ML20217A034

Forwards Summary Technical Rept of Containment ILRT Performed During 1990 Refueling Outage Per 10CFR50,App J. Test Results Satisfactory

ML20217A034
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	11/13/1990
From:	Cross J PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9011200167
Download: ML20217A034 (4)

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g-m MM NMMM James E. Cross Vice President, Nuclear November 13, 1990 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission Attn:

Document Control Desk Washington DC 20555'

Dear Sirs:

Reactor Containment Building Integrated Leak Rate Test Attached is-the summary-technical report of the. Containment Integrated Leak

' Rate. Test (ILRT) performed during the 1990 Refueling Outage.

It is submitted pursuant to Title 10-of the Code of Federal Regulations, part 50, JAppendix J.'"Pelmary Reactor Containment Leakage Testing for Water-Cooled Power Reactors.

The test results are satisfactory.

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' Sincerely, J

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. Attachment-( -t <

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Mr..~ John.B. Martin Regional Administrator, Region V-U.S. Nuclear Regulatory Commission.

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Mr. David: Stewart-Smith

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' State of Oregon Department of Rnergy-i?

Mr. R. C. Bare p

NRC Resident Inspector l

Trojan Nuclear Plant r

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121 SW Salmon St Portland, OR 97204 503/464 8897 l :

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" Trojan Nuclear plant Document Control Desk Docket 50-344 November 13, 1990 r.leanse NPF-1 Attachment Page 1 of 3 REACTOR CONTAINMENT BUILDINC INTEGRATED LEAK RATE TEST i

The 1990 Integrated Leak Rate Test (ILRT) was successfully conducted from May 29 to June 2, 1990.

This test is the first'of three to be conducted r

during the second 10-year inservice inspection' interval as required by Trojan Technical Specification (TTS) 4.6.1.2.a. " Primary Containment Leakage".

It was conducted using the test methodology and provisions identified in American National Standards Institute (ANSI) N45.4-1972,

" Leakage ' Rate Testing of Containment Structures for Nuclear Reactors",

and ANSI /American Nuclear Society (ANS) 56.8-1987, " Containment System j

Leakage Testing Requirements". The results were evaluated using the acceptance criteria specified in the TTS and Title 10 of the Code of Federal Regulations Part 50 (10 CFR 50), Appendix J, " Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors".

Containment Inspections Examinations of.the Containment Building liner plate were conducted par TTS 4.6.1.6.3, " Containment Structutal Integrity, Liner Plate", before and after pressurization.

Examinations of the Containment Building ond anchorages and adjacent concrate surfaces were conducted per i

TTS 4.6.1'.6.2,

" Containment Structural Integrity, End Anchorages and

't Adjacent Concrete Surfaces", while at maximum test pressure.

Significant structural = deteriorationi or structural damage was not observed, thus the

.overail structural integrity was evaluated as acceptable.

Conduct of Leakage Test

! Pressurization of the Containmont Building was accomplished at~an average rato of 3.5 poi per hour. Pressurization was halted at 60.2 psig, and.

-tabilization of the air mass, including verification of the stable condition, was allowed for 13.6 ' hours. Containment Building pressure at

~k

.the end of the stabilization period was 60.6 psig.

Fo11tsing stabilization, the ILRT was run for 11.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to obtain satisfactory data. The Containment Building leak rate was evaluated at 10-minute increments. The verification test which followed failed.to

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validate the first data set of the ILRT. Test instrumentation was reviewed to determine why the data acquisition system did not adequately

-i indicate the induced leak. One dew cell was removed from the data scan i

because it exhibited unusually low readings.

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The ILRT was reentered and run.for 20.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> to obtain satisfactory data. The verification test which followed validated the ILRT.

Following the successful verification, the Containment Building was n

depressurized.

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' Trojan Nuclear plant' musent Control Desk Docket 50-344

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1. saer 13, 1990 License NPF-1 A+

Ochment

'N,e 2 of 3 ILRT Resu{ts The measured leak rate for the ILRT (Lam-TT) using the " Total Time" method was 0.0061465 weight percent of the Containment Building atmosphere per day. The total local leak rate test (LLRT) leakage not included in the ILRT was determined to be 0.0000170 weight percent por day. Therefore, the overall leak rate for the ILRT was determined to be 0.0061635 weight percent per day.

The acceptance criterion is that the everall integrated leak rate shall be less than or equal to 0.75 of the waximum allowable leak rate (La),

which is 0.10 weight percent por day, i

The acceptance criterion was wat because.

i 0.0061635 1 0.75

• 0.10

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0.0061635 1 0.075 As shown, the leak rate is well below the acceptance critorion.

The previous ILRT was completed on May 29, 1986. The summary report, which was provided by letter dated October 31, 1986, reported an overall integrated leak rate for the ILRT of 0.01703 weight percent per day, following-certain corrective action.

i verification Test Results 4

The induced leak rato~for the verification test (Lo) was 0.0856 weight

_ percent por day. The measured'Icak rate for the test (Lc) was 0.0795236 weight percent por day.

-t The-acceptance criterion is' stated mathematically as:

'I (Lo + Lam-TT + 0.25La) > Le > (Lo + Lam-TT - 0.25La) t The acceptance criterion was met because:

(0.0856 + 0.0061465 + 0.025) > 0.0795236 > (0.0856 + 0.0061465.- 0.025) 0.117'> 0.0795236 > 0.067-Summary of Type B and C Leak Tests A review of LLRTs performed since the 1986 ILRT did not reveal a test failure for any penetration.

Since 1986 the results of Type B and c leak

-rate tests, expressed in standard cubic centimeters per minrte (sccm),

are as follows:

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' _'. ' t.' Trojan Wuclear Plant Document Control Desk

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Docket 50-344 November 13, 1990 License NPF-1

~ Attachment-

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Page 3 of 3 L

Year Type B (secm)

Type C (seem)

Iotal (scem) 1990 25,762 i 228 24,873 1 207 50,635 1 308 1989 6,489 i 197 17,989 1 212 24,478 1 289 1988 7,282 1 126 26,236 1 209 33,518 1 244 i

i' 1987 2,498 1 62 12,104 1 243 14.602 i 251 The acceptance criterion is that the combined leak rate for all

. penetrations and valves subject to Type B and C leak rate tests shall be less than or equal to 0.60 of La, which is 119,875 scem.

L The acceptance criterion was met because the " Total" values indicated in

-the summary above are less.than or equal'to 119,875 scem.

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Sunparv of Mod [fications Made to the Contalnment Boundary Modifications made to tht Containment boundary since the 1986 ILRT and

. prior to this ILRT' are lirted tclow.' The LLRT leakage measured after the 6

, work was completed is shown (1* a applicable.

1.

Steam Generator Blowdown System Penetrations:

P-39-1:

. Valves MO-6716 and MO-2810 h

.P-36-1 Valves MO-6717 and M0-2813 P-37-1

-Valves MO-6718 and MO-2812 i;

P-38-l' Valves MO-6719 and MO-2808 The valves and associated piping.outside the containment Building were replaced by Request for Design Chango (RDC)83-052 in May 1988.

These penetrations are not subject to local leak rate testing.-

2." Electrical Penetrations

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ft;.

,E-121-Assembly NZ13 0: secm J'

E-141 Assembly A207 0 seem E-171;

.Assambly C207 11 seem

The-assemblies were replaced by RDC 89-011 in May 1990.

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