IR 05000498/1981029
| ML20010H960 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 09/01/1981 |
| From: | Gilbert L, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010H938 | List: |
| References | |
| 50-498-81-29, 50-499-81-29, NUDOCS 8109290449 | |
| Download: ML20010H960 (3) | |
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
Report No. 50-498/81-29; 50-499/81-29 Dockets: 50-498; 50-499 Category A2 Licensee: Houston Lighting and Power Company Post Office Box 1700 Houston, Texas 77001 Facility Name: South Texas Project, Units 1 and 2 Inspection at: South Texas Project, Matagorda County, Texas Inspection Conducted: August 17-20, 1981 i
Inspector:
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' y L. D. Gilbert, Reactor Inspector, Engineering and Date Materials Section
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Approved:
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R. E. Hall, Acting Chief, Engineering and Materials Date Section Inspection Summary:
Inspection on August 17-20, 1981 (Report 50-498/81-29; 50-499/81-29)
Areas Inspected: Routine, unannounced inspection of construction activities including site tour and welding of safety-related piping and supports.
The inspection involved 26 inspector-hours by one NRC inspector.
Results:
In the two areas inspected, no violations or deviations were identified in one area. One violation was identified in the area of eye examinations for inspection personnel (violation - failure to follow procedure for recording vision examinations - paragraph 3.a).
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DETAILS 1.
Persons Contacted Principal Licensee Employees J. E. Geiger, Site QA Manager
- G. A. Marshall, QA Mechanical Specialist Other Personnel
- F. Hiller, Chief, Welding Engineer, Brown an<i Root (B&R)
- A. W. Smith, Project QA Manager, B&R
- F. W. Rothermei, Assistant Project Manager Special Project, B&R J. Roberts, Supervisor Mechanical Quality Engineer, B&R D. Furr, QA Training Coordinator, B&R The NRC inspector also contacted other licensee and contractor employees including members of the QA/QC and engineericq staffs.
- Denotes those attending the exit interview.
2.
Site Tour The NRC inspector walked through the Reactor Buildings for Units 1 and 2 and Mechanical-Electrical Auxiliary Building for Unit 1 to observe construction activities in progress and to inspect for housekeeping.
No violations or deviations were identified.
3.
Safety-Related Piping and Supports a.
Observation of Work The NRC inspector observed activities related to welding of the Component Cooling Water Pump Support pads that were relocated to comply with Nonconformance Report No. S-M3966.
Two of the pads were in the process of being welded and were identified as Welds 0001 and 0004 on Drawing FSP 0318, Sheet 1, Revision 0.
Welding was being performed in accordance with WPS 2098 using the shielded metal-arc welding promess and E7018 electrode with a 2000F preheat temperature.
In the areas of weld and inspection doc" mentation, procedure compliance, welder qualification, and filler material control; no discreoancies were noted.
During review of inspectors certification records, an incomplete eye examination record was noted and further sampling resulted in approximately nine
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additional discrepancies from the requirements of Procedure ST-QAP-2.1 for recording vision acuity examinations. The eye examination record discrepancies consisted of the following:
(1)
Incomplete vision acuity test results, in that, uncorrected or corrected vision was not indicated.
(2)
Incorrect vision acuity test results, in that, uncorrected or corrected vision was incorrectly indicated.
This is an apparent violation of 10 CFR 50 Appendix B, Criterion V for failure to follow procedure.
b.
Review of Welder Qualification The NRC inspector observed Perfomance Qualification Test (PQT)
4086 for retesting welder ASI on small diameter stainless steel pipe in the GG position using the gas tungsten-arc welding process.
Qualification testing was consistent with the requirements of B&R Procedure MECP-1 and ASME B&PV Code Section IX except for an error noted in the radiographic acceptance criteria of B&R Procedure ST-QAP-9.111, Revision 0.
The procedure specified that the allowable size for slag inclusions was 1/3 inch for thickness up to 3/8 inch, whereas, the ASME B&PV Code Section IX require-ment is only 1/8 inch'for this thickness.
Since this wa' an obvious typographical error, the item is con-sidered unresolved pending a correction to the procedure and re-evaluation of previously accepted radiographs for performance qualification tests evaluated to the incorrect acceptance criteria.
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Unresolved Items Unresolved items are matters about which more infomaticn is required in order to ascertain whether they are acceptable items, violations, or deviations. An unresolved item related to welder qualification testing is discussed in paragraph 3.b.
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Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1)
on August 20, 1981, and summarized the purpose and findings of the inspec-tion.