IR 05000369/1979038
| ML19210E686 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 11/01/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19210E677 | List: |
| References | |
| 50-369-79-38, NUDOCS 7912050532 | |
| Download: ML19210E686 (3) | |
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'o UNITED STATES 8"
g NUCLEAR REGULATORY COMMISSION o
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aE REGION 11
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o, 101 MARIETTA ST., N.W., TUITE 3100 ATLANTA, G EORGIA 30303
NOV - 51579 Report No. 50-369/79-38 Licensee: Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name: McGuire Nuclear Station Docket No. 50-369 License No. CPPR-83 Inspection at McG (r s'te near Charlotte, North Carolina Inspecto.
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// / 7f B. R. Crowley Date Signed Approved by:
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///e[7f A. R. Herdt, RC&ES Branch Date Signed SUMMARY Inspection on October 22-23, 1979 Areas Inspected This special, unannounced inspection involved 7 inspector-hours onsite in the area of steam generator feedwater line radiography (RT) - Bulletin 79-13.
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Results No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees J. C. Rogers, Project Manager
- G. W. Grier, Project Engineer - Construction
- E. B. Miller, Project Senior QA Engineer
- M. S. Starnes, Senior QC Engineer R. P. Ruth, Station Senior QA Engineer M. W. Sample, Licenseeing and Projects Engineer T. M. Hilderbrand, Level II Examiner P. J. Helton, Operations QC Inspector
- W. R. Gillespie, Senior QA Technician Other Organizations R. J. Reed, Westinghouse Site Representative (Catawba)
- Attended exit interview 2.
Exit Interview The inspector met with licensee representatives noted in paragraph 1 above at the conclusion of the inspection on October 23, 1979.
The inspector summarized the scope and findings of the inspection of Bulletin 79-13 and the licensee was advised that no items of noncompliance or deviation were identified during the inspection.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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IE Bulletin (IEB)
(0 pen) IEB 79-13, Cracking in Feedwater System Piping, Unit 1.
Duke Power Company responded to IEB 79-13 by letters dated September 19 and October 19, 1979 and is in the process of performing RT inspection of feedwater nozzle welds and adjacent base material to meet bulletin requirements.
The RT is being performed in accordance with Duke procedure NDE-10, Revision 3, "
General Radiography Procedure" except that evaluation is to the 1977 edition of article NC-5000 of Section III of the ASME Boiler and Pressure Vessel Code and the 2T penetramenter sensitivity level is being used.
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-2-The McGuire steam generators are designed with separate auxiliary feedwater nozzles.
Both the auxiliary feedwater nozzle and the main feedwater nozzles are welded to 90-degree elbows. RT of the nozzle base material to the desired sensitivity level for both nozzles is very difficult because of design. For the main feedwater nozzle, in addition to a drastic change in thickness in the area of interest (2 base material thicknesses from the weld), there is a diffuser inside the nozzle that covers part of the area of interest.
The auxiliary nozzle also charges thickness in the area of interest and has a clad buildup on the inside that covers part of the area of interest.
On both nozzles two shots are being used to cover the full area of interest to the best extent possible with the design limitations.
At the time of the inspection, the licensee had completed working out the RT technique and main feedwater nozzle to elbow weld (Weld CFI718, ISO MCFI-1CF10) and the auxiliary feedwater nozzle to elbow (Weld CAIF575, ISO MCFI-1CA16) for generator "A" had been radiographed but not fully evaluated.
The inspector reviewed the radiographs for these two welds and compared the design indicated on the film with that observed on similar typical nozzles on Unit 2 that had not been welded.
Within the areas inspected, no items or noncompliance or deviation were identified.
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