ML20215C367

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Addenda to Preoperational Integrated Leak Rate Test Final Rept
ML20215C367
Person / Time
Site: Vogtle Southern Nuclear icon.png
Issue date: 06/09/1987
From:
GEORGIA POWER CO.
To:
Shared Package
ML20215C354 List:
References
SL-2613, NUDOCS 8706180088
Download: ML20215C367 (5)


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' ENCLOSURE.

6 PLANT V0GTLE - UNIT ~1

'l NRC DOCKET 50-424 OPERATING LICENSE NPF-68 ADDENDA TO PREOPERATIONAL INTEGRATED LEAK RATE TEST FINAL REPORT l

The addenda' to the Vogtle Unit 1 Preoperational Integrated Leak Rate Test

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Final. Report submitted:to the NRC.by. Georgia Power Company letter GN-1225'

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-dated December 12, 1986 should be. incorporated:as follows:

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ENCLOSURE i

PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF d ADDENDA TO PRE 0PERATIONAL INTEGRATED LEAK RATE TEST FINAL REPORT.

-l The addenda ~ to the Vogtle Unit 1 Preoperational Integrated Leak Rat'e. Test.

Final Report submitted to the NRC by Georgia Power Company letter GN-1225 dated December 12, 1986 should be incorporated as follows:

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11. Penetrations not in post-LOCA Alignment During ILET Penetration System Leakage Rate l

l Elect. #35 ILPT Pressure Sensing 1.25 SCCM FSA 20.2 68 4.2 86C 20.5 87 5.2 Total 51.35 SCCM i

3.4 Integrated Leakage Rate Measurement S,ystem a

i Instrument Description Data (No. of sensors) 1.

Absolute Mensor Range:

0-100 psia Pressure Quartz Monometer Accuracy:

+0.0154 Read j

(2)

+0.002*FS Sensitivity:

+0.00lpsia Repeatability:

+0.00lpsia I

2.

Drybulb Platinum Range (Calib):

60-120degF Temperature Accuracy:

+0.ldegF (30)

Sensitivity:

+0.0ldegF i

Repeatability:

+0.OldegF 3.

Dewpoint Chilled Mirror Range (Calib):

40-100degF Temperature Accuracy:

+.54degF (6)

Sensitivity:

+0.ldegF Repeatability:

+0.OldegF 4.

Flow Meter Differential Press Range:

0-20 SCFM (1)

Accuracy:

+0.1%

Repeatability:

+0.254 Drybulb and dowpoint temperature sensor locations and volume fractions are provided in Table 1.

3.5 Type B & Type C Leakage Rate Results These results of the various respective tests per procedure (see refer'ence 8) are presented below.

Pene.

Meas.SCCM (Max. Path) llA 747 12A 36.6 13A 1222.0*

138 7700 15 6

  • Indicates an update in the measured leakage.

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r Pene.

Measured 22 1760 l

23 380 24 6.0*

28 940 29 174.6*

34 545 35 323 40 685 41 107.1 i

42 178 48 6.0*

j 49 19.5*

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50 1092 62 6

63 67.2

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64A 6

648 6

67A 16860 678 11.1 68 4.22 I

69A 22.9 698 1480 t

70A 4.4 70B 3720 11A 15.58*

718 166.3 72A 63.8 728 6

73A 509 733 6

77 22 78 108.3 79 6

80 175.8*

81 89.5 83 533 84 141.2*

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86A 5770 i

86C 16.2*

87 6

89 2.2*

100 306 Pene.

Meas. SCCM Pers. Hatch 970.2*

Escape Lock 125.8*

Equip. Hatch 2.2*

Elec. Pene 27.19*

Encap. Vessels 148.9 **

Total 47,332.79 SCCM or 1.6715SCFM or.10790La

  • Indicates an update in the measured leakage.
    • Indicates additional leakage path not originally included.

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4.0 ANALYSIS AND INTERPRETATION I

4.1 ILRT Test During the ILRT, five penetrations were not in post-LOCA alignment.

The total leakage rate correction for penetrations not in post-LOCA alignment and water level changes (insignificant - 2cf per. total time period) is 0.00002%/ day.

i The calculated. leakage rates during the Type A for LSF and 95% UCL are shown below.

Adding the total leakage rate corrections for penetrations not in post-LOCA alignment yields the corrected, leakage t

rates as follows:

1 Mass Point Total Time '

LSF UCL LSF UCL Calculated 0.02397 0.02487 0.0236 0.02641 j

Corrections 0.00002 0.00002 0.00002 0.00002 l)

Corrected 0.02399 0.02489 0.02362 0.02643 Since the corrected 95% upper confidence levels for mass point (and total time) are less than.75La (0.150%/ day), the -test results demonstrate the leakage through. the primary containment and systems is within allowable limi ts.

Components penetrating primary containment' do not exceed. maximum leakage rates specified in the Vogtle Nuclear Power Plant Unit 1 FSAR and Technical. Specifications.

4.2 Instrumentation, Data and Calculations ILRT test data were gathered through sensors and a data acquisition system.

The data acquisition system' received these inputs and transmitted them into a mini-computer which reduced the raw data to containment 1 (See Appendix A for a

software program description. ).eakage.

4.2.1 Instrumentation The instrumentation was chosen for its stability and.

dependability.

The instrumentation used during the-ILRT satisfied all Instrument Selection GuideJ requirements.

All' instrumentation performed adequately during the test.

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