ML19341C549

Reactor Containment Bldg Integrated Leak Rate Test Suppl 1

ML19341C549
Person / Time
Site:	McGuire
Issue date:	02/27/1981
From:	DUKE POWER CO.
To:
Shared Package
ML19341C547	List: ML19341C546 ML19341C549
References
NUDOCS 8103030734
Download: ML19341C549 (16)

Text

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9 DUKE POWER COMPATI McGUIRE NUCLEAR STATION UNIT 1 Reactor Containment Building Integrated Leak Rate Test Supplement 1 81030ao734

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Table of Contents t

Introduction 1

Personnel Air Lock Leak Rate Test Results 2

Replacement Mechanical Penetration Follow-up Testing 3

Mechanical Penetration Leak Rate Test Results 4

Testing of New Instrument Penetrations 5

Resolution of Discrepancies on Structural Integrity Inspection 6

Correspondence on Structural Integrity Inspection Resolution - Attachment 1 i

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.I Introduction This report is issued as a follow-up to "The Containment Vessel Integrated Leak Rate Test Report."

Its purpose is to document the resolution of items that were lef t open in the previous report, and to document leak rate testing that has been performed since the previous report was written.

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1 Personnel Air Lock Leak Rate Test Results Following the Containment Integrated Leak Rate Test, all four Personnel Air Lock doors were removed and sent back to Woolley Co. for modific'tions.

An integrated Structural Integrity and Leak Rate Test was satisfactorily performed on the Upper Personnel Air Lock using TP/1/A/1200/18 on February 9, 1980. An overall leakage of 50 scem was measured in this test.

The same test was performed on the Lower Personnel Air Lock using TP/1/A/1200/19 on March 7, 1980. Overall measured leakage was 25 scem.

Both of these leakages are smaller than were measured in TT/1/A/9100/14, Upper and Lower Personnel Air Lock Leak Rate Test, which was performed prior to the ILRT (and prior to the air lock modifications).

Because of this, it is not necessary to add any penalty leakage to the measured overall leak rate test result.

Following the above testing, a ply separation probler, was identifi, I with the door seals. As a result, a new type door seal was developed and installed on all doors. An overall leakage test was performed on both air locks following this change using the periodic test procedures.

The results were an overall leakage of 138 seem on the upper lock and 270 secm on the lower lock.

Both of these leakages were lower than that measured in the temporary test performed prior to the ILRT, so again no penalty leakage is required to be added to ILRT test results.

During the ILRT, so=e problems were experienced with leakage in the backup air supply system to the seals when plant instrument air was isolated. This caused some of the seals to deflate during the ILRT. Maintenance has subsequently been performed to assure that the backup air supply is tight enough to ensure the integrity of the seals for several days. Testing was conducted to verify the leak rate of the total backup air supply system.

The measured leak rates are as follows:

Auxiliary Door Reactor Door Small Seal Large Seal Small Seal Large Seal Upper Lock 0

0 1.4 4.3 Lower Lock 1.5 0

8.7 0

All of these leakages are adequate to ensure that the seals with remain inflated for at least one week upon loss of plant instrument air.

~

l Replacement Mechanical Penetration Follow-up Testing Due to leaks discovered in the bellows assemblies of some mechanica' penetrations, several penetrations were cut out and replaced following the ILRT. TP/1/A/1200/29, Mechanical Bellows Reactor Vessel Side Structural Integrity and Leak Rate Test, was used to verify the integrity of the new weld on the inside of the Containment Vessel. This test provided a structural integrity test by pressurizing the weld to structural integrity test pressure, holding for ten minutes, reducing pressure to 14.8 psig and verifying no measurable leakage. Mechanical penetrations which were replaced and tested in this manner were:

M376, M377, M359, M256, M320, and M349 In addition, penetration M361 was cut out and rewelded due to a QA problem with weld material. This penetration was tested in the same manner outlined above on October 29, 1980, using PT/1/A/4200/0lK, Mechanical Bellows Reactor Vessel Side Structural Integrity and Leak Rate Test.

. i

Mechanical Penetration Leak Rate Test Results The Mechanical Penetration Leak Rate Test tests the structural integrity of the Mechanical Penetration Bellows assembly by pressurizing the space between the inner and outer plies of the bellows to 4 psig, and verifying no measurable leakage. This testing was performed under TP/1/A/1200/15, and was satisfactorily completed on November 14, 1980.

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Testing of New Instrument Penetrations Several new instrument penetrations have been added to containment following the ILRT. These have been tested using TP/1/A/1200/30, Instrucant Penetration Structural Integrity and Leak Rate Test.

This test verified the structural integrity of the weld at the inside of the containment vessel by pressurizing the weld to structural integrity test pressure, holding for 10 minutes, reducing pressure to 14.8 psig, and verifying no measurable leakage. The instrument line numbers that were added and tested in this manner are:

1NILT3260 - tested 9/2/80 1MISV6910 - tested 12/22/80 INILT5270 - tested 9/2/80 1MISV6920 - tested 12/22/80 1NSPT5550 - tested 10/8/80 1CFLT6080 - tested 11/20/80 1CFLT6110 - tested 11/21/80 1CFLT6090 - tested 11/24/80 1NCLT5151 - tested 11/24/80 1CFLT6100 - tested 11/24/80 In addition to the above, during the course of adding the new instrument pene-trations, a hole was made in the containment vessel at the wrong location. The hole was subsequently welded up and a structural integrity and leak rate test was performed on it.

TP/1/A/1200/31, Repaired Reactor Vessel Penetration Structural Integrity and Leak Rate Test, was used for the test.

The test was successfully completed on October 21, 1980.

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Resolution of Discrepancies on Structural Integrity Inspection During the Structural Integrity inspection conducted during the ILRT, several discrepancies were noted. These were evaluated at the time as having no effect on the ILRT itself. These discrepancies were followed up by Design Engineering and were resolved. Attachment 1 includes correspondence explaining the resolution of these discrepancies.

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e: M:Guire Unit 1 Cantainment vessel cressure iest File fic: MC-1131.00 We na ze cen.:le:ed resolving interferer.ces identifiec during the preliminary visual inspe: tion for the 5tructural Integrity Tes; (TP/i/A/1200/C6).

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-="= " =ched a copy of Our memo to file dated 6/23/50 docurrenting the resa'iu icn of tr.ese pr:blems.

3. E. Ha;er, Chief Engineer Civii/Envir:nnentai Divisica sv'.L l-Je E3

. 5. Sills

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cntainment '!essel Structural Integrity Test File No: MC-Il31.00 Tne Structural Integrity Test (pressure test cer section III, Subsecticn S, of the ASME C ce) was completed by Steam Production August 16, 1979. As part of this test, a visual insaection was performed in accordance with 5 team Froducticn Frccedure TP/1/A/1200/06. The results of this inscection, as cccu ented on the attached forms, indicate that there were no abnormal effects cue to the pressure test.

Several possible interferences <.ere identified during the preliminary visual inspection.

Mr. D. L. Rehn's letter to Mr. R. R. Whitt dated July 13, 1979 rerwested tne t :.iterferences wi tn* H'/ AC and pipe sup; orts te i rvestigated and ccrrected rs necessary. Letters frca Mr. J. F. Snipes, Jr. Of March 19, 1950, anc "r. L. G. G:ocman of June 9,19S3 incicate trat this work is complete and all interfarences have been corrected (ccpies of these letters are attached).

Interferences with conduit and cable tray were consicered ac:eptable cue to tre #1exibility of these compcnents.

All outstancing items f rom the Structural Integrity Test are resolved.

hjj' z bt M. 5. Sills, Cesign Engineer

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Attacnments cc:

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n;erfe ences uitn rice and :f.%C Su;:cets fil e !.:: iC-li31.00

uring a r.relin inery ins ec tion of the C:nta ira.cnt Vessel prior ta the Con ta irc.e nt pres sa c test, several in' erferences be tween tne Con te inn:ent

'ies s el a nd ':hel l

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Picing a ttached to both Con:ain. ment an: tne Shell '..a ll n.ust provi'ie ade';ua ;e fl exicili ty to allo. for the ciffer-er. :al :Ovc ents t t:..cen the struc turns.

Suracets a ttacned to ei t.ier struc ture

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.'e 5 f ficient Clearanc e rela tive to the O tner to OllCu fCr the Gifferen.

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In ; e c 'se Of i"!'C aanners. s: :e ecdi-2

• i;c tion sill :e re. ; ired.

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e ere ces. All c L;ier areas uhere similar proclems ::ay e(ist sivuld also be eu :e...a.

-.e l a test '.onta irment Vesso! wovemer.s are given in J.

P. Eul t.un's l e t:er of

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5. Sills at 7450.

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sures.

f.1I ctonr rne ii v/c..'nt3 arc dne to a cc,l'io,tico of internal pres-sure end ::c tr rcr,tur: di.tributirri in t he - L e i l, ri i.,,,i in 9, L, C:nyp s i

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w i mnr i s ir;l I terrcra:nre of 39r,*I in the i-r : enar t: tont.

The corres;c-dlu: tr.per,tur t's e d in the criginal anal; sis it ITO'F The r evr.cn t s bn ed c, ttis analysis ucre ;Iven In O. A. Ge:i f r e y ' - 6 t.t t e r da teri flarch i f), 1971 to U.

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i.: ri: ental rm in thn VI sys ter: rear El i:3 ana ': 253* ;;as supcorts a :tached to Contairacnt an ; :ne Shell hall.

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2 Files: MC-1211.05 & :-tC-1131.00 As revestec in your letter :o 5. K Sia:ki=y, File No. 9c.ii 3;.0., ca ed July 13, 1979, a review of interfererces bitueen F. AC 5/2's and tne Con-ta i r.me n t lessei or Snell nas ' een c;ro'=:ed via a field,.a!' j wn.

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