Text

Reactor Containment Bldg Integrated Leak Rate Test
	ML20244C257
Person / Time
Site:	Peach Bottom
Issue date:	01/31/1989
From:	Danni Smith; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 8904200116
	Download: ML20244C257 (88)
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PEACH BOTTOM ATOMIC POWER STATION

. UNIT 2 L .:- p REACTOR CONTAINMENT BUILDING

! - INTEGRATED LEAK RATE TEST.

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JANUARY'1989 m.

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PHILADELPHIA ELECTRIC COMPANY

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4 . TABLE OF CONTENTS.

Title Page-Sect.. Item SYNOPSIS. 1

..A '

1.0 INTRODUCTION

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1 , ;3;0 GENERALiTECHNhCAL. AND TEST DATA 3-'

3.1. GENERAL DATA '3 3.2 ^ '

TECHNICAL DATA' 3' 3.3 TEST DATA :4 ACCEPTANCE CRITERIA 5 4.0 TEST INSTRUMENTATION 6 5.0 5.1

SUMMARY

OF' INSTRUMENTS. 61 5.2 SCHEMATIC ARRANGEMENT 7

5. 3- CALIBRATION CHECKS 7 5.4 INSTRUMENTATION PERFORMANCE' 8 5.5 VOLUME WEIGHTING FACTORS .8

, 5.6- SYSTEMATIC ERROR ANALYSIS 8

.5.7 SUPPLEMENTAL VERIFICATION 12 6.0 TEST PROCEDURE 13 6.1- PREREQUISITES 13 6.2 . GENERAL DISCUSSION 13 6.3 : TEST PERFORMANCE 15 7.0 METHODS OF-ANALYSIS- 17 7.1 ABSOLUTE METHOD '17

7. 2 - STATISTICAL EVALUATION 19

'8.0 DISCUSSION OF RESULTS 21 8.1 RESULTS AT Pa 21 8.2 ' SUPPLEMENTAL TEST RESULTS 23 8.3 AS FOUND ANALYSIS 24 8.4 TYPE B AND C' TESTING 24

9.0 REFERENCES

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TABLE OF. CONTENTS (Cont'd)

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- APPENDICES r A '

' SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION REDUCED TEST DATA i

- B- -

LEAKAGE RATE TEST GRAPHS C -

D -

COMPUTER-RESULTS

SUMMARY

OF LEAKAGE RATE RESULTS

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AS FOUND ILRT. CALCULATIONS

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TYPE B AND C TEST RESULTS W

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L '1. 0 SYNOPSIS

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The Peach Bottom Atomic Power Station Unit No. 2 reactor containment building was subjected to a periodic-integrated

. leak rate test during the period'of January 2 to-January 4,'1989. The purpose of this test was to demonstrate the acceptability of the building. leakage rate at an internal pressure of 49.1 psig (P a). Testing was performed in accordance with'the; requirements of 10CFR50 Appendix ~ J, ANSI N45.4-1972, 'and'-Peach Bottom Atomic Power Station Unit No. 2 Technical Specifications.

The Mass Point method of analysis resulted in a measured leakage rate of 0.208% by weight per day at 49.1 psig. The leakage rate at the upper _ bound of the 95% confidence interval was 0.215% by weight per day. A correction factor of 0.018% by. weight per day for 9 penetrations which were not vented for the test, sump level changes, and HCU accumulator in leakage must be added to the test results.

Therefore, the leakage rate at the upper bound of the 95%

confidence interval is 0.233% by weight per day which is well below the allowable leakage rate of 0.375% by weight

'per day (0.75 L a)*

Using-the minimum pathway _ leakage analysis to determine the leakage savings indicates an additional 0.135% by weight

.per day needs to be added to the_"as left" reactor containment integrated leakage rate. Therefore tL- "as found" containment integratedfleakage rate is 0.368% by weight per day which is below the allowable leakage rate of 0.375% by weight per day.

~T he supplemental instrumentation verification test at Pa demonstrated L1 agreement between measured reactor contair.inent building-integrated leakage rates of 18.4% of .l L,a using the Mass Point method which is within the 25% of L a requirement of 10CFR50, Appendix J, Section III A.3.b.

Testing was performed by Philadelphia Electric Company with the technical assistance,of United Energy Services j Corporation. Procedural and calculational methods were q witnessed by Nuclear Regulatory Commission personnel. l l

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i 7,- 2 2.0: INTRODUCTION The objective of.the integrated leak rate test was.the establishment of the degree of overall leak tightness of

' the reactor containment building at the calculated design basis' accident. pressure of 49.1 psig. _The allowable leakage is defined by the design basis acoident applied in the safety analysis in accordance with site exposure guidelines specified by 10CFR100. For Peach. Bottom Atomic

. Power. Station Unit No. 2, the maximum allowable integrated' leak rate at the design basis accident pressure of 49.1.

psig (P a) is 0.5% by weight per day _(L a)*

Testing was performed in accordance with the procedural requirements as stated in Peach Botton Unit 2 Surveillance Test, Integrated Leak Rate Test ST 12.5. This procedure was reviewed by'the Plant Operations Review Committeeland-approved by the Plant Manager. prior to the commencement of the test.

Leakage rate testing was accomplished at the pressure level of 49.1 psig for a period-of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test period was followed by a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months supplemental test for'a i

verification of test accuracy.

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, Owner: Ph'iladelphia Electric Company. , .

. Docket No.- ~50-277 Location: -Delta, Pennsylvania -

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. Type: - Mark 1, BWR-4 Cont'ainment Steel lined, reinforced. concrete,.

Description:

' light bulb' shaped drywelliwithL torusishaped suppression chamber connected;by..a yent system. . Vacuum breakers are provided between the suppression chamber and both the drywell and reactor-l building. '

'Date Test: January.4, 1989.

Completed:

1 3.2 TECHNICAL DATA Containment Net Free Volume: 293,900 cubic feet Design: Pressure: 56.psig..

Desian Temperature: 281 F Calculated nccident' Peak Pressure: 49.1'psig Calculated '

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. Accident Peak.

Temperature: 283 F i

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4' 3a3' TEST DATA ' '

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, Test Method: . Absolute

/ Data Analysis: Mass Point

., - Test. Pressure: 63.875 psia

' Max Allowable Leakage .

Rate-(La. }:- 0.500'wt 1 per. day; Measured Leakage Rate:

Mass' Point

.O.208 wt.% per' day ,

Measured Leakage Rate at UCL:' ;

Mass Point' O.215 wt % per day

.- 1 Supplemental ]

Test' Flow Rate: 0.500 wt % per day ;

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.i supplemental. -l Test Measured f Leak Rate:-

Mass' Point 0.616.wt % per day

' Supplemental j Test and'L am J 1

Agreement:

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,, Mass Point 18.4% of L a 1

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'4.0' . ACCEPTANCE CRITERIA 1

Acceptance criteria' established prior-to the~ test and as specified by 10CFR50, Appendix J, ANSI N45.4-1972 and the Peach Bottom Atomic Power Station Unit No. 2 Technical

' Specifications are as follows:

1. ' The measured leakage rate (Lam) at the calculated (P -shall be design accident pressure of 49.1 psigless than 75% of the maximum allowab '

(La ), specified as 0.5% by weight of the building

- atmosphere per day. The acceptance criteria is.

determined as follows:

La = 0.5%/ day 0.75 L a = 0.375%/ day .

2. The test instrumentation shall be verified by means of a supplemental test. Agreement between the containment leakage measured during the Type A test and the containment leakage measured during the supplemental test shall be within 25% of L a*

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l; L: 5.0- TEST INSTRUMENTATION

- 5.1'

SUMMARY

OF INSTRUMENTS Test: instruments employed are described, by: system,- in .the following subsections.--

5.1.1;- Temperature Indicatina' System Components:

Resistance Temperature Detectors: -

Quantity: 12.

Supplier. Volumetrics

- Range,fUF 0 to 120 Accuracy,. F +/- 0.1

' Sensitivity,. F +/- 0.01 5.1 2 .

-Dewpoint Indicatina System Dewpoint Sensors:

Quantity 6 Supplier Volumetrics Type Chilled mirror hygrometer Range,; F 40 - 120 dewpoint Accuracy, UF +/- 0.54

. Sensitivity, F +/- 0.1 5 .1. 3 - Pressure Monitorina System Precision Pressure Gauges Quantity 2 (1 operational, 1 standby)'

~,, Manu f acturer - Mensor Type Quartz Manometer Range, psia 0 - 100 Accuracy, psia. ,

+/- .015% of reading +

.00?% of full scale sensor sensitivity, psia +/- c. . :01 Repeatability, psia +/- 0.001 1

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5.1.4 'Sucolemental Test Flow Monitorina' System Flowmeter Quantity 1 Supplier Volumetrics Type Thermal Mass Flowmeter 1

-Range, scfm 0 - 9.73 Accuracy +/- 1% of full scale 5.1.5 Data Acquisition Systen Quantity. .1 Manufacturer Volumetrics Type Model A 100 Accuracy +/.- 0.005% of full scale Repeatability / ~

Resolution +/- 0.'01 0F

+/- 0.001 psia 5.2 SCHEMATIC ARRANGEMENT The arrangement of the four measuring systems summarized in Section 5.1 is depicted in Appendix A.

Drybulb temperature sensors were placed throughout the reactor containment vessel volume to permit monitoring'of internal temperature variations at 12 locations. Dewcells were placed at six locations to permit monitoring of the reactor containment partial' pressure of water vapor.

5.3 CALIBRATION CHECKS Temperature, dewpoint, and pressure measuring systems were checked for calibration before the test as recommended by ANSI N45.4-1972, Section 6.2 and 6.3. The results of the calibration checks are on file at Peach Bottom Atomic Power Station. The supplemental test at 49.1 psig confirmed the instrumentation acceptability.

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8 5.4 INSTRUMENTATION PERFORMANCE The.six dewcells,'12 RTDs, precision pressure gauges,;and flow meter performed satisfactorily throughout the performance of the integrated-leak rate test and provided sufficient: coverage of the reactor primary containment.

5.5 VOLUME WEIGHTING FACTORS.

Weightingl factors wereLassigned to each drybulb temperature

. sensor and' dewpoint temperature sensor based on the calculated volume of the reactor containment building each.

sensing device monitored. Drybulb:and dewpoint temperature sensors weighting factors for the. test were as follows:

Temperature Weighting-Element Factor TE ' 1 0.0603 TE 2 0.0603 TE'3' O.0640 TE 4 0.0640 TE 5 0.0923 TE 6 0.0923 TE 7 0.0522 TE 8 0.0522 TE 9 0.0274 TE 10 0.1450 TE 11 0.1450 TE 12 0.1450 4 DPE 1 0.1206 DPF 2 0.1280 DPE 3 0.1846 DPE 4 0.1318 DPE 5 0.2175 DPE 6 0.2175

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5.6 SYSTEMATIC ERROR ANALYSIS Systematic error, in this test, is induced by the operation of the temperature indicsting system, dewpoint indicating

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system, and the pressure indicating system.

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! Justification of instrumentation selection was L

accomplished,-using manufacturer's sensitivity and repeatability tolerances stated in Section 5.1, by computing the instrumentation selection guide (ISG) formula.

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. 5.6 .' SYSTEMATIC ERROR ANALYSIS ~

(Continued)

Containment leakage. determined.by'the Absolute Method requires accurate measurement of small changes in containment pressure;with suitable corrections for temperature.and water vapor. . -Since the Absolute' Method utilizes the change in a . reading ;(i.e. , pressure and

temperature)-to calculate leak rate,.the repeatability,

sensitivity,'and readability of;the instrument system is of more concern than the accuracy. To perform the ISG~

calculation,.the sensitivity error of the sensor and the ~

. repeatability. error of the measurement system must- be' ~used.

Sensitivity is defined as "the' capability of a sensor to!

respond to change.'" Sensitivity is usually a function of_.

the system measuring the se.sor 7 output. When the. sensor energy state is raised.or lowered an. amount equal to the smallest value.which'the entire system.will process, a change'of indication will occur. To determine sensitivity for'ILRT sensors,.it is necessary to analyze.the smallest value of the analog sensor output which will cause a one

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digit change in,the digital display.

Repeatability is defined as "the capability of the

. measurement system to reproduce'a given reading from a constant source."

Utilizing the methods, techniques, and assumptions in Appendix G to ANS 56.8-1987, the ISG formula was computed

'for the Absolute Method as follows: ,

1. Conditions:

La = 0.5 wt.%/dt/

63.875 psia P =

T = 525.79 R drybulb T dp = 55.77 F dewpoint t = 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months l

2. Total Absolute Pressure: e- p

'No. of sensors = 1 Range = 0 - 100 psia Sensor sensitivity error (E p) = +/- 0.001 psia L

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Measurement 's_ystem error (c p ) : -Resolution: O.001-. psia

. Repeatability: 0.001 psia'

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c p;=;['.(0.001)2 4- (0.001)2') 1/2 1.414'X'10~3 psia; i

-c p' =

ep = ~+ /, -[(E p)2 + (c )2)1/2-p /[no. ._ of. sensors]1/2

.e p =

' +/ ~ [ ('0. 001) 2 + (0.001414)2)1/2 7 [1'3 1/2_

.e p '=~+/. O.001732' psia 3.. Water Vapor Pressure: epy No. of sensors = 6-0 Sensor.' sensitivity error-(Epy) = +/- 0.1 F U

Measurement system error (cEy): Resolution: 0.01 F C excluding sensor Repeatability: 0.01 F

-c py = [ (0. 01) 2 + (0.01)2)1/2 c

py = 0.01414 F

'At a-dewpoint temperature of approximately 56 F, the equivalent water vapor pressure change (as determined from steam' tables) is 0.0081 psia / F

' U Epy = +/- 0.1 F (0.0081 psia / F)

,, E py = +/- 0.00081 psia-0 O c

py = +/- .01414 F (0.0081 psia / F) pv = +/- 0.00011 psia e py = +/- [(Epy)2 + (cp )2)1/2/[no. of sens W 1/2 e py = +/- [(0.00081)2 + (0.00011)2)1/2/[6)1/2 e py = +/- 0.00033 psia

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-4 . Temperature: eT

> ~No..of sensors'= 12 Sensor sensit'ivity error (E T) = +/- 0.01 F0 = +/- 0.01 R 0

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C T = [(O.01)2 + .(0.01)2)1/2 U 0 C

T.= +/- 0.01414 F = +/ >0.'01414 R

+'ICT) )1/2 /.[no, of sensors) 1/2L a

eT " +/~~'.[(ET) ,

1/2 ,

' eT = : +/- :[ ( 0. 01)L 2 + (0.01414)2)1/2 / (12) eT.= +/- 0.00499 R

5. Instrument Selection Guide (ISG):

ep 2 e 2 e 2 1/2' ISG = +/

2400 [2( + 2( py) +2( ) ]

t P) P 2 2 0.00499 2 1/2 ISG = +/ 24 2400(2(0.00173263.875 ) + 2 (0. 00033 63.875

)+2( 525.79 ) ]

I'SG = +/-100(1.470 x 10-9+5.338 x 10-11+1.801 x 10-10) 1/2 ISG = +/- 0.004 wt.%/, day

-The ISG value does not exceed 0.25 La (0.125 wt.%/ day) and it is therefore concluded.that the instrumentation selected was acceptable for use in determining the reactor containment integrated leakage rate.

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12 5.7 SUPPLEMENTAL VERIFICATION In addition to the calibration checks described in Section 5.3, test accuracy was verified by a supplemental test subsequent to the completion of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leakage rate test. This test consisted of imposing a known calibrated leakage rate on the reactor containment building. After the flow rate was established, it was not altered for the duration of the test.

During the supplemental test, the measurec leakage rate was:

L c"L'+L v o l

Where:

Lc = Measured composite leakage rate consisting of the reactor containment building leakage rate plus the imposed leakage rate Lo = Imposed leakage rate 19' = Leakage rate of the reactor i containment building during the supplemental test phase Rearranging the above equation, L'y =L c -L o The reactor containment building leakage during the l Supplemental test can be calculated by subtracting the known superimposed leakage rate from the measured composite 1,eakage rate.

The reactor' containment building leakage rate during the supplemental test (L ')y was then compared to the measured reactor containment building leakage rate during the preceding 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test (Lam) to determine instrumentation acceptability. Test accuracy is considered acceptable if the difference between the two building leakage rates is within 25% of the maximum allowable leakage rate (L ) *a l

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' q 6.0 . TEST PROCEDURE 6.1' PREREQUISITES Prior to commencement of reactor containment building.

pressurization, the following prerequisites'were satisfied:

1. Proper: operation of test instrumentation was verified.

.s 2.. The reactor containment building isolation valves were-

. closed using the normal' mode of operation. 'The' associated system valves were placed in post-accident positions.

.3. -Portions.of_ fluid systems,.which under post-accident' conditions become extensions of the containment.

boundary, were drained and vented to' the extent possible.or the Type C penalty;taken'as appropriate.

'4. Type B.and cl testing was completed with a leskage-value less than 0.6 L a*

5. Containment pressurization system was operational.

6. Drywell cooling fans were in operation.

7. . Potential pressure sources were removed or isolated.

from the containment.

8. An inspection of the accessible interior and exterior surfaces of the containment was completed.

6.2 GENERAL DISCUSSION F.ollowing the satisfaction of the. prerequisites stated in Section 6.1, the reactor containment building --

pressurization was initiated at a rate of approximately 7.3 psi per hour. After containment conditions had stabilized, leak rate testing was initiated at the 49.1 psig pressure level, t

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j 6.2, GENERAL DISCUSSION (Continued)

During the test the following occurred at 15 minute intervals (see Appendix B - Reduced Leakage Data). ;

a Readings indicated by the precision pressure gauges j 1.

were recorded and entered automatically into the l computer.

2. Readings indicated by the 12 RTDs were recorded and automatically entered into the computer. The computer program calculated the weighted average containment builc'ing drybulb temperature by use of a weighting factor that was assigned to each RTD. This value was subsequently converted to degrees Rankine for use in the ideal. gas law equation to calculate containment ~

I building weight of air.

3. Readings indicated by the six dewpoint temperature sensors were recorded and automatically entered into the computer. The computer program converted the readings to dewpoint temperatures and then calculated the average containment dewpoint temperature by use of ;

a weighting factor assigned to each sensor. This weighted average dewpoint temperature was then converted to a partial pressure of water vapor.

The use of water vapor pressure (P , temperature (T), and the total pressure (P t) is describ5E)in more detail in i

Section 7.1.

Data was entered into an IBM AT Portable Computer located at the leak rate panel. The ILRT computer program utilized for the test had been previously checked with sample data of known results and certified prior to the test. The 6cmputer program then calculated the following at 15 minute intervals:

1. Total weight of containment air.

2. Mass point least squares fit leakage rate.

3. Mass point 95% upper confidence level leakage rate.

4. Observed total time leakage rate.

5. . Total time mean leakage rate.

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j 6.2 GENERAL DISCUSSION l (Continued)

! 6. Total time least squares fit leakage rate.

7. Total time 95% upper confidence level leakage rate.

! A plot of weighted average containment temperature, 5' containment total pressure, containment average dewpoint temperature, and weight of air was performed for each 15 minute data set (see Appendix C).

Immediately following the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months leak test, a superimposed leakage rate was established for a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months test period.

During this time, temperature, pressure, and vapor pressure were monitored as described above.

I i 6.3 TEST PERFORMANCE l

6.3.1 Pressurization and Stabilization Phase

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j Pressurization of the reactor containment building was started at approximately 0625 on January 2, 1989. The pressurization rate was approximately 7.3 psi per hour.

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During pressurization, a leak survey of the containment

- isolation valves found no significant leakage. When i j containment' internal pressure reached 63.77 psig at approximately 1810 on January 2, 1989, pressurization was By 2230, on January 2, 1989, temperature secured.

stabilization criteria had been met.

6.3.2 Intearated Leak Rate Testina Phase >

At 2236 on January 2, 1989, 15 minute frequency test data collection was initiated. At 0700 on January 3, 1989, the 1.eakage rate calculations at the upper 95% confidence interval were 0.53%/ day (total time) and 0.36%/ day (mass point). Both total time and mass point leakage rates 4 showed a decreasing trend. A decision was made to proceed with a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mass point leakage rate test. At 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months on January 3, 1989, the hass point upper confidence leakage rate was 0.272%/ day and continued to show a slow decrease.

At 2236 on January 3, 1989, the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months integrated leakage rate test was concluded with an upper 95% mass point i

leakage rate of 0.215%/ day. .

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. 6.'3.3 Sucolemental Leakace Rate Test Phase

= Following completion of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months integrated leak rate test, a leakage rate of 4.43 scfm was imposed on the containment building through a calibrated thermal flow meter at 2240 on January 3,'1989. Leakage' rate data was

' again collected at 15 minute. intervals beginning at 2252 on January 3, 1989, for a period of.4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . With an imposed leak rate of 0.500%.per day, a measured composite leakage-rate of 0.616% per day was obtained using the Mass Point'

. method. This results in a containment building leakage rate agreement of 18.4% of L with the results'of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months _

test. This value is wi$hin the acceptance' limit 'of 25% of _.

I. L* a 6.3.4 Drvwell to Torus Bvoass Test .

i After. required data was obtained and evaluated, containment

- building.depressurization to conduct the Drywell to Torus Bypass test was started. The test was started at 0851 on January.5, 1989 and was.successfully-completed after 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The calculated bypass area was 0.0446 square inches which-is well below the maximum allowable value of 0.785 square inches. Subsequently, the drywell and. torus were depressurized to^0 psig and a post test inspection revealed no unusual findings.

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7.0' METHODS OF ANALYSIS r

' 7 .1 ABSOLUTE METHOD 7.1.1- General ,

The Absolute Method of leakage rate determin tion was' employed during testing at the 49.1 psig pressure level.

The ILRT computer code calculates the percent per day leakage rate using the mass point method.

7.1.2 ' Mass Point Analysis The. Mass Point method ofEcomputing leakage rates'.uses the followingfideal gas law equation to; calculate.the weight of air inside containment for each 15 minute interval:

y. 144 PV , ]2 RT R Where:

W= Mass:of air inside containment, lbm 5 lbm OR - in.2 K=- 144 V/R = 7.93282 x 10 bf P.= Partial pressure of' air, psia T= Average internal containment temperature, R V= 293,900 ft 3 Ibf - ft

',R= 53.35 lbm- R The partial pressure of , air, P, is calculated as follows: i P= PT-Pyy 1

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A 18 7.1;2 Mass Point Analysis (Continued)

Where:

a. PT = Total containment pressure Pyy = Partial pressure of water vapor determined by averaging the six dewpoint temperatures and converting to partial pressure of water vapor, psia The average internal containment temperature, T, is calculated as follows:

1 T= y E 11 i Ti i Where:

th sensor Vfi = Volume fraction of the i Ti = Absolute temperature of the i th sensor The weight of air is plotted versus time for the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test and for the 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months supplemental test. The ILRT computer code fits the locus of these points to a straight line using a linear least squares fit. The equation of the linear least squares fit line is of the form W = At + B, where A is the slope in Ibn per hour and B is the initial weight at time zero. The least squares parameters are calculated as follows:

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A= N ( E t,1 W.)

1 -

( E t,)

1 ( E W.)

1 S

xx E t.2 It B= I 1 ) I I W.1 ) -

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1 ( i W.)

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Where: .

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-S xx =N . ( 'I ti) -

(E t i)2 N = Number of-data points s ,

.W i- = Measured mass.of containment air

-t i

' = Time interval The weight percent leakage per day can then be determined

>from the following equation:

g , -2400 A .

am B

where the. negative sign is used.since A is a negative slope to' express the leakage rate as a positive quantity.

7.2 STATISTICAL EVALUATION

i. 7.2.1 General After performing the least squares fit, the ILRT computer code calculates the limits of the 95 percent confidence interval for the mass point leakage rate (Cg ).

This statistical parameter'is then used to determine that the measured leakage rate plus the 95 UCL meets the j a'cceptance cr,iteria.

7.2.2 Mass Point Confidence The upper.95 percent confidence limit for the mass point leakage rate is calculated as follows:

Cg = 2400 t95 (SA/B) ,

Where:

C3 = Upper 95 percent confidence limit t95 = degrees Student's t distribution with N-2 of freedom

>S A = Standard deviation of the slope of the ,

t least squares fit line L

h

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

-9; .; e e' 21 r' m e HB.0, DISCUSSION OF RESULTS

8. l' RESULTS AT'P a

Mass Point Method of' Analysis' Data obtained during the leak rate' test'at'Pa indicated the following changes (highest to-lowest) during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

- test.

s Variable Maximum Chance P

T 0.383 psia -

P yy 0.0017 psia T 0.786 0 F

'The.nethod used in calculating the MassEPoint leakage rate' is described in'Section 7.1.2. The results~of this calculation is a mass point leakage' rate'of 0.208%/ day (see

-Appendix D)..

The.95 percent confidence-limit associated with this leakage rate ~is 0.007% per day. Thus, the leakage' rate at' ,

-the. upper., bound of the 95 percent confidence level becomes:

UCL = 0.208 + 0.007 UCL'=-0.215%/ day Additional leakage rates must be applied-to the measured leakage rate at the upper 95 percent confidence level to l account'for penetration paths not exposed to the test pressure and for changes in the net free volume of the containment due to water level changes. Penetration paths not exposed to the test pressure'and the corresponding 1,eakage rates based on analysis of minimum pathway local leakage rate testing are as follows:

Minimum Pathway Containment Local System Isolation Valves Leakace Rate (SCCM)

Shutdown Cooling MO-10-017 206 Reactor Building MO-2373 35 Cooling Water MO-2374 30 l

1

-~ ,.. - . _ ,.

o 3- .

y. .; .- ..

.e 22

.i

' 8 . 14

. RESULTS AT'P 3

.(Continued)

Minimum-Pathway.

Containment Local L System Isolation Valves Leakace Rate (SCCM) l-Drywell Chilled. MO-2200 A 1171 Water MO-2200 B 974 t- MO-2201 A 591 MO-2201 B. 448 -

ILRT Test ,- 7A-29871/7A-29872 10 Valves. 7A-29873/7A-29874 10 7A-29875/7A-29876 , 10

'Drywell' Floor A0-20-082/ 10 Drain Sump A0-20-83 Drywell Equipment A0-20-094/ 10 Drain Sump A0-20-095 PCAC Sample '40 The total applicable local leakage rate is 3545'secm which is equivalent to a leakage rate of 0.014%/ day.

Water level changes in the containment during the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

. integrated leakage rate test are summarized below:

Reactor Vessel Water Level / Torus Water Level:

Durir.g the test, both the reactor vessel level and' torus level showed a decrease. The decrease in levels is~

, accounted for in the calculated containment integrated leakage rate and no further correction is required.

7 Drywell Sump Level:

During the test, the drywell equipment ~ drain sump and the drywell floor train sump each showed a 3 inch increase in level. This level increase is equivalent to a decrease

'in the containment net free volume of 566 secm, which equates to an addition of 0.002% wt/ day to the calculated integrated leakage rate.

C -__.__m__ _ . ._ _ _ _ _ . _ _ _ _ _

.- e q

, 23 8.1 RESULTS AT P a (Continued)

Since the HCU accumulators were not vented for the test,

_ pressure readings were taken prior to the start of'the test and at the end of the test. The pressure changes were equivalent to an addition of 0.002%/ day to the calculated integrated leakage rate.

The total containment leakage' ra'te at the upper 95 percent confidence level (UCL) is calculated as follows:

UCL = Lam + 95 percent confidence limit +

Type C leakage + changes in net free ,

volume + HCU accumulator leakage UCL = 0.208%/ day + 0.007%/ day + 0.014%/ day +

0.002%/ day + 0.002%/ day UCL = 0.233%/ day This value is below the acceptance criteria leakage rate of 0.375%/ day.(.75L a)*

Therefore, the reactor containment building leakage rate, based on the mass point method of analysis, at the calculated design basis accident pressure (P a) Of 49 1 PSI 9 is acceptable.

8.2 SUPPLEMENTAL TEST RESULTS 9

After conclusion of the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test at 49.1 psig (P a), the flowmeter was placed in service and a flow rate of 4.43 scfm was established. This flow rate is equivalent to a leakage rate of 0.500% per day. After the flow rate was established it was not altered for the duration of the supplemental test. The measured leakage rate (L during the supplemental test was calculated to be 0.616k)per day using the Mass Point method of analysis.

The building leakage rath during the supplemental test is then determined as follows: 1 L'

y

= L c ~L o L'

y

= 0.616 - 0.500 L'

y

= 0.116%/ day

$1i ,

e .

c 3 (. .

, 24 I

8.2 SUPPLEMENTAL TEST RESULTS 1 (Continued)- .

Comparing this leakage rate with the building leakage rate' A -measured during.the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months test yields the following:

L L '-

r Mass-Point =- am v '= .208 - .116 - = - 0.184 L La 0.5 Thel building leakage rates agree within 18.4%fof L a

~

using the. Mass Point method which is below the acceptance-criteria of 25% of L a*

-Using the formulation of ANS 56.8-1987, ;

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

(0.500 +'O'208 - 0.125):5Lci (0.500 + 0.208 +-0.125) 0.583 I'Lc I'O.833 Since L -was measured.to be.0.616%/ day, this value falls.

l within She acceptable range of 0.583% to 0.833% per day.

Therefore, the: acceptability of the test instrumentation is' considered to have been verified.

8.3' _AS FOUND ANALYSIS L .To determine the as-found containment leakage' rate, an i analysis was performed to evaluate any leakage savings from

' repairs or maintenance to containment isolation barriers. '

Leakage savings are realized when' containment isolation barrier repairs or maintenance result in a lower minimum p,athway leakage than that which existed prior to the. repair or maintenance. The results of'the analysis are presented in Appendix F.

l 8.4 TYPE B AND C TESTING The results of- the Type B and Type C tests conducted since the last containment integrate leakage rate.on Peach Bottom .

Atomic Power Station Unit 2 in 1985 are presented in Appendix G.-

m i i r i__ _ __ _ = = n _ _ _ ____ ___ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

l

.. =..-

25 -

i 9.O PREFERENCES

1. ST-12.5, Integrated Leak Rate Test.

2. ' Peach Bottom Atomic Power Station Unit No. 2. Final .,

Safety Analysis Report, and Technical Specifications. ,

.3. .-C,o d e of-Federal Regulations, Title 10, Part 50, Appendix J.

l ANSI N4,5.4-1972, . Leakage Rate Testing of' Containment

~

4.

' Structures for Nuclear Reactors, American. Nuclear-Society.(March 16,~1972).

ANS-56.8-1987, " Containment System Leakage' Testing 5.

Requirements", American Nuclear. Society.

6.- ILRT'Compu.ter Code, Gilbert Services, Inc.

a< -

7. Steam Tables, American Society of Mechanical Engineers, 1967.

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APPENDIX A SCHEMATIC ARRANGEMLn!' OF-TEST INSTRUMENTATION ,

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APPENDIX B REDUCED TEST DATA f

9 9

l k

l J

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.j

i I

REDUCED ILRT TEST, DATA DATE TIME PAVG PWV TAVG MASS WEIGHT-01-02-89 2236 63.875 0.2200 66.102 96038.05 2251 63.864 0.2203 66.016 96037.92 2306 63.856 O'2199 66.002 96028.65 2321 63.847 0.2198 65.935 96027.27 2336 63.840 0.2198 65.898 96023.20 2351 s 63.832 0.2197 65.841 96021.57 01-03-89 6 63.823 0.2190 65.809 96014.45 21- 63.816 0.2192 65.777 96010.84 36 63.809 0.2189 65.704 ~ 96013.91 51 63.801 0.2194 65.663 96008.38 106 63.795 0.2192 65.650 96001.84 121 63.789 0.2188 65.622 95998.30 136 63.781 0.2185 63.579 95994.26 151 63.775 0.2184 61.549 95990.59 206 63.769 0.2184 65.505 95989.47

(. 221 63.762 0.2183 65.503 95980.66 236 63.756 0.2181 65.456 95980.45 251 63.750 0.2182 65.376 95985.70 306 63.745 0.2181 65.408 95972.12 321 63.739 0.2178 65.372 95969.91 336 63.734 0.2178 65.347 95966.76 351 63.729 0.2178 65.330 95962.27 406 63.724 0.2176 65.300 95960.34 421 63.720 0.2174 65.300 9595.4.55 436 63.718 0.2176 65.270 95956.52 451 63.714 0.2179 65.310 95944.18 506 63.709 0.2180 65.248 95947.56 521 63.706 0.2156 65.273 95937.71 536 63.702 0.2164 65.260 95934.22 551 '3.697 0.*165 2 65.194 95938.31 606 63.694 0.2185 65.198 95932.91 621 63.689 0.2180 65.124 95939.41 636 63.685 0.2184 65.130 95931.67 651 63.682 0.21G3 65.150 95923.55 706 63.678 0.2181 65.072 95931.86 721 63.673 0.2181 65.084 95922.10 736 63.669 - 0.2181 65.032 95925.49 751 63.664 0.2178 65.020 95920.20 806 63.659 0.2177 65.003 95917.50 821 63.654 0.2178 64.982 95913.35 1 836 63.650 0.2176 64.938 95915.44 851 63.646 0.2173 64.924 95912.46 906 63.642 0.2170 64.922 95907.09 921 63.637 0.2169 64.904 95902.92 936 63.634 0.2170 64.864 95905.42 i

f

== =- _ _ . _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ - _ - __. _ _ _ _ . ______:__-___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

REDUCED ILRT. TEST DATA

- DATE- TIME' PAVG PWV TAVG MASS WEIGHT 01-03-89 951 63.630 0.2168- 64.888 95894.98-1006 63.628 0.2171 64.815 95904.88 1021 63.624 0.2170. '64.809 95900.02 1036 63.621 0.2170' 64.778 95901.15 1051 63.617 0.2170 64.763 95897.70 1106 63.614 0.2171 '64.776 95890.50 1121 63.609 0.2168 64.721 95894.94 1136 63.606- 0.2168 64.705 95892'.99 1151 63.602 0.2169 64.697 95888.21 _.

1206 -63.599 0.2166 64.666 95889.65-1221 63.596 0.2165 '64.675 95883.55 1236 63.594 0.2166 64.652 95884.48-1251 63.590 0.2168 '64.631 95881.83 1306 63.587 =0.2168 64.593 95884.31 1321 63.585 0.2165 64.623 95876.18 1336 63.582 0.2168 64.580 95879.02' 1351' 63.580 0.2166 64.571 95877.91-1406 '63.577 0.2169 64.571 95872.71 14211 63.575 0.2166 64.544 95875.04 1436 -63.571 .O.2167 64;527 95871.85 1451 63.569 0.2165 64.518 95870.55 1506 63.566 0.2164 64.502 95869.27:

1521 63.563 0.2164 64.487. 95867.21 1536- 63.560 0.2164 64.456 '95868.24 1551 63.556 0.2162 64.461- 95862.96-1606 63.554 0.2166 64.453 95860.87 1621. 63.550 0.2168 64.430 95858.59 1636' 63.547 0.2165 64.392 95861.36 1651- 63.545 0.2164 64.409 95855.33 1706 63.542 0.2158 64.377 95857.42 1721 63.540 0.21o2 64.367 95855.55 1736 63.538 0.2160 64.367 95852.90 1751 63.535 0.2162 64.356 95849.75

' 1806 63.534 0.2162 64.315 95855.83 1821 63.530 0.2162 64.293 95853.61 1836 63.529 0.2161 64.280 95854.63 1851 63.526 0.2160 64.291 95848.03 1906 63.523 0.2162 64.250 95850.68 1921 63.521 0.2157 64.281 95842.59 1936 63.518 0.2161 64.248 95843.52 1951 63.516 0.2162 64.227 95844.22 2006 63.514 0.2158 64.226 95841.81 l

l- 2021 63.511 0.2159 64.215 95838.98 L 2036 63.510 0.2159 64.221 95836.41 2051 63.507 0.2157 64.202 95835.55 i

1 b__m_

_ _ _ _ _ _ _ _ . _ ______._m______ _.._ _ _ _ - _ _ #_ _ _ _ _ _ m ____._

i 9

REDUCED ILRT TEST DATA ,

DATE TIME PAVG PWV TAVG MASS WEIGHT 01-03-89 2106 63.504 0.2158 64.201 95832.36 2121 63.502 0.2157 64.164 95836.35 l 64.122 95839.44 !

2136 63.499 0.2156 -

2151 63.498 0.2155 64.161 95830.97 2206 63.495 0.2154 64.137 95830.80 (

2221- 63.493 0.2159 64.125 95829.23 l 2236 63.492 0.2157' 64.102 95832.31 {

VERIFICATION TEST DATA f i

2252 63.486 0.2157 64.121 95819.54 2307 63.481 0.2155 64.106 95814.80- 1 2322 63.475 0.2156 64.082 95809.88 l 2337 63.471 0.2156 64.088 95802.47 2352 63.465 0.2156 64.049 95800.48 01-04-89 7 63.460 0.2154 64.068 95789.49 22 63.455 0.2157 64.035 95787.23 37 63.449 0.2155 64.032 95780.58 52 63.444 0.2157 64.036 95771.73 107 63.439 0.2159 64.019 95766.83 95753.69 122 63.433 0.2156 64.043 137 63.428 0.2156 63.991 95755.42 152 63.422 0.2154 63.993 95746.09 207 63.417 0.2155 63.990 95738.81 222 63.412 0.2156 63.967 95735.16 237 63.407 0.2152 63.954 95730.33 252 63.401 0.2156 63.925 95725.82

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APPENDIX C LEAKAGE RATE TEST GRAPHS

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L EOS ME I \

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W s E H ER E -

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/

\ . s APPENDIX D

' COMPUTER RESULTS e

0 t

Y l

\

l r

I

. . . . .. . . l

INTEGRATED LEAK RATE TEST R E S LJ L T S by GILBERT / SERVICES INC.

CURRENT DATE : 01-24-1989

- - MASS POINT ANALYSIS ***

- - ILRT ***

. FROM 2236 (01/02/89) TO 2236 (01/03/89)

TIME 095. WEIGHT OBS. MIN. CALC.

INTERVAL (LB) (LB)

O 96038.06 27.89603

.25 96037.92 29.8433

.5 96028.65 22.64994

.75 96027.27 23.35502 1 96023.2 21.35698 -

1.25 96021.57 21.81206 1.5 96014.45 16,77495 1.75 96010.84 15.24565 2 96013.91 20.38823 2.25 96000.38 16.94487 2.5 96001.84 12.47808 2.75 95998.31 11.02691 3 95994.26 9.060113 3.25 95990.59 7.47613 q

3.5 95989.47 8.43121 3.75 95980.66 1.698789 l 4 95980.45 3.567931 4.25 95985.7 10.89801 4.5 95972.12 .6000351 4.75 95969.91 .7230805 5 95966.76 -1.799251 5.25 95962.27 -4.203547 5.5 95960.34 -4.053155 5.75 95954.55 -7.76995 6 95956.52 -3.713308 6.25 95944.18 -13.97698 .

6.5 95947.56 -8,514086 6.75 95937.71 -16.28557 7 , 95934.22 -17.69768 7.25 95938.31 -11.52385 7.5 95932.91 -14.84221 7.75 95939.41 -6.262126 8 95931.67 -11.92.423 l 8.25 95923.56 -17.96134 8.5 95931.86 -7.576575 j 8.75 95922.1 -15.25431 9 95925.49 -9.783603 9.25 95920.2 -13.0004 9.5 95917.5 -13.61563 9.75 95913.35 -15.68399 10 95915.44 -11.51797 10.25 95912.46 -12.41446 10.5 95907.09 -15.70938 10.75 95902.92 -17.79336 )

11 95905.42 -13.21328 1 ---_ i

~

13 ,

-1

'1 3 , ]

l 1

)[ . 01-24-19E LTI'ME OBS. WEIGHT 'OBS. MIN.~ CALC.

M ~ INTERVAL ('B)

L -(LB) 11.'25' 95894.98 ' -21.5707 11.5- 95904.88. -9.592182

.11.75 -95900.02 .-12.37148 12- 95901.15 -9.166398' 12.25 95897.7 -10.53944 12.5 95890.5 -15.65468 12.75: 95894.94 -9.137097 1 3 13- 95892.99 -9'00233 13.25 95888.21 -11.7035 ^ ~~ ~

13.5 ~ 95889.65 -8.185921; 13.751 95883.55 -12.2074, 114 95884.48' -9.197637 14.25' 95881.83 -9.765995 14.5 95884.31 -5.20154 _

14.75' .95876.18 -11.25427

~15 .

.95879.02 -6.338256-15.25 .95877.91 -5.367551

- 15.5 95872i71 -8.482784 15.75 95875.04- --4.07458

'16 95871.85 -5.182

.16.25: .95870.56 -4.398796 '

16.5 95869.27 -3.607779 16.75 95867.21 -3.582387-17- .95868.24 .4710569 17.25 95862.96 -3.672227 L1'7.5 95860.87 -3.685898

17.75 95858.59 -3.887068

,18 95861.36 .9664488 ,

1:8.25- 95855.33 -2.984722 18.5 95857.42 1.189108.

18.75' 95855.56 . 1.402 19 95852.9 .8258296

'19.25 95849.75 .2425284 19.5 ,r 95855.83 7.915676 19.75 95853.61 7.777006 20- 95854.63 10.87271 20.25 95848.03 6.35904 20.5' 95850.68 11.08?56 20.75 95842.59 5.073886 21 95843.52 8.083654 21.25 95844.22 10.86686 21.5 95841.81 10.54069 21.75 95838.98 9.7C483 2 2 ..- 95836.41~ 9.294S?7 22.25 95835.56 10.52311 l

---z_- _

i

l I

01-24-1H I TIME OBS. WEIGHT OBS. MIN. CALC.

INTERVAL (LB) (LB) 22.5 95832.36 9.407881 ,

22.75 95836.35 15.48015 23 95839.44 20.64617 23.25 95830.97 14.25749 23.5 95830.8 16.1657 ]

95829.23 16.67547 j 23.75 21.84148 l 24 '

95832.31 WO = 96010.15865473122 LB W1 = -8.320318252945508 LB/HR LEAKAGE RATE = .207986 % PER DAY

THE 95% UPPER CONFIDENCE INCREMENT = 7.467175E-03 % PER DAY UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = .2154531 % PER DAY *

RATE IS <. 75% OF LA ( .375 )

e

._-___CA__-_me_.,., _ _ _ _ _ _

o

.n . .: .,

INTEGRATED L_ E A K RATE TEST' R E S LJ L_ T S by GILBERT / SERVICES'INC.,

CURRENT DATE ::01-24-1989

/*** (M ASS- POINT A N A L_ Y S I S '* * *

- - ILRT ***

FROM 2252 (01/03/89)-1TO 252 (01/04/89),

i I ' TIME. OBS. WEIGHT-' OBS. MIN. CALC.

' INTERVAL (LB)- '(LB) 0- 95819.54 -1.898744

.25 95814.81 .4854473

.5 95809.88L -.7325368-p . .75. 95802.47 .5260417-E l 95800.48 .3.637255 - -

1.25 95789.49 -1.207261:

' 1.5 95787.23 2.682598 1.75. 95780.58 .2.17402 2 .95771.73' .5298713 2.25 95766.83 .7193627 -

2.5. 93753.69 ' -6.273591 2.75' 95755.42- 1.608456 3 95746.09 --1.571998 1

3'.25 95738.81 -2.705576

-3.5 95735.16 .2063419 3.75' 95730.33 1.105392 4 _ 95725.82 2.745251 WO = 95821.43780637255- LB-W1 = -24.5906862745098 LB/HR LEAKAGE RATE = . 6159128 % PER-DAYL

-THE 95% UPPER CONFIDENCE INCREMENT = 2.160389E-02 % PER DAY UPPER LIMIT OF THE 95% CONFIDENCE LEVEL = .'6375167 % PER DAY

RATE'ISS<-75% OF LA ( .375 ) ,

i L . - . . . . .- - . .

,a e I

a r

\ \

APPENDIX E

SUMMARY

'OF LEAKAGE RATE RESULTS r

I l

j

_ man.x_ _ _ _ . - - - - - - -. _ _ - ~ _ _ _ . - _ . - _ -

.' . V .: ..

101-24"1989:

l L* * *

SUMMARY

OF~ L_ E A K ' R A T E - R E S U L_ T S ***

- - ILRT **t- l I

'FOR :1 PHILADELPHIA-ELECTRIC CO.

~

PEACH BOTTOM UNIT.2 FROM '2236 (01/02/89) TO 2236-(01/03/89)

/ TOTAL < 24 > 24 MASS MASS. . UCL POINT:

TIME WEIGHT TIME UCL UCL 2236L 96038.055 12251' 96037.922 2306- 96028.648

'2321 96027.273 2336 96023.195 -

O.4480 -1.4095 0.9193 0.4035- 0.5703 2351 '96021.570 0.4155- 1.0933 0.7344 0.3655- 0.4748 6 96014.453 0.4292 ~ O.9470 .O.6663 0.3890 .O.4670 21- 96010.844 0.4332 0.8651 0.6256 0.3964. O.4531 O.3980- 0.7975 iO.5710 0.3531 O.4170;

'36 96013.906-51: 96008.383- 0.3845 0.7451 0.5363 0.3418. O.3933

106 96001'.836 O.3859 0.7125 0.5197 0.3499 0.3922 121= 95998.305 0.3863 0.6,866 0.5060 0.3547 0.3899 136- 95994.258 O'.3872 0.6663 0.4957 0.3592 0.3891 151 95990.594 0.3877~ O.6494 0.4869 0.3623 0.3878 206 95989.469 0.3832 0.6313 0.4751 0.3580. O.3804 221 .95980.656 0.3881- 0.6231 0.4732 0.3667 0.3881 2361 '95980.445- O.3867 0.6111 0.4662 0.3659 0.3847 251 95985.695. O.3742 0.5934 0.4502 0.3497 0.3730 306 95972.117 0.3758 0.5860 0.4472 0.3540 0.3752 95969.914 0.3756 0.5780 0.4429 0.3552 0.3743

.321 0.5703 0.4387 0.3556 0.3728.

336 95966.758 0.3749 351 95962.273 0.3750 0.5640 0.4356 0.3570 0.3727 406 95960.344 0.3737 0.5572 0.4316 0.3563 0.3706 421 95954.547 0.3742 0.5523 0.4294 0.3580 0.3711 436 95956.523 0.3709 0.5447 0.4239 0.3542 0.3668, 451 .95944.180 0.3735 0.5425 0.4242 0.3587 0.3712 506- 95947.563 0.3716 0.5367 0.4204 0.3567 0.3684 521 95937.711 0.3733 0.5344 0.4201 0.3598 0.3711 536 959,4.219 3 0.3746 0.5319 0.4197 0.3622 0.3729 551 95938.313 0.3722 0.5266 0.4158 0.3592 0.3696 606 95932.914 0.3709 0.5222 0.4131. O.3578 0.3677 621 95939.414 0.3657 0.5154 0.4069 0.3510 0.3624 636 95931.672 0.3628 0.5100 0.4028 0.3475 0.3588 651 95923.555 0.3618 O'.5064 0.4006 0.3470 0.3576 706 95931.859 0.3571 0.5001 0.3949 0.3410 0.3526 721 95922.102 0.3548 0.4956 0.3916 0.3388 0.3499 736 9592t.492 0.3508 0.4899 0.3867 0.3340 0.3455 751 95920.195 0.3477 0.4850 0.3828 0.3307 0.3421 806 ,95917.500 0.3448 0.4803 0.3790 0.3277 0.3388 821- 95913.352 0.3424 0.4760 0.3757 0.3254 0.3362 836 95915.438 0.3389 0.4710 0.3715 0.3216 0.3325 851 95912.461 0.3357 0.4662 0.3676 0.3182 0.3291 906 95907.086 0.3332 0.4621 0.3644 0.3160 0.3266 l 921 95902.922 0.3312 0.4584 0.3616 0.3143 0.3246 936 95905.422 0.3282 0.4540 0.3580 0.3113 0.3215 I

A _: -_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

01-24-1989

SUMMARY

O Fr LEAK RATE R E S U L_ T S ***

- - ILRT ***

FOR : PHILADELPHIA ELECTRIC CO.

PEACH BOTTOM UNIT 2 FROM 2236 (01/02/89) TO 2236 (01/03/89)

MASS TOTAL < 24 > 24 MASS '

WEIGHT TIME UCL UCL POINT UCL TIME 951 95894.984 0.3268 0.4511 0.3560 0.3106 0.3204 1006 95904.883 0.3232 O.4463 O.3518 0.3066 O.3168 1021 95900.023 0.3202 0.4421 0.3482 0.3035 0.3137 1036 95901.148 0.3167 0.4375 0.3442 0.2998 0.3102 1051 95897.695 0.3136 0.4333 0.3406 0.2966 0.3070 1106 95890.500 0.3113 0.4297 0.3378 0.2947 0.3049 1121 95894.938 0.3081 0.4255 0.3342 0.2914 0.3017 ,

1136 95892.992 0.3050 0.4214 0.3306 0.2883 0.2986 1151 95888.211 0.3024 0.4176 0.3276 0.2858 0.2961 1206 95889.648 0.2994 0.4136 0.3241 0.2829 0.2932 1221 95883.547 0.2971 0.4102 0.3213 0.2808 0.2909 1236 95884.477 0.2944 0.4065 0.3182 0.2782 0.2883 1251 95881.828 0.2919 0.4029 0.3153 0.2759 0.2859 1506 95884.313 0.2889 0.3991 0.3120 0.2730 0.2830 1321 95876.180 0.2867 0.3959 0.3094 0.2712 0.2810 1336 95879.016 0.2841 0.3923 0.3064 0.2687 0.2785 1351 95877.906 0.2814 0.3888 0.3034 0.2662 0.2760 1406 95872.711 0.2792 0.3857 0.3008 0.2643 0.2739 1421 95875.039 0.2766 0.3822 0.2979 0.2618 0.2715 1436 95871.852 0.2742 0.3790 0.2952 0.2597 0.2693 1451 95870.555 0.2719 0.3758 0.2925 0.2575 0.2671 1506 95869.266 0.2695 0.3726 0.2899 0.2554 0.2649 1521 95867.211 0.2673 0.3695 0.2873 0.2534 0.2628 1536 95868.242 0.2648 0.3663 0.2846 0.2511 0.2605 1551 95862.961 0.2627 0.3634 0.2822 0.2494 0.2586 1606 95860.867 .O.2607 0.3607 0.2800 0.2477 0.2569 1621 95858.586 0.2588 0.3580 0.2778 0.2462 0.2552 1636 95861.359 0.2566 0.3550 0.2753 0.2442 0.2531 1651 958,55.328 0.2548 0.3524 0.2732 0.2427 0.2516 l 1706 95857.422 0.2527 0.3497 0.2709 0.2409 0.2497 1721 95855.555 0.2507 0.3470 0.2687 0.2392 0.2479 1736 95852.898 0.2488 0.3444 0.2665 0.2376 0.2462 1751 95849.750 0.2471 0.3420 0.2646 0.2362 0.2447 1806 95855.828 0.2449 0.3391 0.2621 0.2341 0.2427 1821 95853.609 0.2428 0.3364 0.2598 0.2322 0.2407 1836 95854.625 0.2406 0.3335 0.2574 0.2301 0.2386 1851 95848.031' O.2387 0.3311 0.2553 0.2285 0.2370 1906 95850.680 0.2367 0.3284 0.2531 0.2266 0.2351 1921 95842.586 0.2350 0.3262 0.2512 0.2254 0.2337 i 1936 95843.516 0.2333 0.3238 0.2493 0.2239 0.2322 1951 95844.219 0.2315 0.3214 0.2473 0.2224 0.2306 2006 95841.813 0.2297 0.3191 0.2454 0.2209 0.2290 2021 95838.977 0.2281 0.3169 0.2436 0.2196 0.2276 2036 95836.406 0.2266 0.3148 0.2418 0.2184 0.2263 2051 95835.555 0.2250 0.3128 0.2401 0.2172 0.2250

_ _ ~ - - _ _ _ _ _ _

I 01-24-1989 i

SUMMARY

OF L_ E A K RATE R E S U L_ T S ***

{

- - ILRT ***

FOR : PHILADELPHIA ELECTRIC CO.

PEACH BOTTOM UNIT :2 FROM 2236 (01/02/89). TO 2236 (01/03/89)

MASS TOTAL < 24 > 24 MASS TIME UCL UCL POINT UCL TIME WEIGHT 0.2236 0.3108 0.2385 0.2161 0.2239 2106 95832.359 0.2147 0.2224 2121 95836.352 0.2219 0.3086 0.2367 0.2201 0.3063 0.2347 0.2130 0.2207 2136 95839.438 0.2186 0.3043 0.2331 0.2118 0.2195 2151 95830.969 0.2182 2206 96830.797 0.2171 0.3023 0.2314 0.2106 0.2157 0.3003 0.2298 0.2094 0.2169 2221 95829.227 0.2155 2236 95832.313 0.2140 0.2982 0.2280 0.2080

/

t e

L f

a

(

E-__ l

l '

-T_

.a L '. J. -

. 01-24--1989

SUMMARY

- OF L.E A K. RATE RESUL TS ***

- - ILRT ***

FOR>:--PHILADELPHIA ELECTRIC CO.. ,

- PEACH, BOTTOM-- ,

^

UNIT':2

~FROM: 2252-(01/03/89)- ,TO 252 (01/O.4/89)-

MASS TOTAL .< 24 > 24 MASS.

eTIME WEIGHT 1 TIME- UCL' UCL- POINT 'UCL'

2252 --95819.539-

- 2 3 0 7 .' 95814.805

2322. 95809.875 2337 95802.469'

2352 95800.484 0.5157 0.7880 0.6492 0.5054 0.6044-

-7 95789.492 0.5713 0.7746- 'O.6669 0.5742' O.6773 22 95787.234 0;5664 0.7331 0.6427. 0.5615 0.6320

-- 37 ~ 95780.578- O.5713 0.7101 O.6331 -O.5650 0.6158' 52 95771.727 O.5909 0.7106 0.6428 O.5881- 0.6340'

^107 -95766.828' O.5988 0.7058 0.'6438 'O.5945 0.6311

-122 95753.688 "O.6289 0.7319 0.6711 0.6308 'O.6793 137 95755.422 0.6258 0.7299 0.6673 0.6209. 0.6621 152 95746.094 0.6317 0.7297 0.6698 0.6252 0.6600 207 95738.813- 0.6382 0.7309 0.6734 O'.6308: 0.6610 222 95735.164' O.6382 0.7299- 0.6722 0.6279 0.6540 0.6228 0.6461 237 95730.328 0.6360. 0.7281 0.6693

252 95725.820- 0.6319 0.7254 0.6650 0.6159 0.6375 Y

L>

Y.

l 8

L_ '- *e.em.,._'._,

l

--: . o . .

l 4

3 l

s. ,

l APPENDIX F AS FOUND ILRT CALCULATIONS w'

O Y

l l

l 6 4Fr l

_ _ _ - . ____ ____df8O_]"_

. a: . .

Leakage Savings Data Ali 6 ce um nr ineinaed eu, to the ev+.ne.a 1.'new er the eutace.

h Type C Tests Pen No. N(7"ES

. 7A AD-1A-080A As round 10 A0-1A-08EA As 14f t .112.

j Savings- 0 7B A0-1A-080B As round 10 A0-1A-086B As 14ft .1101 Savings 0 7c A0-1A-080c As round 10 A0-1A-086C As Left .ZiQ. -

Savings 0 7D A0-1A-080D As round. 10 A0-1A-086D As left .2211 Savings 0 8 HO-1A-074 As Found 100001 H0-1A-077 As Left .19.

Savings 9990 9A H0-23-019; H0-6-038A As Found 603 Check Valves 6-028A and 6-096A As Left J.El.

Savings 22 9B Ho-13-021; HD-6-03BB; N0-12-068 As Tound 1110 check Valves 6-028B and 6-096B As Left .322.

Savings 738 10 HO-13-015 As Found 120 NO-13-016 As left .13.

Savings 107 11 NO-23-015 As Found 280 NO-23-016 As Left .10.Q.

A0-4807 Savings 180 12 Ho-10-018 As round 123 MO-10-017 As left .2d2.

' Savings 0 13A HO-10-025B; AD-10-154B As Found 87 As Left 1592 Savings 0 13B HO-10-025A; A0-10-154A As Found 21 As 14ft .2.0.

Savings 1 14 Ho-12-015; As Found 94 HO-12-018; - As Left .E.0.

Savings 14

1. As Found data is not available for this penetration'.10,000 sccm has been assigned as a con-servative as-found leakage. See attached discussion for details.

_m_._______ _ _ _ _ . _ . _ _ . _ _ . _ _ _ _ _m _

____.y____ , _ _

W-;,. f . _ ;f,. ,

L

}l, e:,,,.Y_ ,E .

Pan No. y

.16A: -HO-14-012B; As round- 20 r2, - A0-14-011B;- , ' As .Inft -

1.2D.

Savings. O-16B - : H0-14-012A; O As Found ' 20 ^.

A0-14-011A;- ,-As Left . 2DD.L .

-Savings- 'O-17 Ho-10-032 As round 28

[ HO-10-033 : As Left - ~ .16; :

I -Savings- 0 18 A0-20-082 :As round ;67' A0-20-083 As 14ft /R Savings - 57.

h 19 'A0-20-094' As round 2162. _

A0-20-095 . As 14ft M Savings 2152.

21; . Service Air System Inner Globe Valve (36A-00165) As Found .10 Service Air System Outer Globe Valve (36A-20163) . As 14f t -R' +

Savings- 0 -

22 A0-2969A' As Found 10.

- Qieck Valve (16-23202A) As 14f t '- R Savings - :0

'~

23' H0-23'13 . , -As Found '72 .

.As Left .21 Savings: 37' 245 'HO-2374- As'Found. 290 1 As Left= 'R ;

Savings 260'

, ; 25, . *

'A0-2502A ;AO-2505 '

As round. '680 205B A0-2519 ;AD-2520 As Left .111

i. ; A0-2521A ;A0-2521B Savings 217'

y. 7

-A0-2523 ; Check Valve-9-026A; Two Check Valves (9-40095A, 9-40095B) .

26 A0-2506;A0-2507 As Found 61 A0-2509 ;A0-2510 As Left .ftfL

/ SV-2671G ;SV-2978G Savings 0

.A0-4235 ;SV-4960B SV-4961B iSV-4966B SV-8100 ;SV-8101

)

_32Ci. ILRT System, Two Globe Valves As Found 10 (7A-29871, 7A-29872) As Left M Savings 0 32D IIRT System, Two Globe Valves As Found 120 j- 4

w. ,; - . .--+- -e - (7A-29873, 7A-29874) As left R Savings 110 l l

35A to E TIP Ball Valves (7E-104A to E) As Found 255 Tip Shear Valves (7E-102A to E) As I4ft .122.

Savings 0 f.

1

.. f Q E _- , a _- . . _ _ _ _ - .-

.J y . 'e

~

Pen No. NOTES 35F SV-7E-109; Check Valve (7E-41504) As Found 20 As Left M '

Savings, ' O 38 ' CV-3-032A; CV-3-032B; CV-3-033 As Found 1394 CV-3-035A; CV-3-035B; CV-3-036 As Left. .21f.

CRD Withdrawal; HCU Savings 1138 ,

39A MD-10-031B ;MO-10-026B As Found '1816 j SV-4949B l Check Valve (7C-40143) As left 'M ,

Savings' 1756 39B M0-10-031A ;MO-10-026A As Found 181 SV-4949A ; Check Valve (?C-40142) As Left .210.

Savings 0 41 A0-2-039 As Found .' 10 A0-2-040 As Left 2 Savings 0 42 Check Valve 11-016 As Found 10 XV-014A,B As 14ft .10.

- Savings 0 47 SV-8130B As Found 30

, check Valve (16A-23299B) As 14ft - 3 i Savings 10 I

51A SV-2671E As Found 20

! SV-2978E As Left E

' Savings 0 i

( 51B SV-2671D As Found 20 L SV-2978D As Left .2.0.

Savings 0 51C SV-2671C ;5V-2978C As Found 50 SV-4960C ;SV-4961C As Left &

SV-4966C ; Savings 10 51D , SV-2980 As Found 630 Check Valve (16-23202B) As Lef .22.

Savings 598 52F ..' A0-2969B As Found 20 Cheek Valve (16-23202A) As Left .21 Savings 0 53 MO-2201B As Found 860 As Left .118 savings 412 54 MO-22003 As Found 20 As 14ft .221 Savings 0 55 MO-2200A As Found 40 As Left .1121.

, savings 0 t

i I

I

s . ,

<*,L '

l

-e 4 v. .- .

' pes No.

~

NOTES

~. 5 6 H0-2201A- As ToundJ 3658

, As 14f t '121.

Savings; 13067 57 :A0-1J-316 As Found. 10

~

..A0-1J-317. , _As.Left- .10. ' ,

, Savings 0

-102B. .SV-8130A,; ', As round . 340 Check ' Valve (16A-23299A) . As Left .~ .210. ,

Savings 50 l ._. 203: SV-2671B ; SV-2978B ; As Tound -155 I .

SV-4960D ; SV-4961D . -As Left ' 10. .

li ' '

SV-4966D ; Savings 115

[- -

205A A0-2502B ; As round- 10 . '

~

Check Valve 9-026B As 14ft .121 Savings 0.

210A H0-10-034B; MD-10-038B As round 1892 211A' .H0-10-039B; SV-4951B' As 14ft .22Di '

Savings- 5660 o 210B HO-10-034A; MO-10-038A' 'As Found 1270 l '211B H0-10-039A; SV-4951A ; As Left' .221

!' ~

Savings 934.-

~

' 212, - HD-4244 As Found- 44 214, A0-4240 ; A0-4241 ; As 14ft- ' .10.

i 217B : Check Valve 13-050; Check Valve 23-065 Savings 34 l

L*

R.

MD-4244A ;

A0-4247 ; A0-4248 As Found' As Left 56

.12.

Check Valve 13-009;, Check Valve 23-012 Savings 0 t'

=218A A0-2968 ; _

_As Found 100 Check Valve (16-23261) As Left E

'h-Savings 80 218B "SV-2671A As Found 20 SV-2978A As Left .22 Savings 0 218C / ILRT System-Two Globe Valves As Found 10 (7A-29875, 7A-29876) As Left M Savings 0 219 A0-2511 ; A0-2512 ; . As Found 452 i

, , , , . _ . A0-2513 ; AD-2514 : As Left .220. i SV-2671r ; SV-2978T ; Savings 232 SV-4960A ; SV-4961A ;

SV-4966A ;

. _.. 221 Q)eck Valve 13-038 As Found 47 As Left .20.

Savings 21 223 Check Valve 23-056 As Found 1243 As Left .lli Savings 1107 l

[

l.

__ w=_= . _ _ _ . - _ -l

*L*. *

y. . . il , c

1. ; .

..- ' ")., . ,

6 w

'r -Pan No. . NOTES i -- -225- :HO-14-011; H0-13-039E ~ As round 463 H0-13-041; Ho-14-070: As h ft ' 13.0. '

Savings 333' "227 H0-23-057- As round 21 .

- HD-23-058 As Left .221 Savings.. 0

.20

~

234 PASS . Check Valve. (14-40244) - As Found As Left. 2 19.

Savings 0

-Packing LLRTs s.

210Al H0-10-034B;- As Found 3400 -

. . As Left 10. , . _ .

Savings. 3390-210B Ho-10-034A; As round 10' As Left .19. .

Savings- 0

.. +, .

211A H0-10-038B; As round 10 As Left. .@.

Savings' 0 211B HO-10-038A; .As round 400 As Idif t . A0.

F Savingss 390 Type B Tests Drywell Head- As round .423-(Remove and Reinstall 'O-Ring') As 14f t 10.

Savings .413 FPV Stabalizer Hanways As round 210 As Left- 10.

Savings 130 1 Equipment Hatch

As round 10 (Remove and Reinstall 'O-Ring') As Left .22.

Savings ~0

'2 Airlock As Found 2618 (Remove and Reinstall 'O-Ring') As Left 6774 Savings 0 6 CRD Hatch As Tound 10 (Remove and Reinstall 'O-Ring') As Left 10.

Savings O L.

200A Torus Hatch As Found 10 (Remove and Reinstall 'O-Ring') As Left .lD.

'~

.. Savings 0 200B Torus Hatch As Found 10 (Remove and Reinstall 'O-Ring') As Left .19.

Savings 0 TOTAL SAVINGS 33,896 seem

% LEAKAGE 0.135%

ILRT AS FOUND 0.368%

L

};

l^ .

c ,- . , ,.

E' PENETRATION N-8 DISCUSSION f

Due to the problems encountered at the beginning of this' refuel outage an As-Found leakage was not obtained on penetration N-8, Main Steam Line Drains. The assumption has been made that the MO-77 leakage was minimal prior to the troubleshooting done on 4/4/87 and conservative leakage of 10,000 cc/ min has been assigned to this penetration. The actual leakage was most likely much less.

l This assumption is based on the following:

L o The MO-77 was a tight boundary during the MSIV Local Rate test conducted on 3/14/87. This test involves pressurizing the reactor vessel to 25.1 pounds. The inboard MSIV's, HPCI Steam Supply, RCIC Steam Supply, and the Main Steam Line Drains are all part of the pressure boundary (See Figure 1, next page). In past tests it was always necessary to maintain flow with the pressurizing system in.

order to maintain test pressure due to leakage of the different boundaries. During the test conducted on 3/14/87 make-up flow was stopped for as much as fifteen minutes at times indicating that.the boundary valves were tight.

o The LLRT performed on the MO-77 on 4/4/87 (prior to the

, troubleshooting) involved closing the valve manually prior to the test. The valve could not be closed under its own e power due to a wiring problem and was closed by hand until it felt " snug". This test resulted in a leakage rate of 350 cc/ min for the MO-77 valve.

o The MO-77 and MO-74 are new valves that were installed under MOD 1117 during the last Refuel outages on both Units 2 and 3. The as-left test result for Unit 2 was 221 cc/ min. There have been 3 LLRTs performed on the Unit 3 valves, all of which resulted in a leakage of less than 600 cc/ min.

These three items indicate that the MO-77 did not have a significant amount of leakage at the end of the operating cycle.

An estimation would be less than 1,000 cc/ min. This estimate has been increased by a factor of ten in order to be conservative.

O M. _ _ - . _ _ _ - . - _ _ _ ~ _ _ _ . . _

MSIV R l HPCI Steam G : NIVR M $

15 16 9 Supply ,

O 4- sessurize Here h

~

A 6 4 -

L2 :

w2 't FT F T

>4--

83 84 Reactor g2 g; E Vessel r , r,

]

Presurized g to 25 #

80 e83 g e 1

84 c:

y, .['l;gi

, . . augll

_ .. ,.-- em, g2 E

g3

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$ ..J' 9 7 A 0 8 83 84

$bIUflyfl9d t; F3

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,dgdyOt@g <

74 77 g ihji .

l Fk +0$

(My[?

eW ,,

Read b

~ ' ~

Main Steam M + nessure 75 76 "*'*

Line Drains I Containment Outboard MSIV Room Valve a:ignment for the Main Steam Iso:.ation Valve Local Leak Rate Test Figure 1.

dn 89 N-______--_-_-________-________-______________ =

1

- 4 g[- h 5 -

o l'

l

\

APPENDIX G TYPE B AND'C TEST RESULTS e

Y e

- m a-- M-a_-- . - - a

. i i

l APPENDIX G PEACH BOTTOM UNIT 2 TYPE B TEST

SUMMARY

PENT SYSTEM OR DESCRIPTION REMARKS TEST LEAKAGE PENT TOTAL NO. DATE SCC / MIN SCC / MIN _

- Drywell Head 3/14/87 423 50 12/16/88 10 10 10

-- Rov stabilizer 5/2/87 210 50 Assy's (A thru H) 7/19/88 80 10 .

80 N1 Eauipment Access Hatch 3/14/87 10 10 6/27/88 22 10 22 N-2 Personnel Airlock 9/29/85 1579: 450 10/20/85 628 50 12/25/85 1828 450 1/19/86 1953 450 2/7/86 1039 450 3/20/86 1300 450 6/26/86 1039 450 8/27/86 2217 450 10/20/86 1560 450 3/4/87 2598 450 12/31/88 6754 450 Airlock 'O" Rina 3/15/87 20 10 6/27/88 20 10 6774 N-4 Head Access 4/30/87 1 10 8/18/88 it 10

,- 10 N6 CRD Hatch 2/4/86 10 10 8/15/86 10 10 3/14/87 10 10 12/21/88 10 10 10 N-7A Main Steam Line "1 total for N 7A,78 3/24/87 40 10 Bellows 7C,7D,9A, and 98, is 6/9/88 773 50 reported under N 7A 773 l

l

! APPENDIX G - TYPE B page 1 L_ _ _ _ _ _ -.o . . .

'APPSNDIX G P.EACH BOTTOM UNIT 2 TYPE B TEST

SUMMARY

PENT SYSTEM OR DESCRIPTION REMARKS TEST LEAKAGE PEN'T TOTAL NO. DATE SCC / MIN SCC / MIN N-78 Main Steam Line *1 Bellows N-7C Main Steam Line *1 ,

Bellows N-7 D Main Steam Line *1 Bellows N 9A Feedwater Line *1 Bellows N-98 Feedwater Line *1 Bellows N 11 HPCI Steam line *2-total for N-11.12 3/17/87 330 50 Bellows .13A.&16A is 6/16/88 265 50 recorted under N-11 265 N-12 RHR Suction Line *2 Bellows I

N-13A RHR Suction Line *2 Bellows N-138 RHR Injection Line '3-total for N-13B. 3/17/87 10 10 Bellows 14.168. and 17 is 6/7/88 10 10 recorted under N 13B 10

_ N 14 RWCU Suction Line *3 Bellows N-16A Core Soray Bellows *2 APPENDIX-G - TYPE B page 2

l . . . .

f APPENDIX G PEACH BOTTOM UNIT 2 TYPE B TEST

SUMMARY

SYSTEM OR DESCRIPTION REMARKS TEST LEAKAGE PEN'T TOTAL PENT DATE SCC / MIN SCC / MIN NO.

N-16B Core Soray Bellows *3

> 1 N-17 Head Soray Bellows *3 .

N 25 AO 2505.2519,2520 3/16/87 30 10 12/2/87 30 10 9/13/88 30 10 30 N-26 AO-2507.2506 3/16/87 20 10 9/8/87 20 10 9/9/88 10 10 10 N-35A-G Tio Penetration 3/22/87 10 10 "O" Rinas 6/13/88 10 10 10 i

N-100A 'bsetri 2; *4-total for N-100A 3/24/87 70 10 100C,104 A.1048 6/10/88 10 10 104C,104D,105A 10 1058,106A.1068 107 & 220 is reoorted under N-100A

'4 N-100,C. Electrical N-1000 Electrical '5 total for N-100D 3/17/87

20 10 100E,1010,101 D. 6/8/88 20 10 ,

101 E.1038,1048, 20 104 F.104G.104 H, 105C 105D.106C.

1060 is reoorted under N-100D N-100E Electrical *5 APPENDIX.G - TYPE B page 3 I

__qnem- w :.=_i---m.--

, o . .

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

i P E N'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 7A MSIV 80A and 86A Total Boundary 3/14/87 3352 450 Total Boundarv 6/11/87 3040 450 Total Boundary 8/11/88 913 50 913 N-78 MSIV 80B and 86B SOB 3/14/87 30 10 -

858 3/14/87 130000 450 86B 3/25/87 6429 450 Total Boundary 5/16/87 Off scale Total Boundarv 5/20/87 Off scale 86B 6/3/87 533 50 Total Boundarv 6/11/87 Off scale Total Boundarv 6/19/87 Off scale Total Boundarv 6/29/87 Off scale Total Boundarv 6/30/87 Off scale Total Boundary 7/6/87 OfI scale 86B 7/7/87 640 50 Total Boundarv 7/10/87 1956 450 Total Boundary 3/16/88 Off scale Total Boundary 8/11/88 Off scate 868 8/19/88 628 50 Total Boundarv 8/29/88 Off scale Total Boundarv 8/30/88 01I scale l 80B 10/15/88 OfI scale l

863 10/17/88 903 50 80B 10/21/88 1279 450 Total Boundary 10/23/88 Off scale Total Boundary 10/26/88 Off scale Total Boundary 10/27/88 Off scale Total Boundary 10/29/88 3009 450 Total Boundary 10/30/88 3968 450 3968 APPENDIX G - TYPE C page 1

~

.u--se...,..,,. .

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 7C MSIV 800 and 86C Total Boundary 3/14/87 2016 450 Total Boundarv 5/16/87 2257 450 Total Boundary 8/11/88 011 scale 86C 8/20/88 Off scale 86C 9/7/88 119 50 86C 9/13/88 143 50 -

Total Boundary 10/12/88 Off scale Total Boundary 10/13/88 Ot! scale 86C 10/14/88 287 50 800 10/18/88 Off scale 800 10/30/88 Off scale Total Boundary 11/1/88 2182 450 Total Boundary 11/2/88 560 50 560 l

N 7D MSIV BOD and 86D Total Boundary 3/14/87 1418 450 Total Boundarv 6/11/87 1656 450 Total Boundary 8/11/88 4638 450 4638 N-8 Main Steam Line Drain Total Boundarv 6/20/86 Not Ouantified Total Boundary 6/22/86 221 50 Total Boundarv 3/14/87 Off scale Total Boundarv 3/16/87 Off scale Total Boundary 4/5/87 Otf scale Total Boundarv 4/6/87 1001 450 Total Boundary 4/7/87 Off scale Total Boundarv 7/1/87 Off scale MO-74 8/17/87 10 10 Total Boundarv 9/18/87 Off scale Total Boundarv 9/23/87 10 10 Total Boundarv 9/22/88 10 10 Total Boundarv 12/7/88 5315 450 Total Boundary 12/9/88 Off scale Total Boundarv 12/10/88 220 50 220 l

i APPENDIX G - TYPE C page 2 l

-::.:x :- l

. ~ . .

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL DESCRIPTION DATE SCC / MIN SCC / MIN NO.

N 9A Feedwater Check 28A - 28A 3/14/87 1504 450 3/22/87 1121 450 12/16/87 Off scale 12/17/87 7515 450 7/13/88 581 50 MO 6 29A.MO 6-38A 12/13/85 600 50 MO-2319. Feed Check 8/20/86 15567 450 96A 8/24/86 395 50 3/22/87 613 50 5/15/87 Off scale 12/17/87 1041 450 7/13/87 2512 450 HPCI Pumo Discharce 12/13/85 30 10 3/19/87 181 50 9/6188 243 50 2512 N-9B Feedwater Check 28B 8/10/86 4705 450 3/22/87 1120 450 12/17/87 1658 450 7/13/88 372 50 MO-6-38B MO-13 21, 8/9/86 19R219 450 MO 12 68.Feedwater. 8/12/86 6807 450 Check 968 3/22/87 011 scale 4/1/87 717 50 4/5/87 1912 450 12/17/87 4057 450 7/13/88 1817 450 RCIC Pumo Discharge 3/19/87 20 10 12/10/88 Off scale 12/16/88 10 10 1817 l

APPENDIX..G - TYPE C page 3

~

u. . ...

w_____._____

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL N O. DESCRIPTION DATE SCC / MIN SCC / MIN N 10 RCIC Steam Sucolv 6/20/86 Ott scale 6/21/86 10886. 450 8/19/86 15943. 450 8/20/86 16192. 450 8/24/86 Off scale 1 8/25/86 65 10 3/14/87 220. 50 -

12/1/88 26 10 26 N-11 HPCI Steam Sucoly MO-13-15 & 16 3/14/87 480. 50 Test Tao 11/3/88 200. 50 200 N-12 Shutdown Coolino 4/20/87 225. 50 6/6/87 485. 50 6/19/87 674. 50 6/10/88 20 10 11/9/88 391. 50 12/19/88 483. 50 483 N-13A LPCI Injection 12/19/85 960. 50 MO-10-258. 9/19/88 1582. 450 MO-10-1548.

SV-4222 MO-10-258 4/22/87 2803. 450 7/9/87 20 10 9/19/88 2743. 450 2743 i

APPENDIX G - TYPE C -

page 4

.:;;~M: . .; _ _ _ - ~ ' ~

a APPENDIX G

- PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

PEN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL l SCC / MIN N O. DESCRIPTION DATE SCC / MIN N-13B LPCI iniection 8/15/85 20 10 MO 10-25A, 8/25/85 20 10 MO-10154A SV 4221 MO-10-25A 3/15/87 2370. 450 -

4/18/87 441. 50 11/6/87 800. 50 10/12/88 1401. 450 MO-10-154A & 3/15/87 21 10 SV 4221 4/18/87 1542. 450 10/12/88 10 10 1401 N-14 ' RWCU Suction 3/23/87 177. 50 7/11/87 20 10 6/25/88 149. 50 149 N-16A Core Sorav iniection SV 4225 only 3/7/87 20 10 4/16/87 20 10 5/21/87 10 10 7/26/88 160 50 160 N-168 Core Soray injection Total Boundary 8/12/86 600. 50 Total Boundary 3/16/87 10 10 12A & 14A 3/16/87 289. 50 Total Boundarv 4/4/87 465. 50 Total Boundary 4/11/87 Off scale Total Boundary 10/26/87 Off scale Total Boundary 9/24/88 389. 50 389 N 17 Head Spray 12/7/85 30 10 3/20/87 28 10 10/13/88 120. 50 11/4/88 56110 56 APPENDIX G - TYPE C page 5 l en .: , t.,3 5 . c. - , .s.. -

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

LEAKAGE PEN'T TOTAL

. P EN'T SYSTEM OR REMARKS TEST DESCRIPTION DATE SCC / MIN SCC / MIN N O.

N 18 Drywell Floor Drain 8/9/86 16 10 Sumo 3/24/87 86 10

- 10/23/87 657. 50 8/24/88 10 10 4 10 N-19 Drvwell Eauipment 8/8/66 823. 50 -

Drain Sumo 3/25/87 1123. 450 10/26/87 219. 50 8/22/88 10 10 10 N 21 Service Air 6/6/85 10 10 7/1/85 10 10 3/26/87 20 10 6/1/88 82 10 82 N-22 Instrument Nitrocen AO-2969A 8/8/86 20i10 8/10/86 20 10 3/16/87 81 10 7/21/87 145. 50 6/6/88 205. 50 Check Valve 8/8/86 011 scale i 8/10/86 20 10 1 3/16/87 20 10 !

7/21/87 10 10 )

6/6/88 10 10 205 N-23 RBdW to/from Drywell 8/19/86 117. 50 4/7/87 72 10 6/24/87 118. 50 ]

7/25/88 622. 50 (

8/23/88 539. 50 9/9/88 Otf scale 9/13/88 Off scale ._

9/21/88 24 10 24 APPENDIX G - TYPE C page 6

. M*

4 h eram.me er esse me*-

APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 24 RBCW tc/from Drywell 8/19/86 208. 50 4/7/87 280. 50 6/24/87 43 10 ,

7/25/88 30 10 30 N-25 Drywell Purge Sucoly 3/12/87 243. 50 ' -

11/23/87 270. 50 9/9/88 665. 50 AO-2523. Check valves 3/12/87 642. 50 9/9/88 509. 50 1174 N 26 Drywell Purge Exhaust 3/13/87 20 10 AO-2506.AO-2507 11/18/87 Ott Scale 9/9/88 75 10 AO 2509.2510.4235, 3/13/87 71 10 ,

SV-8106 6/22/88 55 10 AO 2509.2510.4235 7/9/88 82 10 PCAC1 8/14/86 20 10 3/10/8'7 10 10 3/29/87 10 10 9/1/88 10 10 PCAC 2 8/14/86 20 10 3/10/87 10 10 3/29/87 10 10 _

9/1/88 10 10

'B' CAD Analyzer SV-4960B 8/13/86 20 10 Isolation Valves 11/1?J86 31 10 3/12/87 11 10 9/14/88 10 10 12/13/88 10 10 l

l l

APPENDIX G - TYPE C page 7

APPENDIX G

, PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL P EN'T SCC / MIN DESCRIPTION DATE SCC / MIN ,

NO.

SV-4961B & 49668 7/17/86 65 10 l 8/13/86 20 10 3/12/87 26 10 9/14/88 1301. 450 12/13/88 10110 SV 8101 8/13/86 40 10 -

3/12/87 31 10 9/14/88 Ott Scale 12/13/88 20 10 187 N 32C ILRT Test Valves 3/23/87 20 10 5/18/87 40110 6/21/88 10 10 10 ILRT Test Valves 3/23/87 150. 50 N 32D 5/18/87 10 10 6/21/88 10 10 10 TIP Ball Valves 3/21/87 10 10 N 35A 8/25/88 122. 50 122 TIP Ball Valves 10/17/86 143. 50 N 358 3/21/87 10 10 8/25/88 20 10 <

20 N 35C TIP Ball Valves 12/17/85 Off Scale 12/18/85 300. 50 3/21/87 10 10 8/25/88 10 10 10 b

APPENDIX G - TfPE C page 8 l

'I

t , **

f..

. , , e [

APPENDIX G PEACH BOTTOM UNIT 2 I TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL N O. DESCRIPTION DATE SCC / MIN SCC / MIN N-35D TIP Ball Valves 3/21/87 200. 50 8/25/88 175. 50 Check & Manual Vivs 3/31/86 50 10 3/22/87 10 10 6/20/88 10 10 SV-7113 & Manual VN 3/31/86 10 10 3/22/87 10 10 6/20/88 10 10 185 N 35E TIP Ball Valves 3/21/87 15 10 8/25/88 135.50 135 N 39A Containment Soray 9/22/86 2198. 450 4/22/87 2950. 450 4/22/87 3400. 450 6/16/87 388. 50 9/10/88 50 10 MO-31 B 9/26/88 40 10 CAD iniection Check Valve 3/10/87 10 10 SV-49489, SV-4949B, SV-4948B only 3/10/87 126.50 Check Valve SV-4949B only 3/10/87 131. 50 Check Valve 12/16/88 10 10 SV-4948B only 12/16/88 10 10 SV-4949B only 12/16/88 35 10 MO-31B Packino 9/20/88 5643. 450 9/26/88 75 10 160 l

APPENDIX G - TYPE C page 9

~

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}

APPENDIX G PEACH BOTTOM UNIT 2

TYPE C TEST

SUMMARY

P E N'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 398 Containment Soray 3/11/87 311. 50 4/17/87 146. 50 10/13/88 220. 50 CAD injection Check Valve 3/13/87 10 10 SV-4948A, SV-4949A, SV-4948A only 3/13/87 10 10 ,

Check Valve SV 4949A only 3/13/87 10 10 -

l Check Valve 12/15/88 10 10 SV-4948A only 12/15/88 300. 50 i SV 4949A only 430. 50 12/15/88 MO-31 A Packing 10/3/88 80 10 730 N-41 Recire. Samole 8/12/86 20 10 3/17/87 20 10 8/23/88 20 10 20 N-42 Standby Liouid Control X 14 A.14 8 3/20/87 20 10 6/1/87 10 10 11/8/88 20 10 12/16/88 20 10 Check Valve 5/20/87 Off Scale 5/24/87 2403. 450 4 5/26/87 800. 50 5/27/87 1400. 450 5/28/87 Off Scale /

5/30/87 621. 50 /

9/30/88 6506. 450 10/17/88 Off Scale 11/5/88 Off Scale 12/12/88 10 10 20 N-47 ADS Backuo Nitrogen Check Valve 3/18/87 20 10 Sucoly 7/24/87 10 10 11/28/88 10 10 SV 8130B 3/18/87 145. 50 7/24/87 25 10 11/28/88 Off Scale 12/30/88 10 10 10 APPENDIX G - TYPE C page 10

- 9"'"'8,FT ,, * *

APPENDIX-G

- PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P E N'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 51 A PCAC Samole - SV-2671 E 3/9/87 10 10 4/6/87 20 10 9/1/88 10 10 SV 2978E 3/9/87 10 10 4/6/87 20 10 -

9/1/88 10 10

~

10

-N-51B PCAC Samole SV-2671 D 3/10/87 2100. 450 3/13/87 220. 50 4/6/87 20 10 9/1/88 10 10 SV 2978D 3/10/87 10 10 4/6/87 20 10 9/1/88 10 10 10 N-51C PCAC Samole SV 2671C 12/12/85 20 10 2/4/87 16 10 3/9/87 10 10 3/31/87 10 10 9/1/88 10 10 SV-2978C 12/12/85 20 10 5/1/87 20 10 3/9/87 10 10 3/31/87 10 10 9/1/88 10 10

'C' CAD Analyzer SV-49610,4966C 3/11/87 30 10 Isolation Valves 9/21/87 Off Scale 10/7/88 10 10 SV-4960C & Globe 3/11/87 10 10 9/21/87 20 10 10/7/88 10 10 20 l

l l

APPENDIX G - TYPE C page 11 l .

3;:.p. ., ,.o r -

e l

)

i APPENDIX G J PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N-51 D PCAC Samole Return Check Vah/e 2/4/86 310 50 11/1/86 90 10 J/13/87 66552 450 5/6/87 3504 450 7/13/87 600 50 9/7/88 Off Scale 10/18/88 380 50 - !

)

SV 2980 2/4/86 20.10 2/6/86 10.10 7/31/86 20.10 10/31/86 Off Scale !

11/6/86 20.10 12/11/86 26.10 3/13/87 620. 50 7/17/87 10.10 9/7/88 22.10 380 N-52F Instrument Nitrocen AO 29698 8/11/86 20.10 3/15/87 20. 10 7/16/87 40.10 '

6/24/88 20.10 l

Check Valve 8/11/86 20.10 l 3/15/87 20. 10 7/16/87 10.10 6/25/88 20.10 20 l N 53 Drywell Chilled Water MO 22018 5/9/87 20.10 9/10/87 10.10 Test Tao = 1400 7/23/88 1508. 450 f 8/2/88 448. 50 i 448 N-54 Drvwell Chilled Water MO-2200B 5/9/87 20.10 9/10/87 2508. 450 l

7/23/88 974. 50 974 l

N-55 Drywell Chilled Water MO 2200A 5/9/87 20.10 9/10/87 1243. 450 7/23/88 1171. 450 1171 APPENDIX G - TYPE C page 12

=

a 40 % ,

u _ - -_.____ . _ _ _ _ _ >

, APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P E N'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL N O. DESCRIPTION DATE SCC / MIN SCC / MIN N 56 Drywell Chilled Water.- MO 2201 A 8/20/86 1658. 450 5/9/87 3648. 450 9/10/87 1243. 450 7/23/88 591. 50 591 N 57 Main Steam Sample 10/16/86 1120. 450 3/15/87 30.10 4/16/87 4764. 450 l 2/10/88 2610. 450 8/12/88 20.10 20 N-102B ADS BackUD Nitrocen Check Valve 3/16/87 360. 50 !

7/24/87 280. 50 11/28/88 280. 50 SV 8130A 3/16/87 340. 50 7/24/87 280. 50 11/28/88 280. 50 280 N 203 PCAC Samole SV 26718 3/9/87 500. 50 3/31/87 20.10

( 8/31/88 10.10 SV 29788 3/9/87 10.10 3/31/87 20.10 8/31/88 10.10 SV-4961D & 49660 3/11/87 115. 50 10/21/88 Off Scale 12/14/88 Off Scale 12/15/88 Off Scale 12/23/88 Ott Scale 12/31/88 751. 50 SV 4960D 3/11/87 150. 50

, 10/21/88 Ott Scale l 12/14/88 Off Scale l 12/15/88 Off Scale

, 12/23/88 45.10 12131/88 10.10 761 APPENDIX G - TYPE C page 13

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APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 205A Torus Vacuum Breaker 12/18/85 701. 50 12/21/85 960. 50 1/17/86 55.10 1/20/86 50.10 3/13/87 20.10 4/14/87 Otf Scale -

4/16/87 6051. 450 6/29/87 370. 50 6/28/88 893. 50 8/11/88 350. 50 350 N 205B Torus Vacuum Breaker 1/26/86 50.10 3/21/86 122. 50 4/11/86 100. 50 3/13/87 20.10 6/28/88 130. 50 130 N-210A, Torus Coolino 4/22/87 46728. 450 211 A 6/6/87 7854. 450 7/8/87 1897.450 9/15/88 4167. 450

'B' C AD In.iection SV-4950B 3/11/87 61. 10 Test Taos = 850 12/17/88 1001. 450 12/22/88 40.10 Post Accident 4 Valve 3/11/87 71. 10 Test Taos = 850 12/17/88 1001. 450 12/22/88 40.10 Check Valve 3/11/87 51. 10 12/17/88 10.10 SV-4951 B 3/11/87 81. 10

. Test Taos- 850 12/17/88 1001. 450 12/22/88 40.10 i

APPENDIX G - TYPE C page 14

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APPENDIX G PEACH BOTTOM UNIT. 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN MO-348 Dackino 4/22/87 3400.450 9/10/87 2000. 450 11//20/87 31. 10 9/17/88 10.10 MO 388 packing 4/22/87 10.10 9/10/87 10.10 -

9/1.7/88 60.10 4277 N-2108. Torus Coolina 3/10/87 2339. 450 211B 4/18/87 1174. 450 10/4/88 624. 50

'A' CAD Iniection SV-4950A 3/12/87 281. 50 12/14/88 Off Scale 12/30/88 10.10 SV 4951 A 3/12/87 50.10 12/14/88 10.10 Check Valve 3/12/87 10.10 12/14/88 10.10 j MO 34A Dackino 4/23/87 10.10 9/10/87 20.10 10/3/88 10.10 MO-38A Dacking 4/23/87 400. 50 9/10/87 500. 50 10/3/88 10.10 654 N 212 RCIC Exhaust 3/16/87 80. 10 7/15/88 21. 10 RCIC Exhaust Drain 3/9/87 782. 50 Test Tao- 2400 7/18/88 3021. 450 9/28/88 621. 50 Stop Check O ring 3/9/87. 10.10 3/16/87 10. 10 9/14/87 10.10 7/15/88 10.10 652 APPENDIX G - TYPE C page 15

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APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P E N'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOT AL NO- DESCRIPTION DATE SCC / MIN SCC / MIN N-214 HPCI Exhaust 3/16/87 8925. 450 5/21/87 Off Scale 9/15/87 3921. 450 9/28/87 Off Scale 11/4/87 6883. 450 5/18/88 8910. 450 -

7/18/88 Off Scale 7/19/88 Off Scale 7/20/88 Off Scale 7/27/88 1201. 450 8/17/88 1801.t450 f 8/18/88 1201. 450 8/23/88 2202. 450 HPCI Exhaust Drain 3/12/87 10451. 450 9/16/87 Off Scale

- 8/3/88 550. 50 Stop Check O rina 3/12/87 10.10 9/15/87 10.10 8/18/88 250. 50 8/19/88 300. 50 8/23/88 10.10 2762 N-2178 RCIC Exh. Vacuum Relief 3/9/87 44. 10 9/9/87 104. 50 7/22/88 20.10 HPCI Exh. Vacuum Relief 3/12/87 56.10 9/11/87 39. 10 10/8/88 63. 10 83 N 218A Torus Inst. Nitrocen AO 2968 3/22/87 170. 50 7/24/87 80.10 6/2/88 67. 10 l

Check Valve 3/22/87 100. 50 7/24/87 10.10 6/2/88 10.10 67 APPENDIX G - TYPE C page 16 "c ; . W ' . .. * /., ,,

i

>< a s APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P EN'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL NO. DESCRIPTION DATE SCC / MIN SCC / MIN N 2188 PCAC Samplina SV 2671 A 10/8/85 20.10 11/4/85 20.10 3/10/87 580. 50 3/30/87 180. 50 i

7/9/87 10.10 8/31/88 10.10 SV-2978A 11/4/85 20.10 l 3/10/87 10.10 3/30/87 10.10 7/9/87 10.10 1 8/31/88 10.10 l 10 N 218C ILRT Test Valves 3/23/87 20.10 5/18/87 10.10 6/21/88 10.10 10 N-219 PCAC 5 amole SV 2671F 3/10/87 10,10 4/7/87 30.10 9/7/88 10.10 SV-2978F 3/10/87 10.10 4/7/87 20.10 9/7/88 10.10 Torus Purae Exhaust AO-2511.2512 3/12/87 10.10 11/16/87 40.10 9/2/88 75.10 AO 2513.2514 3/12/87 803. 50 8/10/88 730. 50 10/14/88 961. 50 10/25/88 450. 50 10/31/88 340. 50_

'A' CAD Analyzer SV-4960A 3/12/87 10.10 Isolation Valves 9/18/87 10.10 10/8/88 10.10 SV 4961 A.4966A 3/12/87 10.10 9/18/87 20.10 10/8/88 10.10 435 APPENDIX G - TYPE C page 17 M '~

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c .' u APPENDIX G PEACH BOTTOM UNIT 2 TYPE C TEST

SUMMARY

P E N 'T SYSTEM OR REMARKS TEST LEAKAGE PEN'T TOTAL DESCRIPTION DATE SCC / MIN SCC / MIN NO.

N 221 RCIC Vacuum Pumo 3/9/87 37.10 Discharge 7/8/88 20.10 20 N 223 HPCI Exhaust Drain 3/12/87 1243. 450 8/30/88 1529. 450 -

9/22/88 126. 50 MO 31 Packino 10/11/88 45.10 171 N-225 Torus Water Clean-uo 3/18/87 496. 50 6/25/C7 494. 50 7/24/87 32.10 6/29/88 20.10 RCIC Pumo Suction 3/9/87 440. 50 11/30/88 240. 50 260 N-227 HPCI Suction 3/12/87 52.10 8/4/88 750. 50

- 750 N-234 Post Accident 3/19/87 20.10 Samolino Retum 8/20/88 210. 50 210

--- Scram Discharge Volume CV 32A 8/8/86 55.10 Vent and Drains 4/30/87 22.10 9/23/88 10. 10 CV 35A 8/8/86 6009. 450 8/10/86 1202. 450 4/30/87 788. 50 9/23/88 530.150 10/24/88 39.10 CV-328 8/8/86 561. 50 4/30/87 357. 50 9/23/88 806. 50 10/24/88 1598. 450 11/2/88 255. 50 11/3/88 156. 50 APPENDIX G - TYPE C page 18 i

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s. a . s APPENDIX G

. PEACH BOTTOM UNIT 2 i TYPE C TEST

SUMMARY

{

I P E N'T SYSTF.M OR REMARKS TEST LEAKAGE PEN'T TOT AL J NO. DESCRIPTION DtTE SCC / MIN SCC / MIN l t (

- CV 35B 8/8/86 1302. 450 )

4/30/87 320. 50 1 9/23/88 190. 50 CV 33 8/8/S6 177. 50 4/30/87 8226. 450 5/10/87 155. 50 9/23/88 O!! Scale 10/24/88 Off Scale 10/31/88 Off Scale 11/2/88 851 A50 i 11/3/88 298. 50 11/3/88 209. 50 11/5/88 54. 10 CV-36 8/8/86 1618. 450 4/30/87 1022. 450 9/23/88 117. 50 10/24/88 10. 10 283 NOTE : Allleak rates are reported using the format specified in ANSI /ANS 56.81981, which requires that a leakage rate deviation be specified.

Totalleakage: 49358 1526 sec/ min.

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APPENDIX G - TYPE C page 19

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7 89-14049 10CFR50, App J, VB1

w ,

PIIILADELPilIA ELECTRIC COMPANY PEACil llOTTOM Kf0MIC POWEll STATION

11. D.1. Ilox 208 N Delta, i consylvania l'.414 j nAat wnow-nu nm tu os tutauvi (71T) 156-7011 D. M. Smith Vice Prc.sident April 11, 1989 Docket No. 50-277 i U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 i

h

SUBJECT:

Peach Bottom Atomic Power Station Unit 2 Reactor Containment Building Integrated Leak Rate Test Gentlemen:

Attached is the Peach Bottom Unit 2 Reactor Containment Building Integrated Leak Rate Test (ILRT) Report for the ILRT performed in January,1989. This submittal is in accordance with 10CFR Part 50, Appendix J, Section V, paragraph B.

Sincerely, y -

DMS/MJB: cmc Attachment ec: W.T. Russell, Administrator, Region I, USNRC T.P. Johnson, USNRC Senior Resident inspector 1ccoco.coc gf 1

4 i

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ML20244C257

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1.0 INTRODUCTION

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