ML20005E037

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Steam Generator Number 3 Inservice Insp,Yankee Nuclear Power Station
ML20005E037
Person / Time
Site: Yankee Rowe
Issue date: 12/07/1989
From: Heider K, Mckenney H, Mellor R
YANKEE ATOMIC ELECTRIC CO.
To:
Shared Package
ML20005E032 List:
References
NUDOCS 9001030153
Download: ML20005E037 (33)
v • d • e


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4 Yankee Atomic Electric Company

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Steam Generator Number 3 Inservice Inspection Yankee Nuclear Power Station December, 1988 I

Prepared Dy: /2 [M8' _m '_e

//////7 H. E. bckhnne, Reactor Engineering Date Department M&zd b

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Revlewed By:

_"fk.

J. Mdider, Reactor Engineering

~ Date f

Department Approved By M

/Z!7!09 R. 'A. Mellor, Tekhnical Director Date 9001030153 891212 PDR ADOCK 05000029 G

PNV

l Table of Contents Section Pace 11 List of Figures List of Tables...................................

iii 1.0 Introduction 1

2 2.0 Eddy Current Testing Program 3

3.0 Eddy Current Testing Results 4.0.

Referen:es 5

25....................................

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'g r6 List of Floures-TNumber Paay c

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.1 Number and Estent of Tubes Tested From

-- 12 l

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-Inlet: Side; 1

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- 2l Number and Extent-of Tubes) Tested From 13 v}

~ Outlet Side P

3 All. Indications"Tubesheet Plot' 14 g,,

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' 3AL All Indications Distributlonl Plot 15' f

. 4 Inlet Side Indications Tubesheet Plot'

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5, E Inlet Side' Indications Distribution ~ Plot 17 ii 5"

Outlet: Side Indications Tubesheet Plot 18 I

~ 5A Outlet Side Indications Distribution Plot 19 f

6-

'Antivibratlon.,Bar. Region Indications

'20

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Tubenheet Plot l

o 7?

Dent Indications ~at Outlet Side #4,. Support 21

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.DentLIndications'at Inlet Side #4 Support

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Dent: Indications at Inlet : Side :#3: Support 23 i

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Steam-Genera. tor-Number 3 Plug Location 24

j Tubesheet
Plot j

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List of Tables Number hge 1

1908 Plugged Tube Locations 6

2 Indication Sire and Locations 7

3 Number and Extent of Tubes Inspected 9

4 Dent Indication Size and Locations to 5

Steam Generator Number 3 Plugging History 11 9

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In November' 'and December of.1988,- Steam. Generator' Number 3

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' underwent an inservice inspection, in accordance with-Yankee g

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Nuclear Power-Station- (YNPS).. Technical -Specification 3.4.10.

k This: report presents the'results of--

the inspection pursuant. to E

l Technical; Specifications 4.4.10.5.b and 6.9.6.m.

The-following P

.results are presented:-

o The. number and extent of tubes inspected.

. n o The' location and percent of wall-thickness penetration for

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.each indication of an imperfection, oLidentification of. tubes plugged.

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L YNPS'has:fout-Westinghouse-Model 13 steam generators, each'with b

1620 vertical-U-tubes.-

The tubes are 3/4 inch-0.D. -Type 304.

L stainless steel', with an average wall-thickness of 0.072 inches.

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Prior' to this inservice inspection, Steam Generator Number 3 had L

.101 tubes plugged (6.2%).

Eight additional tubes were plugged following the 1988 inspection.

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'2.0 Eddy Current Testino Procram L,

'The-' inservice inspection of. Steam Generator

~ Number 3-was.

' conducted-by Zetec, Inc. 1The data ' acquisition'and analysis 1was conducted -utilizing both Zetec and plant procedures (References t

1, 2,: 3 ).- The ' majority of the eddy current data are from full D

length' tube inspections acquired from the inlet side of the steam

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generator.L. Rows: 1. through 4 were--inspec ted, on both the inlet and outlet-side of the generator-becauseL small.radli U-bends f

- precluded full ^1ength inspection..

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' 'The ! hardware. and software that was utilized during this o,

6 inspection. consisted:of the followingt

1..

'o SM'10 Nonentry-Positioner o. 4D-Probe ' Pusher-Pul l er'-

4 3

o MIZ-18/DDA-4 Data Acquisition System p

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1The inspectionsVwere. completed in two phases c..

O' Bobbin Coil Insoections - -This phase determined the amount b

of tube wall thickness degradation-to identify the tubes; h

which'should'be' plugged.-

o Rotatino Pancake Probe inspections -- This. phase.further characterized selected larger. defects.-

These inspections were1a new addition to the testing program to provide better.

characterization of.the defects (Reference 4).

I

.Ed'dy -current-data were analyzed by primary -and secondary

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P

-reviewers provided-bye 2etet.-

-Yankee also used an independent'

, third. party. experienced Level IIIA eddy current analyst to review the results of-the: Inspections and to resolve any discrepancien.

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. Yankee's-inspector'also-reviewed 'all-procedures,. guidelines,.and gg

' training programs prior to inspections.

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4 3.0 Eddy Current Testino Results The results of the bobbin coil inspections are presented in Tables 1 through 4 and Figures 1 through 9.

Eight of the 1518 tubes that were inspected (0.53 percent) were plugged.

Table I lists the identification of the eight tubes.

The plugging criteria used were more restrictive than the Technical Specification 4.4.lO.4.a.6 limit of 40 percent.

Any tube with an indication greater than 37 percent was plugged.

Table 2 oresents a compilation of all indications found during

- the first phase of inspections.

Forty tubes were found with indications of tube degradation.

Using the Technical Specification-criteria the indications can be categorized as follows:

Imperfections (<20% degradation) 4 tubes Degraded (>20% degradation) 36 tubes Plugging Required (>40% degradation) 7 tubes Table 3 summarizes the number and extent of the tubes tested during the inspection.

Only one tube (location 5-32) was not tested.

Tube 5-32 was -not tested because of both SM-10 positioning difficulties and ALARA concerns.

Figures 1 and 2 present tubesheet plots of the extent and number of tubes tested from the inlet and outlet sides of the steam generator.

All rows, except rows 1 through 4, were tested full length from the inlet side.

About 75 percent of Row I was inspected from the inlet side to the fifth support column on the inlet side.

The remainder of rows 1 through 4 were inspected from the inlet side past the U-bend to the fifth support column on the outlet side.

The inspections on rows 1 through 4 were completed from the outlet side to the fifth support > column on the outlet side.

Figures 3

and 3A present plots of all of the indications identified during the testing.

The percent indications correspond to the largest indications measured in each tube.

Most of the indications are located in the center, or kidney

region, of the tubesheet.

This region historically has had a small sludge pile in the secondary side of the tube bundle.

All indications are plotted on the inlet side plot regardless of actual location.

Figures 4, 4A, 5,

and SA present plots of the indications for the inlet and outlet sides respectively.

Figure 6 presents a tubesheet plot of the indications in the antivibration bar region of the steam generator.

All of the indications are plotted on the inlet side plot regardless of the actual location.

Table 2 presents the actual locations.

Figures 7,

8, and 9

present tubesheet plots of the dent indications in the steam generator.

The location and voltages of these indications are presented in Table 4, A total of 10 dent indications were detected in 7 tubes.

Most of these indications are on the outside of the tube bundle, near the fourth tube supports on both the inlet and outlet sides.

The dent indications are minor and limited in nature.

3

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4 Table' 5 and Figu're 10- present a listing and. tube map of the

! current"plugssinstalled in_ Steam Generator' Number 3.

In twenty-eight years oft operation, 109 tubes (6.7 percent) have been plugged..

The

v. umber of tubes plugged following the 1988 b

, inspections is consistent with' historical levels.

The higher tube plugging; rates' in 1984 andL1987 is due to the introduction

of.sfull.

length 1. tube-inspections and advanced inspection

',,Ltechnology.

. Thirteen' defects were t'nspected using the rotating-pancake' probe.-

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'The, rotating 1 pancake. probe. data ~were analyzed to characterize the-nature.

of' the: : indications in Steam.

Generator-Number 3.

' Attachment 1 (Reference 6) documents an evaluation of the data.

bc Based on the shape,: profile, and location of the indications, it

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is 'unlikely that the indications are associated with cracks.

The-locations-of the indications and their nonlinear shape suggests-j I!

pitting.

This result:is. consistent-with previous evaluations of k

YNPS steam generator defects.

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.2etec procedure FSP'301-18

" Eddy Current Inspection of Non Ferrous. Tubing using MI2-10 Multifrequency/ Multi-Parameter D v Techniques, Rev.

4."

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'2etec procedure' FSP.301-EVAL, " Data Analysis Procedure of

'l Nuclear Steam Generators,-Rev.-3."

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Yankee Nuclear Power Station Plant' procedure OP-7203, " Eddy-Current Examination and/or Repair of Steam Generator 3

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" Rev. 9.

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~4.

Letter,-Yankee Atomic' Electric Company to the United States

. Nuclear Regulatory Commission, FYR 88-00, " Steam Generator

- if Surveillance ~ Program Improvements," dated January 12. 1980.

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Analysis Guideline.for the Evaluation of Yankee Rowe Steam j

F, Generator-Eddy Current Data, Rev.

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i 6.

Memo, C.B.

Larson to H.-

McKenney, PED 346/09, Steam Generator Eddy. Current Data " dated October 26, 1989.

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1988 Steam Generator Number-3 Inservice i nsoection i

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22 EE 11S-31 +2*00 4

22 E2 11S-31 +0*80 II 22 EB 11S-31 +O'GO 2G 22 28 i-VAB 29 22 22 4-VAB 8

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198B' Steam Generator Number 3 Inservice inspection p

t, g(. y;c Indication Size and Locationsi

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%'Deoradation: Location of Dearadation

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41' 22 TTS-CL +0.90

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~ TTS-CL +3.00

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-41 26-TTS-CL +0.70

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52 TTS-CL:+0.00-25; 42 31 4-AVB o

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43 63

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43 36-TTS-CL +0.70 iX 9

~43-24 TTS-HL +2.30 1

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-TTS-HL = Top of. Tube Sheet, Hot. Leg (Inlet); inches.

y L1, cTTS-CL.=-Top of Tube Sheet, Cold Leg-(Outlet),

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1-AVB et

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Antivibration Bar, Hot. Leg

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Tubelthat'was plugged during this inservice

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Table'3 1

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1988 Steam Generator Inservice Inspection' W+; ;<

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Number and Extent'of Tubes' Tested.

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'From From i

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Inlet,

' Outlet E

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No.lof Tubes. Planned' 1519 245 i

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1518.

245

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No '. ; of ' Tubes L. Completed From Inlet
151EL 0

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lNo._ofRTub'es' Completed.From.Dutlet 0

245' ts E

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PlannedlTubes-Completed (%)'

99.9 100!

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Total
Planned' Tubes Completed: (%)

99.9

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-(from-both' inlet:and outlet)'

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-- 1989-Steam Generator N' umber 3' Inservice Insoection Dent I nd i c a t i o'n Sire and Locations

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Table 5 1988 Steam Generator' Number'3-Inservice inspection n:

Steam Generator Number-3 Pluaoina History 4

M'

Tube Numbers l1967' G 2 9,;
G 3 6, H25, H27, H30,fH34, 135, J34, L31

-1970:

iJ35, N25, 1977L D16,-D17,:D28, G23f J41, J42, K27,-M39' N24, N26 3

11984 (1)- :B47, D21, D22,.D23, E21, E38, F20, F21,:F24; :F27, F29, F35,oF37,.-F38, F39; F40,.F41, F42, GllB, G20,. G24, G25,-

W G27,: G28, G30,,G31,:G33, G34,=G35, G40,'G42,-H23, H26,

H28,:H31, H32, H33 H36,-H42, 123, 124; 128, 131;'I326;

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'K33, K34,,K35,'K36, N30, P19, Y35-K31,.K32, J21, J22, J23, J25,JJ27, J30, J32, J37, K24, s-.

p 1987-(2)

C22, D19 D39, D42, E25, E39', G26, H43, H49, 120, 125, p,

4 138,lJ24, K25, K30, N28, BB47, DD35 1988 E16,.G17,'H20, G22, G37, G38, H41, F43.

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' NOTE: L (1)- First time outlet sicie of steam generator; inspected.

(2)

Tubes were plugged-after reviewing past= data.with i

advanced; analysis technology.

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-o Fioure 1 1988 Steam Generator Number 3 Inservice Inspection t

Number and Extent of Tubes Tested From Inlet Side v

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XXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXEXXXXXXXXXXXXXXXXXXXXXXX XXXXXXXXXXXXXXXXXXXXXXXXXXXXEXXXXXXXXXXXXXXXXXXXXXXXXXXXXXXX

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10 20 30 40 50 SO

<- MANWAY NOZZLE ->

NAME EXTENT TU8ES TESTED X OF TOTAL e

PLUGGED 101 6.2 H/L STRT 5-HL 50 0F 50 3.1 0F 3.1

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U-BEND 5-CL 197 0F 197 12.2 0F 12.2' X

F/L TE-CL 1271 0F 1272 78.5 0F 78.5

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- C YANKEE ATOMIC - BOLTON

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~H. McKenney -M gate October 26, 1989 Grou PED 346/89

' Frem C. B. Larsen

. W,(1, #

3100 Subl00t STEAM GENERATOR EDDY CURRENT DATA 1.M.8. #

REFERENCE 1.

Yankee Plant Steam Generator No. 3. December 1988 Eddy Current Report EXECUTIVE

SUMMARY

The indications on the secondary side of Steam Generator No. 3 near the tube sheet do not appear to be crack-like in nature and are most likely pitting.

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< BACKGROUND-The locations of 16 indications, which were discovered by standard bobbin-type L

' eddy current examination, were re-examined by a rotating pancake probe technique.(MRPC) in order to further evaluate their nature.

DISCUSSION

-The MRPC data is summarized in the attachment. The tube number, the location along.the tube length, the dimensions of the indication taken from the raw

. data, the estimated dimensions of'the flaw, and the percent throughwall dimension (taken from the original bobbin coilidata) are shown in the table.

'The flaw size is estimated by subtracting one coil diameter from the indication size as displayed in the clipped plot. This is done because the coil' sees the flaw from the extended magnetic field before the center of the coil reaches the flaw. One coil diameter is only an approximation of this factor.

In fact, for small flaws, some of the dimensions become negative'when estimated.

If the flaws can be shown to be nonlinear, then it can be assumed that they are not cracks.

In seven instances, the estimated flaw sizes are signiffcantly longer than they are wide. However, when looking at the raw dimensions, it can be seen that the indications are closer to being equidimensional. Also, in each of the seven indications, the long dimension i

is axial with the tube. Per discussion with S. Alspaugh of Zetec, this could very well-be error introduced by the integration of the probe retraction rate versus the probe revolution rate. And it is unlikely that in steam generator

-(

tubes, cracks would be so oriented.

Another argument for discounting cracks is that in the MRPC data graphics, the edges of the discontinuities have a definite slope.

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- H. McKenney October 26, 1989 Page 2 Cracking, on the other hand, would be very sharp.

Mr. Alspaugh states that when artificial calibration flaws are represented in the graphics, they are very geometric, e.g., holes appear as cylinders.

The MRPC data also shows a considerable amount of deposit on'the secondary side, which is represented by valleys'in the plots. This is consistent with their.. locations, being just above the tube sheet where sludge deposits are common and magnetite can form.

In this area, pitting is a common problem.

Generally,' cracking is more a problem associated with tube sheet crevices, and is found most commonly on the hot leg. According to t w original eddy current,

data,-there were only 11 indications of this type on the hot leg, and 36 on the cold leg.

CONCLUSION Based on.their shape, profile, and location, it is unlikely that the

(

indications in question could be associated with cracks. The location of the L

indications.and their nonlinear shape definitely suggests pitting.

l L

ll/h W%

0. B.J 'a'rifen L

Inservice Inspection Level III-l Plant Support Department L

J./antSupportDepartment J. Lance, Manager l

Pl l

l CBL/JJL/b11/0702w

' Attachment cc: 'D. B. King (YNPS)

T. K. Henderson (YNPS)

G. Maret (YNPS)

J. K. Thayer

I[ \\ _ y..

l,; }

cff.' '

ATTACHMENT e-Indication Flaw Estimate Percent Tube No.

Location Length Width Length Width Throughwall 14-29 TTS-HL+2.1" 0.349 0.332 0.071 0.054 32.000 7-17 TTS-HL+0.8" 0.434 0.294 0.156-0.016 52.000

~5-16 TTS-HL+0.9" 0.378 0.200 0.100

-0.078 53.000 8-41 TTS-CL+0.8" 0.368 0.368 0.090' O.090 52.000 6-43 TTS-CL+1.0" 0.310 0.310 0.032 0.032 64.000 0.180 0.148

-0.098

-0.130 36.000

)

6-43 TTS-CL+0.7" '

O.445 0.445 0.167~

0.167 47.000 1

7-38 TTS-CL+1.7" 7-37\\

TTS-CL+1.6" 0.601 0.300 0.323 0.022 38.000 7-37/

.TTS-CL+1.6" 0.466 0.272 0.188

-0.006 38.000 20\\'

TTS-CL+0.9" 0.388 0.281

~0.110 0.003 46.000 8-20/-

TTS-CL+0.9" 0.287 0.209 0.009

-0.069 46.000 7-22 TTS-CL+2.5" 0.515 0.292 0.237 0.014 42.000 7-22 TTS-CL+2.0" 32.000 7-22 TTS-CL+0.8" 32.000 28\\

TTS-CL+0.7"'

O.282 0.267 0.004

-0.011 33.000 j

6-28/,

TTS-CL+0.7" 0.341 0.222 0.063

-0.056 33.000 1

l 4

l 1

1 l

3

\\ Originally called as a single indication, MRPC data indicates that there are

/ two small indications very close to each other.

  • Signal amplitude too small for MRPC.

NOTE: Small flaws become negative numbers when size is estimated. 0702w

'

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