ML20236L691

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Generator Eddy Current Test Rept,1987 Refueling Outage
ML20236L691
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 03/31/1987
From: Andrews R
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LIC-87-665, NUDOCS 8711110025
Download: ML20236L691 (10)
v • d • e


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l .. Fort Calhoun Ststion-7 Steam Generator Eddy Current Test'Reocrt

-)987 Refuelino Outaae l

INTRODUCTION l

l This report summarizes; steam generator. eddy current results obtained during the. I 1987 refueling outage. Summaries.of results of previous eddy current inspec-r tions were submitted to'the Commission in the following documents: j 1

i

" Steam Generator' Tube Rupture Incident Final' Report," dated June 19, l '1984. ,

"Special Report on Steam Generator Denting Derived from 1985 Eddy Cur-i rent Inspection Data for the Fort Calhoun Station," dated February'21,  !

,' 1986. >

DESCRIPTION OF EXAMINATION Combustion Engineering conducted an inservice eddy current examination of.the steam generator tubing at Fort Calhoun Station in March of 1987. The.examin-ation program included multi-frequency testing for indications of degradation and dents and dent profilometry.in Steam Generators A and B.

The examination program was conducted to meet the necessary requirements of the  !

Technical Specifications and was subdivided into three discrete . tube popula-tions. Testing was performed from the outlet side of each steam generator.

1. Tubes in Row'74 and above to determine any further progression of tube  ;

degradation and denting in the vertical support (VS) region.

2. Random selection of 102 tubes in each steam generator, including tubes I with previous indications of 20-40%.
3. Dent profilometry examination of 117 tubes in Steam Generator A and 193 tubes in Steam Generator B.

Tubes in ' population 1 and 2 were examined full length using a .560 inch diame- l ter bobbin probe. The inspection patterns are shown on Figures 1 and 2. The probe design incorporates magnetic saturation capabilities to minimize indica-tions from magnetic permeability variations commonly found in Inconel 600 tub-

.ing.

The recorded multi-frequency eddy current data was analyzed for the presence of defect indications. Tube wall degradation was evaluated using the phase anal-ysis technique for determination of the origin and percentage of tube wall loss represented'by the indication. The data was independently analyzed by two groups of certified Level IIA data analysts. Discrepancies between the two sets of evaluation results were reviewed and resolved by a Level III eddy cur-rent examiner.

8711110025 870331 h  ;

PDR ADOCM 05000295 -

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In addition to being analyzed for defects, tubes in the vertical support region j

. were analyzed for the presence of dents at supports H7, H8, VI, V2, V3, C8 and '

C7 as indicated on the steam generator elevation drawing (Figure 3). The use of the bobbin probe for tube dent measurement calculates the average radial dent. Dent data was evaluated by comparison of dent indications to a dent stan- ,

dard of known dimensions for which one volt corresponds to one mil reduction in l radius for an axisymetric dent such as dents typically occurring at drilled sup-port intersections. This correlation does not apply at eggcrates or vertical strap intersections. Dents greater than 1 volt were reported from the 400 KHz ,

absolute signal. l l

The examination was conducted with a Zetec MIZ-18 digital eddy current acquis-ition system and analyzed utilizing a Zetec DDA-4 digital data analyzer. The l frequencies utilized during the examination were as follows:

400 KHz Differential and Absolute )

300 KHz' Differential and Absolute 600 KHz Differential and Absolute 100 KHz Differential and Absolute The primary frequency of 400 KHz satisfies the requirements of the ASME Boiler-and Pressure Vessel Code for the examination of nonferromagnetic steam gener-ator tubing. The 100 KHz absolute mode provides detection of gradual varia-tions in tube wall thickness and is used for confirmation of flaw indications.

A total of 310 tubes (Population 3) were reexamined in 1987 with the 8 coil pro-filometry probe. The profile probe has the advantage over the standard eddy current probe in that eight separate radial dent measurements are taken at any tube cross section. This data is used to determine the minimum diameter and characteristic shape of the deformation present.

RESULTS OF THE EXAMINATION Defect Examination There were no tubes in either generator containing degrad-ations greater than or equal to 40%. No indications of degradation were de-tected at the vertical strap intersections. A list of indications and their locations is provided in Table 1.

Dent Examination The 400 KHz absolute data from bobbin coil exams was used to evaluate average radial dents for all tubes in the vertical strap region of both steam generators. The results of the dent analysis shows little growth over the last cycle. As was the case in 1985, both the magnitude and frequency '

of tube denting is greater in Steam Generator 8 than in Steam Generator A.

Also, tubes in Vertical Support 1 display more denting than Vertical Support 2 and Vertical Support 3. The Vertical Support 1 strap is the strap closest to the hot leg. Dent analysis results are listed in Table 2 and show x values for 1987 compared to 1985 for generators A and B, respectively.

Tubes determined to have deformation sufficient to restrict the passage of the l .560 inch diameter probe were reinspected with a .540 inch diameter probe to determine presence of tube wall degradation or the presence of other restric-tions in the uninspected region of the tube. Eighty-three (83) tubes in Steam Generator A and 92 tubes in Steam Generator B restricted the passage of the

.560 probe.

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- ' Profilometry' Examination- Results from the Profilometry Examination-show no sig  :

? nificant- dent growth. over the last' cycle. Table 3 shows the dent-growth since

.the last outage. '

CONCLUSIONS Since there were no tubes in either steam generator containing degradations

' greater than orJequal to 40% through wall, no indications of degradation in the vertical. strap region, and no-tubes, that restricted passage of a .540 inch l diameter probe, no tubes required plugging during the 1987 refueling. outage.

' ' Results of bobbin' coil and profilometry dent measurements indicate ,no .signifi-cant dent growth since the last outage.

~ Boric acid. treatment of the secondary side.was initiated in January, 1986, to help mitigate tube denting. The treatment appears.to be successful based on these results and is being continued for the current cycle.

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, s Y 2 The following. tubes were found to have wall' degradation as"in'dicated:. 0 'I s

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Line/ Row Indication Location. .!

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76/83 20% -- C3 + 22.7" i

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C7: 3.63 3.69l Steam Generator B l r ,

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C8- 4.43 4. 64 '-

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Profilometry Exam"ination Results. ,  ;,

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o _ _ _ - _ _ .

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Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 2247 402/536 4000 November 5, 1987 LIC-87-665 V. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 f z

{

Reference:

Docket No. 50-285 Gentlemen: j

SUBJECT:

Steam Generator Eddy Current Test Report - 1987 The Omaha Public Power District submits the enclosed summary of Steam Generator Eddy Current Testing performed during the 1987 Refueling Outage. This report should be used to fulfill eddy current reporting requirements as per Technical Specification 3.17(5)(ii).

Sincerely, hW R. L. Andrews Division Manager Nuclear Production RLA/rh Attachments c: LeBoeuf, Lamb, Leiby & MacRae 1333 New Hampshire Avenue, N.W.

Washington, DC 20036 A. Bournia, NRC Project Manager R. D. Martin, NRC Regional Administrator P. H. Harrell, NRC Senior Resident Inspector ph\

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