* B and *c Test*ing. Brior to* Shutdown:

3878.590 493.116 786.5%

Percent of Limit for Type B and C Testing Prior to Startup:

, * '40s*.-s4 9 493. 116 82.85%

LLRT Not Drained and Vented During ILRT (all units in SCFH)

'A' Feedwater

'B' Feedwater Shutdown Cooling SBLC Cleanup Isolation Condenser

'A' Core Spray

'B' Core Spray

'A' LPCI

'B' LPCI Primary Sample Drywell Cam HPCI Suction TOTAL 0.0

0. 7178 3.3174 6.01 0.0 1.353 1.828

1. 221 12.372 3.651

o. 017 3.956 1.281 35.724

Appendix A (Continued)

ILRT Result (1986) 0.6533 Wt.%/Day

.LLRT. Not.. Drained.or Vented during ILRT Total Containment Leak Rate Prior to Startup

.LLRT Back Correction Total Containment Leak Rate Prior to Shutdown Percent of Limit for Type A Testing Prior to Shutdown:

454.655 616.392 73.76%

Percent of Limit for Type A Testing Prior to Startup:

371.300 616.392 60.24%

SCFH 335.576 35.724 371.300 83.355 454.655

Table 1 Dresden Unit 3 Local Leak Rate Test Summary INITIAL

• FINAL MSIV's 6.672 9.654 Isolation Valves 3727.932 305.868

.Electrical Pen.

96.704 73.160

. Bellows Seals 42.238 10.022 Double Gask.

5.044 9.845 TOTAL 3878.590 408.549 Table 2 Dresden Unit 3 Local Leak Rate Test Failures Initial Final Cause Leakage Leakage of Corrective (SCFH)

(SCFH)

Failure Action Valves or Penetration MO 3-220-2 54.328 1.736 Packing Replaced Leak Packing 3-220-58A 250.570 0.0 Worn Seat Replaced Valve AO 3-1601-21 55.287

27. 601 Worn Seat to Replaced Disc.Clearance Valve RV 3-8526 3026.35 1.239 Teflon Tape on Cleaned Seat Valve Seat:

3-2599-23B 38.8 0.0 Check Valve Lubricated Hung up - Open Shaft and Cleaned Valve Electrical Penetration X-204L

31. 83 8.286 Inner Drywell Applied Seal Leak Sealant CRD Return Bellows X-109B 32.0 0.0 Outer Bellows Cut Line out Seal Leak and capped inside Drywell

LOCAL LEAK. RATE TESTS PE ED DURING THE UNIT 3

.REFUELING OUTAGE OF 1985-1986 TYPE OF PENETRATION:

MS IVs

)'

Type B and Type C Testing Tvpe A Testine:.

Initial Fi rial Measured Initial Measured Final

!!test Penetration Leak*

Valve(s)

Reported Leak Reported As Found As Left Back

~umber Number Volume Being Tested Rate;:

Repaired Leakage Rate Leakage Leakage Leakage Correctior<

I 1

105A 203-1A&203-2A 2.66 Re~acked 2.66*

5.566 5.566

1. 33 2.783 0

Bo h 2

105B 203-1B&203-2B

2. 72 Re~acked Bo h 2.72 2.747 2.747

1. 36

1. 374 0

Re~acked 3

105C 203-1C&203-2C

1. 292 Bo h

1. 292 o~o 0.0 0.646 0.0 0.646 o.d Re~acked 4

105D 203-1D&203-2D 0.0

1. 341

1. 341 0.0

o. 671 0

Bo h

)

TOTALS 6.672 9.654 3.336 4.828 0.646

Test Penetration Number Number 5

X-147 6

X-147 7

X-106 8

X-122 9

X-107A 10 X-107A 11 X-107B 12 X-107B 13 NA 14 NA 15 NA 16 NA 17 X-109B 18 X-109B 19 X-11lA,11 lB 20 X-138 21 X-138 22 X-113 23 X-108A 24 X-109A 25 X-108A,109A 26 X-310A 27 X-149A LOCAL.

UNIT 3;,

TYPE Lt;:AK RATE TESTS 1.JRMED D. URING:TllE

• . REFD£LING O~

bF 1985-1986 oFiPENETRATION:

Primary C6ntairiment Isolation Valves

.,1 Type B and Type c Testing Type Initial Final Meas.tired Initial Measured Final LeaR Valve(s)

• Reported LE~ak Reported As Found Volume Being Tested Hate*

Repaired Leakage Ra,te Leakage Leakage 205-2-4&flange 17.~916 NA 17.916 17.916 17.916 205-2-7& flange 1.,2424 NA 1.2424 220-1&2

. 54.'j28 220-2.

54.328

i. 736

1. 736

1. 736 220-44&45

'*033 NA

.033

~ 033

.033 0.017 220-57A&58A 250 *::5 7 220-58A 250.57 ci. 0 0.0 10.85 220-57A&62A 10... 85 NA 10.85 10~85 220-57B&58B 0..7178 NA 0.7178 220-57B&62B 4.::577

.NA

4. 577

4. 577

4. 577 302-156A&l57A 3.:i822' NA 3.822 3.822 3.822

1. 911 301-160A&l61A 0.-,1929 NA 0.1929 0.1929 0.1929 0.096 301-156B&l57B 3 -'>8 NA 3.58 3.58 3.58

1. 790 301-160B&l61B 5.:368 NA 5.368 5.368 5.368 2.684 301-95&99 0.;:8449 [line ~PWoved O*

O*

0.8449 301-98&99 1.714 line Remo\\ed

1. 714 O*

O*

RPR 1001-1A,1B,2A,2B&2C 17.'.676 RPR W~rk 1001-A-lB 17.676 6.347 6.347 8.838 1101-1&15 6.:01 NA 6.01 1101-1&16 1L81 NA

11. 81

11. 81

11. 81 1201-1,lA,2&3 4.207 RPR 4.207 0.0 0.0 2.104 1301-1&2 0.'9365 NA 0.9365 0.9365 0.9365 0.4683 1301-3&4 17.311 1~5~-3,4 17.311 2.706 2.706 8.655 1301-17&20 L742 NA

1. 742

1. 742

1. 742 0.871 1402-4A,8A,25A,36A 3.44 NA 3.44 3.44 3.44 -

1. 72 1402-24A&25A 0.21.56 NA 0.2156 0.2156 0.2156

o. 1078

• Line Removed PAGE TOTALS 399.439 75.272 50.663 c

A Testin:g As Left Back Leakage Correctio=

t 1.2424 0

0.868 0.868 0.017 0

0.0 10.85 0.7178 0

l; 911 0

0;096 0

1.790 0

2.684 0

0 0.8449 3.174 5.664 6.01 0

0 2.104 c

0.4683 0

1. 353 7.302 0.871 0

1. 72 0

0.1078 0

c 23.030 27.633

>rest Penetration

Number Number 28 X-310B 29 X-149B 30 X-311A

' 31 X-311B

)

32 X-310B 33 X-310A

' 34 X-116A 35 X-116A l

36 X-116B l

37 X-116B 38 X-145 39 X-150A 40 NA

' 41 X-304 42 X-304 43 X-126,304

' 44 x-125,318 l

45 X-126,304

)

46 X-313A 47 X-313B 48 X-316A 49 X-304 so X-118

)

)

LOCAL LEAK RATE TESTS P

REFUELING OUT i

MED DURING TllE UNIT 3; 1985-198-6 TYPE OF P~NETRATION:

Primary Containment Isolation Valves Tvoe B 'an<l Tvlle C Testiilg Type lnitial Final Measu~ed Initial Measured Final Leak Valve(s)

Reported Leak Reported As Found Volume Being Tested Rate Repaired Leakage Rate Leakage Leakage 1402-4B,8B,2SB,36B 1.821" NA 1.821

1. 821

1. 821

o. 911 1402-24B&25B 0.6193 NA 0.6193 0.6193 0.6193 0.310 1501-18A&l9A 4.534 NA 4.534 4.534 4.534 2.267 1501-18B&l9B 0.5917 NA 0.5917 0.5917 o.. 5917 0.296 1501-20B&38B

1. 294 NA

1. 294

1. 294 1.294 0.647 150l-20A&38A

1. 94.:

NA

1. 94

1. 94

1. 94 0.970 1501-22A,26A,1001-5A

4. 824.

RPR 1501-22A 10.699 10.699 4.824 1501-25A&26A 8.722 RPR 8.722 7.998 1501-25A 1501-25B&26B 12.06

~sBi-25B 12.06 21.973

21. 973 1501-22B,26B,1001-5B 2.049 RPR 1501-22B 2.310 2.049 1501-27A&28A 2.273 NA 2.273 2.273 2.273

1. 137 1501-27B&28B 0.7959 NA 0.7959 0.7959 0.7959 0.398 1599-61&62 2.762 NA 2.762 2.762 2.762

1. 381 1601-20A&31A

~RIT

.323 NA 4.323 3.J94 3.394 2.162 l 601-20B&31B GRIS

11. 2 NA

11. 28 15.951 15.951 5.64 gg8~-500LL,)),)b 55.287

~IT-~-56 Cl-2IR ed 55.287 27.601 27.601 27.643 1601-23,24,60,61,62,62 29.827

{;; lU T Kano.e:t 29.827 12.583 12.583 14.914 NA 1601-57,58,59 3026.35 RV3-8526 3026.35

1. 239

1. 239 1.239 1699-63A& Flange 0.044 NA 0.044 0.044 0.044 0.022 1699-63B & Flange

0. 928 NA 0.928 0.928 0.928 0.464 1699-73A & Flange 0.0 NA 0.0 0.0 0.0 0.0 1699-73B & Flange 0.0 NA 0.0 0.0 0.0 0.0 2001-5&6 1.482 NA 1.482 1.482 1.482 0.741 PAGE TOTALS 3166.934 112.525 68.015 A Testing As Left Back Leakage Correction 0.911 0

0.310 0

2.267 0

0.296 0

0.647 0

0.970 0

7.998 0

2.310 0

1.137 0

0.398 0

1. 381 0

1. 697

.465 7.975 0

13.80

13. 842 6.292 8.622 0.6195 0.6195 0.022 0

0.464 0

0.0 0

o.o 0

0.741 0

50.236 23.549

Test Penetration Number

• Nuinber Volume 11eing 51 X-li7 2001-105&106 52 X-128 2301-4&5 53 X-312 2301-34& 71 54 NA 2301-35&36 55 x-317 2301-45&74 56 X-202V 2499-1A&2A 57 X-204B 2499-1B&2B 58 X-316A 2499-3A&4A 59 X-316B 2499-3B&4B 60 X-202V 2599-2A&23A 61 X-204B 2599-2B&23B 62 X-316A 2599-3A&24A 63 X-316B 2599-3B&24B 64 Xl25,318 2599-4A&5A 65 X-125,318 2599-4B&5B 66 X-123 3702&3799-126 67 X-124 3703&3706 68 X-139D 4720&4721 69 X-121 4722 & Check 70 X-101 9207A & End 71 X-101 9207B & End 72 X-101 9208A & End 73 X-101 9208B & End PAGE TOTALS LOCAL LEAK RATE TESTS P

. ' REFUELING OU' I

TYPE OF PENETRATION:

Type B Initial

.j:

Measured Leak 1 Valve(s)

Tested Rate :

Repaired o.2o3 NA 3.44.*

NA 0.9925 NA 1.437 NA 2.562 NA

1. 903 NA 0.3278 NA 0.6078 NA 0.545 NA 1.62 NA 38.80 2599-23B 3.207 NA 5.92 NA 14.0L NA 4.02 NA 0.0 NA 22.265

~78~cked 2.62 NA 1.949 NA 3.146 NA

1. 65 NA

2. 30,6 NA 4.345 NA i

RMED DUHING THE UNIT 3~

F 1985-198*6 *

~~imary Containment Isolation Valves

and Type c Testing Type Final Initial Measured Final Reported L~a~

Reported As Found Leakage Rate Leakage Leakage 0.203 0;203 0.203 0.102 3.44 3;44 3.44

1. 72 0.9925 0.9925

0. 9925 0.4963

1. 437

1. 437 1.437 0.7185 2.562 2.~62 2.562

1. 281

1. 903 1.903

1. 903 0.9515 0.3278 0.3278 0.3278 0.1639 0.6078 0.6078 0.6078 0.3039 0.545 o.545 0.545 0.2725

1. 62

1. 62

1. 62 0.81 38.80 o:o 0.0 0.0 3.207 3.207 3.207 1.604 5.92 5.92 5.92 2.96 14.01 14.01 14.01 7.005 4.02 4.02 4.02 2.01 0.0 0.0 0.0 0.0 22.265 17.637 17.637

11. 133 2.62 2.62 2.62

1. 31

1. 949

1. 949

1. 949 0.975 3.146 3.146 4.146

1. 65 2.306 4.345 4.345 4.345 113.980 70.492 37.773 A Testing

~ ~-*

As Left Back Leakage Correction 0.102 d

c

1. 72 0

c 0.4963 0

o. 7185 0

1. 281 0

0.9515 0

O.i639 0

0.3039 0

0.2725 0

0.81 0

0.0 0

1.604 0

2.96 0

c 7.005 0

2.01 0

0.0 0

(

8.819 2.314

1. 31 0

0.975 0

1. 65 0

2.306 0

35.459 2.314

LOCAL LEAK RATE TESTS JRMED DURING: THE UNIT f REFUELING 0 OF 1985-19~6 TYPE OF PENETRATION:

.Primary Containment Isolation Valves Type B and Type C Testing Type A Testing

(

• Initial Final Meagured Initial t:f~asured Final Test

~enetration Leak Valve(s)

Reported Leak Reported As Found As Left Back Number Number Volume Being Tested Rate Repaired Leakage Rate Leakage Leakage Leakage Correct le[

74 X-313A E.Torus Drain Vlvs

0. ~.991 NA 0.1991 0.1991 0.1991 0.996 0.0996

.o I

75 X-313B W.Torus Drain Vlvs 0.2109 NA 0.2109 Q.2109 0.2109

0. 1055 0.1055.

0 76 X-136J Tip Valve A

1. 2o NA

l. 20 l.20

l. 20

l. 20

l. 20 0

\\

(

77 X-'-136F Tip Valve B 2.535 NA 2.535 2.535 2.535 2.535 2.535 0

78 x~l36E Tip Valve c 0.599 NA 0.599 0.599 0.599 0.599 0.599 0

(

79 X-136H Tip Valve D 0.627 NA 0.627 0.627 0.627 0.627 0.627 0

80 X-l36E Tip Valve E

0. 214.

NA 0.214 0.214 0.214 0.214 0.214 0

81 X-309A 8501-lA & End 0.199 NA 0.199 0.199 0

(

82 X-309A 8501-lB & End 0.206 NA 0.206 0.206 0.206 83 X-204 8501-3A & 3B

9. 213 NA 9.213 9.213

9. 213 4.607 4.607 0

84 X-143 8501-5A & End 0.212 NA 0.212 0.212 0

85 X-143 8501-5B & End 0.244 NA 0.244 0.244 0.244 86 X-143 9205A & End

l. 615 NA

l. 615

l. 615

l. 615 87 X-143 9205B & End 0.581 NA 0.581 0.581 0

88 X-143 9206A & End

l. 122 NA 1.122

l. 122 0

(

89 X-143 9206B & End 1.454 NA 1.454 1.454 1.454 90 X-101 Personnel Airlock 25.il7 NA

25. 117

25. 117

25. 117 12.559 12.559 0

91 X-l36E Purge Chk Valve(Tip) 4.145 NA 4.145 4.145 4.145 4.145 4.145 0

(

(

PAGE TOTALS 47.579 47.579 28.805 28.805 0

LOCAL LEAK RATE TESTS P MED DURING Tl1E UNIT 3~

~REFUELING OUT F 1985-198~

TYPE OF PENETRATION:

Electrical Penetf1itions Type B and Type C Test:l,ng Type A Testing Initic;il Final Measured Initial Mecisured Final Test Penetration Leak Valve(s)

Reported Leak Reported As Found As Left Back Number Number Volume Being Tested Rate Repaired Leakage Rate Leakage Leakage Leakage Correction 92 x-2cioc

- LV Power & Control 10.105 NA

• l.0.105 lO.-ib5 10.105 5.053 5.053 0

6.06i 93 X-201B HV Power NA 6.063 6.063 6.063 3.032 3.032 0

9/f X-202B CRD Indication 0

NA 0

d 0

0 I

0 0

95 X-202BB CRD Indicator 2.621 NA 2-. 627 2.627 2.627

1. 314

1. 314 0

96 X-2020 HV Power 0

NA 0

.()

0 0

0 0

97 X-202F Thermocouples 10.105 NA 10.105 10.105 10.105 5.053 5.053 0

98 X-202J Neutron Monitor 0

NA 0

0 0

0 0

0 99 X-202N Neutron.Monitor 0

NA 0

0 0

0 0

0 100 X-202Q Instrumentation 2.021 NA 2.021 2.021 2.021

1. 0105 1.0105 0

101 X-202S CRD Indicators 0

NA b

d 0

0 0

0 102 X-202W CRD Indicators 5.053 NA 5.053 5.053 5.053 2.527 2.527 0

103 X-203B HV Power 3.234 NA 3.234 3.234 3.234

1. 617

1. 617 0

104 X-204A HV Power

1. 516 NA

i. 516

1. 516

1. 516 0.758 0.758 0

105 X-204E Newtron Monitor 0

NA 0

b 0

0 0

0 106 X-204H Neutron Monitor 2.627 NA 2.627 2.627 2.627

1. 314

1. 314 0

107 X-204L Power & Ground

31. 83 Inner

31. 83 8.286 8.286 15.92 4.143

11. 78 Boundarv 108 X-204M LV Power 2.526 NA 2.526 2.526 2.526 1.263 1.263 0

109 X-204N CRD Indicator 2.021 NA 2.021 2.021 2.021 1.011

1. 011 0

110 X-204Q CRD Indicator 2.627 NA 2.627 2.627 2.627

1. 314

1. 314 0

111 X-204S LV Power & Control 12.126 NA 12.126 12.126 12.126 6.063 6.063 0

112 X-205B CRD Indicator 2.223 NA 2.223 2.223 2.223 1.112 1.112 0

TOTAL

96. 704 73.160 48.362 36.585

11. 78

Test Penetration Number Number 113 X-105A 114 X-105B 115 X-105C 116 X-105D 117 X-106 118 X-107A 119*

X-107B 120 X-108A 121 X-109A 122 X-lllA

• 123 X-1 llB 124 X-113

. 125 X-128 126 X-116A 127 X -116B 128 X-123 129 X-124 130 X-125 131 X-126 132 X-138 133 X-109B 134 X-147 135 X-149A 136 X-149B LOCAL LEAK RATE TESTS REFUELING 0 JRMED DURING :THE UNIT 3~

OF 1985-198*6 TYPE OF PENETRATiON:

brywell Bellow Seals Type B and Type C Testing Initial Final Measured Initial

• Measured Final Leak Valve(s)

Reported L~ak Reported Volume Being Tested Rat~

Repaired Leakage Rate Leakage Main Steam

3. 9:74 NA 3.974 3.974 3.974 Steam 0.0 Main 0.0; NA 0.0 0.0 Main Steam

0. ci NA 0.0 0.0 0.0 Main Steam 0.0 NA 0.0 0.0 0.0 Main Steam Drain 0.0 NA 0.0 0.0 0.0 Feedwater 0.864 NA 0.864 0.864 0.864 Feedwater 0.0 NA 0.0 0.0 0.0 Iso.Cond. Steam 0.0 NA 0.0 Q.O 0.0 lPR RemovaJ

• Iso.Cond. Condensate o.o

& Renlace 0.0 o.o 0.0 Shutdown Cooling 3.024 NA 3.024 3.024 3.024 Shutdown Cooling 0.0 NA 0.0 0.0 0.0 Cleanups 0.648

~PR Removal 0.648 0.432 0.432

& Reolace HPCI Steam 0.0 NA 0.0 0.0 0.0 LPCI Injection 0.0 lPR ReTova1

& Rep ace.*

0.0 o.o 0.0 LPCI Injection 0.0 lPR Remova1 0.0 o.o o.o

& Replace RBCCW Inlet 0.0 NA 0.0 0.0 0.0 RBCCW Outlet o.o NA 0.0 0.0 0.0 Vent From DW 0.0 NA 0.0 o.o 0.0 Vent to DW O.o NA 0.0 o.o 0.0 SBLC 0.432 NA 0.432 0.432 0.432 CRD Return 32.0 Cut out & 32.0 0.0 0.0 Capped Rx Head Spray 0.0 NA 0.0 0.0 0.0 Core Spray 0.216 NA 0.216 0.216 0.216 Core Spray

1. 08 NA

1. 08

1. 08 1.08 Totals 42.238 10.022 Tvpe A Testing As Found As Left Back Leakage Leakage Correctio.

1. 987

1. 987 0

0.0 p.o 0.0 0.0 0

0.0 0.0 0

0.0 0.0 0

0.432 0.432 0

0.0 0.0 0

0.0 0.0 0

~

0.0 0.0 0

1. 512

1. 512 0

0.0 0.0 0

0.324 0.216 0.108 0.0 0.0 0

0.0 0.0 0

o.o 0.0 0

0.0 0.0 0

0.0 0.0 0

0.0 0.0 0

0.0 0.0 0

0.216 0.216 0

16.0 0.0 16.0 c

0.0 0.0 0

0.108 0.108 0

0.54 0.54 0

21.119 5.011 16.108

Test Penetration Number Number 137 X-100 138 X-102 139 X-136A 140 X-136B 141 X-=136C 142 X-136D 143 X-136E 144 X-136F 145 NA 146 X-137 147 X-301F 148 X-301F 149 X-301E 150 X-301E 151 X-301D 152 X-301D 153 X-301A 154 X-301A 155 X-301B 156 X-301B 157 X-301C 158 X-301C 159 X-306A 160 X-306B 161 X-313A LOCAL LEAK RATE TESTS

. REFUELING 0 JR.MED DURI.NG,,THE UNIT 3; OF 1985-198"6 TYPE OF ~ENETRATION:

Double Casketed *:seals Type B and Type C *Testing Ini.tlal Final Meas'.iired Initial M_~asured Final Leak Valve (s)

• Reported Leak Reported Volume Being Tested Rate Repaired Leakage Rate Leakage i

0.0 0.0 0.0 DW Equip Hatch 0.0 NA CRD Hatch

0. cf-NA

. 0. 0 0.0 0.0 Tip Flange o.on9 NA

0. 0779

0. 0779 0.0779 Tip Flange 0.0783 NA 0.0783 0.0783 0.0783 Tip Flange 0.1093 NA b.1093 0.1093 0.1093 Tip Flange 0.1;,25 NA 0.125 0.125 0.125 Tip Flange

o. 5_933 NA 0.5933 0.5933 0.5933 Tip Flange

0. 0,694 NA 0.0694 0.0694 0.0694 DW Head

0. 6 1909 NA 0.6909 0.163 0.163 DW Head Manway 0.0 NA 0.0 0.0 0.0 Tor.Vac. Bkr 32A 0.072 NA b.072 0.015 0.015 Tor.Vac. Bkr 32B 0.2249 NA 0.2249 0.0 0.0 Tor.Vac. Bkr 32C 0.1272 NA 0.1272 b.064 0.064 Tor.Vac. Bkr 32D 0.0474 NA 0.0474 2.729

2. 729 Tor.Vac. Bkr 32E 0.0 NA 0.0 0.036 0.036 Tor.Vac. Bkr 32F 0.0992 NA 0.0992 0.015 0.015 Tor.Vac. Bkr 33A

o. 2'465 NA 0.2465 0.348 0.348 Tor.Vac. Bkr 33B 0.0972 NA 0.0972 0.048 0.048 Tor.Vac. Bkr 33C

0. 1'444 NA 0.1444 0.031 0.031 Tor.Vac. Bkr 33D o.6806 NA

o. 6806 0.032 0.032 Tor.Vac. Bkr 33E

0. 577 NA

0. 577 o.o 0.0 Tor.Vac. Bkr 33F 0.4389 NA 0.4389 0.137 0.137 E. Torus Hatch 0.0 NA 0.0

1. 621

1. 621

w. Torus Hatch 0.0 NA 0.0 o.o 0.0 E. Torus Drain 0.0 NA 0.0 L335 1.335 Type A Testin*g As Found As.Left Back Leakage Leakage Correctio 0.0 0.0 0

0.0 0.0 0

0.0390 0.0390 0

c

o. 0392 0.0392 0

0.0547 0;0547 0

0.0625 0.0625 0

0.2967

o. 2967 0

0.0347 0.0347 0

0.3454 0;0815

.264 0.0 0.0 0

0.036 0.0075 0.029 0.1125 0.0 0.1125 0.064 0.032 0.032 0.024

1. 365 0

0.0 0.018 0

0.0496 0.008 0.042 0.123 0.174 0

0.049 0.024 0.025 0.072 0.016 0.056 0.340 0.016 0.324 0.289 0.0 0.289 0.2195 0.0685 0.151 0.0

o. 811 0

c 0.0 0.0 0

c 0.0 0.6675 0

r LOCAL LEAK RATE TESTS P

• . REFUELING OU' TYPE OF PENETRATION:

Tvoe B lniti.~l Measured Test Penetration Leak Valve{s)

Number Number Volume Being Tested Rate '

Repaired 162 X-313B

w. Torus Drain

0. 0 :

NA 163 NA Shear Hatch 1 0.0613 NA 164 NA Shear Hatch 2

o. li43 NA 165 NA Shear Hatch 3

o. 0511 NA 166 NA Shear Hatch 4 0.1594 NA 167 NA Shear Hatch 5 0.0932 NA 168 NA Shear Hatch 6

. 0. 06;31 NA 169 NA Shear Hatch 7 0.0 NA 170 NA Shear Hatch 8 0.0 NA TOTALS JRMED DURING THE UNIT 3~

F 1985-1986 Double Casketed Seals and Tvne C Testing Final Initial Measured Final Reported Leak Reported Leakage Rate Leakage o.o L675

1. 675 0.0613 0.0613

0. 0613 0.1143 0;1143 0.1143 0.0511 0: 0511

o. 0511 0.1594 0.1594 0.1594 0.0932 o.0932 0.0932 0.0631 0~0631 0.0631 0.0 o.o 0.0 0.0 0.0 0.0 5~044 9.845 c

Type A Testing As Found As ief t Back Leakage Leakage Carree t iot1 0.0 0.8375 0

0.0307 o.6307 0

0. 0572 0.0572 0

0.0256 0.0256 0

0.0797 0.0797 0

0.0466 0.0466 0

~

0.0316 0.0316 0

0.0 0.0 0

• ~

0.0 0.0 0

2.522 4.925

1. 325

~

c c

1983-1984 UNIT 3 OUTAGE

TO:

SUBJECT:

April 16, 1984 D. J. Scott Unit 3 Primary Containment Local Leak Rate Testing During The 1983-1984.Refueling Outage v / s c.f* w

. JO I * ; <1 o

._,q 6 )

/

/

'L*c_", 0 /-.f)9'1

/

Unit 3 entered its eighth refueling outage/with a total initial or "as found" local leak rate fromlthe primary containment of 596.33 SCFH, which is 72.6%

of La, the maximum a!~owable leak rate (82~.36 SCFH).

See Appendix A.

The initial leak rate froi_\\ all. testable penetrcitions, isolation valves, and double-gasketed seals was jli..--9-.;-~SCFH, which is~of the Technical Specification limit (493. I 16 SCFH = 60% of La).

The containment leak prior to startup was

323.4-8 SCFH; which is *52.5% of the Technical Specification allowable opera-tional containment leak rate, Lam (616.39 SCFH = 75% of La).

A total of approximately 400 local leak rate tests were performed during the course of the Unit 3 outage.

A summary sheet listing all test results for equipment failures is shown on Table 2.

Test Procedure The drywell bellow seals were tested using the permanently installed.flow make-up stations. The electrical penetrations were tested using a flow make-up leak rate monitor.

The remainder of all tests were performed using the pres-sure decay method.

The local leak rate equipment, including the permanently installed bellow seals flow make-up stations, were ~alibrated throughout the

outage, Test Results Six initial local leak rate test results were greater than the recommended limit of 30.82 SCFH (3.75% of La).

None of the six initial test failures exceeded the Technical Specification limit (493. I 16 SCFH) for thru leakage for all testable penetrations combined.

Two of the initial failures did not merit maintenance and repair; the RBCCW discharge from drywell coolers and the electrical penetration to CRD indicators.

Consequently, the initial leakage was left as the final leakage for the two test failures.

The reasons for this were the difficulty involved in performing maintenance on the test volume and also the relatively low leakage rate; i.e. close to the recom-mended limit of 30.82 SCFH.

Maintenance was performed on the equipment involved in the four other initial test failures and also on two initial leak tests which showed higher than average leakage.

The results for each inoividual local leak rate test and a summary table of all the tests are shown on Tables 3 and 1, respectively.

D. J. Scot"t April 16, 1984 Page 2

• • rt** should be noted that the method used to determine thru leakage for penetration boundaries has changed.

Starting with the Dresden Unit 2 1983 refueling outage, thru leakage is one-half the total volume leakage measured on any penetration. *This method.of calculating thru leakage is conservative and yields large leak rates when compared to previous *outage test results

• JDB :LC :hjb

/

cc:

R. Coen/.

. L. Coyle T. Ciesla J. Brunner File/T.S. File,.LLRT

._/

Prepared by()/~

. !:. Coyle Technical Staff Approved by t'./,/~ {ot-J. D / B~unner Technical Staff Supervisor Dresden Nuclear Power Station

DRESDEN UNIT 3 LOCAL L AK RATE TEST

SUMMARY

Penetration Thru Leakage In SCFH (At 48 PSIG) 1978 1980 1982 1983-1984 Initial Final Initial Final Initial Final Initial Final MS I Vs I. 12 1.31

4. I

4. I 19; 22 3.82 I. 314 1.314 Isolation Valves 459.823 104.479 76.73 70.37

57. 13 55.58 407.8 135.82 Electrical Pen.

12.324

11. 662 11.683

11. 683 129 ~.16 32.07 30.6 30.6 Bellows Seals

.972

.972 3.49 3.49 4.8 4.8 8.33 8.33 Double Gasketed 30.397 14.4 76 5.53 o.o 17.97 4.0 I. 137

.303 Seals Total 504.636 132.899 105.53 89.64 288~28 100.27 449.2 176.35 Table I

. I

DRESDEN UNIT 3 INITIAL OUTAGE LOCAL LEAK RATE TEST FAILURES Initial Fimil Leakage Leakage Valves or Pen.

System (SCFH)

(SCFH)

Cause* of Leakage Corrective Action 3-220-62A 220 87.9 9.33 Worn "O" Ring Replaced "O" Ring 3-1301-3 1300 12.27 1.4 IS Worn Valve Seat Lapped Disc to Seat 3-1601-21 1600 285.55 17.S Worn Valve Seat Replaced Valve 3-2301-35 2300 79.82 19.73 Worn Valve Seat Lapped Disc to Seat 3-301-156Il 300 116. 23

.864 Improper Valve Adjustment Valve Adjusted 3-1599-62 1500 28.58 I.49 Improper Valve Adjustment Valve Adjusted X-124 3700 40.29 40.29 X-202W 300 45 45 Table 2

'I

APPENDIX A Dresden Unit 3 LLRT Summary (All Units in SCFH)

As Found As Left LLRT Improvement LLRT Not Drained and Vented During ILRT Feedwater Check Valve~

Core Spray LPCI Shutdown Cooling SBLC Isolation Condenser CRD Return

.Rx. Clean-up Primary Sample Total Dresden Unit 3 Containment Leakage Summary ILRT Result (i982) 0.54 Wt.%/Day LLRT Not Drained or Vented During ILRT Total Containment Leak Rate Prior to Startup LLRT Improvement Total Containment Leak Prior to Shutdown Maximum Allowable Leak Rate (La)

I.6 Wt.%/Day 82 I.85 7 SCFH Allowable Operational Containment Leak Rate (.75 La) 1.2 Wt.%/Day 616.392 SCFH 272.85 6.06

.459 18.63 1.29 5.56

.708 11.8 1.64 0

46. 15 277.33

46. 15 323.48 272.85 596.33

l.

c.:.

/ol>/Y'f

APPENDIX A -

(Continued)

Per.cent of Limit. for Total Containment Leak Rate Prior to Startup:

323.48 x 100 = 52.5%

616.392 Percent of Limit for Total Containment Leak Rate Prior to Shutdown:

596.33 x JOO= 72.6%

821.857 Total Containment Leak Rate LLRT Untestable Containment Penetrations:

. (Using 1982 ILRT *Results) 323.48 L.c.

'0/~ s)Y'f..

TEST Nll.MRER I

2 3

4 5

6 7

8 LOCAL LEAK RATE TESTS PERFORMED DURING THE UNit 3 REFUELING OUTAGE OF 1983-1984 PENETRi\\TION

• 'NUMBER X-105A X-105A X-lOSB X-105B X-105C X-IOSC X-105D X-IOSD TYPE OF PENETRATION:

MAIN STEAM ISOLATION VALVES TESTED AT 25 PSIG 1982 FINAL INITIAL T!JRU LEAKAGE LEAK RATE VOLUME BEING TESTED SCFH SCFH 203-lA* &. 203-2A 203-lA &. 203-2A 0

2.627 203-IB* &. 203-2B 203-lB &. 203-2B b

0 203-lC* &. 203-2C 203-lC &. 203-2C 3.82 0

203-ID*

&. 203-2D 203-ID &. 203-2D 0

0 TOTAL Tl!RU LEAKAGE FOR PAGE

'I INITIAL THRU LEAKAGE SCFH 1.3:14 0

0 0

J.314

,qndicates waterhead present on one side of valve.

Table 3 FINAL FINAL TH LEAK RATE LEAKAGE SCFII SCFH 1.314 c

0 0

0

(

1.314

LOCAL LEAK RATE TESTS PERFOllMED PURING THE UNIT 3 REFUELiNG OUTAGE OF 1983-1984 TYPE OF PENETRATION:

ISOLATION VALVES 1982 FINAL

. ~NITIAL INITIAL THRU FINAL FINAL THRU TEST PENETRATION Tl!RU LEAKAGE LEAK RATE LEAKAGE LEAK RATE LEAKAGE NUMBER

• NUMBER VOLUME BE ING TESTED SCFH SCFH SCFH SCFH SCFII 9

X-147 205-2-4 & Blind Flange

.09 0

0 0

10 X-14 7 205-2-7 & Blind Flange 0

0 0

l I X-106 220-:-1 & 220-2 I.42

}.67 3.84 3.84 12 x.-122 220-44~'t & 220-45 0

0 0

0 13 X-107A 220-57A* & 220-58A 0

0 44.0 4.67 14 X-107A 220-57A* & 220-62A 87.9 9.33 15 X-107B 220-5 7Il* & 220-588 0

2. 77 I.39 1.39

)

(

16 x-107ll 220-57B* & 220-62B 0

)

17 X-109B 301-95 & 30 l-99>'t 0

.5. 16 11.8

11. 8 18 X-109B 301-98 & 301-99*

18.37 19 X-11 IA, 11 IB 100 I-IA*, IB*, 2A, 2B & 2C I.30 2.576 1.29 I. 29

)

(

20 X-138 1101-1* & 1101-15

.96

11. 115

'5.56 5.56 21 X-138 1101-1* & 1101-16 0

l

(

22 x-113 1201-1*, 2 & 3 2.73 6.51 3.26 3.28 1.64 23 X-108A 1301-1* & 1301-2 0

2. 15 I.08 1.08 24 X-109A 1301-3 & 130 1-4*

0 12.27

6. 14 1.415

.708 25 X-108A, 109A 1301-17 & 1301-20

.54

.649

.325

.325 26 X-310A 1402-4A, 8A>'t, 25A & 36/\\*

.56 0

0 0

27 X-149A 1402-24A & 1402-25A

.4

.832

.4 16

.416 '

)

28 X-310il 1402-Lf]3, 8B>'t, 25B & 36B>'t 0

.918

.459

.459

)

29 X-149B 1402-24B & 1402-25B 0

0 0

0 TOTAL THRU LEAKAGE FOR PAGE 79.6

33. 18

• .I

• Indicates waterhcad present on one side of valve.*

Table 3

.,.~

.r ;;.

LOCAL LEAK RATE TESTS PEl{[*'ORMED DURING TllE UNIT 3 REFyrn.ING OUTAGE OF 1983..;. I 984 TYPE OF PE~~TRATION:

• iSOLATION VALVES 1982 FINAL INITIAL INITIAL THRU FINAL FINAL Tt

• TEST PENETRATION THRll LEAKAGE

• LEAK RATE LEAKAGE LEAK RATE

'*LEAKAGJi NUMBER NUMBER VOLUME BE.ING TESTED SCFll SCFH SCFH SCFH SCFII

(

30 X-31 IA 1501-18A & 1501-19A 0

I. 185

.593.

1.36

.68 31 X-3 I lB 1501-18B & 1501-19B

. 19 0

0

.. 783

.391 32 X-310A 1501-20A & 1501-38A 3.92 4.05 2.03 2.03 33 X-310B 1501-20B & 1501-38B" I. 24 0

0 0

34 X-l 16A 1501-22A, 26A-k & 1001-SA

.4 0

2.86 5.69 12.43 3S X-116A ISOl-25A & ISOl-26A*

s. 72

19. 16 36.

X-l 16B ISOl-22B, 26B* & 110 I-SB 4.62S

11. 22 6.2 6.2

~

37 X-l 16B 1501-25B &

150!-26B>~

I. 17 38 x...: 14S ISOl-27A & 150!-28A 0

0 o..

0 39 X-ISOA 1501-27B & i50!-28B

'.L45

• 198

. I 40 X-304 160 l-20A & 1601-31A 3.27 4.29

2. 14 4.5S

2. 77.

41 X-304 160 l-20B & 1601-31B 3.29

8. 72 4.36 7.32 3.66 42 X-126, 304 1601-21, 22, S5 & 56

.8 i 285.S5 143.0 17.5 8.75 c

43 X-12S, 318 1601-23, 24, 60, 6 I, 62 & 63 6.03 10.237

5. 12

5. 12 44 X-126, 304 1601-57, 58 & 59

.4 7

.308

• IS4

. 154 4S X-118 2ooi-5 & 2001-6

.09

.029

.015

.015 46 X-117 2001-105 & 2001-106

.59

.710

.3SS

.355 L, 7 x-.128 2301-4>'* & 2301-S

. 5 I

2. 12 1.06 1.06 48 X-312 2301-34 & 2301-71

. 19 0

0 0

49 2301-35 & 2301-36 0

79.82

39. 9.

19.73 9.87 so X-317 2301-45 & 2301-74 1.4 s 0

0 0

TOTAL THRU LEAKAGE FOR PAGE 207.9 53.S9

'I

>qndicates waterliead present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS PERFbHlmD DURING. ~NIT 3 REFUELING OUTAGE OF 1983-1984 TYPE OF PENETRATION:

ISOLATION VALVES 1982 FINAL

_ INITIAL INITIAL THRU FINAL FINAL THR TEST PENETRATION THRU LEAKAGE LEAK-RATE LEAKAGE LEAK RATE LEAKAGE NUMBER NUMBER VOLUME BEING TESTED SCFH SCFH SCFH SCFll SCFH 51 X-202V 2499-IA & 2499-2A

. 19

.592

.296

.296 52 X-204B 2499-IB & 2499-2B 0

.344

• 172

. 172 53 X-316A 2499-3A & 2499-4A 0

0 0

0 54

!{-316B 2499-3B & 2499-4B o_

0 0

0 55 X-202V 2599-2A & 2599-23A

• I I 1.84

.92

.92

--(

56 X-204B 2599-2B & 2599-23B 0

. 781

.391

.391 57 X-316A 2599-3A & 2599-24A 0

0 0

0 58 X-316B 2599-3B & 2599-24B 0

.991

.496

.496 59 X-125, 318 2599-4A & 2599-5A 4.09 7.63 3.82*

3.82 60 X-125, 318 2599-4B & 2599-5B

.28 I. 59

.795

.795 61 X-139D 4720 & 4721 0

4. 14 2.07 2.07 62 X-121 4722 & Check Valve

. 12 3.92 J.96 I. 96 63 X-309A 8501-IA & End of Line

.08

.89

.445

.445 6L1 X-309A 8501-lB & End of Line

• 16

.60

.30

.30 65 X-204 8501-3A & 8501-3B 3.38 7.75 3.88 3.88 66 X-143 8501-5A & End of Line

.25

.594

.297

.297 67 X-143 8501-5B & End of Line

.31 0

0 0

(

68 X-143 9205A & End of Line

.26 2.21 I

• I I

• I 69 X-143 9205B & End of Line

. IO

.317

• 159 I. 59 70 X-143 9206A & End of Line 4.58 0

0 0

71 X-143 9206B & Encl of Line 0

0 0

0 TOTAL THRU LEAKAGE FOR PAGE.

17. I

17. 1

'I

>qndicates waterllead present* on one side of valve.

Table 3 LOCAL LEAK RATE TESTS PERFORMED DURING THE UNIT 3 REFUELING OUTAGE OF 1983-1984 TYPE OF PENETRATION:

"ISOLATION VALVES 1982 FINAL INITIAL INITIAL THRU FINAL FINAL THI(

TEST PENETRATION THRU LEAKAGE LEAK RATE LEAKAGE LEAK RATE LEAKAGE NUMBER NUMBER VOLUME BEING TESTED SCFH SCFH SCFH SCFll SCFII 72 X-101 9207A & End of Line

.94

• 158

.079

.079 73 X-101 9207B & End of Line

.695

.019

.O 1

."07 7L1 X-101 9208A & End of Line

.26

.045

.023

.023 75 X-101 9208B & End of Line

.53

.077

.038

.038 76 X-136F TIP Purge Check Valve

.37 6.87 3.44 3.44 77 X-136C TIP Ball Valve A

• 18

.383

• 192

• 192 78 X-136B TIP Ball Valve B 3.21 5.01 2.51 2.51 79 X-136D TIP Ball Valce c

.28

.6 7

.335

. 335 80 X-136F TIP Ball Valve D

.43

.755

.378

.378 81 X-136E TIP Ball Valve E

~ 11

.344

. 172

• 17 2 82 X-313A East Torus Drain Valves 0

0 0

0 83 X-313B West Torus Drain Valves 0

0 0

0 84 X-101 Personnel Air Lock 0

0 0

0 84a N/A 301-157A & 301-156A

• 12 I.6 7

.835

.835 84b N/A 301-160A & 301-161A

.44

.529

.265

.265 84c N/A 301-157B & 301-15613

.o I 116. 23

58. 12

.* 864

.432 8L1d N/A 301-160B & 301-161B J.29 4.39 2.2 2.20 8t1e N/A 1599-61 & 1599-62 N/A 28.58

14. 29 1.49

.75 84f X-124 3702 & 3799-126 N/A

.289

• 145

• 145 84g X-124 3703 & 3706 N/A 40.29

20. 15

20. 15 TOTAL TIIRU LEAKAGE FOR PAGE 103.2 3 1. 95

'I

• Indicates waterhead present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS PEHFOl{MED DURING REFUELING OUTAGE OF 1983-1984 0TYPE OF PENETRATION:

ELECTRICAL*

. 1982 FINAL

• INITIAL INITIAL THRU FINAL c

FINAL THR TEST PENETRATION TllRU LEAKAGE LEAK RATE LEAKAGE LEAK RATE LEAKAGE NUMBER NlJMllER VOLUME BEING TESTED SCFH SCFH SCFH SCFH SCFH 85 X-200 LV Power & Control 3.55

,..26~~ 0 '-/

1..* cs; yz_

z.s_~S--'

86 X-20 IB HV Power

. 32 0

0 0

87 X-20213 CRD Indicators 0

0 0

0 88 X-20213B CRD Indicators 0

0 0

0 89

• x-202D HV Power 0

0 0

0 90 X-202F Thermocouples 5.48 l'r' *'?. 'f~.

3.5 tf ;.?J:>-

5-* ~~----*-

91 X-202J Neutron Monitor 0

0 0

0 92 X-202N Neutron Monitor 0

0 0

0 93 X-202Q LV Power & Control 0

0 0

0 94 X-202S CRD Indicators 0

, 9 *::...-6s-

_. '/&s** _.......3:1

. ~'C 5*-

_33~

95 X-202W CRD Indicators 4.85 Jo 7: "3 '5_9.5-

.)J.i.(. 2-;5-****-

)'J *Gr; 2 ~ '

96 X-20313 HV Power 0

0 0

0

(

97 X-204A HV Power 2.4 I 0

0 0

98 X-204E Neutron Monitor

.33 0

0 0

99 X-204H Neutron Monitor

.34 0

0 0

100 X-2041 Power & Ground 5.3

~,~-"'5>~

'/.N.-~- -~

'f. Zl. ~ ~2--~

{d."3z.-~

10 I X-204M v Power 3.59 3 i lo _1-.-S--

3,.1(.,.,.h-5--***

102 X-204N CRD Indicators 0

0 0

0 0

103 X-204 Q CRD Indicators

3. 7 I 0

0 0

104 X-204S LV Power & Control

2. 19 i.? z __ _...3......--

'., 1..........--1-is--*--

-;. 1 t.,. I. 5 105 X-20513 CRD Indicators 0

0 0

0 TOTAL THRU LEAKAGE FOR PAGE

.-3 o-:-b" ______

_30.-0---*

'I c /

75. tv-

,qndicates waterllead *present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS-PERFORMED DURING TllE UNIT 3 REFUELING OUTAGE OF 1983-1984 TYPE OF PENETRATION:

DRYWELL BELLOWS SEALS 1982 FINAL

.INITIAL INITIAL THRU FINAL FINAL THR' TEST PENETRATION THRU LEAKAGE LEAK RATE LEAKAGE LEAK RATE LEAKAGE NUMBER NUMBER VOLUME BEING TESTED SCFII SCFH SCFI-1 SCFH SCFH

-~*-2-S->~.

106 X-109A Iso. Cond. Condensate Return 2.01

. ~5~;1.~"?:

n

.l(j 7-f _ 3

• 2 5 - -

"\\

\\

\\.

107 X-149A Core Spray

\\ \\

108\\

X-149B Core Spray

\\

\\

109 X-1 CRD Return

\\

\\

\\

110 X-105A Main Steam Line

\\

--c 111 X-105B Main Steam Line 112 X-105C Main Steam Line I

I 113 X-105D Main Steam Line J

I I

114 X-106 Main Steam Drain I

J I

115 X-107A Feedwater

? 2.79

~

9.33

?

4.665 4.665 116 X-107B Feedwater

\\

\\

\\

I 17 X-11 IA Shutdown Cooling

\\

I

\\

118 X-11 Jn Shutdown Cooling 119 X-128 HPCI Steam Line 120 X-1 i6A LPCI Injection

\\

121 X-l 16B LPCI Injection

/

I 122 X-123 RBCCW Inlet

)

I 123 X-124 RBCCW Outlet I

124 X-126 Vent to Drywell

/

i TOTAL THRU LEAKAGE FOR PAGE

~~-

__:;,92--

'I

,'<Indicates waterliead present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS PERFORMED DURIN-UNIT 3 REFUELI,NG OUTAGE OF 1983-1984 TYPE OF PEN~fRATION:

DRYWELL BELLOWS SEALS 198 2 FINAL

• INITIAL INITIAL THRU TEST PENETRATION THRU LEAKAGE LEAK RATE LEAKAGE NUMBER NUMBER VOLUME BE ING TESTED SCFII SCFH SCFH 125 X-J08A Isa. Cond. Steam Line J

I\\

I\\

126 X-113 Cleanup I

J

)

127 X-125 Vent from Drywe 11 I

(

.821

(

.411 128 X-138 Standby Liquid Control I

)

)

129 X-147 Reactor Head Spray

/

/

I TOTAL THRU LEAKAGE FOR PAGE

.4 I I

, I

>tlndicates waterhead present on one side of valve.

Table 3 FINAL FINAL T.

LEAK RATE

'LEAKAGli.

SCFH SCFH

.4 11 c

c

=

.4 11

LOCAL LEAK RATE TESTS PERFORMED DURING TllE UNIT 3 REFUELING OUTAGE OF I 983-I 98l1 TYPE OF PENETRATION:

DOUBLE CASKETED SEALS 1982 FINAL INITIAL INITIAL THRU FINAL FINAL Tille TEST PENETRATION T!IRll LEAKAGE LEAK RATE LEAKAGE LEAK, RATE LEAKAGE NUMJ3ER NllMllER VOLUME BEING TESTED SCFII SCFH SCFH SCFH

• scFH 130 X-(OO Drywell Equipment Hatch

• 13

.4 15

.208 0

0 131 X-102 CRD Hatch 0

0 0

0 0

c 132 X-135E Spare N/A N/A N/A 133 X-136A TIP Monitor Flange (Spare) 0 0

0 0

134 X-136B TIP Monitor Flange 0

0 0

0 135 X-136C TIP Monitor Flange 0

0 0

0 136 X-136D TIP Monitor Flange 0

0 0

0 137 X-136E TIP Monitor Flange 0

• 145

.07)

.073 138 X-136F TIP Monitor Flange 0

0 0

139 X-136G TIP Monitor Flange N/A*

N/A IL10 X-136H TIP Monitor Flange N/A N/A 141 X-136J TIP Monitor Flange N/A N/A 142 X-137 Drywell Head Manhole 0

0

.o 0

143 N/A Drywell Head Flange

• 2 I

0.

0

.221

• 1 I I IL14 X-301A Torus Vacuum Breaker 1601-32A

.27

.054

.027 0

0 145 X-301A Torus Vacuum Breaker 1601-328

. 9.1

.283

• .142 0

0 146 X-30 IB Torus Vacuum Breaker 1601-:}2C

.39

.036

.018

.238

. I 19 14 7 X-301B Torus Vacuum Breaker 1601-320 0

0 0

0 0

148 X-301C Torus Vacuum Breaker 1601-32E 0

.352

• 176 0

0 149 X-301C Torus Vacuum Breaker 1601-32F 0

.09

.045 0

0 TOTAL THRU LEAKAGE FOR PAGE

.689

.303

'I

• Indicates waterliead present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS PEIH~ORMED REFUELING OUTAGE OF 1983-1984 TYPE OF PE~ETRATION:

DOUBLE GASKETED' SEALS 1982 FINAL INITIAL INITIAL THRU FINAL FINAL Tl TEST PENETRATION THRU LEAKAGE LEAK RATE LEAKAGE LEAK RATE LEAK.AG(

NUMBER NUMBER VOLUME BE ING TESTED SCFll SCFH SCFH SCFII SCFH 150 X-30JF Torus Vacuum Breaker 1601-33A 0

.0725

.036 0

c 0

151 X-301F Torus Vacuum Breaker 1601-33B 0

.0542

.027 0

0 152 X-301E Torus Vacuum Breaker 1601-33C 0

.539

.270 0

0 153 X-30 IE Torus Vacuum Breaker 1601-33D

.4 7

.0716

.036 0

0 154 X-30 ID Torus Vacuum Breaker 1601-33E 1.26

. 11

.055 0

0 155 X-30 ID Torus Vacuum Breaker 1601-33F

.34

.049

.024 0

0 156 X-306A East Torus Access Hatch 0

0 0

0 0

~

15 7 X-306B West Torlls Access Hatch 0

0 p

0 0

158 X-313A East Torus Drain 0

0 0

0 0

159 X-313B West Torus Drain 0

0 0

0 0

160 Shear Lug Hatch ti I 0

0 0

0 16 I Shear Lug Hatch 112 0

0 0

0 162 Shear Lug Hatch 113 0

0 0

0 163 Shear Lug Hatch 114 0

0 0

0 164

. Shear Lug Hatch 115 0

0 0

0 165 Shear Lug Hatch 116 0

0 0

0 166 Shear Lug Hatch 117 0

0 0

0 16 7 Shear Lug Hatch 118 0

0 0

0 TOTAL THRU LEAKAGE FOR PAGE

.448 0

'I

• Indicates waterhead present on one side of valve.

Table 3

LOCAL LEAK RATE TESTS PERFORMED REFUELING OUTAGE OF 1983-1984 TYPE OF PENETRATION:

MISCELLANEOUS TESTS & AUGMENTED TESTS

. INITIAL INITIAL THRU FINAL FINAL THRU TEST PENETRATION LEAK RATE LEAKAGE LEAK RATE LEAKAGE NUMBER NUMBER VOLUME BE.ING TESTED SCFH..

SCFH SCFH SCFH ccsw 3-1510-16"0 Passed ccsw ccsw 3-1514-16"0 Passed Wall ccsw 3-ISIOA-10"0 Passed Penetrations ccsw 3-1505B-12"0 Passed ccsw 3-1512C-12"0 Passed Power Supply to "B II ccsw Pump Passed Hypochlorite 3-4505-3"AS Passed Hypochlorite 3-4506-3 "AS Passed Service Water to Hypochlorite Passed CCSW Vault Door

. 3 I gal/hr Target Rock Pneumatic System 12.3 psig/hr X-312 Piping to Torus from HPCI Drain Pot 0

'I

""2£ ")

... ~ £..,,

>- c; '.9

<..l

'C 6.

-f. /.. *t.. I

/...,o *_'7 c-

_c *z

c. =><;Y:Jr'J)

O~*.r

) "O°C) <;-

c:.,,.,-, 0 71 ? g h/ /,. 0;::,{

7 hOI: X

/ ?OL' J,

-.) ()~) ( x t::"-( f) I '\\.*1°( ~ii *1>*;, ~

~(\\

<f*.'*}-1 "0 l"'./J l "(Y.'

co*/

~o ?fnf:'l_-1 Cl <"*1 <J'°' >~0 f,,_t-11.ttcl ! i "'~

J.)

-..1' r 55, ~6 l..,r'.!.,:y-

<.f! "I

. t '*? (j.

7'>:-;... 7

("... ?' A{,-..,;. Vi'

-- ? 7 //!,/

fV ~.' r-t-*</ '] ! /-'>Jo

('I I

?7J0i'? 3 <">-f iJl'f

~o~

s~,~s~ v~~N

_i.-:t*n