ML17310A330
| ML17310A330 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 06/10/1993 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9306150368 | |
| Download: ML17310A330 (28) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 205%-0001 June 10, 1993 Docket No. 50-529 LICENSEE:
Arizona Public Service Company FACILITY:
Palo Verde Nuclear Generating Station, Unit No.
2
SUBJECT:
SUMMARY
OF MEETING HELD ON JUNE 3, 1993 TO DISCUSS THE STEAM GENERATOR TUBE RUPTURE ROOT CAUSE INVESTIGATION On June 3, 1993, the NRC staff met with representatives of Arizona Public Service Company (APS) and its consultants to discuss the steam generator tube rupture root cause investigation.
The meeting was held pursuant to notice issued on May 27, 1993.
Persons attending the meeting are shown in Enclosure 1.
Viewgraphs and other material shown at the meeting are contained in Enclosure 2.
Highlights of the meeting are summarized below.
The purpose of the meeting was to brief the NRC staff on the significant efforts underway to determine the root cause of the steam generator tube rupture and the other tube degradation that is being detected by eddy-current testing.
Arizona Public Service Company (APS) representatives described their root cause of failure analysis process; the status of eddy-current testing (ECT), including the scope of expanded testing and the number of ECT indications found to date; a review of the chemistry of the Unit 2 steam generators; metallurgy studies that are underway, including the laboratory analysis that is currently being conducted; crack growth studies; and other analytical studies being conducted to understand the root cause of tube degradation.
On March 14,
- 1993, a steam generator tube rupture occurred at Palo Verde Nuclear Generating Station, Unit No. 2, one week prior to a scheduled refueling outage.
The rupture occurred high in the steam generator in the free span between tube supports.
The licensee has been conducting extensive eddy-current testing, using both the bobbin and rotating pancake (RPC) probes.
All of the tubes in both steam generators (SGs) have been examined with the bobbin.
Out of a total of 11,000
- tubes, 3803 tubes will be examined with the RPC in SG No.
1 between the 08H support and the batwing, and 3330 tubes will be examined in SG No.
2 at the same elevation.
- Also, 10 percent of the tubes have been examined between the tube sheet and the first support in both SGs.
For SG No.
1, 14 axial cracks have been found as follows: 2 at or near the tube sheet, 5 at supports, and 7 in the free span high in the SG.
Six of these were not detectable with the bobbin.
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June 10, 1993 ll Arizona Publ ic'ervi ce Company For SG No. 2, 58 axial indications have been found as follows: 4 near the 01H
- support, 34 at or near upper supports, and 20 in the upper free spans.
Fourteen of these indications were not detectable with the bobbin.
Host of the defects found appear on an "arc" pattern of the tubesheet on the hot leg side high in the steam generator between the 08H support and the batwing.
Expanded RPC examinations have been focused on this area, with some sampling in other areas to confirm that the degradation is confined to the "arc."
Visual examinations of the tubes have revealed the presence of linear deposits A total of eight tubes have been removed for analysis, including visual, dimensional characterization, ECT, radiography, analysis of deposits, burst
- testing, and metallurgical analysis.
So far, the cracking found has been attributed to intergranular attack (IGA) and intergranular stress corrosion cracking (IGSCC).
As for schedules, the additional RPC inspections will be completed by June 17.
Tube plugging is scheduled to be finished by June 27.
APS plans to submit its root cause report about June 25 and startup is scheduled for about July 11.
Original signed by:
Charles H. Trammell, Senior Project Manager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Enclosures:
1.
Attendance List 2.
Viewgraphs cc w/enclosures:
See next page DISTR I BUTION:
Docket File NRC
& Local PDRs PDV Reading File
- KPerkins, RV CTrammell LTran j 00Q~
I.:
THurley/FMiraglia, 12G18
- JPartlow, 12G18 JRoe EAdensam Tguay DFoster
- HConrad, 7D4 KKarwoski, 7D4
- WAng, RV
- CSerpan, NLS217C SFlanders, RGNI
- EMurphy, 7D4
- OGC, 15B18
- EJordan, 3701 ACRS(10),
P-315 JMitchell, 17G21 JStrosnider, 7D4 BLiaw, 7D26
- TReed, 14H25
- LGreger, 17G21
- GJohnson, 7D4
- JMuscara, NLS217C EBenner, llAl OFC NAME DATE PDV/LA r
DFoster 93 PDV P
LTran PDV/D CTrammell:lh TOuay OFFICIAL RECORD COPY DOCUMENT NAME:PVHTGSUH.603
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Arizona Public Service Company Palo Verde CC:
Mr. Steve Olea Arizona Corporation Commission 1200 W. Washington Street
- Phoenix, Arizona 85007 James A. Beoletto, Esq.
Southern California Edison Company P. 0.
Box 800
- Rosemead, California 91770 Senior Resident Inspector Palo Verde Nuclear Generating Station 5951 S. Wintersburg Road
- Tonopah, Arizona 85354-7537 Regional Administrator, Region V
U.
S. Nuclear Regulatory Commission 1450 Maria Lane Suite 210 Walnut Creek, California 94596 Mr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Mr. William A. Wright, Acting Director Arizona Radiation Regulatory Agency 4814 South 40 Street
- Phoenix, Arizona 85040 Chairman Maricopa County Board of Supervisors 111 South Third Avenue
- Phoenix, Arizona 85003 Jack R.
- Newman, Esq.
Newman 3 Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington,'D.C.
20036 Mr. Curtis Hoskins Executive Vice President and Chief Operating Officer Palo Verde Services 2025 N. 3rd Street, Suite 220
- Phoenix, Arizona 85004 Roy P.
Lessey, Jr.,
Esq.
Bradley W. Jones, Esq.
Akin, Gump, Strauss, Hauer and Feld El Paso Electric Company 1333 New Hampshire Ave., Suite 400 Washington, D.C.
20036 Mr. William F.
Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-9333
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Arizona Publ i c Servi ce Company For SG No. 2, 58 axial indications have been found as follows:
4 near the 01H
- support, 34 at or near upper supports, and 20 in the upper free spans.
Fourteen of these indications were not detectable with the bobbin.
Host of the defects found appear on an "arc" pattern of the tubesheet on the hot leg side high in the steam generator between the OSH support and the batwing.
Expanded RPC examinations have been focused on this area, with some sampling in other areas to confirm that the degradation is confined to the "arc."
Visual examinations of the tubes have revealed the presence of linear deposits A total of eight tubes have been removed for analysis, including visual, dimensional characterization, ECT, radiography, analysis of deposits, burst
- testing, and metallurgical analysis.
So far, the cracking found has been attributed to intergranular attack (IGA) and intergranular stress corrosion cracking (IGSCC).
As for schedules, the additional RPC inspections will be completed by June 17.
Tube plugging is scheduled to be finished by June 27.
APS plans to submit its root cause report about June 25 and startup is scheduled for about July 11.
Enclosures:
1.
Attendance List 2.
Viewgraphs cc w/enclosures:
See next page 81.~<
Charles H. Trammell, Senior Project Hanager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
ENCLOSURE 1
List of Attendees June 3
1993 Meetin Between NRC Staff and APS To Discuss The Steam Generator Tube Ru ture Root Cause Investi ation NAME ORGANIZATION W.
J.
M.
D.
J.
M.
M.
L.
R.
A.
S.
C.
K.
R.
R.
J.
C.
M.
K.
T.
C.
C.
J.
T.
K.
L.
S.
H.
W.
J.
G.
E.
B.
J.
D.
J.
L.
E.
Heilker Hall Sniegowski Hansen Provasoli Melton Hodge Johnson Schaller Amr Quan Brechtel Sweeney Stevens Boberg Gorman Chiu Bauser Redmond Quay.
Trammell Serpan Strosnider Reed Karwoski Greger Flanders Conrad Ang Muscara Johnson Murphy Liaw Begley Kirsch Mundis Connor Benner ABB-CE ABB-CE ABB-CE APS APS APS APS APS APS APS APS APS APS APS BWNS Dominion Engineering FPI International N&H NESI NRC/PDV NRC/PDV NRC/RES NRC/EMCB NRC/PD II-1 NRC/EMCB NRC/EDO NRC/OEAB NRC/EMCB NRC/RGN V
NRC/RES NRC/EMCB NRC/EMCB NRC/DE Packer Engineering RV SCE STS NRR/OEAB
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ENCLOSURE 2
PVNGS UNIT2 S/G TUBE RUPTURE ROOT CAUSE OF FAILUREANALYSISSTATUS I. INTRODUCI1ON (R SCHALLER)
- h. AGENDA B. TEAM MEMBERS C. MEEI1NG ATI'ENDEES Q. ROOT CAUSE OF FAILUREANALYSISPROCESS (S. QUAN)
IQ. EDDY CUIuu&TTI~ING STATUS (D. HANSEN) h SCOPE OF THiINNG B. NUMBER OF INDICATIONS C. EDDY CURIKNTISSUES IV. CHEMISTRY REVIEW (L JOHNSON)
A DESCRIFI1ON OF REVIEW hfEI1IOD B, RESULTS V. METALLURGYRESULTS (M. MELTON)
A. IGA/IGSCC PHENOMENON B. TUBE PULL AC11VITY C. RESULTS OF LABORATORYANALYSIS D. PLANNED MEI'ALLURGYTESTS E CRACK GROWTH STUDIES VI.ANALYTICALSTUDIES (DR AMR)
VII,PLANNED ACI1VITYAND SCHEDULE (M. HODGE)
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DATA:~61 93 SjG:
21 EDDY CURRENT
SUMMARY
FOR ROOT CAUSE ANALYSISTASK FORCE MGALINDICATIONS SAI, MAIINDICATIONS NO. OF TUBES EVALUATEDBOBBIN COMPLETE NO. OF TUBES EVALUATEDMRPC 2700 Row coL DEprH TUBE ~
6 1
149 76 SAI 140 89 SAI 149 98 SAI "*
140 105 81 io 148 111 SAI
'7 112 MAI 146 117 SAI*
139 118 SAI""
108 143 SAI STRUC.
LOC.
TO tND.
LENGTH START TSH
-.86" 08H 34.35".21" BW1
-.71"
.38" BW1 19.00".41" 09H 25.72".55" 09H 25.13".41" 09H 23.55".41" BW1
+1.41".19" BW1
-1.25"
.10" 09H 28.08".50" TSH
-.71" 09H
+.45"
.50" 09H 25.02".24" 08H
+.93" BWl TO ~~
STRUCTURE
@END
- xuaum, TO BW DlST.
TANGE NO PDP NO NO PDP PDP PDP NO NO PDP NO NO PDP NO
+g>tion TSH MID BWl MID MID MID MID BW1 BW1 MID TSH EGG MID EGG 108 31 SVI
- 01H
-2.2" 117 82 SVI"*
08H 35.32" 137 140 SVI** 02H
- 3. 18" NO PDP PDP NOTE:
Measurements are to center line ofsupport structures.
P
~) P
(>-3.3 JAr Qp6.
3
- %through wall calls made with bobbin probe MRPC indications where no initial bobbin calls
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EDDY CURRENT
SUMMARY
FOR ROOT CAUSE ANALYSISTASK FORCE DATE:~61 93 S/G:
22 AXIALINDICATION BOBBIN TOTAL COMPLETE SAI, MAIINDICATIONS MRPC TOTAI. 2000 ROW
¹ 22 10 29 97 112 117 115 117 115 118 123 141 134 134 l49 144 146 150 137 145 140 142 142 137 141 135 129 135 128 128 COL TUBE 0 13 23 24 38 39 4Q 40 42 42 45 50 74 105ill 114 115 115 115 116 118 119 119 123 124 124 130 132 132 133 135 DEPTH
~S 52%
30%
NQI 46'io NQI 19%
37 /0 SAI'"
SAI*
SAI SAI "
SAI 64%
- SAI "
76%
- 84%
79%
LOC.
01H 01H 01H 08H 08H 08H 08H 08H 08H 09H 09H Bwl BW1 09H 08H 09H 09H 09H BW1 09H 09H 09H 09H Bwl 09H 08H 09H Bwl 08H Bwl 09H 09H STRUC.
TG IND.
START
-.26"
+.24"
-.16"
+ 99" 29.38" 41.00" 40.85" 40.00" 39.51"
-.31"
+.75"
+.23"
+1.61" 20.47 q 34" 23.47" 22.95" 23.79"
-1.17" 28.91"
- 23. 1" 22.20"
+.90"
+.77"
-.23
+.70"
+ 75"
+.84"
+.39"
+1.88"
+.74"
+.39"
.21" 34"
.16"
.77"
.18" 09H 5.23 09H 5.92
.21"
.22 09H 29.97 09H 31.48
.96"
.51" Q
tl LENGTH STRUGTIIRE TO BW DIST 4.29
- 2. 14
- 2. 13 PDP PDP NO NO NO NO PDP NO PDP PDP PDP NO PDP PDP PDP NO NO NO NO NO NO NO NO NO Bwl TO ~~
BEND nauru ThNGE NO NO NO NO PDP 4,81 NO PDP PUl L PULL PULL PULL 01H 01H 01H EGG MID MID MID MID MID EGG EGG BW1 BW1 MID EGG MID MID MID BW1 MID MID MID EGG BWl EGG EGG EGG BW1 EGG Bwl EGG EGG
" %through wall calls made with bobbin probe
- MRPC indications where no initial bobbin calls
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ROW 125 131 126 128 123 125 129 128 127 122 128 121 74 117 115 124 118 122 110 107 17 110 105 103 107 104 97 93 COt.
TUBE ~
136 136 137 137 138 138 138 139 140 141 141 142 143 144 144 145 145 147 149 152 152 153 156 156 156 157 158 160 DEPTH 7%
SAI*
SAI*'AI 28%
SAI SAI
'1%
39%
SAI*"
37%
71%
'AI 100%
SAI""
43%
230/0 SAI "
85%
NQI 85oio SAI SAI I.OC.
09H 09H BW1 08H BW1 08H BW1 08H 07H 08H 09H 08H 09H BW1 VS3 08H STRUC.
~OIND.
START
+.39" 17.96"
-1.65"
+ 57
-1.05"
+.24"
+.77
+.81"
+.48"
+.27"
+.53"
+.71"
+.20"
-.76"
-.92" 33.92" 09H BW1 08H BW1 BW1 01H 07H 08H 08H 08H 08H BW1 08H
-2. 16"
+1.34"
+.33"
+.62"
+.09"
-. 14"
+1.92" 25.92" 19.22" 24.75" 26.84"
-1.92" 19.21" 08H 34.99" BW1 +1.03"
.65"
.44"
.30"
.41" 27tl
.28" 44"
-9.00" 1 71I
.79"
.19" 09H 7.55
,62"
.09"
-.2' II BW1 TO BEND TANGE 3.40 1991
.71", 2.
43"
.12" 2.31" 08H 43.63 1.83 08H 41.99 2.93 LENGTH STRUCTURE TO BW DlST.
.76"
.67" NO PDP NO NO NO NO NO NO NO NO NO NO NO NO NO PDP PDP NO NO NO NO NO NO DATA NO PDP PDP PDP PDP NO PDP TUBE PULL PULL PULL PULL PULL EGG MID BW1 EGG BW1 EGG BW1 EGG EGG EGG EGG EGG BW1 VS3 MID MID BW1 EGG BW1 EGG BW1
" %through wall calls made with bobbin probe
"* MRPC indications where no initial bobbin calls
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ROOT CAUSE INVESTIGATIONTEAM - SGTR EVENT FAILURE MODES WI&IIIOICI arOn CeCCC Ittctctr CPfQII~
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- r. tIrQr,rccIr
~WtIlCCCC ICIICICNICC wrytire
~ wIa IIcCp WtttWICIM Iootl MIOCI~
r arrorl ~
kl OOC
~ttttrcIIM WlWC MIblltcIIcC CMCIWi
" Ioccottrc aNCMI CCIICI IICCrtOC lrltllC CtttttC confirm based on examination Itesting of putted tubes iC r CMCIMC
~IWIIlaOIIII Irtrta&tll analysis required lo supper I P.,
kiiocNn lo be susceptible Ifactoi t
WIIIIICIICIIICI Ccttrc CIIIWt
~c trtrMtttrt~
trillClrttl
~IAO MIIIII~
~IIIII1&II no dala has indicated problems in this area
Tube Pull Candidates 09H
.2924 22->30 0-.
i span A
B u
e upture uppo i span 0
C 0 L
U il H
39 88 41 42 83 119 X.
118 p 116 p
11+
X
":O=-=.O-=-.C 09Hhas wee. 08H ud O9H<<ed'.
Circuaferaxe hsue.
COLUMH M2 M3 lie 165 166 122,;000-00 s
115 COLUMH L37 138 139
)68 181
,'"-00.0-00
",0-00~0 "00000 128 COLUMN 135 136 137
]38 139
,,';;00.000 pN v
0~0-00 0-8-GOD 0 I 'IJ I will I'IIII
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04/93, ARIZONA PUBLIC SERVICE, PALO VERDE, UNIT 2 STEAM GENERATOR:
22 LOCATION:
ALL CRITERIA:
POP DATE: 05/27/93 TIME:
17: 32: 01 STAYS 195 o
RP 142 x
150 150 140 140 130 130 120 120 110 100 90 110 100 80 70 60 50 40 30 20 10 80 70 60 50 40 30 20 10 10 20 30 40 50 60
/0 150
!)0 100 110 120 130 140 150 160 170 180 CONAN NVCLEAfL INC. QQ
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SID seeks sludge and foreign bodies in steam generator upper heads while. ~ ~
By A. T. Ashton and'John Gay Robotic technology to access, inspect and maintain the complete secondary side of steam generators is under development. The developers of SID and CECIL have teamed up to produce a system that should allow utilities to deal directly with the causes of tube degradation.
The CECIL (Consolidated Edison Combined Inspection and Lancing) system provides a ranre of maintenance tools tor cleining the region bet<<'een the, tubeshee; and the tirst suppon plate in steam generators.
SID (Seconds'n.
spection Device) extend>
access to and inspecrion ot the upper bundle region.
Xv'csrk is being done to combine CECIL and SID:e'hnology to inspect 2nd hvdrzulicaily clean rlie upper bundle.
XX'hile earlier problems <<'ith sludge deposition.
such as tube
<<'astage or denting. hil e been allevi )red. ne<<prob.
lvfl)lintr.Ile tn he tound Deposits or) rube 5!Irt'.lect
.InJ in support pi.tfe
- rvlicci c.)n cnncentrate soliible chemi.
c.il species.
resulting in intergrattul.tf
.utack anJ stre's;r)rrnsirsn iri;king rICA.SCC!. In I".91 these combined phenomena.
occurring on rhe outside Jiansetef o! tubes. accounted tor 1uo nt iL"..;.ni'hill!: ife.i!1) gc'ner.i'Iilr Iiillv Pq ii ~II iII!J"c.I,-pi>>.'i;.In reduce tliv.iyhilcltr~
i ~ 'i p'c<<IIfe Jire:n nihe Jelsnr! ts I.le.ir!eic pl.lntl.l.l'e rvpnrfcJ pressure lnvv nl! ull hl.im':Ih Ar') UI)f).sr) i)r'II) liner.iting red!:ce J electr:col nutput Jue:n:he Inc:e.<<:Iig:IL -. ii:itvr.Iiinict;r,'.vn i i'i
<<h!cii I wr.tti.Ii oscf 3'r rilllrriri::n i>>t
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Dc>>osi.f oii the nutcf di.imcicr nt'ubes hase lone been knosvn rir oc:ur.
ScconJa.-:.ide; isual inrlsec::nns h.)vc lhn<<n ihickcr ruhe deposits:o<<'.Ir Js the
- np ot thc 5:bc bundle. These trcuucn cxccca 0 '>mm n:hrcknc55...5 pllnts
~nd thermal efticicncs decrease CURRENT INSPECTION EOUIPMENT Robotic sysrems Ior maintenance in the prinuiry channel
- head, such as eddy eurtent testing. tube plugging and sleev-ing. are <<cII developed.
These prim.iry side robotic systc ms are useful tor analysing and charicterising tube degra-dation I'or rube plugging decisions tor example hur provrh Timited intor-nution on Secondirv tub>> <<urti c
tI on s, Extremely limited second.ir')cccss has made robotic cysfcni Jeseln!>>-
ment difticult, Steam generitor hanII-hole sizes viry I'rom approximately ~0 to
- 150mns, The bio<<'do<<'n one <<idrh is 50 ro '10mm. but this is orten restricted by tlnsv disrribution bittles or blocking devices.
L'pper bundle access is turrhcr limited by the size ot th>> tlusv slnts nr holes in rhe suppnrt pi.tres. Ilpic.il Iln<<
S nct ii was iasi ftaiurta in Nue(tar Enprnttrr'np I
. (nrtrnarionar !December 199! I, CECiL nas undtr gone a sties ot atsgn rsp!ovcmcnls a'vtstd ai making Int tqvipmtni molt tfftcrivc and abrt lo I.
aCCC55 a wiatr rangt OI S!tarn gtntra!Or initrnai gtomtirits Thrtt varialions ol the equipment
~ haVC bttn dtvt!OPtd: CECIL 3. CECIL 4 and Iht I siding ianct gviat ISLGI Trt SyetemS dtiivtr ianCCS attp inSidt:nt Ivbt pundit m OOIh OI rnt mOSI rtetni ataigr S
t( aft csi!'. nt b)' 'o'njrallta '.hlbugr'hc caen 5!Cam gent!alar.Osptciion pan Fwc:ypts
- ! Ia:t a!i <<in (5th cacabi'.v naut btt" CCS9-ta
'O 5'ge Cmevar ana
'O tg~
Obte';
t.a' S"ace*: t '.?
Ca O!5SO t nt"rtSi
~
io remove loose sivdgt tram Int Ivbc rant and,n btiwttrlInt Iubt rawS.
~ Scale removal Ita aat tan noults) io (tmovai scale aH hard skrdgc ala! s born ar=und the tvbts
~ Hard sivdgt (lour high pressure nouos) -Io (C!nOVC ICnaeiOVS hard Siudgt dtPOS!IS I!Om Int lube lane
~ In bund!t FOSAR I!VniaiirrtgraPP!t IOOkng IO rtiritvt IO!tgn OOICCIS Irom w!Ihin ihc Ivbt
~ Annviar FOSAR- <cmoitly anieuia!Cagrapprt dtsigntd!o remove iargtr fort gn objtcis 'ovna in
~rt 5!Cam gtntiaior annvNS btrwttr nt ruat
.vna!t ana'.I t Srtam gent a!Ci Sntrr CECII. can a!so:ance and 'rvsn son srvogt a"d
~0 (r'r '
iA'I'tI c'
...CECIL. robotically removes them
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CECIL SLG is sptciticalty designed to work within tht contihas ot Frtnch 1300Mwt unit steam generators.
2D NUCLEAR ENGINEERING INTERNATIONAL
." ROSNICS 8, r.>AWTExaNCE
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~r Sleeving requires a structural joint to be created by joining the sleeve to the tube at each of the sleeve's ends. Traditional joining techniques have included roll expansion. hydraulic expansion. braaing and TIG ivelding. h<ore recently. laser ivelding has been used.
The primary disadvanrage of roll expansion and hydraulic expansion is that these joints are leak-limiting me.
ch~ica) joints. The design ofthe e pan-sion and the number of rube<
being repaired determine ivhether the leakage is acceptable to the plant concerned.
The amount of leakage is not usually a
limiting consideration For plant opera-tion.
TIG ivelding and brazing are ivell established technologies that produae a
le>k-tight joint. but 6oth su!Ter tfnm the con>plcxira of field application. For TIG
<<elding. sophisticated tooling is neces-safa to deliver the iield head to the <ube.
In addition. the paran<c<crs needed to achieve an adequate ivelJ must bc cs:ablishcd on site and the process pfoduaes a heat-affected tone <HEI >n the tube A1atcfisl ivith ass<>oined high
<<fcs<es. 5(ress
<>>lie< Iollnivin<<elding is fcquifcJ. Bfaaing h.>s <in>il,>f Jis.>di,u>-
fagcs
<A a Ja)<t>on to dicult>a's >A.>ahicv-ing proper temper>(uf..>AJ cn<ufing b:.>ac Ila><< in thc jniA<.
T'h e ohica'fiic nt I.><cf iv>>IJ<ng ><<ai ifndua>>
.> Ic>k.iigh< )oint <<i<boa<<h>>
>igh Nrcsies anJ cxcessiic HAZ n! TIG ii'>>IJing. but corrosion
<ests have shoivn (ir>t laser-<<cldcd joints pfa>Juac high
<cns>IC sire><. ivhi>>h also require itrcsc
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A>i<i'.Ass a<))i>ion p<<in<. pfnJuc>>J bi';hc i)acv<
h>tting the ti!bc at an oblique angle. The high.<peed jct <cour<<hc Avn ft'.<<c<,
al!o<<ing the:fcshly exposed metal iuf.
f>cc> to obta:1 intimz<c cnn<ac< at:hc a<on>ic!>>vcl u1dcf high'nf:ci %~he<>nn
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<I'.1 ssa 4 Inserting the sleeve Into the tube with a posltlonar tool on a manipulator. The characteristic wavy bond interface at a kinetic welded joint is shown at the top.
metals do not occur. The iveld produced is
.> leak-tigh<. structural bond.
Sleeving by kinetic <<:elding has been
(>>cog>>isc3 bi'he AS<a)E Code. and is add(>>SSC'J in SeeriOA XI (1<)S<) Editian
<<ith
)')S<)
A)JCAJ.>).
in ivhich the csscnti.>l P.>ran<etc(( Ior kin>><ia ivc)ding<
.>fc Jcsafibc J. Th>> proc>>s< h.>s.>!<<1 hccn
.ipproveJ fnf u<>> by the I.'q '.anal>>.ir pacgu).ll<>(y Cn>1>A'>is<><1A.
X <Igni<>oint bci>cfi< n< <hc technique ic that the cs<cntial paran<c<ers for success!>>l ivelding Jn not require sct-up on. site. but are.>chievcd hy the design of
<he kinetic ivclding dei'icc
)V%'D).
ivh<ah ii.>caco>hl>>J iu <Ilc m.>ni>iaa<uring
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EXPERIENCE IN THE FIELD Ov>>f 1()I)fi ki>>>><>C iv>>IJcJ ilccvci h)vc hccn uacd by BR'<V'ac)car Techno)<> ~
gicc n> fcp>ir,lcfcctii'>> itc.l>u gcncra<ilf iubei. 1 he pfnceis ii cnmp)etc J quickly and fcmn<>>lv 1v using (nb<<<i; n>anipu.
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~ Yon-destructive examination (NDE).
Surface oxides are removed bv insert-ing a flexible hone inro rhe tube ro be cleaned. h is routed and oscillated in the
<<aid regions ivhile a vacuum is pulled across ir to remove rhe debris from the tube, ivhich is captured in disposable filters to reduce contamination.
After the cycle is completed. ir is ivithdraivn, positioned to the nexr rube. and the process repeated.
The hone is qualified ro clean mu)tiple tubes.
The sleeve and integral
)a,>TD is inserted into the tube bv using a
positioner rool n>ounred onto rhe ma-nipulator.
The positioner inserts the sleeve into the rube until a hards<op is reached.
ensuring that the sleeve is positioned properIy. The ivelding occurs simply by pressing a detonation sivitch at the ren<ote control sutinn. The ive)ds for both sleeve joints are produced simultaneously. After ivelding. rhe posi-tioner ivithdraivs the sleeve-positioning sheath from the tube and over ro the manivay tor disposal.
The next sleeve assembly is loaded in<o the positioncr for instillation in the next cube.
The joint produced by kinetic ive)J-ing is stress-relieved
<o remoic residual tensile
<trcs<cs by using a simple fcsis-
<ance heater iiithcmb>>3J>>J thcfmiscou-plcs.
The heater is ins<.f<>>J info <hc positinner. ivhich pushes u into the tub>>
in a similar manner tn sleeve inse<tinn.
The heater hardsrops on thc end of <he sleeve to be stress relieved. thus a)<<~ys ensuring proper positioning. The s<rcss-fcliafh>>><cr ic aon>pu<cf-cain<f<>)lcd hv.>
Icmpcf.u>i>>>
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