IR 05000368/1979019
| ML19256E563 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear |
| Issue date: | 09/28/1979 |
| From: | Gilbert L, Randy Hall, Tomlinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19256E559 | List: |
| References | |
| 50-368-79-19, NUDOCS 7911080040 | |
| Download: ML19256E563 (3) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
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Report No. 50-368/79-19
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Doc' ?t No. 50-368 License No. NPF-6 Licensee:
Arkansas Power and Light Company P. O. Box 551 Little Rock, Arkansas 72203
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Facility Name: Arkansas Nuclear One (AN0), Unit 2 Inspection At: AN0 Site, Russellville, Arkansas Inspection Conducted: September 25, 1979 Inspectors:
9/.27/79 L. D. Gilbert, Reactor Inspector, Date/
Engineering Support Section 1*'
bA99 4 26 ~l')
DT P. TonitTnso'n,' Reactor Inspector, Date Engineering Support Section Reviewed By:
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f/2f/ 9 W. D. Johnson, Resident Reactor Inspector Date Approved By:
7f R. E.' Hall, Chief, Engineering Support Section Date /
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lb 9/ 21/ 79 T. F. Westerman, Chief, Reactor Projects Section Date
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Inspection Summary Inspection conducted on September 25, 1979 (Report No. 5C-368/79-19)
Areas Inspected:
Routine, unannounced inspection of followup to IE Bulletin No. 79-13. The inspection involved eight inspector-hours on-site by two NRC inspectors.
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Results: Within the one area inspected, no items of noncompliance were identified.
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DETAILS 1.
Persons Contacted
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Arkansas Power and Light Company
- G. H. Miller, Engineering & Technical Support Manager
- J. R. Anderson, Acting QC Supervisor E. C. Ewing, Production Engineering Superintendent C. Shively, Plant Performance Engi reer
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Peabody Testing
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R. A. Jones
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- Denotes those attending the exit interview.
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Followuo to IEB 79-13 (Unit 2)
The IE inspectors reviewed the radiographic examination records for the two steam generator feedwater nozzle to pipe welds, including adjacent pipe and nozzle areas. Compliance with IE Bulletin No. 79-13, including use of the 2T penetrameter sensitivity level with system void of water was verified. The radiographs were identified as weld No. 017-001 on CE Drawing C 6370-501-064, Revision 2, and Weld No. 019-001 on CE Drawing C 6370-501-063, Revision 2.
In addition to the shop fabricated nozzle to pipe weld on eacn steam generator, the adjacent pipe to pipe field weld, which was located approximately 2-1/2 inches from the nozzle to pipe weld, was also radiographed and evaluated to the requirements of IEB 79-13.
The pipe to pipe welds were identified as Weld Nos.11 and 12 on ISO Drawing 2DBB l-2, Revision 12F23 and 2DBB 2-2, Revision 9F19, respec-tively.
In the areas inspected, no discrepancies with the requirements of IE Bulletin No. 79-13 were noted.
No items of noncompliance were identified.
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Exit Interview
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The IE inspectors met with Messrs. G. H. Miller and J. R. Anderson on September 25, 1979 to summarize the scope and findings of the inspection.
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