IR 05000313/1982017
| ML20055B965 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 07/08/1982 |
| From: | Randy Hall, Hunnicutt D, Tomlinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20055B961 | List: |
| References | |
| 50-313-82-17, NUDOCS 8207230661 | |
| Download: ML20055B965 (4) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-313/82-17
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Docket:
50-313 License:
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Licensee: 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:
June 1-3, 1982 r/[w l - O Rf>>
Inspector:
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D. P. Tonrrinson, Reactor Inspector, Engineering Section Date Reviewed: A 7- (- 74
R. E. Hall, Ch'ief, Reactor Project Section C Date Approved:
NN _2[whW 7[8[8:2, D. M. Hunnicutt, Chief, Engineeririg Section D'a te'
Inspection Summary Inspection conducted June 1-3, 1982 (Report 50-313/82-17)
Areas Inspected:
Special, announced inspection of the nondestructive examination of four high pressure injection nozzles.
This inspection involved 20 inspector-hours by one NRC inspector.
Results: Within the area inspected, no violations or deviations were identified.
8207230661 820709 PDR ADOCK 05000313 G
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-2-DETAILS 1.
Persons Contacted Principal Licensee Employees
- J. M. Levine, General Manager
- E. C. Ewing, Production Engineering Superintendent
- M. J. Bolanis, Health Physics Superintendent
- E. L. Sanders, Maintenance Manager
- L. Schempp, Manager Nuclear QC
- K. Coates, Mechanical Maintenance Supervisor
- L. W. Humphrey, Administrative Manager
- P. Jones, I&C Supervisor NRC Personnel
- W. D. Johnson, Senior Resident Reactor Inspector
- L. J. Callan, Resident Reactor Inspectcr The NRC inspector also contacted other personnel including members of the administrative, engineering, and QA/QC staffs.
- Deno'es those attending the exit interview on June 3, 1982.
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2.
Repair of HPI Nozzles NRC Reports 50-313/82-06 and 50 313/82-08 stated the conditions which were noted during the inspection and repair of four high pressure injection nozzles on the Unit I reactor coolant system piping.
During these previous inspection periods, the NRC inspector monitored or witnessed the radiography, liquid penetrant, and ultrasonic examinations and the nozzle repair operations.
During the current inspection period, the NRC inspector conducted a detailed review of all the records related to this inspection and repair.
A total of seven welded joints were produced on the three HPI lines that required major repairs.
The safe-end to nozzle weld, the safe end to elbow weld, the elbow to pipe weld, and one new pipe to pipe weld were accomplished on Loop "A."
Loop "B" required replacement of the safe end to elbow weld only, and Loop "D" required the safe-end to nozzle weld and safe-end to elbow weld.
The personnel records indicated that each of the ten welders was qualified to the proper procedures at the time these welds were made.
The detailed operational sheets for each operation were complete and contained quality control (QC) signatures for each step of the repairs.
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' The NRC inspector reviewed 'the material certifications for the four lots of weld filler material, backing ring material, two safe-ends, and two thermal sleeves.
Each certification indicated that the chemical analysis and mechanical. test results were within the acceptable limits for each material. The material certifications were checked for the liquid pene-trant materials to assure that they did not exceed the requirements for sulfur and halogen content.
The NRC inspector reviewed the calibration records for all of the measurement and alignment tools used, including dial indicators, tong testers, surface thermometers, pyrometers, micro-
' meters, and torque wrenches.
Each had been calibrated recently, and each calibration was performed by a laboratory claiming traceability to the National Bureau of Standards.
Included in the record package were the results of the solubility tests conducted on the rice paper material which was used for purge / debris dams in the piping.
Followi.ng the documentation review, the NRC inspector reviewed all of the radiographs (39) associated with the rework. This consisted of one expo-sure on each safe-end (to assure that the thermal sleeve rolling operation had been performed and that the safe-end to thermal sleeve contact was adequate) and five exposures on each of the seven welded joints.
Each radiograph was reviewed to ascertain that at least the minimum' film' quality requirements were met. This included verification of film densities, pene-trameter selection, penetrameter placement, proof of coverage, and film identification. A second examination was conducted to verify that correct interpretation of the indications was made. An independent evaluation was made of each radiograph and the results were compared to the B&W interpre-tations. No discrepancies were identified.
No violations or deviations were noted during this portion of the inspection.
3.
Inspection of Steam Generator Tubing Because a leaking steam generator tube was discovered, AP&L decided to perform a partial inspection of the
"A" steam generator tubing.
The leaking tube was determined to be in the peripheral row adjacent to the inspection lane. As this area of the steam generator is historically the most susceptible to leaks, AP&L decided to fully examine three rows of tubes on each side of the inspection lane and to randomly examine other tubes in the bundle. Approximately 500 tubes were examined using the eddy current method. Three hundred and eighty-five of these tubes were in the ~ area adjacent to the lane, and the remaining 115 were dispersed throughout the tube bundle.
The preliminary results of this examination indicate that nine additional tubes registered sufficient degradation to warrant permanent plugging.
These nine are in addition to the one leaking tube. The preliminary results show a wall reduction varying from 33% to 89% of the original wall thickness. All of the tubes exhibiting a reject.able wall thickness loss are in the inspection lane area.
.one of the randomly selected tubes were rejecte *
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_4 The NRC inspector reviewed eight B&W procedures relative to the eddy current inspection of once-through steam generator (OTSG) tubing and found no dis-crepancies with the requirements of ASME Section XI, 1974 Edition with Addenda through Summer 1975.
No further review was conducted as the final inspection results had not been fully evaluated nor the report issued.
j No violations or deviations were noted during this portion of the inspection.
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Exit Interview The NRC inspector met with the licensee representatives (denoted in para-graph 1) on June 3, 1982, to discuss the scope and findings of the inspection.
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