IR 05000313/1982039
| ML20028G248 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/19/1983 |
| From: | Hunnicutt D, Johnson W, Tomlinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028G242 | List: |
| References | |
| 50-313-82-39, NUDOCS 8302070556 | |
| Download: ML20028G248 (4) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/82-39 Docket:
50-313 License:
DPR-51 Li ce.nse:
Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203 Facility Name:
Arkansas Nuclear One (ANO), Unit 1 Inspection At:
AN0 Site, Russellville, Arkansas Inspection Conducted:
December 27-29, 1982 Inspector:
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/ MAv l " L')-O D. P. To'1tlTihson, Reactor Inspector, Engineering Section Date Reviewed:
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W. D. f nson, Chief, Reactor Project Section C
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I Approved:
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D. M. Huidicutt, Chief ffingineering Section Date -
o Inspection Summary Inspection conducted December 27-29, 1982 (Report 50-313/82-39)
Areas Inspected:
Routine, unannounced inspection of the nondestructive examination of steam generator tubing.
This inspection involved 17 inspector-hours by one NRC inspector.
Results:
Within the area inspected, no violations or deviations were identified.
9302070556 830124 PDR ADOCK 05000313 G
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1 DETAILS 1.
Persons Contacted Principal Licensee Employees J. M. Levine, General Manager
- E. C. Ewing, Engineering and Technical Support Manager Babcock and Wilcox Personnel G. J. Navratil, Outage Supervisor, Level II G. G. Baker, Level II D. N. Bryant, Level II The NRC inspector also contacted other personnel including members of the administrative, engineering, and QA/QC staffs.
- Denotes those attending the exit interview on December 29, 1982.
2.
Inspection of Steam Generator Tubing As a part of the Unit 1 Inservice Inspection Program (ISI), a planned eddy current examination of steam generator tubing was begun during the current refueling shutdown.
Unit 1 has two once-through steam generators (OTSG), each containing approximately 15,000 Inconel-600 tubes.
An inspection team from Babcock and Wilcox was performing a remote eddy current examinatinn of the
"B" steam generator when the NRC inspector arrived at the ANO site.
The inspection of the "A" OTSG had been started but was temporarily halted due to equipment difficulties.
The NRC inspector reviewed Babcock and Wilcox (B&W) Procedure 151-416, Revision 5, for the "Multifrequency Eddy Current Examination of 0TSG Tubing in 177 Steam Generators." The procedure contained the significant examination elements necessary for a meaningful inspection.
The procedures specified the eddy current instrument, the strip chart and magnetic tape recorders, probe alignmeoc and drive devices, and calibration standards to be used.
The NRC inspector observed that all equipment in use was as t
required and that each displayed a current calibration sticker, indicating that calibration had been performed just prior to beginning this inspection.
The NRC inspector did not have an opportunity to observe the initial calibration of equipment but did witness four in progress calibration verification checks as required by paragraph 7.4.5 of the inspection procedure (ISI-416).
In each case the calibration was within the allowable limits and no recalibration or tubing reinspection was
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required.
The inspection personnel identified the beginning and finish of each tube on the magnetic tape and the start of each tube on the strip chart recording.
The NRC inspector also observed three verification checks of the probe position to assure that no manipulator malfunctions had occurred.
All of the above activities were monitored or performed utilizing one or more of the three closed-circuit television cameras mounted in the area where the examination was being performed.
The NRC inspector, while observing the calibration verifications, noted that a multifrequency examination was being performed using 35, 200, 400, and 600 kHZ with a separate trace for each appearing on the storage scope.
These magnetic tapes, upon completion, were transferred with the attendant strip chart recordings to another inspector responsible for the interpre-tation and analysis of the recorded data.
This inspection system provides a permanent record of the existent conditions in each inspected tube that may be retained and reviewed at a later time.
At the end of this inspection period, the examination team had fully inspected the "B" OTSG in the lane area, all peripheral tubes, several inspection expansions around the lane area, and numerous random tubes throughout the tube bundle.
Preliminary analysis of the recordings indicated that approximately half of the 15,000 generator tubes had been inspected with 39 of these exhibiting rejectable indications.
The original ISI plan called for the inspection of 3% of the total tubes in each steam generator but the detection of tubes with a 40% wall reduction or greater necessitated several inspection expansions.
The number of rejectable tubes noted sc far has necessitated the 100% inspection of all tubes in this generator.
The majority of the rejectable indications were found to be in the annular area between the outer wall of the tubing and the upper tube sheet.
Each tube is inserted into the 24" thick upper tube sheet and rolled internally until hard contact is made with the tube sheet.
This contact area extends only a short distance into this tube sheet leaving approximately 22 linear inches of gap between the tube and tube sheet.
Following the rolling operation each tube is seal welded to the tube sheet. Most of the wall reduction indications found in the upper tube sheet area gave the appearance of an isolated pitting condition.
In some cases, however, several indications were noted but their appearance was that of isolated attacks and not a general corrosion condition.
The NRC inspector reviewed the personnel qualification records of two Data Analysts, two Level II inspectors, and two Level I inspectors.
This review and informal interviews with the individuals indicated that each had sufficient education, experience and knowledge of the requirements to perform at the levels specified.
l No violations or deviations were noted during this inspection.
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2.
Exit Interview The NRC inspector met with the licensee representative (Denoted in paragraph 1) on December 29, 1982, to discuss the scope and findings of the inspection.
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