ML17310A430
| ML17310A430 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 07/07/1993 |
| From: | Trammell C Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 9307190022 | |
| Download: ML17310A430 (70) | |
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0 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555.0001 July 7, 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 30, 1993 TO DISCUSS THE STEAM GENERATOR TUBE RUPTURE ROOT CAUSE INVESTIGATION AND TUBE INSPECTION RESULTS On June 30,
- 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 investigations The meeting was held pursuant to the notice issued on June 28, 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.
This was the second "working" session to keep the NRC staff abreast of information as it is being developed.
Arizona Public Service Company (APS) representatives described the root cause of failure; the status of eddy-current testing (ECT), including the scope of expanded testing and the number of ECT indications found to date; metallurgical studies that have now been completed; crack growth rate conclusions; eddy-current crack detection thresholds for the bobbin and motorized rotating pancake coil (RPC); the proposed operating interval until the next eddy-current steam generator tube inspection; and calculation results based on Regulatory Guide 1. 121, "Bases for Plugging Degraded PWR Steam Generator Tubes."
On March 14,
- 1993, a steam generator tube ruptured 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.
Thirty-eight hundred tubes (out of a total of 11,000 tubes) will be examined with the RPC in both steam generators between the 08H support and the first vertical support on the hot leg side.
Also 10 percent of the tubes have been examined with the RPC between the tube sheet and the first support in both SGs.
9307190022 930707'DR ADOCK 05000529; PDR.'C KE MTQ~
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Arizona Public Service Company July 7, 1993 For SG No.
1, 17 tubes with axial cracks have been found, "as follows:
2 at or near the tube sheet, 5 at supports, and 10 in the free span high in the SG.
Ten of these were not detectable with the bobbin.
For SG No. 2, 84 tubes with axial indications have been found, as follows:
4 near the 01H support, 40 at or near upper'supports, and 39 in the upper free spans.
Thirty-six of these indications were not detectable with the bobbin.
Most 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 first vertical support after the 90 degree bend.
Expanded RPC examinations have 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.
,Thermal-hydraulic analysis indicates that the region where the indications are occurring is an area of the steam generator where deposition could be expected based on steam blanketing (film boiling) and possibly dryout.
Although preliminary, it appears that axial cracking may only occur where large deposits exist in this region.
APS believes that the appropriate crack growth rate for tubes in the arc area is 2 mils per month, and that the appropriate crack growth rate for other areas of the SG is 1.4 mils per month.
Based on the examinations of the removed tubes and other data, the crack detection threshold for the bobbin and RPC probes is 50 percent and 40 percent, respectively.
Applying the methods contained in Regulatory Guide
- 1. 121, this results in an operating interval of six months until the next steam generator tube inspection (Unit 2 is fueled for a 15-month operating cycle).
This information is preliminary pending receipt of the licensee's final report.
As for schedular matters, the eddy-current inspections with the RPC should be completed by about July 13, thereby extending the outage until mid-August.
The final report should be submitted to NRC in mid-July, with a final meeting with NRC about one week later.
Original signed by Charles M. 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 DISTRIBUTION:
See next page IItlPJLE WJTHI Lt-'SPV OFFICE DATE PDV LA os e
urseen 93 8'ran:lh 93 P
V rammell 4
93 PDV D
Tquay
~
I 93 OFFICIAL RECORD COPY DOCUMENT NAME:PVMTGSM.630
~ ~
Arizona Publ ic Servi ce Company For SG No.
1, 17 tubes with axial cracks have been
- found, as follows:
2 at or near the tube sheet, 5 at supports, and 10 in the free span high in the SG.
Ten of these were not detectable with the bobbin.
For SG No. 2, 84 tubes with axial indications have been found, as follows:
4 near the 01H support, 40 at or near upper supports, and 39 in the upper free spans.
Thirty-six 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 first vertical support after the 90 degree bend.
Expanded RPC examinations have 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.
Thermal-hydraulic analysis indicates that the region where the indications are occurring is an area of the steam generator where deposition could be expected based on steam blanketing (film boiling) and possibly dryout.
Although preliminary, it appears that axial cracking may only occur where large deposits exist in this region.
APS believes that the appropriate crack growth rate for tubes in the arc area is 2 mils per month, and that the appropriate crack growth rate for other areas of the SG is 1.4 mils per month.
Based on the examinations of the removed tubes and other data, the crack detection threshold for the bobbin and RPC probes is 50 percent and 40 percent, respectively.
Applying the methods contained in Regulatory Guide 1. 121, this results in an operating interval of six months until the next steam generator tube inspection (Unit 2 is fueled for a 15-month operating cycle).
This information is preliminary pending receipt of the licensee's final report.
As for schedular matters, the eddy-current inspections with the RPC should be completed by about July 13, thereby extending the outage until mid-August.
The final report should be submitted to NRC in mid-July, with a final meeting with NRC about one week later.
Enclosures:
- 1. Attendance List
- 2. Viewgraphs cc w/enclosures:
See next page Charles H. Trammell, Senior Project Hanager Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
I 1
Arizona Public Service Company Palo Verde CC:
Hr. 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 Hr. Charles B. Brinkman, Manager Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkway, Suite 330 Rockville, Maryland 20852 Hr. Aubrey Y. Godwin, 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
& Holtzinger, P.C.
1615 L Street, N.W., Suite 1000 Washington, D.C.
20036 Hr. 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. Thomas R. Bradish, Manager Nuclear Regulatory Affairs Arizona Public Service Company P. 0.
Box 52034
- Phoenix, Arizona 85072-2034 Hr. William F.
Conway Executive Vice President, Nuclear Arizona Public Service Company Post Office Box 53999
- Phoenix, Arizona 85072-3999
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DISTR!BUTION w enclosures:
Docket file NRC 3 Local PDRs PDV Reading File
- KPerkins, RV CTrammell LTran 2:
THurley/FHiraglia, 12G18
- JPartlow, 12G18 JRoe EAdensam Tguay DFoster-Curseen
- OGC, 15B18
- EJordan, 3701 ACRS (10),
P-315 JHitchell, 17G21
- JWinton, 9D4
- JHuscara, NLS217C KKarwoski, 7D4
- FOrr, 8E23
- HConrad, 7D4
- GJohnson, 7D4
- EHurphy, 7D4
- CSerpan, RV JHopenfeld, NLS314 3uly 7, 1993
r I
List of Attendees Meetin Held June 30 Between 1993 ENCLOSURE 1
NRC Staff and Arizona Public Service Com an NAME ORGANIZATION B.
S.
A.
M.
D.
K.
R.
R.
L.
M.
D.
J.
R.
P.
C.
C.
J.
C.
L.
H.
J.
K.
E.
J.
G.
F.
W.
L.
Heilker Juan Amr Radspinner Sachs Sweeney Stevens Schaller Johnson Melton Hansen Begley Cipolla Sherburne Chiu Serpan Winton Trammell Tran Conrad Hopenfeld Karwoski Murphy Muscara Johnson Orr Marsh Connor ABB/CE APS APS APS APS/ISI APS APS/RIA APS APS APS APS/ISI APS APTECH Engineering BWNS GPS International NRC/RGNV NRC/NRR NRC/NRR NRC/NRR NRC/NRR NRC/RES NRC/NRR NRC/NRR NRC/RES NRC/NRR NRC/NRR SCE STS
C*
ENCLOSURE 2 PVNGS UNIT'DVO STEAM GENERATOR TUBE RUPTURE INVESTIGATION
MEETING AGENDA e INTRODUCTION
'OOT CAUSE OF FAILUREANALYSIS
~ ECI'NSPECTION RESULTS
~ ~ PULLED TUBE EXAhGNATIONS m ~ CRACK GROWTH RATES RICH SCHALLER KILNSWEENEY DOUG HANSEN hGKE hfELTON JIhf BEGLEY W CRACK DETECTION/R G. 1.12I. LIMI'IS MATC RADSPINNER
~ RIEAM GENERATOR PLAN, LARRYJOHNSON
0 CRACK GROWTH RATE ANALYSIS
~ NDE RESULTS
- CURRENT DATA
- PREVIOUS DATA
~ DEGRADATIONMODE AND ENVIRONMENT
- INDUSTRYEXPERIENCE IN SIMILAR CIRCUMSTANCES
- LABORATORYTEST DATA REASONABLE, CONSERVATIVE PRO '"'AGATIONRATE
~ BOBBINDEPTH CALI.S APPARENTLYFROM SAME DISTRIBUTIONFOR 0yH, EGGCRATE, BATWINGAND FREE SPAN CREVICES
~ ADDITIONALDATAMAYOR MAYNOT REVEALSYSTEMATIC DIFFERENCES FOR THESE LOCATIONS
CUMULATIVE PROBABILITY OF OCCURRENCE O
NH U
O 0
0
~ IGA/IGSCC DEGRADATION MODE OPERATIVE IN PREVIOUS CYCLE INDICATIONS
- 01H
- FREE SPAN
~ PRECURSOR SIGNALS TO PRESENT BOBBINCALLS NOT FOUND ABOVE BACKGROUNDLEVEL
Bobbin Call < 50%
100%
75%
0
<o 50'I Cl 25%
Bobbin Call 2
- Ooj, 50% Detection Limit Start Bobbin Coil Crack Growth Rate Cycle End
Bobbin Call > 50%
100%
Bobbin Coil 75%
O
~O 50" Cl O
25%
50% Oetection Limi r,
~-
Crack Growth Rate 0%
Start Cycle 4
04 IS.l I
I I
Caw s
~ PROPAGATION RATE OF 2 MILS/MONTHIS A REASONABLE, CONSERVATIVE VALUE.
~ MUST COMPARE WITH INDUSTRYEXPERIENCE AND LABORATORYDATA
~ DEGRADATIONMODE IGA/IGSCC
~ ENVIRONMENT CAUSTIC (WITHSULFATE)
~ MATERIALCONDITION WITHINNORMALEXPECTATIONS NO NOTABLESUSCEPTIBILITY OR RESISTANCE TO IGA/IGSCC
~ INDUSTRYEXPERIENCE
~ IGA/IGSCC IN CREVICES USUALLYCONSISTENT WITH FULL CYCLE OPERATION, IMPLIEDGROWTH RATES LESS THAN 1 MIL/MONTH
~ MIDCYCLE OUTAGES OCCASIONALLYREQUIRED, IMPLIEDGROWTH RATES ON THE ORDER OF 1-2 MILS/MONTH
~ LABORATORYTEST DATA
~ ADJUSTMENTS
- MATERIALCONDITION
- TEMPERATURE
- LOADINGSEVERITY
Crack Growth Rate vs. Reciprocai Temperature (NiiliAnnealed Alloy 600) 1000
~~ CERT at ~190IV D WOL-PLATE C RINGS AT ~150 mV 100 C RINGS AT + 190 mV 0
V) 4)
m 10 K
0 U
V SO CT-PLATE at w 100mV 10% NBOH C RINGS PALO VERDE FREESPAN PRESSURIZED CAPSULES HOOP STRESS = 20 TP 25 KSI 0.1 0.0016 I
I I
I I
I 0,001 64 0.001 68 0.001 72 0.001 76 Reciprocal Temperature, 1/deg K 0.0018
PROM NUREG/CR-3117 0.1 E
0.01 Q
(D 0.001 2-8 mils/month p
gO q(
<ze
/
Q
/r Q
r
/
ZO
/
go"
/
~(
~0 QCapsu(es, 10% NaQH (Partridge 1987)
C3Capsules, 25% NaQH (Partridge 1987)
QC-Rings, 9% NaQH/1% KOH (Partridge 1987)
Q C-Rings. 10 5 50% Caustic (Partridge 1987)
Capsules,10 8c 50% Caustic (Partridge 1987)
IIC-Ring 40'Yo NaOH/10% KOH/Cr203 (Hermer, et al. 1986)
ICapsules. 40/10, 20/5. 8/2. 4'Yo. 1%
NaOH/KOH (Aspden 1986)
+Mode( Soiler (Partridge 1987)
C-Rings 10.40ga NaOH [Mewsnan.es al.19971
- Capsules, Calculation (Partridge 1987) 0.0001 280 300 320 340 Temperature.
oC 360 380 Temperature Dependence of IGA Growth Rate
10 PROM NUREG/CR-SI.X7 PURE WATER AND SIMULATED PWR WATER POINTS DELETED
,n~
ga g(
ye~
E CC 0.1 0
OM C9 0.01 0.001
~r+
~i+
coun ice'
~C' qO 0
/
go
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+e<
/
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////
2.8 mils/month Q Capsules. 10'aOH (Partridge 1987)
Q Capsules.
25~o NaOH +
Carbonate (Partridge 1987)
Capsules 25~a NaOH + Sulfate (Partridge 1987)
MA C.Bing, 10% NaQH (Jacko 1986)
TT C-Ring, 10% NaOH (Jacko 1986) 280 300 320 Temperature.
C 360 380 Temperature Dependence of gCC Growth Rate
~ 2 MILS/MONTHIS A REASONABLE, CONSERVATIVE DEGRADATIONRATE FOR STRUCTURAL INTEGRITY EVALUATIONS (INCLUDES MARGINS FOR OTHER CONTRIBUTING FACTORS)
CRACK SHAPE OBSERVATIONS
~ BURST TESTS REVEAL STRUCTURALLYSIGNIFICANT CRACK LENGTHS
~ STRUCTURALLYSIGNIFICANT CRACK LENGTHS CONSISTENT WITH RPC DETECTED LENGTHS
~ DISTRIBUTIONOF RPC DETECTED CRACK LENGTHS APPEAR ESSENTIALLYTHE SAME FOR ALLTYPES OF CREVICES, BUT SEVERAL FREE SPAN OUTLIERS OBSERVED
WEREJEIIIWRRRlllllWRSSEIII
. ~REElllll~HSIIIA~s~llRllllll
. WQHIIIIIWRRSKIIIWRISlllll Rklll~MRF:;4%8!~~555IH
. MEESllllMRS:-olllll REEIIII
. WRSSkllHWSH[llll RRIIHt llllll~¹iSINII IMMI lltW"Stll[lll lllNI I
~ LONG CRACKS UNDER BRIDGING/RIDGEDEPOSITS ASSOCIATED WITH SCRATCHES
~ SCRATCHES ENABLED NEAR SIMULTANEOUS INITIATIONOF CRACKS OVER LONG LENGTHS
~ WORST CASE CRACK LENGTHS WILL APPEAR EARLY, PLUGGING WIIL DECREASE WORST CASE CRACK LENGTHWITHTIME.
REG. GUIDE 1.121 EVALUATION PROCESS o
DETE ALLOWABLE CRACK SIZE TO MEET RG 1.121 SAFETY FACTORS (EOC CONDITION) o DETE INITIALCRACK SIZE BASED ON ECT DETECTAB1LITY THRESHOLD (BOC CONDITION) o APPLY CRACK GROWTH RATE TO INI-TIALCRACK SIZE o
DETERMINETIMETO REACH ALLOW-ABLEEOC CONDITION
DETE ALLOWABLE CRACK SIZE o
RG 1.121 REQUIRED SAFETY FACTORS SF = 3 FOR NORMALOPERATION SF = 1.4 FOR ACCIDENT(MSLB) CONDITION o
EPRI NP-6865/L BURST CORRELATION a= [ I -~la t ] af 1+2t SF
<<z = Hoop Stress at Flow. Stress = 0.577(a> + a) a>.
Yield Strength a= Ultimate Tensile Strength 1 = Flaw Length a = Flaw Depth t = Tube Wall Thickness SF = Safety Factor o
95%/95% MATERIALPROPERTIES a> + a= 128.3 KSI (OPERAT1¹ TEMPERATURE)
14000 12000 C3 C3 10000 FRAMATGME EQUATION PREDICTION BURST TEST DATA
- UNFIANED
~ - EDM SLOTS
+ - V NOTCHES o - SCC DEFECTS x - lGA DEFECTS CD M
U3 CD CL CQ C3 CD C3 C3 8000 6000 4000 2000 X
)
TUBE SIZES 7/8 OD (50 mil]
3/4 OD (45 & 50 mil]
5/8 OD (34 mil]
0 2000 4000 6000 OOOO 10000 12000 14000 Measured Burst Pressure, tpmeas (psi]
1.00 AXIAL FLAW SIZE EVALUATION 0.95 0.90 Normal Operation 0.85 0.80 0.75 Accident (MSLB) 0.70 0.65 0.60 RG 1.121 Limit 0.0 0.2 0.4 0.6 0.8 1.0 1.2 1.4 1.6 1.8 2.0 Flaw Length, L Iinches]
1.00 AXIALFLAW SIZE EVALUATION 0.95 0.90 Hormal Operation 0.85 0.80 0.75 Accident (MSLB]
0.70 0.65 0.60 0.0 0,2 0.4 0.6 0.8 1.0 1.2 1.4 Flaw Length, L {inchesj RG 1.12]Limit 1.6 1.8 2.0
Eddy Current Detectability Based on Average Crack l)epth 100%
80%
60%
9 8
40%
5/8 20%
2/8 0%
<40%
Palo Verde Steam Generator 22 40 49%
50 59%
Percentage Through Wall Bobbin MRPC
TABLE5 DEFECT BURST STRENGTH
SUMMARY
".i:.WSil8oi":@'127C 140
<)R)PC440...".,"
07H'/13 74 Fhibm":;-
0.58 y'.c
<<abM
'tie
'<<O'C',e~'x "S>>
5330 7491 1455 270 Midspan/
16 98 1.38 3200 2656-3171 725-866 g
. ".:; ~.~ "i'i?.".,"'.-<<",~'" i."",;;:"~~&
0o
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00
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38 38 35 31 NBI NBI NDD N/A NDD N/A N/A N/A R103C156 Midspxg/
17 57 45 NBI MAI 0.325 6968 6983-7171 5923-6082 IRkffcAF";-'mdpW=~S>':'"~ +~@++~ l~'m 4
?h?>>: ?.S.'.0.:>> '....:"""~ax~ ':-'88 "'
ance ~)>>A".: k."?? ~~0'.. 'x.
DEFECT BURST STRENGTH
SUMMARY
FlGURE Vll.E.2.a.b.
14000 APS Burst Data - Average Depth BURST DATA PULLFD TUBFS TURF SI7F.. - 3/0 TIR [42 Mll.j
~~ 10000 CI g
8000 6000 (I)
L.~
4000 (l)n 2000I R 127C 140-07H R 105C 156-MIO RIODC156-MID R l27C140-OQH R29C24-OIH R22C 15-01H 2000 4000 6000 0000 10000 12000 14000 Measured Burst Pressure, apmeas (psi)
CHARTS
Root Cause Investigation Team - SGTR Event Failure Modes Failure fulOdeS ODSCC Deposit Induced Lockup Cross Flow I
1 I
I Metefiat I I
L I
Stress Environ.
ment High Stress During HU,CD Abnormal Flow Direclion I Velocity Vortex Shedding Abnormal Vibration at Supports Loose Supports at ON fchgtrc Gotten.
trXesg ucchsnnne, QI"'-".e
'ttfSCtI'"
3h~,
rp thrtitIl Depose Contrkions tstcntn ate nhchng)
I 1
I fttt>>ht t
I Ik%.a~'
heel rItJt r rnf44I IoI V4fchorl tor sesnet v4Qson rtro tel Utter tel Oeted tScrachi urterul Property tttccl frectmcnt) rhernstl Crchng Scconecttt Su esses frenetg
." Weel h
cg lri Po cntt Sotphetc Accetetcnr Po cnd SStPtStte AccetNent LEGEND:
Confirmed based on examination/
testing of pulled tubes o
Anatysts required to supporl I Known to be susceptible.'factor I~
'ep'No data has indicated problems in this area
~ IS ~ g Ierol ~
Root Cause investigation Team SGTR Event Failure Modes
.I 0DScc:;:
Material Properties Stress Environment Heat Treatment
~ Arfa>><4 <<<4 its Affords
~ s I'ra spa<a por cn<S Co <dnd co<re<tv>>th t>>bcs t<<<rerd
~ Kelt <<re>>41 ~Ib>> I~
it as<(sue Kc(CS<t lo eccl orant
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Crtt V<en4b lo bt 4<t<<a>><4 Mictostructure
~ tatsncdhita 4 bh Veto<<<sdwe>>u Iccttctbtc'. ad>>teel Nd lcrlust4
~ At<dot<(tse y<sned Material Composition
<ac corda ~ <4 a~tv
~ llCO spec.
clic Vibration
~ r>><4<Ke ot >>tv ace be
~
'hyh<<>>tat u U2 CUO U<.Ul(I22>> I2<)
~Welf con<ad t<<ca art
~
~ orso>> Kr ~
~ Norssit p<odeccs cree>>Art<Col c<ICU Pressute apprcc <M ps<act<ass t
~ Ccwlid<<cd acyiOS<c Thetmal
~ 42.50ast
't>>close I<ales coo<4 l
hdwe ctciny
~
SG2>>sot (tg
'n<tat to tet 4<<
Tvto.Phase Flow Instability
~ Poarb<c btae4 oa
~oar<<as
~ No s<ctbnpcel ctfb Residual Cold Wo(k A<It<Ill<triad< II
~usa cd oa asst Uaep EKSCC alla<4 (Qr<atwycd tt Wtv sari ~ 'rdca< ~
ttcacnce ct ed4>><<1 Sera(ches tart< h>>t K'ASCC
~<load <<t (ad aha pcs(
thtscfoelK<dchu loon4 onltbts Tube Ovatization Notstcasteb
~tb aac4 h conte
'aterial Heat Treatment Physical Damage Fretting:
Poaaibb hdcd sa la bslc4ettes Physical Damage V(ear:
~ pl ea<<4 h ssppodt
~calop bv
~Ndlnahvtas>>lb
~<Oaten<I dlaelouidl
~ Local<cd cled A
lied Hoop Stress
~
Kpp<osat<c<<r<O<2KS<
~ Knc>>s <O bc lfca<<4
~
Bowing h4cdrd lrt4tpoli helios
~
. V<4to <err>>tot b
~
- It<Ye<ron
~
~ Csa rtleihos bbrclboa
~
~ S reu tad ce b slain al Thermal Expansion
~
Oc act std lo et pand (Iaab <<4
~
llttcclllhbossy 4nueat
~ Ippo<t ~is l<lynstfd t
Srldract d y<ou>>tv
~
1I troars cod4 bc retd<4 Support Misalignment General Characteristics
~ Re4ec <no
~ yHPtas tete ~ a<U<se
~ lbOi fo trans pol
~ to dana <dora SG 2l >>
2(~ rtt<(
~Co<salad>><JI dbs U<4
'dv te<ioe>> 2
~ Opvftedu Cet<ee pbca
~ Acth IntrIBOOinonl Caustic
~ Vty<<tPI<4<de el<ate
~ tyyh lb t5024 <ctata
~ Hob pronto Ik cossrsicttre
~ Sort coro<< bu dtpbt cato(a trad<<I <alto
~ tbb olidca cs a ffbe
(<OOOO
~ Vd<<utlo swh>> yes ttyb so top
~Crt Id<<ass<noh+
bd~CWOI PP I (os< atdt c<tfbct Acidic
~Icbbc pou*b ~ SIW
~rid<act ~ <Oper<a ty 4rpbt 'sa <t urtKO
~ tbt s ay paced bt SIN Chra<crt
- General, Characteristics lyyhfe blsspal
~ (Wad lb>><<
~ Kssro to bile sypic Icosa rrhcfsllbtd<lbtc ss4t
'Ciesbtrt ooaetd siss
~Kppc<< to isla tais bdysy<cos<vt
~Ktctse4 ls cobra as
~LSI>>(
u4<ttyo ycnubsa'pao4
~ Adye dtpoe I so<ster<<<
awced<ftloa ls 2 ~ 5 bs ea Ntlcl
~ lldyto ate alia( snd ac<clpon4 toaKU General Characteristics
~ Kaon<<b he Or<is(hen sod ybnts (thI42<'ll
~(toit<4d 75 Oxrf,:.,
~I 5IO:SI2fdOIH~'
Sr i(te dlposta thefts bclllespvdss(sp
'o AC5 itsy<<vert(
General Characteristics
~ Lbd 2 bnyfet t<r tsa sai
~ Nosinstop<<atbe at LOOK(cc bey<<luu tbcnUatat ss(2
~ V<at oper those< NsI too ~ too NW hosts Of< s<>iny tabes BulkChemical QeviceCheml De
'onnatio
- Tem erature Time SII Ma(tt(a( P<oP Ittily
~ <ass
<C>>O< I
SCC Synergism Crevice Formation Freespan
'u~e supports
- 4 i.~"c
"'-.-."..:Tensile Stresses
- Applied
~ Residual Environment
~ Caustic
~ Arc - THACC
AX/ALClRlACKIINQ SUIMMAIRY TSH 08H Frees an 09H Frees an BW1 Free span NBI
~
~
0 NQI OTHER
~
~
G.uo n4C+lq hen 47 Tubes
-':-'-:NBI NQi:"OTHER
"'.:--:-'==:=-OSH
- F-ree i a'
--'-'-"-'-"-=OSH Fre'e-s in 4
10
i:=~~~j+4'+++~+
Free'pan 13 MK p~s AlkgIV>>
'".~ B.-",NoBobbin, Indication,.,.;;:.;-,, >-. "
-..=, ",'.'~ Tribes
~~NQI,.Non,.Quantifiable Bobbin Indication,,. =.,. ~~,
%~4~'Ã'kiWNFVP~A
~M Pw"i 4M"'RX~e~<:"kW'
SG 21 AXIALINDICATION
SUMMARY
6/27/93 ROW LINE LOCATION LENGTH BOBBIN DEPOSIT INDICATION 6
1 104 41 109 42 106 45 131 46 147 76 149 76 145 84 140 89 149 98 141 104 140 105 148 111 27 112 146 117 139 118 108 143 TSH
-.86 BWI +4.67 08H
+34.35 BW1
+3.73 BW1
-.71 BW1
+19.00 09H
+25.72 09H
+25.13 BW1
+4.93 09H
+23.55 BW1
+1.41 BW1
+3.25 BW1 -1Z5 09H
+28.08 09H
+33.90 TSH
-.71 09H
+.45 09H
+25.02 08H
+.93
.14 26 6.96
.49
.38
,41
.56
.41
.49
.41
.19 91
.10
.50
.40 95
.50
.20 23 NQI NBI NBI NBI NBI NQI NBI NQI NBI NQI NBI NBI 81%
NBI NBI 7%
NBI NBI DSI NO YES YES YES NO NO YES YES NO YES NO NO NO YES YES NO NO YES NO TSH MID MID MID MID MID MID MID MID MID BW1 MID BW1 MID MID TSH EGG MID EGG
SG22 AXIALINDICATION
SUMMARY
6/27/93 ROW LINE LOCATION LENGTH BOBBIN INDICATION DEPOSIT I&22 10 29 112 115 117 115 117 113 123 118 115 123 128 129 128 123 129 132 141 142 140 151 131 138 41 127 129 142 13 23 24 39 40 40 42 44 45 46 46 47 48 49 50 50 57 74 83 87 90 92 93 94 96 96 99 01H OIH 01H OSH OSH 08H OSH OSH OSH BW1 08H 09H BW1 OSH 09H 08H OSH 08H 09H 09H BW1 BW1 BW1 BW1 05H 09H BW1 TEH OSH OSH OSH OSH BW1 Bwl BW1 BW1 BW1
-26
+.24
-.16
+29.38
+40.85
+41.00
+39.51
+40.00
+42,02
+4.53
+.55
-91
+5.66
~+32
+.36
+.66
+.76
+.76
+.75
+.72
+.07
+.~~"
+18.35
+19.24
+.88
+16.37
+2.79
+2.28
+14.46
+33+ /3
+39.79
+41.33
+Zo3 2
+3.92
+3.10
+6.71
+3.53
.60 98
~21 34
.78
.55 e/7
.82
.18
.19
.55
.64 91
.18 QO n>>
~cD
.89 so73
.96
.24 36 2.41
.51 94
~
~~S
.6" "38
.54 1.80
.57 52%
30%
DSI NQI NQI NBI NQI 46%
NQI NDD/NQI 71%
71%
NQI DSI NBI 82%
DSI 39%
37%
NBI NBI 99%
NBI NBI NBI NBI NBI NBI NQI NBI NBI NO NO NO YES YES NO YES YES YES YES NO NO.
NO NO NO NO NO NO NO NO YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO 01H 01H 01H MID MID MID MID MID MID MID EGG EGG MID EGG EGG EGG EGG EGG EGG EGG MID Bwl MID MID EGG MID MID TSH MID MID iMID i%iID MIP.
ROW LINE LOCATION BOBBIN INDICATION DEPOSIT 144 135 133 134 134 149 144 146 150 137 143 145 134 140 145 140 142 142 137 141 135 129 135 128 128 125 129 131 126 128 123 125 129 99 102 104 105 111 114 115 115 115 116 116 116 117 117 118 119 119 123 124 124 130 132 132 133 135 136 136 136 137 137 138 138 138 BWI +4.55 BWI +1.45 BWI +6.19 BWI +2.23 BWI +1.61 09H
+20.47 OSH
+.34 09H
+26.08 09H
+27.94 09H
+32.57 09H
+22.95 OSH
+.78 09H
+24.46 BW1
-1.17 BWI +3.5 BWI +6.42 09H
+14.10 BWI +2.63 09H
+28.91 09H
+23.11 09H
+22.75 09H
+.90 BWI +.77 09H
-23 09H
+.88 OSH
+.70 09H
+.75 BWI +.84 OSH
+.39 BWI +1.88 09H
+.74 09H
-.95 09H
+.39 BWI +5.39 09H
+.39 BWI
+6.96 09H
+17.96 BWI
-1.65 OSH
+.57 BWI
-1.05 OSH
+.24 BWI +.77 2.55
.55
.41
.71 1.00
.63
.13 31
.50
.56 2.54
.25 7.31 232
.50 28 1.19 1.00 Zl 3.95 33
.56
.14
~n
.96 34 36
.53 38
.52
.88
.76
.76 (7
.13
.65 1.19
.44
.19 NBI NBI NBI NBI NBI NDDNQI NBI NBI NQI NBI NQI 26%
NQI NDD/NQI NBI NBI NBI NBI NQI 64%
NQI NBI 28%
NDD/NQI NBI NBI 84%
31%
79%
NQI 57%%uo NBI NBI NBI 55%%uo NBI 28%%uo NBI NO NO NO NO NO YES NO YES YES YES YES NO YES NO NO NO YES YES YES YES YES NO NO NO NO NO NO NO NO NO NO NO NO NO NO NO YES NO NO NO NO NO MID MID MID MID EGG MID MID MID MID EGG MID BWI MID MID MID MID MID MID MID EGG BWI EGG EGG EGG EGG BWI EGG BWI EGG EGG EGG MID EGG MID M?D 0171 EGG BWl EGG BWI
ROW LINE LOCATION LENGTH BOBBIN DEPOSIT INDICATION 128 139 127 140 122 141 128 141 121 142 115 144 117 144 123 144 118 145 124 145 122 147 110 149 17 152 107 152 110 153 103 156 105 156 107 156 1Q4 157 97 158 93 160 08H
+.81 07H
+.50 08H
+.27 09H
+.53 OSH
+.71 09H
+.20 BW1
-.79 QSH
+34.99 OSH
+33.92 09H
-26 BW1
-1.66 BW1
+5.60 09H
-2.16 BW1
+1.03 BW1
+1.34 QSH
+33 BW1
+.62 01H
-.14 BW1
+.09 07H
+.62 OSH
+19.22 OSH
+19.64 OSH
+25.92 OSH
+24.75 OSH
+26.84 BW1
-1.92 0SH
+19.21 22 30
.d+
30
.62
.28 ZS
.17
-9.00
.47 1.16
.60
.19
.79 04
.62
.09
.40
-.2" est.
.41 2.83 136 339
.12 3.al
.13
.19 NBI 31%
39%
NBI 37%
71%
NBI NBI 100%
62%
96%
NBI 23%
43%
NBI 85%
NBI 32%
NDD/NQI NDD/DSI NBI
..NBI 84%
NQI 85%
NBI NBI NO EGG NO EGG NO EGG NO EGG NO EGG NO EGG NO BW1 YES MID YES MID NQ EGG NQ BW1 NQ MID NO EGG NQ BW1 NQ BW1 NO EGG NO BW1 2992 DATA OXH NO BW1 NO EGG YES MID YES MID YES MID YES MID YES MID NO BWl YES MID "PULLTUBES
STEAM GZNZRATOR 21 6-28-93 BW1-VS4 BW1-VS3 BW1-VS2 BW1-VS 1 08H-BW1 07H-08H 07H 06H 05H 04H 03H 02H 01H TSH ARC AREA 137 1501 258 627 3806 1065 1999 123 106 108 127 124 652 696 OUTSIDE ARC 5
166 830 734
/62 494 201 109 109 142 327 242
STEAM GZlVERATOR22 6-28-93 ARC AREA OUTSIDE ARC BW1-VS4 BW1-VS3 BW1-VS2 BW1-VS1 142 553 148 478 12 185 4
08H-BW1 07H-08H 07H 06H 05H 04H 03H 02H 01H TSH 3508 489 3300 257 222 229 219 220 709 525 573 343 434 98 87 88 89 92 329 340
Min/MaxChemistry
'jMIOlfDIZe
'=.Molar Ratios::-;."..4~"::."
'<<Mainltain.Catioii to,; -.;
'";-"'Anion'ratio.within'""'.
'a'pproved """...'-';;"".-.;;";::.:,':"
.,;",specifications
'.,:.".::,w
.".Cont'roJ/rediice,':, ""'Q
'"'contamInant. soUrce "Corr'osiori-Prod o'ct'.."Trans oR':"":""'-'!:";":,'=.;:;:--:.;g
'.:Maintain.,fIn'at '.;.',-'.~"~""'.
'i.;feedw'ate'r Iron".,'-'.;-".'l:::.';.'::,;...",
.,'.".levels withIri.;,,~,".-'.':;-:,.:I::,',.:
'::approved'",::.;;".';::.':,.':;:,"."':-:.-',';:
"':speclfIcatioris "-,.".~j v"i cw17 I,
I I~I II'II I I>-I'l I!; I.I i>c rll
> ~I'l III Ik v<!II (II !II e.. 'il>
II'!I C
II I ~
Buffer Crevices:
~ Add Boric Acid fdH
~ Maintain feedwater Hydrazine levels within approved specifications
',:Ma'ximize:
- .:Blowdown::Flow;:":.;,-.."';.
Most:beneficiat.".':.,":~
.:~'AbnarmiljHIghrate j'HIdeo'Ut;Retorn
=-i,":;.":.,~
"'DownpoNefsi~-';~~jj.
PjHold j'oinls::.~":~":.':,'i
~ >
~ 5 tl
~
Activities Under Evaluation
~Mossbauer Analysis
~ECP Measurements
~TReductions
~Chemical Cleaning
~ATHOS III Run
~Improved Eddy Current Technology
LEAKAGE MONITORING P.ROGRAM
~ PROGRAM ENHANCEMENTS
~
CHANGED ACTION LEVELS IN MONITORING PROGRAM TO REFLECT UNIT 2
EVENT FOOTPRINT
~
CHANGED SAMPLE LOCATION ON S/G BLOWDOWN MONITORS TO IMPROVE SENSITIVITYAND RESPONSE TIME
~
LOWERED CVE/GSE MONITOR SETPOINT TO PROVIDE EARLIER ALARMANNUNCIATION
~
ESTABLISHED LEAK DETECTION METHOD PRIORITIES
04/93, ARIZONA PUBLIC SERVICE, PALO VERDE, UNIT 2 STEAM GENERATOR:
21 LOCATION:
ALL CRITERIA: SAI. MAI DATE: 06/28/93 TIME:
i0: 29: i9 STAYS PLUGGEO 114
+
HAI Ghl 150 150 140 140 130 130 120 120 110 110 100 100 90 90 80 70 7O 60 60 50 50 40 -
40 30 30 20 20 10-10 10 20 30 40 50 60 70 80 90 100 110 1?0 130 140 150 160 170 180 CONAM MUCLEAA. INC.'$
04/93, ARIZONA PUBLIC SERVICE, PALO VERDE, UNIT 2 STEAM GENERATOR:
22 LOCATION:
ALL CRITERIA: SAI. MAI DATE: 06/2B/93 TIME:
10: 20: 10 STAYS 196
+
NAI 3
+
641 150 150 140 140 130 130 120 120 110 110 100 100 90 90 80 70 60 60 50 50 40 30 20 10 30 20 10 10 20 30 40 50 60 70 UO 90 100 1 10 120 130 140 150 160 170 180 CONAN NUCLEAR, JNC.
BN
~ BOBBINDEPTH CALLS APPARENTLYFROM SAME DISTRIBUTIONFOR EGGCRATE, BATWINGAND FREE SPAN CREVICES
~ ADDITIONALDATAMAYOR MAYNOT REVEALSYSTEMATIC DIFFERENCES FOR THESE LOCATIONS
I 1
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gzC cpu s P l
P I
O a.
D0
%o 0
IQ 0
/o OBBIN DEPTH INDICATION, PERCENT OF WALL THICKNESS Cumulative probability of occurrence versus bobbin depth call.
~ t
~ ~
II I
Batwing Ovp)
Row FIGURE 3 Potential Tube Spacing & Potential Freespan Tube Movement::.
Movement
"~PyxEpjcii'X "6
,. w~<g,<<,'i'gj",,Wi'ube Diameter 3'4" gyp.)
6
. ~pa.<<
.'.S SP@S@3 Pc-
-"-6ysS9
' 6P~.gr
'yYg.
x'<+k%k" "4
à 6
%)<
Sr'M2'ltltp.)
1" Tube Pitch (Typ.)
Scallop Bar at 09H
~/4" Pyp)
,s9 Column 9,1999 SPAC9SG
I rC i::I
<<iYi~RE 2 Upper Tube Bundle Geometry Hot Side (90' 270'xis)
.- ¹;:ili~ly long unsupported length 27.5" MQ 36" I
18" Row 159 UN 58.5" 128 117 09H S
VS2 105 92 45 VS3 08H 54 53 M
m I
VS4 19 18 07H 41" NEXT SUPPORT (06H) ea ee SO 1i
v E
I I
l i
t I
(
t h
100 SO
~O 80 Normal 0 eration Accident 1.4 mih/mooth OPERATIONAL TIME LIMITS FOR RG 1.121 70 60 RG 1.121Limit 50 2
3 4
5 6
7 8
9 10 11 12 Time of Operation (Months]
I
~l t
t k
~
H
~ s I
1 I
1 t
I
100 80 Norma1 0 eration Accident 29 mih/month OPERATIONAL TIME LIMITS FOR RG 1.121 70 60 50 RG 1.121 Limit 40 1
2 3
4 5
6 7
8 9
10 11 12 Time of Opemtion
[Months]
e
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t>
f