ML19274C830

Summary of Meeting on 780707 W/Ielp to Discuss Crack in safe-end on Inlet Recirculation Nozzle,Indications in Other safe-ends on Inlet Recirculation Nozzles & Repair of Crack. W/Sketch,Handouts at Meeting & Attendance List

ML19274C830
Person / Time
Site:	Duane Arnold
Issue date:	07/10/1978
From:	Woodruff R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
To:	Moseley N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 7811280016
Download: ML19274C830 (20)

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Y,M JUL 101973 THIS DOCUMENT CONTAINS POOR QUAUTY PAGES i>:E'9 PARD'31 FOR: !!cman C. Poseley, 0! rector Division of Tscactor Operations Inspection FF0:1:

Rcrjor ti. Ucedruff, Acting Assistant Director for Technical Progrecs

SUBJECT:

1EETI

FI RE RECIP.CULATI0fl SAFE-END CPACK AT CUAf!E AEt:0LD IE and NM met with Iowa Electric Light and Pc:wer Company and their consultants on July 7,1978, to discuss the crack in a safe-end on an inlet recirculation no::le, indications in other sarc-ends on inlet recirculation nozzles, repair of the crack, and dotemination of the cause of crcching.

Prior to the cestinc, Pogion III had transmittsd to the Licensee, five cuestions rcCarding tne design and analysis of the inlet recir-j culatic.n line and the safe-end. t!e were infomed by the Licensee that uritten an: scrs to these questions uill be provided within a week to la days.

During the tectim, the Licensce infor: red us that two of the safe-end asscsly v:alds were perfor::ed in the shop, specifically the Inconal safe-era to carbon stcol vessel weld and the Inconel themal sleeve to stainicts steel extension weld. The safe-end repair wolds were performed at Chicago Bridga and Iron's (CSI's) Girmingham plant. The re2it:ing welds necessary to connrct the safe-end to the pipirp and tb dermal sleeve to the riser were done in the field.

The >:elc; uere field ntress relieved t.t least one or more times.

The crack and C.2 TT cnd UT indications for the eight safe-ends were described.O the Licensee. Two of the sefe-ends had no indica-

'D' tions. With re:;.m to the crac::, the results of !;DE indicate that I

CBI statad that 1 it probchly is.;.-!

n:ad as shc!n in Enclosure 1.

jiv repair crocedure was prepared to cover weld e'

9 repairing of the te we wi.ich bd been ine.dvertently nachined into gO

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.gair w that GE (San Jese) and CCI both have I., n A

copies of thesc ' wds. The rer. fir was c. stick weld with 182 material. ; '

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Noman C. Mosaley 2

JUL 101978 CBI did the total design of the vessel to GE specs and code. The GE specs included temperature transients and piping reactico forces.

CBI stated that a datailed fatigue analysis as pcrformed for a section close to the crack.

The results of this and other stress analyses indicated that the stresses are well within code allowabics.

GE stated that they are 1 coking at existing vibration data for peculiaritics originating at the.iat pumps which may affect the thermal sleeves and safe-ands.

The Licenseo plans to replace the cracked safe-end and probably the other seven as well. The safe-end design has been modified to move the crovice at the thermal sleeve away from the body of the safe-end and to provide a radius to avoid stress risers. The criginal and revised designs are shcun on Figures 7 and 9 of the handout (Enclosure 2)providadbytheLicensco..

All fuel will be unloaded from the reactor prior to rea:oving the crackad safe-cnd. Unicading is in progress.

During the repair, the annulus between the vessel and the shroud will be dry to a level just below the nozzle. The unter icvel within the shroud and in the jet sn=ps will be as indicated in Figure 14 of Enclosure 2.

This level is dictated by the slip fit at the jet pump throat which would permit water to leak to the annulus if the level were higher.

The water level will be maintained in the vessel during the repair to reduce the radiation field, and additional shielding will be installed around the nozzle and exterior to the vessel to further reduce the field.

The expected working field is 200 mR/hr.

Water in the vessel will be circulated at 20 gri to provide appro-priate layup contitions. The supply will be t!ru the control red drives and the return will be thru the vessel drain. Water level will be controlled by referring to a level pecae.

The Licensee expects to cceplete unicading by liid-July and to start cutting before tte end of July for re~ oval of the safe-end.

The cutting sequence is shown in Figure il # Enclosure 2.

Datallurgical work fer identifying the cause of crackirg will be performed by Settalle and is descri5cd in Ficu e 1G cf Enclosure 2.

The Licensee plans to take two boat samples, e;ch 3/5 inch deep.

The Licensee's plan is to take cea at the cent r of the crcok and the other at the tip. The purpose cf these sanples is to obtain quick metallurstcal results.

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!{orman C. !!oseley

'3 1 0 I370 Af. e caucusing with HRR, IE requested that the Licensee consider r..aking three changes to their plans.

These changes *nvolve the beat samples, cut.90. 3 shown on Figuro 14 of Enclosure 2, and vibration sensors.

IE recuested that the Licensco censider not taking beat samples becausa useful information may be destroyed in the process and the cost important results from the completo metallurgical examination are expected to be available shortly after boat sample results would be available. The Licensee will infom IE two working days prior to taking boat sa:nples.

IE requested th.t the Licensce censider moving that portion of cut Ho. 3 which is in the safe-end, further from the crack. That could be done by cutting the thermal sleeve from the inside. The Licensea will infom IE tuo working days prior to make cut No. 3 as shown t, Figure 11 of Enclosure 2.

If high cycle fatigue is indicated as the cause of cracking, the Licensee will consider reinstalling vibration sensors.

In addition, IE,.iRR, and the Licensee discussed the applicability of 10 CFR 50.59 to the safe-end modification.

Counsel for the Licensee stated tnat discussions in this regard are taking place uith URR.

IE stated that dccumentation of the Licensce's 10 CFR 50.S9 review ticuld be inspected. is the attendance list.

l5 l Roger W. 'Joodruff, Acting Assistant Of racto" for Technical Programs Division of Reactor Operations Inspection Enciosures:

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Handouts of the tieeting 3.

Attendance Lbt cc: N"C Attendecs J. H. Sniezek, IE G. W. Reinmuth, IE

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O I y DETERMINATION OF CAUSE OF CRACKING l

l

.o CRACKING MECHAN. ISM ASSUMED TO BE EITHER:

. m.

a. FATIGUE OR,

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~e..-: e~c o. STRESS CORR 0 SIGH CRACKING

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o CREVICE GEGNETRY o

STRESS LEVEL

~

o OPERATING HISTORY o

WELD REPAIR

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' FAILURE ANALYSIS

. TO IDENTIFY FAILURE MECHANISM

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STOP LEAKAGE

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BOAT SAMPIES' (EARLY INFORMATION)

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' ' o ' CONVENTIONAL METALLOGRAPHY s

SEM VISUAL EXAMINATION OF CRArKED SAFE END

. o.CREVICU CONTAMINATION ANALYSIS

o PENETRANT EXAMINATION

,o PHOTOGRAPH

'~

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PREPARE METALL0 GRAPHIC SAMPLES FOR FURTHER EXAM NEAR TIP OF PT INDICATION ON I.D.'

4 SAMPLES o

o NEAR BRANCH FOUND BY RADIOGRAPHY

'.-o THRU - WALL LEAKAGE REGION -

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o AXIALLY BRANCHED REGION (ASSUMED)

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.TO. IDENTIFY CRACK MORPHOLOGY AND MICROSTRUCTURE

- 7_: _

'q' SCANNING ELECTRON NICPOSCOPV TO STUDY FRACTURE FACE MORPHOLOGY MICR0 PROBE ~ ANALYSIS.

. CHEMICAL' C0ffPOSITION CHEMICAL AND STRUCTURAL GRADIENTS CHETHCAL ANAiVSTS ~

IF DECONTAMINATION IS POSSIBLE REEORI l t...

n W Form nFpn9 FOR UTILITY

l$h MEETING WITH IOWA ELECTRIC AND GE July 7, 1978 ATTENDANCE LIST NRC Iowa Electric W. Shafer K. V. Harrington C. Williams E. L. Hammond W. S. Hazelton K. Meyers R. E. Johnson H. W. Rehiauer R. W. Klecker L. D. Root J. R. Fair H. W. Shearer N. Chrissotimos R. F. Decker C. O. Sellers G. M. Gordon M. R. Hum H. T. Watanabe H. F. Conrad F. P. Felini R. J. Goddard R. J. Brandon A. Taboada P. D. Storvick L. Frank T. A. Ippolito LNRA P. J. Polk D. Clark B. W. Howenstein W. J. Collins R. W. Woodruff P. N. Randall NUTECH CBI P. C. Riccardella J. Hagstrom C. R. Patterson me