ML20127C798

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SG Eddy Current Test Rept - 1992 Refueling Outage
ML20127C798
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 08/31/1992
From: Gates W
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LIC-92-288R, NUDOCS 9209100187
Download: ML20127C798 (10)


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l Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 August 31, 1992 LIC-92-288R U. S. Nuclear Regulatory Commission ATTH: Document Control Desk Mail Station Pl-137 Washington, DC 20555

Reference:

Docket No. 50-285 Gentlemen: .

SUBJECT:

Fort Calhoun Station Steam Generater Eddy Current Test Report -

1992 Refueling Outage Attached is the fort Calhoun Station (FCS) heam Generator Eddy Current Test Report-which summarizes testing performed during the 1992 Refueling Outane.

This submittal fulfills the eddy current test reporting requirements of ICS Technical Specifications, Section 3.17(5)(ii).

  • If you should have any questions, please contact me.

Sin' trely, ,

h  ?"~

W. G. Gates

-[I Division Manager Nuclear Operations WGG/tcm-Attachment c: leBoeuf, Lamb, Leiby & MacRae J. L. Milhoan, NRC Regional Administrater, Region IV -

R. P. Mullikin, NRC Senior Resident inspector S.-D. Bloom, NRC Acting Pioject Manager l

9209100197 920031 PDR ADOCK 03000285 /

f p PDR /g' %c I as sm U 0 0 0.1. O Emvoyneggomrturcy ,/1 y , i g/

LIC-92-288R

-Attachment ,

Page 1 FORT CALHOUN STATION STEAM GENERATOR EDDY CURRENT TEST PEPORT 1992 REFUELING OUTAGE INTRODUCTION This report summarizes steam generator eddy current resul2s obtained during the 1992 Refueling Outage. Summaries of results of the two previous eddy current -inspections were submitted to the Commission in the following documents:

" Fort Calhoun Station Steam Generator Eddy Current Test Report -

19BB. Refueling Outage", LIC-89-383, Dated June 9, 1989

" Fort Calhoun Station Steam Generator Eddy Current Test Raport -

1990 Refueling Outage", LIC-90-06c9, Dated August 30, 1990 DESCRIPTION OF EXAMINATION ABB/ Combustion Engineering conducted an inservice eidy current examination of the steam generator tubir.g at Fort Calhoun Station -in February and March, 1992. The examination piagram was conducted to meet the requirements of Technical Specification Section 3.17. It included multi-frequency testing for indications-of dcgradation and dents in Steam Generators A and B.

The test program included:

1. Full length bobbin coil testing of 1318 tubes in Steam Generat r A and 1344 tubes in Steam Generator B (see Figures 1 and 2). This testing included:

An augmented sampla of 410 tubes in Steam Generator A and 442 tubes in Steam GL .or B. The augmented sample included all

+nbos identified as cegrad J tubes (i.e., a 20% wall loss) and one tube adjacent to each of these. Tubes in the areas of the steam

. generators where experience has indicated potential problems were also inspected.

A random sample of 20% of the remaining tubes, or 908 tubes in Steam Generator A and 902 tubes in Ste&m Generator B.

2. Motorized ' Rotating Pancake Coil (MRPC) testing of 20% of the tubes at the top of the inlet tubesheet, or 1001 exams per steam generator (see Figures 3_and 4).

The tubes in the bobbin. coil inspection plan were examined at full length.

The inspection patterns are shown on Figures 1 and 2. Support notation for the steam generator is shown on Figure 5.

Tubes previously detenained to have deformation sufficient to restrict the passage of the 0.560" diameter probe were inspected using a 0.540" diameter probe tc deterinine the presence of tube wall degradation or other restrictions.  !

LIC-90-288R Atta.. ment Page 2 The recorded multi-frequency eddy current data was analyzed for the presence of defect indications and dents. Tube wall degradation was evaluated using the phase analysis-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 evalcation results were reviewed and resolved by a level Ill Eddy Current Examiner.

The examination was conducted with a Zetec MIZ-18A digital eddy current acquisition system and analyzed utilizing the Eddynet digital analysis system.

The frequencies utilized during the bobbin coil examination were as follows:

400 KHz differnntial and absolute 100 KHz differential and absolute 600 VJiz differential and absolute 10 KHz differential and absolute 400/100 KHz differential mix The )rimary frequency of 400 KHz satisfies the requirements of the ASME Boiler and >ressure Vessel Code for the examination of nonferromagnetic steam generator tubing. The 403 KHz absolute is used to measure the radial dent size. The 100 KHz is provided for the confirmation of flaw indications and as a frequency used in the mixes to eliminate support and outer diameter (00) deposit signals. The.100 KHz absolute detects gradual wall thickness variations. The E90 KHz frequency is provided to assist the analysts with additional mixing capabilities in the event of excessive 00 tube deposits.

The 10 KHz is provided to facilitate locating the probe position in the steam ganerator. The 400/100 KHz mix is used to eliminate the tube support signal -

and 00 tube deposits. Other mixes are performed as required by the data analyst.

-The tubes ir. the MRPC program were inspected in the hot leg expansion i transition region of each steam generator. The inspection patterns are shown in Figures'3 and 4. The data was analyzed for the presence of any cracklike indici.tions similar to those found in the expan_1on transition regions at other plants.

RESULTS OF THE EXAMINATION Defect Examination:

There were no tubes in either steam generator identified as containing degradations :e 40%. A list.of indications and their locations is provided in Tabte 1. Additionally, no cracklike indications were found in the hot leg expanion transition regfon of either t, team generator during performance of the MRK exams.

l

1

, 1 4

LIC-92-288R Attachment Page 3 Dent Examination:

-The 400 KHz absolute data from the bobbin coil exams were used to evaluate

- average radial dents for a sample of the most severely dented tubes in the  :

Steam Generators. The profilometry exam which was performed in previous outages was not performed in 1992 based on the fact that no significant change in the dents has been-seen since 1985. Though the bobbin coil prmoe is not as accurate as the profilometry probe in determining actual dent size, the bobbin coil can-be successfully used as an indicator of change. Results of the bobbin coil-dent measurements indicate that there has been no significant increase in the overall average size of the dents of either steam generator

- since the last inspection.

Tubes determined to have deformation sufficient to restrict the passage of the 0.560" diameter probe in past inspectios,s were reinspected with a 0.540" diameter probe to determine the presence of tube wall degradation or the presence of other restrictions in the entire length of the tube. During the 1992 estuination, there were no new tubes that restricted passage of a 0.560" diameter probe due to denting, and no tubes that restricted passage of a 0.640" diameter probe.

CONCLUSIONS No tubes required plugging during the 1992 Refueling Outage because there were no tubes -in either steam generator containing degradations a 40% through wall, no tubes that restricted passage of a 0.540" diameter probe, and no cracks found in the expansion transition region of either steam generator during the b MRPC exams. '

- The results of bobbin coil dent measurements indicate no significant dent 9rowth since the-last outage. This conclusion is furtt er supported by the ract that no new tubes restricted passage of the 0.560" diameter probe due to denting, and no tubes restricted passage of the 0.549" diameter probe.

~

L L Boric acid treatment of the secondary side was initiated in Jat Jary,1986, to -

help minimize tube denting. Yhe treatment appears to be successful based on the results of this inspection.

t-i,

'=

LIC-92-288R' Attachment TABLE 1 Page 4 LIST OF INDICATIONS Line/ Row -

Indication location *


Steam Generator A ---------------------------

9/44 15% HTS +1.0" 43/94 20% HTS +2.6" 47/6 11% HTS +0.8" 50/35 7% HTS +1.2" 18% HTS +1.9" 52/39- 9% HTS +1.8" 56/37 1% H1S +5.4" 63/76 1% HTS +1.1" 71/42- 25% HTS +0.8"'

73/42 23% HTS +6.3" 125/8 31% CTS +3.5"


Steam Gererator B ---------------------------

27/84 27% CTS +1.7"

-29/4' 1% H1 -0.4" -

~30/87 12V. V1 +14.9"

-33/84 20% C3 +22.5" 38/37 6% HTS +3.9"

-46/27 30% HTS +9.6" 48/39 12% HTS +1.1" .

55/84: 17% HTS +0.3" 57/64 7% C3 45.2"

, 59/68 18%- HTS +2.9" 68/75 5% HTS +1.9" f.9/80 39% H7 +1.8"

'73/80 14% CTS +0.6" 79/36. 7% HTS +'.0" f: .79/78 14% CTS +11.8" 83/88' 14% H7 +2.7" 5% H7 +3.0"

'96/21 12% HTS +5.3"

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