ML20101K333

Reactor Containment Bldg Integrated Leak Rate Test, Sept 1984

ML20101K333
Person / Time
Site:	Brunswick
Issue date:	09/30/1984
From:	Blessing J, Blinson M, Shirk R GILBERT/COMMONWEALTH, INC. (FORMERLY GILBERT ASSOCIAT
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ML20101K328	List: ML20101K325 ML20101K333
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Text

D.

BRUNSWICK STEAM ELECTRIC PLANT UNIT NO. 2 REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST SEPTEMBER 1984 CAROLINA POWER & LIGHT COMPANY Prepared by: / eux ,

Reviewed by: I.

ILRT Engineer Approved by: T Ifd d. M k w Geert/CammesseWe 8412310307 841221 PDH ADOCK 05000324 p PDR

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4 TABLE OF CONTENTS Section Item Title Page 1.0 SYNOPSIS 3

2.0 INTRODUCTION

4 3.0 , GENERAL, TECHNICAL, AND TEST DATA 5 4.0 ACCEPTANCE CRITERIA 7 5.0 TEST INSTRUMENTATION 8 5.1

SUMMARY

OF INSTRUMENTS 8 5.2 SCHEMATIC ARRANGEMENT 9 5.3 CALIBRATION CHECKS 9 5.4 INSTRUMENTATION' PERFORMANCE 9 5.5 VOLUME WEIGHTING FACTORS 10 5.6 SYSTEM ERROR ANALYSIS 11 5.7 SUPPLEMENTAL VERIFICATION 14 6.0 TEST PROCEDURE 15 I

6.1 PREREQUISITES 15 6.2 GENERAL DISCUSSION 15 6.3 TEST PERFORMANCE 16 7.0  ;, METHODS OF ANALYSIS 19 7.1 GENERAL DISCUSSION 19 7.2 STATISTICAL EVALUATION 20 8.0 DISCUSSION OF RESULTS 22 8.1 RESULTS AT P 22 '

8.2 SUPPLEMENTM." TEST RESULTS 24

9.0 REFERENCES

26 APPENDICES Appendix A - SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION Appendix B = REDUCED TEST DATA Appendix C - LEAXAGE RATE TEST GRAPHS Appendix D - COMPUTER RESULTS Appendix E - LOCAL LEAKAGE RATE DATA ,

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3 1.0 SYNOPSIS The Brunswick Steam Electric Plant Unit No. 2 reactor containment building was subjected to an integrated leak rate test during the period of September 22 to September 24, 1984. The purpose of this test was to demonstrate the acceptability of the building leakage rate at an internal pressure of 49.0 psig (P ). Testing was performed in accordance with the requirements 8f 10CFR50, Appendix J, ANSI N45.4-1972 and Brunswick Steam Electric Plant Unit No. 2 Technical Specifications.

The integrated leakage rate test was successfully conducted for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> using the Absolute Method of leakage rate d,etermination and the Mass Point analysis technique. The results of the integrated leakage rate test are as follows:

24 Nour Measured Leakage Rate = 0.289 wt 4/ day 954 Confidence Interval = 0.004 wt t/ day Type B and C Penalty = 0.000 wt 4/ day Total Leakage Rate at the Upper 954 Confidence Interval Including Type B and C Penalties = 0.293 wt 4/ day The total leakage rate, as identified above, is well below the allowable leakage rate of 0.375 weight percent per day.

The supplemental instrumentation verification at P demonstrated an agreement between measured reactor containment butiding integrated leakage rates of 4.8 percent which is well within the 25% requirement of 10CFR50, Appendix J, Section III A.3.b.

Testing was performed by Catrolina Power a Light Company with the technical assistance of Gilbert Associates, Inc. Procedural and calculational methods were witnessed by Nuclear Regulatory Commission personnel.

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. 4

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 49.0 psig. The allowable leakage is defined by the design basis accident applied in the safety analysis in accordance with site exposure guidelines specified by 10CFR100. For Brunswick Steam Electric Plant Unit No. 2, the maximum allowable integrated leak rate at the design basis accident pressure of 49.0 peig (P ) is 0.5% by weight per day (L,).

Testing was performed in accordance with the procedural requirements as stated in Brunswick Steam Electric Plant Integrated Primary Containment Leak Rate Test Procedure PT-20.5. This procedure was reviewed by the Brunswick Steam Electric Plant Nuclear Safety Committee and approved by the Plant General Manager prior to the commencement of the test.

Leakage rate testing was accomplished at the pressure level of 49.0 psig for a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. The 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period was followed by a four hour supplemental test for a verification of test instrumentation.

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3.0 , GENERAL, TECHNICAL, AND TEST DATA 3.1 GENERAL DATA Owner: Carolina Power & Light Docket No.: 50-324 Location: Southport, North Carolina Typer Mark 1, BWR-4 Containment

Description:

Steel lined, reinforced concrete,

' light bulb' shaped drywell with torus shaped suppression chamber connected by a vent system.

Vacuum breakers are provided between the suppression chamber and both the drywell and reactor building.

Date Test Completed: September 24, 1984 3.2 TECHNICAL DATA Containment Net Free Volumet 294,981 cubic feet:

Design Pressures 62 peig Design Temperature: 300 F (drywell), 220 F (suppression chamber)

Calculated Accident Peak Pressures 49.0 psig Calculated Accident Peak Temperatures 297'F 3.3 TEST DATA Test Method Absolute Data Analysis: Mass Point Test Pressures 64.1 psia Max Allowable Leakage Rate (L,): .5 wt s/ day

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6 Measured Leakage Rate at UCL: .293 wt t/ day Supplemental Test Flow Rate .500 wt 4/ day Supplemental Test Measured Leak Rates .765 wt t/ day Supplemental Test and L,,

Agreement: 4.8%

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7 4.0 ACCEPTANCE CRITERIA Acceptance criteria established prior to the test and as specified by 10CFR50,' Appendix J, ANSI N45.4-1972 and the Brunswick Steam Electric Plant Unit No. 2 Technical Specifications are as follows:

1. The measured leakage rate (L ) at the calculated design accident pressure of 49.0 psig (P ) s$ Ell be less than 75% of the maximum allowable leakage rate ($ ), specified as 0.5% by weight of the building atmosphere per da,y. The acceptance criteria is determined as follows:

L, = 0.St/ day 0.75 L, = 0.3754/ day

2. TFs 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,.

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8 5.0 TEST INSTRUMENTATION 5.1

SUMMARY

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

5.1.1 Temperature Indicating System Components: '

1. Resistance Temperature Detectors Quantity 24 Manufacturer Rosemount Type 78-S 100 ohm platinum Range, F 0 to 400 Accuracy, F +0.1 Sensitivity, F [0.1

2. Temperature Indicator:

Quantity 3 Manufacturcr Chromalox Type 2310 process indicator

' Accuracy, #F 40.1 Repeatability, F [0.1 5.1.2 Dewpoint Indicating System

1. Dewcell Elements Quantity 8 Manufacturer Foxboro Type 2701 RG Nickel RTD '

Range, F 0 - 150 dewpoint Accuracy, F +2 Sensitivity, F 10.5

2. Dewpoint Transmitters Quantity 8 Manufacturer Foxboro Type Model E94, 4-20 ma output Accuracy, F +0.4 Repeatability, F [0.1 i

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9 5.1.3 Pressure Monitoring System Precision Pressure Gauges

{ Quantity 1 j Manufacturer Texas Instruments Type Model 145 (with direct readout) l Range, psia 0 - 75 l Accuracy, psia 0.015% of of full scale sensor sensitivity, psia 0.0013% of full scale Repeatability, psia 0.001% of full scale 5.1.4 Supplemental Test Flow Monitoring System

)

j Flowmeter  ;

i} Quantity 1 l Manufacturer Brooks I

Type Model 1110  !

j Range, scfm 0-5 Accuracy  ;[2% of full scale 5.2 SCHEMATIC ARRANGEMENT The arrangement of the four measuring systems summarized in Section 5.1

! is dep'i'cted in Appendix A.

3 Drybulb temperature sensors were placed throughout the reactor containment vessel volume to permit monitoring of internal temperature j variations at 24 locations. Dewcells were placed at eight locations to

permit monitoring of the reactor containment partial pressure of water

, vapor. A temperature survey was performed af ter the sensors were

installed which verified there were no large areas of temperature

variation.

5.3 CALIBRATION CHECKS

! Temperature, dowpoint, and pressure measuring systess were checked for i

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 Brunswick Steam Electric Plant. The supplemental test at 49.0 psig confirmed the instrumentation acceptability.

J .

5.4 INSTRUMENTATION PERFORMANCE {

During the pressurization phase, two dowcells exhibited abnormal l behavior and were not used for the test. The remaining eight dowcells, 24 RTDs, one precision pressure gauge, and flow meter performed satisfactorily throughout the performance of the integrated leak rate I

test and provided more than adequate coverage of the containment.

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10 5.5 VOLUME WEIGHTING FACTORS Weighting factors were assigned to each drybulb temperature sensor and dewpoint temperature sensor' based on the calculated voluee of the reactor containment building each sensing device monitored. Drybulb and dowpoint temperature sensors elevation and weighting factors for the test were as follows:

rievation/ Temperature weighting Azimuth ,,

Element Factor 93/0 TE 1 .0264 93/180 TE 2 .0264 78/270 TE 3 .0187 78/90 TE 4 .0187 66/0 TE 5 .0115 66/180 TE 6 .0115 54/270 TE 7 .0136 54/90 TE D .0136 46/300 TE 9 .0194 46/0 TE 10 .0194 46/180 TE II .0194 33/0 TE 12 .0500 33/120 TE 13 .0500

• 33/240 TE 14 .0500 16/0 TE 15 .0577 16/270 , TE 16 .0577 16/180 TE 17 .0577 16/90 TE 18 .0577 Torus /0 TE 19 .0701 Torus /60 ~ TE 20 .0701 Torus /120 Te 21 .0701 Torus /180 TE 22 .0701 Tcrus/240 TE 23 .0701 Torus /300 TE 24 .0701 93/270 DPE 1 , .0527 78/90 DPE 2 .0489 54/0" DPE 3 .0386 46/180 DPE 4 .0583 33/270 DPE 5 .1502 16/90 DPE 6 .2309 Torus /180 DPE 9 .2102 Torus /270 DPE 10 .2102 f.ews tWV

l 11 5.6 SYSTEM ERROR ANALYSIS Systematic error, in this test, is induced by the operation of the

. . temperature indicating . system, dowpoint indicating system, and the pressure indicating system.

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

Cor'-inment 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 utilises 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 messitivity 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 sensor 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 analyse the smallest value of the analog sensor output which will cause a one digit change in the digital displap.' '

Repeatability is defined as "the capability of the measurement system to reproduce a given reading from a constant source."

Utilizing the methods, techniques, and assusptions in Appendix G to ANS 56.8-1981, the ISG formula was computed for the Absolute Method as follows:

1. Conditions:

L, = 0.5%/ day P = 64.1 psia T = 544 R drybulb T = 8 r dowpoint dp t = 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> estam /Cawucuee9

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12

2. Total Absolute Pressures e P

No. of sensors = 1 Range = 0 - 75 psia sensor sensitivity error (E ) = +0.0013% of full scale

= +0.001% of full scale Measurement system error (c p) o p

= + (E ) + (cp) / (no. of sensors] !

'/

e P

= (0.000975)2 + (0.00075)2 / (1)1/2 e, = +0.00123

3. Water vapor Pressures e No. of sensors = 8 Sen:sor sensitivity error (E ) = +0.5 r

'Hessurement system error ( cF ), =

excluding sensor +.1 r At a dowpoint temperature of 78 F, the equivalent water vapor pressure change (as determined from steam tables) is 0.0157 psia / F E

p

= 10.5 r (0.0157 psia / r)

E = 10.00785 psia c = +0.1*r (0.0157 pala/'r) s p

= 10.00157 psia 1/2 1/2 e,p

=

1 (Ep ,)2 + (sp,)2 _

/ (no. of sensors) 1/2 1/2 ,

o p

=

1 (0.00785)2 + (o.00157)2 / (0) e = 10.00283 pela , _

+ .

13

4. Temperatures e 9

No. of sensors = 24 Sensor sensitivity error (E ) = +0.1 F = +0.1 R Measurement system error (c9),

excluding sensor = +0.1 F = +0.1 R 1/2 1/2 e

9

= + (E 9 )2 + (c,)2 / (no. of sensors]

1/2 1/2 e

9

= + ,

(0.1 )2 + (0.1 )2 / [24]

e = +0.0289 R 9

5. Instrument Selection Guide (ISG):

ITG = + 2( ) +. 2( ) + 2( )

ggg ,2400

• 1/2 24 2(

64.1 )

+ 2(0.00283 64.1 32 + 2(0.0289)2 544

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1/2 ISG = + 100 (7.364 x 10-10 + 3.898 x 10-9 + 5.645 x 10-9) ,

ISG = + 0.010%/ day i

The Iso value does not exceed 0.25 L (0.1254/ day) and it is therefore concluded that the instrue$ntation selected was l

acceptable for use in determining the reactor containment integrated leakage rate.

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14 5.7 SUPPLEMENTAL VERIFICATION In addition to the calibration checks described in section 5.3, test instrumentation operation was verified by a supplemental test subsequent to the completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leakage rate test. This test consisted of imposing a known calibrated leakage rate on the reactor containment building. Af ter the flow rate was established, it was not altered for the duration of the test.

During the supplemental test, the measured leakage rate was:

L, =

L,' + L, Where L = Measured composite leakage rate consisting of the reactor ' containment building leakage rate plus the imposed leakage rate L, = Imposed leakage rate L'= Leakage rate of the reactor containment building during the supplemental test phase Rearranging the above equation, L,' =

L, -

L, The reactor containment building leakage during the supplemental test can be calculated by subtracting the known superimposed leakage rate from the measured composite leakage rate.

The reactor containment building leakage rate during the supplemental -

test (L ') was then compared to the measured reactor containment to buildin,g determine leakage rate during instrumentation the preceding 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test (LInstrumentation fI) acceptability.

acceptable if the dif ference between the two building leakage rates is within 25% of the maximum allowable leakage rate (L,).

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15 6.0 TEST PROCEDURE 6.1 PREREQUISITES Prior to commencement of reactor containment building pressurization, the following prerequisites were satisfied:

1. Proper operation of all test instrumentation was verified.

2. All reactor containment building isolation valves were closed using the normal mode of operation. All associated system valves were placed in post-accident positions.

3. Equipment within the reactor containment building, subject to damage, was protected from external differential pressures.

4. Portions of fluid systems, which under post-accident conditions become extensions of the containment boundary, were drained and vented.

5. Type B and C testing was completed with a leakage value less than O.6 L,. -

6. Containment pressurization system was operational.

7. 'F'our drywell cooling fans and six portable blowers were in operation.

8. Potential pressure sources were removed or isolated from the containment.

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

6.2 GENERAL DISCUSSION Following the satisfaction of th2 prerequisites stated in Section 6.1, the reactor containment buildirg pressurization was initiated at a rate of approximately 6.5 psi per heur. After the containment was stabilized, leak rate testing was initiated at the 49.0 psig pressure level. For the duration of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leak test and the four hour supplemental test, average internal containment temperature remained within a band of 30.40 F.

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

1. Readings indicated by the precision pressure gauge were recorded and entered into the computer.

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2. Readings indicated by the 24 RTDs were recorded and entered into the computer. The computer program calculated the weighted j average containment building drybulb temperature by use of

- a weighting -factor that was assigned to each RTD. This value was 4 subsequently converted to degrees Rankine for use in the ideal gas law equation to calculate containment building weight of air.

i j 3. Readings indicated by the eight dowpoint temperature sensors were recorded and 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 j dewpoint temperature was then converted to a partial pressure of water vapor.

l i

The use of water vapor pressure (Pwv), temperature (T), and the total j pressure (P,) is described in more detail in Section 7.1. All original data is on file at Brunswick Steam Electric Plant Unit No. 2.

J Data was entered into an Omotron attache micro computer located in the plant computer room. 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 computer program then calculated the following at 15 minute intervals:

I Total weight of containment air.

1.

2. $ ass Point least squares fit leakage rate.

i l 3. Mass Point 954 upper confidence limit leakage rate.

A plot of weighted average containment temperature, containment total

! pressure, containment average dewpoint temperature, and weight of air I was performed for each 15 minute data set (see Appendix C).

Immediately following the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> leak test, a superimposed leakage rate was established for an additional four hour period. During this time temperature, pressure, and vapor pressure were monitored as described above.

6.3 TEST PERFORMANCE 6.3.1 Pressurization and Stabilization Phase Pressurization of the reactor containment building was started on September 21, 1984 at 1522. The pressurization rate was approximately 6.5 psi per hour. During pressurization the sample canisters on CAC monitors 1260, 1261, and 1262 became dislodged due to the increased i pressure. A clearance was submitted and these monitors isolated as a result. Discussion with engineering indicated that these monitors should have been isolated due to their low pressure rating of 5 psi.

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--ew.~m+----, ,_,--va----- -.--,-_m,-,,-- -- wem.,----,---- _w, --c,g,, e- aw-eem-r---w ---,a--w--~nwwwv---- - - + , - - - =

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

17 i

when containment internal pressure reached.50 psig at 2320 on September 21, pressurization was secured. By 0330 on September 22

~

i temperature stabilization criteria had been met and leakage rate data recording, reduction, and analysis began.

I 6.3.2 Integrated Leak Rate Testing Phase At 0330 on September 22,15 minute frequency test data collection was initiated. Subsequent to 0330, the following sequence of events took place:

I 1. At approximately 0600, leak detection teams were sent to investigate for potential leakage paths. By 0800 a number of leaks were discovered on valve packings, however, no single 4

large leak was found.

4

2. At 0930, the leakage rate based on six hours of data was relatively constant at 0.4304/ day with a 954 confidence

! interval of 0.4394/ day.

i

3. At 1100 operations added water to the reactor vessel due to a level decrease of approximately 1 inch per hour. Leak detection teams searched the RHR piping for possible water leaks and radwaste had been contacted about additional water they may i

have been receiving since pressurization of containment had been

started.

y 4. 5t 1300 a decision was made to initiate repairs on the leakages i

found earlier in the day. By 1900 all packing leaks had been repaired.

l 5. At 2000 operations again added water to the reactor vessel because of a low level. Investigations into where the water was going -

were still underway.

! 6. At approximately 0200 on September 23 a significant leak was I discovered going into the north RRR sump. Further investigation I found the leak to be coming from a drain line off the discharge of the operating mut pump.

7. At 0400 the leakage rate based on 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of data was 0.4214/ day.

i This value is essentially the same as the computed leakage rate I taken at 0930 on September 22, indicating that the packing leak

! repairs made earlier in the day had no significant effects on the I

overall containment leakage rate.

8. By 0500 the drain valves on the discharge of the RNR pumps had j all been torqued closed and a relatively constant reactor vessel

level established.

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l 18 1 Following the sequence of events mentioned above, an acceptable leakage rate of 0.2894/ day with an associated 954 confidence interval of 0.004%

by weight per day was obtained from 0400 on September 23 to 0400 on September 24.

6.3.3 Supplemental Leakage Rate Test Phase

Following completion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> integrated leak rate test, a leakage rate of 4.3 scfm was imposed on the containment building through j -

a calibrated flow meter at 0400 on September 24. Leakage rate data was again collected at 15 minute intervals for a period of four hours. With an imposed leak rate of .5004 per day, a measured composite leakage rate of 0.765% per day was obtained. This results in a containment building

! leakage rate agreement within 4.8% of L with the results of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test, well within the acceptance limit of 25% of L,.

6.3.4 Depressurization Phase After all required data was obtained and evaluated, containment building depressurization to O psig was started. A post test inspection of the drywell and torus revealed no unusual findings.

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19 7.0 METHODS OF ANALYSIS 7.1 GENERAL DISCUSSION The Absolute Method of leakage rate determination was employed during testing at the 49.0 psig pressure level. The Gilbert / Commonwealth, Inc.

ILRT computer code calculates the percent per day leakage rate using the mass point data analysis technique.

The Mass Point method of computing leakage rates uses the following ideal gas law equation to calculate the weight of air inside containment for each 15 minute intervals .

W = 144 PV ,

KP RT T Where:

W = Mass of air inside containment, Ibn

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K = 144 V/R = 7.96199 x 10 g P = Partial pressure of air, psia j T =

Average internal containment temperature, R V.= 294,981 ft ,

lbf - ft R = 53.35

, lbm OR l The partial pressure of air, P, is calculated as follows:

l P =

PT - P, Where:

I l P = Total containment pressure T

P, = Partial pressure of water vapor determined by averaging the eight dewpoint temperatures and l converting to partial pressure of water vapor, psia l The average internal containment temperature, T, is calculated as

! follows:

l l T = Sum of the products of each RTD x assigned weighting

! factor + 459.69 R I

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20 The weight of air is plotted versus time for the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test and for the four hour 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 1-inear least squares fit line is of the form W = At + B where A is the slope in lba per hour and B is the initial weight at time zero. The least squares parameters are calculated as follows:

A = N( i i) -( i) ( i) .

g XX

( i ) ( i) -( i) { i i)

B = g XX Where:

S = N( Itg) -

( It g)

The weight percent leakage rate 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 1e'a'kage rate as a positive quantity.

7.2 STATISTICAL EVALUATION I i

The upper 954 confidence limit for the Mass Point leakage rate is  !

calculated as follows:

C

= 2400 t95 (8A ! '

Where:

C = Upper 954 confidence limit t

g3

= Student's t distribution with N-2 degrees of freedom S = Standard deviation of the slope of the least squares fit line B = Intercept of the least squares fit line m e--- .o

21 The standard deviation of the slope of the least squares fit line (S )

3 is calculated as follows:

8 "

S (N) ' '

A (N(Itg 2) - (Itg)2] 1/2 Where:

=

S Common standard deviation of the weights from the least squares fit line N = Number of data points t g= Time interval of the ith data point The common standard deviation (S) is defined by:

" I( i - W)2 1/2 N-2 Where:

Wg = Observed mass of air W = Least squares calculated mass of air The ILRT computer code calculates an upper 95% confidence leakage rate as follows:

UCL =

L,, + 2400 t95'(8A /"'

The UCL value is then used to determine that the measured leakage rate at the upper 95% confidence limit meets the acceptance criteria.

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22 8.0 DISCUSSIOtt OF RESULTS 8.1 RESULTS AT P Data obtained during the leak rate test at P indicated the following changes (highest to lowest) during the 24 ho$r test period:

Variable Maximum Change P, 0.199 psia

, P, 0.034 psia T 0.79 F The method used in calculating the mass point leakage rate is defined in

Section 7.1. The results of this calculation is a mass point leakage rate of 0.2894/ day (see Appendix D).

The 954 confidence limit associated with this leakage rate is 0.004% per day. Thus the leakage rate at the upper 95% confidence level becomes:

UCL = 0.289 + 0.004 UCL = 0.293%/ day Additional leakage rates must be applied to the measured leakage rate at the upper 95% confidence level to 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 cnanges. Penetration paths not

, exposed to the ' test pressure and the corresponding leakage rates based on analysis of minimum pathway local leakage rate testing are as follows:

Containment Local System , Isolation Valves Leakage Rate (SCFH)

Drywell Drains 2-G16-F003/F004 0.188 Drywell Drains 2-G16-F019/F020 0 l

l Feedwater (RCIC 2-B21-F032B, O Injection Line B) 2-G31-F039,

,' 2-ES1-F013/

2-B21 -F010B Feedwater (HPCI 2-B21-F032A, 0

Injection Line A) 2-E41-F006/

2-B21-F010A Gaartir-**

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

?

23 Containment Local System Isolation valves Leakage Rate (scfh)

Reactor. Building Closed 2-RCC-V28/VS2 0 Cooling Water 2-RXS-PV1222B/ 0 1222C 4

CRD Purge to Reactor 2-B32-V24/V22, O Recirc Pumps V30 2-B32-V32/V22, O V30 Recire Sample 2-B32-F019/F020 0 RER Suction 2-E11-F008/F009 0 Reactor Water Cleanup 2-G31-F001/F004 0 The total applicable local leakage rate is 0.188 scfh which is equivalent to a leakage rate of 0.00034/ day. The addition of this negligible value does not change the results of the integrated leakage rate test.

Water level changes in the containment during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> integrated leakage rate test are summarized below Reactor Vessel Water; Level:

0400 09-23-84 183.5" 0400 09-24-84 181.0" Torus Water Level:

0400 09-23-84 -29.5" 0400 09-24-84 -29.5" During the test, no makeup water was introduced into the reactor vessel.

Therefore, the volume change associated with the change in reactor vessel water level showed an increase in the net free volume of 54 cubic feet. This corresponds to a reduction in the measured containment leakage rate of 0.018t/ day. However, it is conservatively assumed that the water level decrease in the reactor vessel was not lost out of containment and therefore no change in net free volume occurred.

Geert/Camnuaweets

i 24 The total containment leakage rate at the upper 954 confidence level (UCL) is calculated as follows:

. - UCL = L- - + . 954 -corifidence limit + Type B/C leakage T ~

SEanges in net free volume UCL = 0.289%/ day + 0.004%/ day + 0.0004/ day + 0.0004/ day UCL = 0.293%/ day This value is well below the. acceptance criteria leakage rate of

0.375t/ day (.75 L,).

8.2 SUPPLEMENTAL TEST RESULTS i After conclusion of the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test at 49.0 psig (P the flowmeter I

was placed in service and a flow rate of 4.30 scfm w$s), 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 0.765% pee) day using the Mass Point method of analysis (see Appendix D).

The building leakage rate during the supplemental test is then .

determined as follows:

j E' q

=

L, - L, .

L' = 0.765%/ day - 0.5004/ day L' = 0'265%/

. day Co.nparing this leakage rate with the building leakage rate measured f

during the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> test yields the following:

1 b

am - b' v (0.289) - (0.265)

" = 0.48 L, 0.5% day The building leakage rates agree within 4.8% of L whien is below the acceptance criteria of 25% of L,.

i I

I sa sic-- e

4 ,.

25 Using the formulation of ANS 56.8-1981,

( L, + L,, - 0. 25 L, ) < L < (L + L , + 0.25 L,)

(0.500 + 0.289 - 0.125) <L < (0.500 + 0.289 + 0.125) 0.664 <L < 0.914 Since L was measured to be 0.765% per day, this value falls within the accepta$le range of 0.664 to 0.9144 per day. Therefore, the acceptability of the test instrumentation is considered to have been verified.

i s

O 6

l l

t felbert /Conmempeav I

26

9.0 REFERENCES

I

1. PT-20.5, Integrated Primary Containment Leak Rate Test.

2. Brunswick Steam Electric Plant Unit No. 2 Final Safety Analysis Report.

3. Code of Federal Regulations, Title 10, Part 50, Appendix J.

4. ANSI N45.4-1972, Leakage Rate Testing of Containment Structures for Nuclear Reactors, American Nuclear Society (March 16, 1972).

5. ANS-56.8-1981, Containment System Leakage. Testing Requirements, American Nuclear Society.

6. ILRT Computer Code, Gilbert / Commonwealth, Inc.

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

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APPENDIX A SCHEMATIC ARRANGEMENT OF TEST INSTRUMENTATION e

e Geert /Cammenwea's

APPENDIX A SCHEMATIC ARANGEMENT OF TEST INSTRUMENTATION ' l T

. F 3 CO RESSED ELEY. 93' e 180* 270*

ELEY.78' 5 0' 90* 90' ELEY.66' E11 I" F021A ELEY. 54' .g.E TE ort PRECISION

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PRESSURE 1 F016A '. ELEY.46' CAUGES $

TE TE TE DPE 9 10 11 4 300* 0* 180* 180*

AD R E D[E ROTMETER 0 ,120* 240' N0*

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R = TDtFERATURE ELEMENT (RTD)

DPE a DEWPOINT ELDIENT(DEWCELL) i e

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APPENDIX *B REDUCED TEST DATA t

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9

e APPENDIX B REDUCED TEST DATA Date Time PAVG PNV TAVG Weight 09-23-84 0400- 64.162 -

.477 84.66 93150.11 0415 64.157 .475 84.63 93150.59 0430 64.158 .474 84.62 93155.81 0445 64.162 .474 84.63 93157.98 0500 64.170 .473 84.68 93162.66 0515 64.170 .480 84.69 93150.69 0530 64.164 .484 84.70 93135.88 l 0545 64.158 .478 84.68 93137.81 0600 64.160 .481 84.67 93138.46 0615 64.160 .480 84.66 93142.36 0630 64.150 .480 84.64 93131.31 0645 64.149 .476 84.63 93135.41 0700 64.139 .476 84.60 93126.98 0715 64.134 .478 84.57 93121.47 0730 64.125 .474 84.53 93120.99 0745 64.120 .473 84.51 93119.88 0800 64.116 .474 84.48 93118.02 0815 64.11 .470 84.46 93119.85 0830 64.108 .472 84.44 93116.05

. 0845 64.100 .472 84.42 93106.96 0900 64.090 .470 84.38 93102.12

.0915 64.084 .470 84.36 93096.31

'0930 64.088 .468 84.33 93109.75 0945 64.078 ,

.467 84.32 93099.40 1000 64.076 .468 84.32 93095.76 1015 64.071 .468 84.31 93089.88 1030 64.060 .468 84.31 93073.77 1045 64.060 .471 84.28 93074.85 1100 64.054 .470 84.27 93067.45 1115 64.056 .468 84.28 93071.50 1130 64.055 .469 84.29 93067.91 1145 64.060 .471 84 30 93070.70 1200 64.055 .472 84.30 93061.35 1215 64.065 .471 84.32 93074.86 1230 64.062 .475 84.34 93061.12 1245 64.070 .478 84.39 93060.87 1300 64.072 .479 84.42 93055.54 1315 64.075 .483 84.46 93047.77 1330 64.076 .479 84.47 93053.45 1345 64.080 .484 84.51 93044.69 1400 44.094 .486 84.59 93048.66 1415 64.094 .488 84.63 93038.56 1470 64.105 .487 84.67 93049.88 1445 64.105 .492 84.68 93040.57 Gest /fanuusumeWe

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

~

,o Appendix B (Cont'd)

Date Time PAVG PWV TAVG Weight 09-23-84 1500 64.110 .490 84.74 93041.20 1515 64.106 .489 84.77 93031.48 t 1530 64.107 .492 84.78 93026.20 1545 64.107 .495 84.80 93018.89

,1600 64.107 .496 84.80 93016.56 i 1615 64.101 .493 84.81 93009.89 1630 64.109 .493 84.83 93019.70 1645 64.109 .493 84.85 93016.56 1700 64.129 .494 84.87 93040.54 1715 64.108 .497 84.89 93002.29 1730 64.112 .492 84.90 93013.92 1745 64.110 .496 84.94 92998.38 1800 64.120 .495 84.97 93008.77 1815 64.113 .495 84.98 92996.43 1830 64.118 .496 85.02 92994.85 1845 64.122 .501 85.04 92990.73 1900 64.120 .499 85.06 92987.45 1915 64.120 .500 85.05 92987.88 1930 64.114 .497 85.04 92984.70 1945 64.115 .499 85.04 92982.85 2000 64.104 .497 85.03 92972.12 2015 64.103 .495 85.02 92975.95

2030 64.095 .493 84.98 92973.55 l ,2045 64.089 .493 84.96 92968.23 2100 64.085 .492 84.94 92967.66 2115 64.080 .491 84.92 92965.58

! 2130 64.075 .492 84.89 92961.13 2145

• 64.072 .492 84.87 92960.80 2200 64.064 .490 84.86 92953.77 2215 64.060 .490 84.81 92955.09 2230 64.050 .487 84.82 92943.91 2245 64.055 .488 84.82 92948.24 2300 64.055' .486 84.82 92951.82 2315 64.052 .490 84.86 92935.50

. 2330 64.060 .493 84.87 92940.38

! 2345 64.054 .493 84.80 92944.39 i

09-24-84 0000 64.050 .492 84.83 92935.68 0015 64.050 .491 84.83 92936.49 0030 64.046 .493 84.82 92929.10 0045 64.041 .488 84.81 92930.08 1 0100 64.038 .489 84.79 92928.44 0115 64.031 .488 84.81 92916.51 0130 64.028 .489 84.73 92923.88 0145 64.022 .484 84.72 92924.54 Smet/Commen.ese

Appendix B (Cont'd)

I Date Time PAVG PWV TAVG Weight t

0200 64.016 .488 84.71 . 92912.50-0215 64.011 .486 84.69 92911.17 0230 64.008 .484 84.67 92913.53 0245 64.000 .484 84.64 92905.22 0300 63.993 .484 84.61 92900.31 0315 63.986 .484 84.59 92893.71 0330 63.985 .481 84.57 92899.75 0345 63.971 .478 84.52 92891.46 0400 63.975 .478 84.52 92898.42 Verification Test 09-24-84 0400 63.975 .478 84.52 92898.42 I

0415 63.962 .479 84.50 92881.67 0430 63.960 .480 84.49 92878.73 0445 63.960 .477 84.47 92886.34 0500 63.950 .481 84.46 92867.25 0515 63.946 .479 -

84.48 92861.46 0530 63.938 .479 84.49 92848.09

! 0545 63.940 .482 84.49 92847.64 l '

0600 63.930 .483 84.49 92830.55 1

• 0615 63.929 .479 84.50 92832.92

,0630 63.919 .485 84.48 92813.66 0645 63.917 .482 84.49 92812.91 0700 63.913 .483 84.48 92807.42 0715 63.905 .483 84.47 92796.82 0730 63.905 .479 84.46 92803.54 0745 63.894 .480 84.45 92789.81 0800 63.877 .482 84.39 92771.68 i

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APPENDIX C LEAKAGE RATE TEST GRAPHS e

e GJbert /Cammenesatth

APPENDIX C .

WEIGHT OF CONTAINMENT AIR AND AVERAGE CONTAINMENT TEMPERATURE VERSUS TIME 2sa 92,900 g

~

Least Squares Fit Equation d g W = 92,896 - 29.63t

$ 92,850 -

bt 92,800 O g -

g d

z O 92,750 -

4 Hour Superimposed Leak Rate Test i

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APPENDIX C WEIGHT OF CONTAINMENT AIR AND AVERAGE CONTAINMENT TEMPERATURE VERSUS TIME 93,200 _.

i 93,100 _ LEAST SOUARES FIT EQUATION tQ W = 9 3,159 - 11.21 t i,

eg *#** e i s= e

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24 HOUR INTEGRATE 3 LEAK RATE TEST 1

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APPENDIX D COMPUTER RESULTS t

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Gast/Camman m

APPENDIX D COMPUTER RESULTS

1. Mass Point Results:

A = Slope of least squares line (1bs/hr) is -11.-2075 - - --

B = Intercept of least squares line (1bs) is 93,159.2 L,, = Measured leak rate is 0.28874 per day UCL = 954 upper confidence leakage rate is 0.29264 per day I

2. Verification Test:

A = Slope of least squares line (1bs/hr) is -29.62 B = Intercept of least squares line (1bs) is 92,896 l

L, = Composite leakage rate is 0.765% per day 1

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APPENDIX E LOCAL LEAKAGE RATE DATA t

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As noted in Licensee Event Report 2-84-1 local leak rate testing of Unit 2 primary containment isolation valves revealed a nonquantifiable leakage rate initially on seven containment penetrations. This condition makes calculation of the "as found" containment leakage indeterminate.

A suussary of all Type 8 and C testing and maintenance required since the Type A testing follows:

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PREstAINTEllA80CE TESTS MAINTENAasCE REQUIRED POSTMAINTENA80CE TESTS TEST TEST LEAMACE WRaA WORK 1EST TEST LEAMAGE EL_ VALVES fscrh1 DATE 40._ PERFORMED L VALVES fscrh1 g&IE N-7 Pen X2008 0 11-23-83 leone IsA N-7 Pen X2006 0 9-5-84 soone NA .

N-8 Pen MA 0 9-6-84 None NA M-1 CAC-V49 Inbd 0-Rings 3.266 9-6-84 soone NA M-2 CAC-V5 Inbd 0-Rings 0 3-23-84 peone NA M-3 CAC-V6 Inbd 0-Rings 0 3-23-84 Icone NA M-4 CAC-V7 inbd 0-Rings 0 9-7-84 None NA M-5 CAC-V9 Inbd 0-Rings 0 3-23-84 Isone stA M-6 CAC-V16 Inbd 0-Rings 0 6-14-84 Isone NA M-7 CAC-V17 inbd 0-Rings 0 -

3-13-84 None NA B21-1 821-F0 LOA WelP 3-28-84 2M-84-2300 Machined disc and 821-1 B21-F010A 0 8-24-84 replaced sort seat 821-2 821-F0108 WelP 3-28-84 2M-84-2301 Machined disc and B21-2 B21-F0108 0 7-8 replaced sort seat B21-3 B21-F032A, E41-F006 0 3-31-84 None NA B21-4 B21-F0328, E51-F013, WNP 3-30-84 2M-84-2406 Remove G31-F039 and 821-4A B21-F0328, 12.625 7-9-84 G31-F039 install f reeze sea l E51-F013 PM-84 -324 Install valve F039 821-4b G31-F039 1.75 8-19-84 821-5 821-F016, 821-F019 0 3-30-84 2E-84-3878 Replace 4 Jumpers on B21-5 B21-F016, 0 9-19-84 torque switch B21-F019 F016 832-1 B32-V22, 832-V30 0 5-17-84 2E-84-2957 Replace lugs and B32-1 832-V22 0 9-21-84 set stroke, V22 B32-V30 832-2 B32-F019, F020 5.62 4-10-83 2M-82-4241 Reeoved valve, F020, 832-2 832-F019, F020 0 4-14-83 cleaned inte rna l s 1 0 3-20-84 None NA B32-3 832-V24 16.45 5-7-84 2M-84-3095 Complete overhaul 832-3 832-V24 1.166 8-10-84 832-4 832-V32 0 5-6-84 None NA WMP = Would Not Pressurize MSC052 3

e ._. - -- - - . .. - . - - - - . - _. . . - _ _ - _ - . - . . .

e PREMAINTENANCE 1ESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE WR4A WORK TEST TEST LEAKAGE

, No. VALVES (scfhl DATE NO. PERFORMED No. VALVES (scrh1 DATE C41-1 C41-F006 0 4-16-84 None NA i

C41-2 C41-FOO7 0 4-17-84 None NA CAC-1 CAC-V47 WNP 4-7-84 2M-84-2983 Roset actuator CAC-1 CAC-V47 0 8-5-84 CAC-2 CAC-V48 Blanked off Hone NA CAC-3 CAC-V4, VS, V6, V15, Orrscale 3-14-84 2M-84-2983 Reset actuator V47 CAC-3 12.947 8-13-84 V55, V56 2M-84-4990 Replace internals V4 2M-84-2035 Adjust stop V5 1 2M-84-3745 Replace disc V6 i 2E-84-3468 Disconnect operator CAC-3 10.79 8-27-84 j for disc changeout and reconnect upon completion 2M-84-5500 Set stops V15 CAC-3 10.815 8-31-84

CAC-4 CAC-V7, 8, 22 19.35 3-18-84 PM-83-218 Replace CAC-V7 and CAC-4 CAC-V7, 8, 22 0 7-19-84 I CAC-V8

CAC-5 CAC-V9, VIO, V23 4.678 3-18-84 NA Valve cycled V9, CAC-5 CAC-V9, V10, 0.7739 3-18-84

~

VIO, V23 V23 2M-84-2984 set stops V10 CAC-5 CAC-V9, V10, 25.732 8-7-84 i V23 i 2M-84-4897 Set stops V9, V10 CAC-5 CAC-V9, V10, 0 9-8-84

! V23

] CAC-6 CAC-X20A, CAC-V16 WNP 3-12-84 2M-84-1882 Replace V16 PM 83-218 CAC-6 CAC-X20A, CAC-V16 WNP 6-8-84 2M-84-3713 Set stop V16 CAC-6 CAC-X20A, CAC-V16 0 6-14-84 I CAC-7 CAC-X20B, CAC-V17 1.772 3-13-84 2M-84-1882 Replace V17 PM 83-218 CAC-7 CAC-X208, CAC-V17 WNP 6-18-84 l

2M-84-1882 Set stop V17 CAC-7 CAC-X208, CAC-V17 1.035 6-20-84 CAC-8 CAC-V49, CAC-V50 0 3-16-84 None NA j

CAC-9 CAC-PV12008 2.798 3-19-84 2M-84-2175 Tighten retaining CAC-9 CAC-PV12008 0.280 9-18-84 plate CAC-10 CAC-PV1261 0 3-21-84 None NA

! CAC-11 CAC-PV1227A 0 4-3-84 None NA i

CAC-12 CAC-PV12278 0 4-3-84 None NA l CAC-13 CAC-PV1227C 0.324 4-25-84 None NA  !

l CAC-14 CAC-PV1227E O 4-3-84 None NA

CAC-15 CAC-PV1260 0 4-25-84 None NA WNP = Would Not Pressurize MSC052 4 i

i

I PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAl.4TENANCE TESTS TEST TEST LEAKACE WR&A WORK TEST TEST LEAKACE No. VALVES iscfbl_ DATE NO. PERFORMED NO . . VALVES iscrh) DATE CAC-16 CAC-PV12318 0 4-3-84 None NA CAC-17 CAC-PV3440 0 4-2-84 None NA

• CAC-18 CAC-PV12258 0 -

4-2-84 None NA CAC-19 CAC-PV1211F 0 4-12-84 None NA CAC-20 CAC-PV1262 0 4-12-84 None NA CAC-21 CAC-PV1209A 0.0951 4-2-84 None NA CAC-22 CAC-PV1209B 1.042 4-2-84 2M-84-2985 Tighten retaining CAC-22 CAC-PV12006 0 9-8-84 plate CAC-23 CAC-PV1205E 1.559 4-2-84 2M-84-2418 Tighten retaining CAC CAC-PV1205E O 9-8-84 plate CAC-24 CAC-PV1215E O.308 4-2-84 None NA CAC-25 CAC-PV1211E O 3-23-84 None NA CAC-26 CAC-PV3439 0 3-23-84 None NA CAC-27 CAC-PV3441 0.8038 4-2-84 None Removed per PM-80-033 NA CAC-SV4541 0 4-3-84 None NA CAC-28 CAC-PV3442 0 4-2-84 Nnne Removed per PM-80-033 NA CAC-29 CAC-PV3437 0 3-23-84 None Removed per PM-80-033 NA CAC-SV4540 0 4-2-84 None NA CAC-30 CAC-PV3438 0 3-23-84 None Removed per PM-80-033 NA CAC-31 CAC-SV1263-4 3.639 4-2-84 None Removed per PM-80-033 NA CAC-SV4409-4 0 4-3-84 None NA l CAC-32 CAC-SV1263-3 WNP 4-2-84 None Removed per PM-80-033 NA CAC-SV4409-3 0 4-3-84 None NA CAC-33 CAC-SV1263-2 1.716 4-2-84 None Removed per PM-80-033 NA CAC-SV4409-2 0 4-3-84 None NA CAC-34 CAC-SV1263-1 1.469 4-2-84 None Removed per PM-80-033 NA CAC-SV4409-1 0 4-3-84 None NA CAC-35 CAC-SV1259-4 1.313 4-2-84 None Removed per PM-80-033 NA CAC-SV4410-4 0 4-3-84 None NA CAC-36 CAC-SV1259-3 42.204 4-2-84 None Removed per PM-80-033 NA CAC-SV4410-3 0 4-3-84 None NA WNP = Would Not Pressurize MSC052 5 9

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

i

• PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE WR&A WORK TEST TEST LEAKAGE NO . . VALVES iscrhl DATE M0m_ PERFORMED M9 _ VALVES (scfhl DATE CAC-37 CAC-SV1259-2 3.535 4-2-84 None Removed per PM-80-033 NA CAC-SV4410-2 0 4-3-84 None NA CAC-38 CAC-SV1259-1 1.362 4-2-84 None Removed per PM-80-033 NA

• CAC-SV4410-1 0 4-3-84 None NA CAC-39 CAC-PV1218C WNP 5-30-84 2M-84-3451 New valve instal' led CAC-39 WNP 8-14-84 2M-84-5157 Replaced internals CAC-39 0 9-2-84 CAC-40 CAC-PV12198 6.112 5-15-84 2M-84-3183 Lapped seat CAC-40 0 9-9-84 f CAC-41 CAC-PV1225C 0 5-15-84 None NA CAC-42 CAC-PV1209D 22.596 5-15-84 2M-84-3184 Replaced internals CAC-42 0.7977 8-31-84 CAC-45 CAC-PV1219C 10.631 5-15-84 PM-078 Replaced valve CAC-45 0 8-28-84 CAC-46 CAC-SV1213A 0 8-8-84 None NA

]

i CAC-47 CAC-SV1218A 0 8-8-84 None NA I

E11-1 Ell-F008, F009 WNP 5-29-84 2M-84-34'45 Lap seats F009 E11-1 E11-F008, F009 0 6-22-84 E11-2 E11-F011A 0 5-12-84 Mone NA E11-3 E11-F0118 WNP 3-23-84 2M-84-2217 Bounda ry va lve repa i r 2M-84-2604 Bounda ry va lve repa i r E11-3 E11-F0118 0.116 4-17-84 f E11-4 E11-F015A, F017A WNP 5-2-84 None Valve cycled E11-4 E11-F015A, F017A 0 5-2-84 E11-5 E11-F0158, F0178 1.163 3-25-84 None Valve cycled E11-5 E11-F015A, F017B 0.884 3-26-84 E11-6 E11-F016A, F021A 0 5-2-84 2M-83-253 Replaced sten F016A E11-6 E11-F016A, F021A 0 7-28-84 E11-7 E11-F016B, F0218 9.178 3-25-84 None Valve cycled E11-7 E11-F0168, F021B 0 3-26-84 1 0 4-19-84 E11-8 E11-F020A WNP 5-4-84 2E-84-4086 Set torque switch E11-8 E11-F020A 16.209 7-18-84 2M-84-4608 Belville springs adj. E11-8 E11-F020A 11.852- 7-24-84 j 2E-84-4171 Reset torque switch E11-8 E11-F020A 0 7-30-84 1 E11-9 E11-F0208 WNP 3-30-84 2M-83-2335 Replace stem E11-9 E11-F0208 15.13 4-29-84 2E-84-2014 Set torque switch 2M-84-2913 Lapped seat, repa i r disc guides 4 2M-84-2771 Repair guides E11-9 E11-F0208 13.52 8-27-84 E11-10 E11-F022, E11-F023 0 3-24-84 None NA WNP = Would Not Pressurize t

MSC052 6 l

1

.____.Aa a__ + __-# - --- w +v---m -- A +m 4- me *---L& 4 A --  % A1a S

e POSTMAINTENANCE TESTS I PREMAINTENANCE TESTS MAINTENANCE REQUIRED

TEST TEST LEAKAGE WR&A ^ WORK TEST TEST LEAKAGE NO. VALVES iscFhl DATE NO _ PERFORMED NO._ VALVES iscFhl DATE E11-11 E11-F024A, F027A, 0 5-5-84 2M-83-251 Valve stem replaced E11-11 E11-F024A, F027A O 7-27-84 1 F028A on F024A F028A j

E11-12 E11-F0248, F027B, 0 3-24-84 2M-83-0250 Valve stem replaced E11-12 E11-F024B, F0278 0 4-20-84 F0288 on F0248 F0288 E11-13 E11-F025A 0 5-3-84 None PT-11.0 performed E11-13 E11-F025A 0 5-4-84 E11-14 E11-F0258 1.18 3-26-84 2M-84-2246 Cleaned seat E11-14 E11-F0258 0 3-27-84 i E11-15 E11-F037D 0.849 3-28-84 2M-84-2322 Rebuilt E11-15 E11-F037D 10.19 9-1-84 1 2M-84-5558 Lapped seat E11-15 E11-F0370 0.2912 9-1-84 i

? E11-16 E11-F0378 1.150 3-28-84 2M-84-2321 Rebuilt valve E11-16 E11-F0378 0.6326 9-1-84 E11-17 E11-F043D 1.31 3-28-84 2M-84-2319 Installed new 0-rings, E11-17 E11-F043D 2.667 5-12-84 1

bellows, and disc

2M-84-3754 Replace diaphragm E11-17 E11-F043D 2.833 8-4-84 None Cycle valve E11-17 E11-F043D 2.303 9-19-S4 E11-18 E11-F043B 17.97 3-28-84 2M-84-2320 Installed new 0- E11-18 E11-F0438 1.024 9-1-84 rings, bellows, and I disc E11-19 E11-F037C 0.141 3-31-84 None NA 1

E11-20 E11-F043C 1.091 3-31-84 2M-84-2476 Replaced all E11-20 E11-F043C 2.177 8-24-84 inte rna l s l E11-21 E11-F043A 75.70 3-31-84 2M-84-2475 Replaced 0-rings, E11-21 E11-F043A O 8-24-84 i bellows, and disc

\

j E11-22 E11-F037A 0 3-31-84 None NA E11-23 E11-F097 0 5-24-84 None NA E11-24 E11-F007A 0 5-4-84 None NA E11-25 E11-F007B 0.232 3-24-84 None NA ,

E11-26 E11-F103A 0 5-23-84 None NA l E11-27 E11-F103B 0.095 3-27-84 None NA i

E11-28 E11-F055A 0 5-3-84 None Valve pop tested, E11-28 Ell-FOSSA 0 5-4-84 f PT-11.0  ;

l E11-29 E11-F0558 0.2838 3-27-84 2M-84-2259 Replaced spring E11-29 E11-F0558' O 4-3-84 E11-30 E11-V20 0 5-3-84 None Valve pop tested, E11-30 E11-V20 0 5-4-84 l PT-11.0

! WNP = Would Not Pressurize MSC052 7 i

~

%I o

C PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE WR&A WORK TEST TEST LEAKAGE NO. VALVES iscfh) DATE MQm_ PERFORMED NO . - VALVES iscrh1 DATE E11-31 E11-V21 0 3-27-84 None Valve pop tested E11-31 E11-V21 0 3-27-84

- E11-32 E11-F029 0 6-5-84 None Valve pop tested E11-32 E11-F029 0 6-5 E21-1 E21-F001A WNP 5-21-84 2M-84-3317 Machined disc and E21-1 E21-F001A 0 7-19-84

} tapped seat E21-2 E21-F0018 1.343 4-13-84 None NA E21-3 E21-F005A, F004A 0 5-18-84 None NA i

E21-4 E21-F005B, F004B 0 4-10-84 2M-84-2603 Cleaned seats E21-4 E21-F0048, F0058 0 9-19-84

E21-F004B E21-5 E21-F015A 0 5-18-84 2M-83-0260 Replaced stem E21-5 E21-F015A 0 7-18-84 4 E21-6 E21-F0158 0 4-11-84 2E-83-3991 Stem replaced E21-6 E21-F0158 0 5-10-84 E21-7 E21-F031A 0 5-30-84 None NA 4 E21-8 E21-F031B 0 4-15-84 None NA i

E41-1 E41-F002, F003 0.2325 7-31-83 2M-83-2984 Repack valves E41- E41-1 E41-F002, F003 6.20 8-1-83 F002 and E41-F003 E41-1 E41-F002, F003 0 3-14-84 None NA E41-2 E41-F012 0 3-17-84 2M-84-3772 Rebuilt spring pack E41-2 E41-F012 0 8-28-84 E41-3 E41-F042 0 3-15-84 None NA E41-4 E41-F022, F040 0.2382 3-16-84 No.Sd NA E41-5 E41-F021, F049 WNP 3-17-84 2M-84-2174 Lubricate packing E41-5 E41-F021, F049 WNP 6-12-84

, F021 2M-84-3564 Valve F021 was not E41-5 E41-F021, F049 2.055 8-3-84 initially slugged j shut as required E41-6 E41-F075, F079 2.261 3-15-84 None Cycled both valves E41-6 E41-F075, F079 0 3-18-84 E41-7 E41 - PV1218D, PV1220D 0 4-7-84 None NA WNP = Would Not Pressurize I

i MSC052 8 i

t

-~ - - -- -

e e

PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE . WR&A WORK TEST TEST LEAKAGE NO. VALVES iscFhl DATE NO. PERFORMED No._ VALVES (scFhl DATE>

E41-8 E41- PV1219D, PV1221D 1.244 5-25-8'4 2M-84-3387 Complete overhaul E41-8 E41-PV1219D, PV1221D 11.97 8-17-84 E41-PV1221D 2M-84-3386 Complete overhaul E41-8 E41- PV12190, PV1221D 1.753 9-9-84 E41-PV1219D 2E-84-5311 Adj. limit switch E41-8 E41 - PV12190, PV1221D 1.084 9-18-84 E41-PV1219D E51-1 E51-F007, F008 27.455 7-31-83 2M-83-2986 Replaced valve F007 E51-1 E51-F007, F008 30.25 8-1-83 2M-83-3026 Adjust packing FOO7 E51-1 E51-F007, F008 10.266 8-2-83 E51-1 E51-F007, F008 36.432 3-29-84 None Cycled F007 valve E51-1 E51-F007, F008 WNP 3-30-84 2M-84-2336 Install new disc F007 2M-84-5349 Machine disc F007 E51-1 E51-F007, F008 18.026 9-16-84 2M-84-5773 Increase torque switch setting F007 E51-1 E51-F007, F008 6.722 9-17-84 E51-2 E51-F019 0 3-16-84 None NA E51-3 E51-F031 0 3-15-84 None NA E51-4 E51-F002, F028 0 3-20-84 Nona NA E51-5 E51-F001, F040 WNP 3-17-84 2M-84-2173 E51-F040 seat was E51-5 E51-F001, F040 16.45 6-6-84 lapped 2M-84-5511 Lubricate stem E51-5 E51-F001, F040 5.44 8-31-84 E51-F001 E51-6 E51-F062, F066 4.844 3-16-84 2M-84-2159 Reworked seat F062 E51-6 E51-F062, F066 40.67 4-7-84 2E-84-2119 AdJ. torque switch E51-6 E51-F062, F066 51.313 6-7-84 F062 2M-84-3639 Turned down disc E51-6 E51-F062, F066 0 8-17-84 on lathe F062 G16-1 G16-F003, F004 0.1883 4-3-84 None NA G16-2 G16-F019, F020 0 4-7-84 None NA G31-1 G31-F001, F004 WNP 3-30-84 2M-84-3960 Added packing G31-1 G31-F001, F004 0 8-12-84 G31-F004 f

l G31-1 G31-FOO1, F004 WNP 12-4-83 Cycle valves and riush seats G31-1 C31-F001, F004 11.114 12-5-83 12-6-83 2M-83-5086 Lapped seat F004 G31-1 G31-F001, FOO4 WNP 12-7-83 Repacked valve 12-14-83 2M-83-5217 Torqued a l l six bonnet bolts on F004 WNP = Wou!d Not Pressurize MSC052 9 i

'o C.

PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE WR4A WORK TEST TEST LEAKAGE NO. VALVES iscrhi DATE N02 _ PERFORMED HQ _ VALVES Lacfhl DATE G31-1 12-15-83 2M-83-5223 Tightened retaining (Cont'd) ring on FOO4 12-16-83 2M-83-5227 Insta lled pressure G31-1 G31-F001, F004 0.1648 12-17-83 seal ring on FOO4

~

G31-2 G31-F042 WNP 5-6-84 PM-84-325 Replaced valve G31-2 G31-F042 0 8-20-84 RCC-1 RCC-V28, V52 0 5-19-84 None NA RCC-2 RXS- PV12228, PV1222C WNP 5-19-84 2M-84-3302 Replace internals on RXS-PV12228 2M-84-3303 Replace internals on RCC-2 RXS-PV12228, PV1222C 0 8-15-84 RXS-PV1222C RNA-1 RNA-V101 0.141 5-25-84 None NA RNA-2 RNA-V103 0 5-26-84 Hone NA RNA-3 RNA-PV1204B O.710 5-3-84 None NA RNA-4 RNA-PV1204C 0.639 5-3-84 Hone NA RXS-1 RXS-SV4186 0 8-17-84 None NA RXS-2 RXS-SV4187 0 5-15-84 None NA RXS-3 RXS-SV4188 0 5-16-84 None NA RXS-4 RXS-SV4189 2.037 5-29-84 2E-84-4415 F lushed w/a i r to RXS-4 RXS-SV4189 0 8-16-84 remove trash SA-1 SA-V448 0 3-24-84 None NA SA-2 SA-V449 0.1413 3-24-84 None NA TD-1 TD-V22, V1 WNP 6-5-84 2M-84-3553 Replaced all gaskets TD-1 TD-V22, V1 0 7-26-84 and reinstalled TIP-1 TIP-V1 0.0485 4-4-84 None' NA TIP-2 TIP-V2 O 4-4-84 None NA TIP-3 TIP-V3 0 4-4-84 None NA TIP-4 TIP-V4 0 4-4-84 Hone NA WNP = Would Not Pressurize MSC052 10

n. - .-.

4',

5

• a PREMAINTENANCE TESTS MAINTENANCE REQUIRED POSTMAINTENANCE TESTS TEST TEST LEAKAGE vmas WORK TEST TEST LEAKAGE NO. VALVES iscrh1 DATE MQ _ PERFORMED NO. VALVES (scfhl DATE TIP-5 TIP N2 Check Valve 1.343 4-4-84 2E-84-2660 Replace valve TIP-5 TIP N2 Check Valve 0 8-29-84 TIP-6 TIP N2 Solenoid Valve 1.346 4-6-84 2E-84-2665 Replace valve and TIP-6 TIP N2 Solenoid Valve 0 8-29-84.

coil PT-20.3A NA B21-F022A, F028A 9.882 3-13-84 2M-84-1264 Rebuilt actuator NA B21-F022A, F028A 10.379 8-15-64 821-F028A 2M-84-4429 Rebuilt actuator 821-F022A NA B21-F0228, F028B 2.03 3-13-84 2M-84-1263 Rebuilt actuator NA B21-F022B, F0288 11.125 8-15-84 B21-F0288 2M-84-1261 Rebuilt actuator B21-F0228 NA B21-F022C, F028C 8.121 3-13-84 2M-84-1266 Rebuilt actuator NA B21-F022C, F028C 4.25 8-15-84 B21-F028C 2M-84-1262 Rebuilt actuator 821-F022C NA B21-F022D, F028D 0.4693 3-13-84 2M-84-1267 Rebuilt actuator NA B21-F022D, F0280 0 8-15-84 821-F028D 2M-84-1263 Rebuilt actuator B21-F022D MSC052 11

___ _ _ _ _ _ _ _ _ _ _