ML20244B956
| ML20244B956 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 06/09/1989 |
| From: | Morris K OMAHA PUBLIC POWER DISTRICT |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LIC-89-383, NUDOCS 8906140067 | |
| Download: ML20244B956 (9) | |
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OrnahJ Public Power District i
1623 Harney Omaha, Nebraska 68102 2247 l
402/536 4000 June 9, 1989 LIC-89-383 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station PI-137 Washington, DC 20555
Reference:
Docket No. 50-285 Gentlemen:
SUBJECT:
1988 Steam Generator Eddy Current Test Report The Omaha Public Power District (0 PPD) submits the enclosed summary of Steam Generator Eddy Current Testing performed during the 1988 Refueling Outage.
This report fulfills the eddy current reporting requirements of Fort Calhoun's Technical Specifications, Section 3.17(5)(ii).
If you have additional questions on this matter or require additional information, please contact me or members of my staff.
Sincerely, 4
K. J.
orris Division Manager Nuclear Operations KJM/jak Attachment c:
LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector gqo6 Q h h P
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L' Attachment FORT CALHOUN STATION STEAM GENERATOR EDDY CURRENT TEST REPORT 1988 REFUELING OUTAGE INTRODUCTION This report summarizes steam generator eddy current results obtained during the 1988 refueling outage. Summaries of results of the two previous eddy current inspections were submitted to the Commission in the following documents:
"Special Report on Steam Generator Denting Derived from 1985 Eddy Current Inspection Data for the fort Calhoun Station," LIC-86-041, dated February 21, 1986.
l
" Fort Calhoun Station Steam Generator Eddy Current Test Report - 1987 Refueling Outage," LIC-87-665, dated November 5, 1987.
DESCRIPTION OF EXAMINATION Combustion Engineering conducted an inservice eddy current examination of the steam generator tubing at Fort Calhoun Station in October of 1988. The examination program included multi-frequency testing for indications of degradation, dents, and dent profilometry in Steam Generators A and B.
l" The examination program was conducted to meet and exceed the requirements of the Technical Specifications and was subdivided into three discrete tube populations. Testing was performed from the outlet side of each steam L
generator in the following populations:
1 1
1.
Tubes in Row 74 and above were examined to determine any further progression of tube degradation and denting in the vertical support (VS) l region. This includes 882 tubes in Steam Generator A and 880 tubes in Steam Generator B.
2.
A random selection of 151 tubes in Steam Generator A and 150 tubes in Steam Generator B were examined, including all tubes with previous indications of l
20-40%.
3.
Dent profilometry examination of 121 tubes in Steam Generator A and 192 i
tubes in Steam Generator B was performed for evaluation of the vertical supports VI, V2, and V3.
The tubes in population 1 and 2 were examined at full length using a standard bobbin probe. The inspection patterns are shown on Figures 1 and 2.
Support l
notation for the steam generator is shown on Figure 3.
The probe design L
incorporates magnetic saturation capabilities to minimize indications from magnetic permeability variations commonly found in Inconel 600 tubing. Tubes determined to have deformation sufficient to restrict the passage of the 0.560 l
inch diameter probe were reinspected using a 0.540 inch diameter probe to determine the presence of tube wall degradation or other restrictions.
l 1
'The recorded multi-frequency eddy current data was analyzed for the
. presence.of defect indications. Tube wall degradation was evaluated using the phase analysis technique for determination of the origin and per-centage'of tube wall loss represented by the indication. The data was independently analyzed by two groups of certified Level IIA data l
analysts. Discrepancies between the two sets of evaluation results were reviewed and resolved by a Level III eddy current examiner.
The examination was conducted with a Zetec MIZ-18 digital eddy current acquisition system and analyzed utilizing a Zetec DDA-4 digital data analyzer. The frequencies utilized during the examination were as follows:
400 KHz differential and absolute 100 KHz differential and absolute 600 KHz differential and absolute 10 KHz differential and absolute 400/100 KHz differential mix The primary frequency of 400 KHz satisfies the requirements of the ASME Boiler and Pressure Vessel Code for the examination of nonferromagnetic steam generator tubing. The 400 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 600 KHz frequency is provided to assist the analysts with additional mixing capabilities in-the event of excessive OD tube deposits. The 10 KHz is provided to facilitate locating the probe position in the generator and for possible further use in Computer Data Screening (CDS). The 400/100 KHz mix is used to eliminate the tube support signal and OD tube deposits. Other mixes are performed as required by the data analyst.
A total of 313 tubes (Population 3) were examined in 1988 with the 8 coil profilometry probe. The profile probe has an advantage over the standard l
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.
This.is important at eggcrates and vertical supports where bobbin coil tends to be nonconservative in the measurement of denting.
1 l
2 L-_-_-_-_____---_-_-_______-___
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RESULTS OF THE EXAMINATION Defect Examination: There were no tubes in either steam generator containing degradations greater than or equal to 40%. No indications of degradation were detected at the vertical support 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 support region of both steam generators.
Results of the bobbin coil dent measurements indicate that there has been no significant dent growth since the last inspection. Since vertical supports and eggcrate intersections show poor correlation between dent size and eddy current voltage, profilometry data presents a more accurate assessment of the size and progression of dents at VI, V2, and V3.
For this reason, the results of the profilometry examination are included in this report for dent comparison.
Tubes determined to have deformation sufficient to restrict the passage of the 0.560 inch diameter probe were reinspected with a 0.540 inch diameter probe to determine the presence of tube wall degradation or the presence of other restrictions in the uninspected region of the tube. During the 1988 examination, there were no tubes that restricted passage of a 0.540 inch diameter probe.
Profilometry Examination:
Results from the profilometry examination show no significant dent growth over the last cycle. Table 2 shows the dent growth since the last outage. Data from 1987 was reanalyzed by the same analyst that evaluated the 1988 data to provide a consistent comparison.
Since dents do not typically decrease in size, this information indicates the degree of variability possible in the average data when a large number of data points are used.
CONCLUSIONS No tubes required plugging during the 1988 refueling outage because there were no tubes in either steam generator containing degradations greater than or equal to 40% through wall, no indications of degradation in the vertical support region, and no tubes that restricted passage of a 0.540 inch diameter probe.
The results of bobbin coil and profilometry dent measurements indicate no significant dent growth since the last outage.
Boric acid treatment of the secondary side was initiated in January, 1986, to help minimize tube denting. The treatment appears to be successful based on these results and is being continued for the current cycle.
3
l I
TABLE 1 List of Indications The following tubes were found to have wall degradation as indicated:
Steam Generator A line/ Row Indication location 40/87 8%
CTS + 36.2" 43/94 33%
HTS +
2.6" 73/42 10%
HTS +
6.4" 1
125/8 17%
CTS +
2.9" Steam Generator B Line/ Row Indications location 26/75 6%
CTS +
1.0" 27/84 21%
CTS +
0.9" 32/83 22%
H4 + 14.1" 33/84 24%
C3 + 22.6" 57/64 16%
C3 +
5.1" 62/57 31%
C1 + 15.0" 76/83 1%
C3 + 22.8" 83/88 17%
H7 +
2.3" (REFERENCE FIGURE 3 FOR ABBREVIATIONS) 4 L________________________-__.-____
L 1-1 TABLE 2 Profilometry Examination Results Steam Generator A Average Dent (in mils)
Eleyation 1281 1288 V1 26.7 22.9 V2 10.9 10.1 V3 4.9 5.3 Steam Generator B Average Dent (in mils)
Elevation 193 2 1988 V1 34.3 31.0 V2 4.2 5.5 V3 6.5 9.3 o
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