IR 05000382/1981022
| ML20010H899 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/31/1981 |
| From: | Randy Hall, Tomlinson D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010H888 | List: |
| References | |
| 50-382-81-22, NUDOCS 8109290396 | |
| Download: ML20010H899 (3) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION OfrICE OF INSPECTION AND ENFORCEhENT
REGION IV
Report:
50-382/81-22 Docket:
50-362 Category A2 Licensee:
Louisiana Power and Light Company 142 Delaronde Street New Orleans, Louisiana 70174 Facility Name: Waterford Steam Electric Station, Unit 3 Inspection at: Waterfo J Site, Taft, Louisiana Inspection Conducted:
August 10-14, 1981
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Ir.ipector:
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D. P. TomHfison, Reactor Inspector, Engineering Date and Materials Section Other Accompanying Personnel:
W. C. Seidle, Chief, Engineering Inspection Branch (August 13-14,1981)
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Approved:
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R. E. Hall, Acting Chief, Engineering and Materials Date Section Inspection Summary:
Inspection Conducted August 10-14, 1981 (Report 50-382/81-22)
Areas Inspected:
Routine, unannounced inspection and observation of construc-tion welding activities.
This inspection involved 27 inspector-hours by one NRC inspector.
Results:
In the areas inspected, no violations or deviations were identified.
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l DETAILS 1.
Persons Contacted Principal Licensee Employees
- L. L. Bass, Project QA Manager
- B. P. Brown, Project QA Engineer
- R. G. Pittman, Project QA Engineer
- R. G. Bennett, Project QA Engineer
- B. M. Toups, Project QA Engineering Technician
- 0. D. Pipkins, Project Coordinator Other Personnel
- G. L. Constable, NRC Resident Inspector
- W. B. Jones, NRC Co-op
- L. A. Stinson, Manager, Site Quality Program (Ebasco)
L. Nunez, QA Supervisor, Chicago Bridge and Iron The NRC inspector also interviewed other licensee and contractor personnel including members of the engineering and QA/QC staffs.
- Denotes those attending the exit interview.
2.
Site Tour The NRC inspector walked through various construction and storage areas to observe construction activities in progress and to inspect the general state of cleanliness and adherence to housekeeping requirements. The tour included the Reactor Building, Reactor Auxiliary Building and the Fuel Handling Building.
No violations or deviations were identified.
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3.
Inspection of the Equipment Hatch Closure Weld The NRC inspector performed a vir al examination of the closure weld on the Containment Equipment Hatci.. The welding and inspection of this weld is being performed by Chicago Bridge and Iron (CB&I). The closure weld is a circumferential full-penetration weld approximately one-hundred and one feet in length that joins the equipment hatch
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with the free standing steel containment. Due to incomplete scattolding,
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only about 75% of the inside and outside weld surfaces could be examined by the NRC inspector. Although the weld surfaces were slightly rough,
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they appeared to be free of undercut, laps, surface porosity, and other surface discontinuities.
The NRC inspector selected forty-five radiographs of this weld for review.
The sample was taken from a total of one-hundred-one shots required to assure full coverage of the weld. Each film was reviewed first to ascer-tain that at least the minimum film quality requirements were being met.
This inspection was to determine the adequacy of film Msities, penetra-meter selection, penetrameter placement, proof of co miage, and film
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identification. A second examination was conducted to verify that correct interpretation of the indications was'being made. An independent evaluation was made of each radiograph and the results were compared to the CB&I interpretations. The radiographic interpretations had been
recorded by CB&I on informal worksheets pending final review by an Ebasco radiography inspector. No discrepancies between the in-process evalua-tion and the requirements of the ASME B&PV Codewere identified by the
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NRC inspector.
This item will be further examined during a subsequent inspection as the radiography, film interpretation, and final field inspection report have not yet been completed.
3.
Potential Construction Deficiency i
The NRC inspector was informed by a licensee representative that several bolts installed in the reactor coolant pump supports had failed during installation. Approximately 1400 bolts of A-490 material are presently installed in the four pump supports. The licensee and Ebasco have begun
analyses to determine the cause of the failures.
Preliminary results indicate that the bolts are satisfactory for this application and that the failure problem is due to improper installation and torquing. The
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licensee is' continuing the evaluation of this problem and will submit a l
30 day report in accordance with 10 CFR 50.55(e).
4.
Exit Interview The NRC inspector met with the licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on August 14, 1981. The-NRC inspector summarized the purpose, scope, and findings of the inspec-tion and emphasized the importance of prompt reporting of potential 10 CFR 50.55(e) items.
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