ML19210A640

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Addendum to Reactor Containment Bldg Integrated Leak Rate Test, Apr 1977
ML19210A640
Person / Time
Site: Three Mile Island Constellation icon.png
Issue date: 11/15/1977
From: Klingaman R, Shirk R
METROPOLITAN EDISON CO.
To:
Shared Package
ML19210A639 List:
References
NUDOCS 7910300671
Download: ML19210A640 (12)
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Text

THREE MILE ISLAND NUCLEAR STATION Ci1T 1 ADDENDUM TO REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST APRIL 1977 METROPOLITAN EDISON COMPANY SUBSIDIARY OF GENERAL PUBLIC UTILITIES CORPORATION

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PREPARED BY . . v R. E. Shirk Gilbert Associates, Inc.

APPROVED BY T '

/N J. M. K/Qgaman /

/Managd-Geheradonering Engine //h)

MetropolitanEdisonCo.

1492 273 Geert/Commemmeau 910300{y(

TABLE OF CONTENTS Item Title Page Section I

1.0 SYNOPSIS 2

2.0 INSTRUMENTATION CORRECTION FACTORS 2.1 PRESSURZ MONITORING SYSTEM 2 2.2 TEMPERATURE MONITORING SYSTEM 3 4

2.3 DEWPOINT INDICATING SYSTEM 4

2.4 SUPPLEMENTAL TEST FLOW MONITORING SYSTEM DISCUSSION OF RESULTS 5 3.0 3.1 RESULTS AT P a 5 3.2 SUPPLEMENTAL TEST RESULTS 5 6

4.0 REFERENCES

1492 274 i

Geert/Commemsene i

1.0 SYNOPSIS The measured leakage rate based on the mass point method of analysis and using absolute values corrected for instrument error was found to be 0.041 percent by weight per day at 50.6 psig.

The leakage rate at the upper bound of the 95 percent confidence interval is 0.051 percent by weight per day which is well below the allowable leakage rate of 0.075 percent by weight per day at 50.6 psig.

The supplemental instrumentation verification at P, was 2.0 percent, well within the 25 percent requirement of 10 CFR 50, Appendix J, Section III A.3.b.

1492 275 Geert/CommennesRA 1

2.0 INSTRUMENTATION CORRECTION FACTORS _

Instrumentation correction factors were determined from Metropolitan Edison Company Procedure, 1430-Y-23, " Reactor Building Integrated Leak Rate Test" and were applied to the te=peratures, pressures and vaior pressures recorded in Metropolitan Edison Company Procedure, SP 1303-6.1, " Reactor Building Integrated Leak Rate Test". Both of these procedures are on file at Three Mile Island Nuclear Station Unit 1.

2.1 PRESSURE MONITORING SYSTEM Due to the high accuracy of the precision pressure gages, it is not possible to do a field calibration. The gages were compared with each other at various pressure levels as a check to determine the relative calibration status. Calibration information from the manufacturer, Texas Instruments, for the pressure plateau closest to the test pressure, indicates gage PI-390 (S/N 2604) was reading 0.005 psi above the true pressure and gage PI-391 (S/N 2605) was reading 0.000 psi from the true pressure. However, a conservative correction factor of -0.015 psi was applied for both gages (representing the maximum nossible error).

1492 276 2

l 2.2 TEMPERATURE MONITORING Sn 'EM - - - .c, Correction f actors for each RTD reading (sensor, bridge card, and digital readout) are listed below:

Temperature Correction Reading Factor, F 655 A +0.1 655 B +0.6 655 C +0.6 655 D +0.5 655 E +0.6 655 F -0.4 655 G -0.6 655 H -0.4 655 I -0.4 655 J -0.2 655 K -0.2 655 L +0.5 655 M +0.6 655 N -0.5 655 0 +0.2 655 P -0.2 655 Q +0.4 655 R -0.2 655 S -0.5 655 T +0.4 655 U +0.3 655 V +0.1 655 W +0.3 655 X -0.6 1492 277 Geert/w 3

2.3 DEWPOINT INDICATING SYSTEM Correction factors for each dewpoint temperature reading are listed below:

Dewpoint Dewpoint Dewcell Recorder Applied Temperature Correctgon Correctgon Correction Reading Factor, F Factor, F Factor, F 654 A -0.3 +0.4 +0.1 654 B -0.1 +0.4 +0.3 654 C -0.5 +0.4 -0.1 654 D -0.1 v0.4 +0.3 654 E -0.1 +0.4 +0.3 654 F -0.5 +0.4 -0.1 654 G -0.2 +0.4 +0.2 654 H -0.1 +0.4 +0.3 ,

654 I -0.4 +0.4 0.0 654 J NOT USED 2.4 SUPPLEMENTAL TEST FLOW MONITORIdG SYSTEM A comparison check was made between the flowmeters at various flow rates to determine the relative calibration status. Since it was not possible to perform a field calibration, a correction factor of 3.09 scfh (representing the maximum possible error) was applied in the conservative direction.

[492 278 Qtart/h 4

3.0 DISCUSSION OF RESULTS The reduced test data, corrected for instrument error, is presented in Table 1. The plot of average temperature and weight of air, correcteo for instru=ent error, is shown in Figure 1.

3.1 RESULTS AT P, The mass point leakage rate using absolute valves corrected for instrument error was found to be 0.041 percent by weight per day.

The 95 percent confidence limit associated with this leakage rate is 0.010 percent per day. Thus the leakage rate at the upper bound of the 95 confidence interval is:

L = 0.041 + 0.010 %/ day ,

L ,= 0.051 %/ day The measured leakage rate and the measured leakage rate at the upper bound of the 95 percent confidence level are well below the acceptance criteria of 0.075 percent per day.

3.1 SUPPLEMENTAL TEST RESULTS The measured leakage rate, (L ) using absolute values corrected for instrument error, during the supplemental test was calculated to be 0.09' percent per day using the mass point method of analysis. The 95 percent confidence interval associated with this leakage rate is 0.018 percent per day.

1492 279

~~ _

5

O _

A flow rate, corrected for instrument error, of 204 SCFH was superimposed on the building leakage rate. This flow rate is equivalent to a leakage rate of 0.056 percent per day (L,).

The building leakage rate during the supplemental test (L y ') is then determined as follows:

L'=L y e

~

b o

Ly' = 0.099 - 0.056 %/ day Ly' = 0.043 %/ day Comparing this leakage rate with the building leakage rate measured 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:

L,, - Ly ' = (0.041) - (0.043) = 0.02 L, 0.10 The building leakage rates agree within 2.0 percent of L,which is well below the acceptance criteria of 25 percent of L,.

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

4.0

REFERENCE:

5

1. "Three Mile Island Nuclear Station Unit 1 Reactor Containment Building integrated Leak Rate Test, April 1977", Metropolitan Edison Company Test Report.
2. 1430-Y-23, " Reactor Building Integrated Leak Rate Test lastrument Calibrations", Metropolitan Edison Company Procedure.
3. SP 1303-6.1 " Reactor Building Integrated Leak Rate Test",

Metropolitan Edison Company Surveillance Procedure.

1492 280 Geert/Cammanusenh 6

TABLE 1 REDUCED TEST DATA Average Partial Pressure Partial Pressure Average Weight of Containment of Containment of Containment Containment Containment Pressure Water Vapor Air Temperature Air Time (psia) (paia) (psia) ( R) (1bm) 4/18/77 0500 65.324 0.295 65.029 531.41 660,593.61 0530 65.322 0.295 65.027 531.41 660,573.29 0600 65.320 0.296 65.024 531.41 660,542.82 0630 65.322 0.296 65.026 531.42 660,550.70 0700 65.320 0.294 65.026 531.43 660,538.28 0730 65.322 0.297 65.025 531.43 660,528,12 0800 65.324 0.298 65.026 531.49 660,463.71 0830 65.326 0.296 65.030 531.51 660,479.48

{ 0900 65.327 0.295 65.032 531.53 660,474.94 0930 65.328 0.296 65.032 531.56 660,437.67 1000 65.330 0.296 65.034 531.59 660,420.70 1030 65.334 0.297 65.037 531.63 660,401.48 1100 65.336 0.295 65.041 531.67 660,392.41 1130 65.338 0.296 65.042 531.69 660,377.72 1200 65.340 0.294 65.046 531.74 660,356.23 1230 65.340 0.293 65.047 531.75 660,353.96 1300 65.342 0.295 65.047 531.77 660,329.13 j )

~~^

1330 65.346 0.300 65.046 531.80 660,281.73 f}

ps) 1400 1430 65.343 65.342 0.294 0.294 65.049 65.048 531.80 531.81 660,312.18 660,289.61 1500 65.343 0.295 65.048 531.82 660,277.20 rs) 1530 65.342 0.296 65.046 531.83 -o 60,244.48 CX) 1600 65.341 0.293 65.048 531.84 660,252.37

-- 1630 65.340 0.294 65.046 531.82 660,256.89 1700 65.338 0.296 65.042 531.81 660,228.71 1730 65.339 0.295 65.044 531.82 660,236.59 1800 65.342 0.293 65.049 531.83 660,274.93 1830 65.344 0.296 65.048 531.86 660,227.54

TABLE 1 (Cont'd)

REDUCED TEST DATA Average Partial Pressure Partial Pressure Average Weight of Containment of Containment of Containment Containment Containment Pressure Water Vapor Air Tempegature Air Time (psia) (psia) (psia) ( R) (1bm) 65.344 0.393 65.051 531.86 660,257.99 l I 1900 1930 65.341 0.293 65.04H 531.84 660,252.37 2000 65.344 0.295 65.049 531.85 660,250.10 2030 65.344 0.295 65.049 531.85 660,250.10 2100 65.345 0.296 65.049 531.87 660,225.27 2130 65.346 0.295 65.051 531.87 660,245.57 2200 65.345 0.291 65.054 531.86 660,288.44 2230 65.342 0.296 65.046 531.83 660,244.48 2300 65.338 0.295 65.043 531.8' 660,238.86

{

~ 2330 65.336 0.295 65.041 531.70 660,255.80 2400 65.334 0.296 65.038 531.76 660,250.18 4/19/77 0030 65.335 0.294 65.041 531.74 660,305.47 0100 65.332 0.293 65.039 531.72 660,319.00 0130 65.334 0.293 65.041 531.72 660,330.31 0200 65.330 0.293 65.037 531.72 660,289.70 0230 65.330 0.293 65.037 531.73 660,277.28 0300 65.331 0.293 65.038 531.72 660,299.85 g g 0330 65.333 0.295 65.038 531.74 660,275.01 0400 65.333 0.294 65.039 531.76 660,260.33 0430 65.329 0.294 65.035 531.71 660,281.81

- 0500 65.326 0.289 65.037 531.69 660,326.95 4

  • 43 SUPERIMPOSED TEST r%)

0730 65.315 0.295 65.020 531.67 660,179.18 I'3 0800 65.318 0.290 65.028 531.72 660,198.32 0830 65.319 0.293 65.026 531.75 660,140.77 ff$ 0900 65.318 0.293 65.025 531.75 660,130.52 0930 65.315 0.289 65.026 531.72 660,178.02

TABLE 1 (Cont'd)

REDUCED TEST DATA Average Partial Pressure Partial Pressure Average Weight of Containment of Containment of Containment Containment Containment Pressure Water Vapor Air Tempegature Air Time (psia) (psia) (psia) ( R) (Ibm)

SUPERIMPOSED TEST (CONT"D) 1000 65.314 0.293 65.021 531.72 660,127.26 1030 65.312 0.293 65.019 531.71 660,119.37 1100 65.314 0.293 65.021 531.72 660,127.26 1130 65.314 0.292 65.022 531.73 660,124.99 1200 '65.316 0.293 65.023 531.76 660,097.90 1230 65.312 0.291 65.021 531.76 660,077.60

~ 1300 65.307 0.296 65.011 531.71 660,038.14 1330 65.304 0.294 65.010 531.69 660,052.82 1400 65.309 0.292 65.017 531.76 660,036.99 1430 65.314 0.294 65.020 531.84 653,968.16 1500 65.317 0.291 65.026 531.87 659,991.83 1530 65.318 0.292 65.026 531.89 659,967.02 I k M

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