IR 05000445/1982022
| ML20028B693 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 11/02/1982 |
| From: | Hunnicutt D, Roberds M, Stewart R, Tomlinson D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028B690 | List: |
| References | |
| 50-445-82-22, NUDOCS 8212030156 | |
| Download: ML20028B693 (4) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
50-445/82-22 Dockets:
50-445 Category A2-Licensee: Texas Utilities Generating Company 2001 Bryan Tower Dallas, Texas 75201 Facility Name:
Comanche Peak, Unit 1 Inspection at:
Comanche Peak Steam Electric Station Inspection conducted: October 19-20, 1982 i
Inspectors:
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D. P. Tomlinson)-frsattor Inspector, Engineering Section Date (Paragraphs 1, 2, 3, 4, 5)
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R. C. Stewart, W actor Inspector, Reactor Project Date Section A (Paragraphs 1, 3, 5)
W-A A]-82-% M.' J. R6penisT Enginerring Technician, Engineering Date l Sectidn (Paragraphs 1, 2, 5) Reviewed: ' '/ [ [4- //-7-8 % T F. Westerman, Chief, Reactor Project Section A Date Approved: eb b C .7,[82.
D. M. Hunnicutt, Chief, Engineering Section / Date
Inspection Summary: l Inspection During October 19-22, 1982 (Report 50-445/82-22) Areas Inspected: Routine, unannounced inspection of construction activities.
! The inspection involved 36 inspector-hours onsite by three NRC inspectors.
! Results: In the area inspected, no violations or deviations were identified.
! l 8212030156 821110 PDR ADOCK 05000445
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- R. G. Tolson, Site QA Supervisor, TUGC0
- C. T. Brandt, QA/QC Supervisor, TUGC0
- M. R. McBay, Engineering Manager, TUSI R. Blackett, Staff Assistant for Special Projects, TUGC0
L. Yates, Welding Technician, TUGC0 Other Personnel G. R. Purdy, Site QA Manager, Brown & Root (B&R) B. O. Cromeans, QA Supervisor, B&R The NRC inspectors also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
l 2.
Potential Source Inspection Breakdown Information Notice 82-34, dated August 20, 1982, was sent to all holders of power reactor operating licenses or construction permits as early notification of a potentially significant problem with vendor supplied l welded control panels.
The Licensee conducted a visual inspection of the welds on all control panels onsite supplied by the vendors in question.
It was noted by the licensee that the accessible welds on these panels exhibited conditions that were in conflict with the acceptance criteria of American Welding Society (AWS) Standard D1.1.
These anomalies were verified by the NRC inspector and documented in Inspection Report 50-445/82-19.
These findings along with the discovery that other welded items supplied by other vendors, all of which were subject to TUGC0 source inspection, had been received onsite with unacceptable welds.
The licensee, noting that a potential program breakdown could exist, has voluntarily begun a reinspection of these vendor supplied welded components and a comprehensive review of source inspection activities.
A total of 122 components fabricated by Chicago Bridge and Iron (CB&I) have been identified among those requiring reinspection.
Of these, only 12 are listed as being completed with the record packages forwarded to the storage vault.
The CB&I components have been identified and located, but the visual examination had not begun at the close of this inspection period.
The NRC inspectors chose not to examine these components until completion of the TUGC0 examination.
Pending the completion and reporting of the reinspection in progress by TUGCO, this will remain an unresolved item.
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3.
Followup on Potentially Reportable 50.55e Item ' On September 30, 1982, the licensee verbally notified the Senior Resident Inspector, Construction, (SRIC) of a potentially reportable construction deficiency involving structural welding performed by NPS Industries.
This item is directly related to paragraph 2, above, of this report.
A member of the TUGC0 welding engineering department was notified by a painter of a previously unreported cracked weld on the NPS Industries supplied main steam pipe-whip restraint located outside the reactor containment building (RCB) 1.
Further investigation disclosed numerous , ' other nonconforming weld conditions in the immediate area.
A thorough inspection of all welds on this structure was conducted by the TUGC0 weld-ing engineering department personnel documented on NCR M-82-01589.
An engineering analysis of the deficient welds has been initiated to determine their structural significance.
The NRC inspectors toured the structure and visually examined approximately 75% of the vendor supplied welding.
Anomalies such as undercut, lack of fusion, porosity, incomplete welds, undersize welds, overlaps, insufficient weld throats, and base material defects were noted in most sections of the structure.
In some cases, the discrepancies were lengthy, in other cases, the discrepancies extended for only a very small percentage of the total weld length; and in some cases the weld was free of discrepancies. The NCR deficiency tabulation does not differentiate between short or lengthy weld de'iciencies but merely lists the individual weld identification numbers and the conditions existing in those welds.
The NRC inspectors did not perform a total visual inspection due to the lack of complete staging around the structure.
The NRC inspectors reviewed seven receiving inspection reports (RIR) related to this pipe-whip restraint.
The inspection found that documen-tation generated by NPS Industries and TUGC0 indicated that all required NDE and visual examinations had been performed with acceptable results. The RIR packages contained no notations for the existing deficiencies.
RIR numbers 16756, 16826, 16896, 17033, 17112, and 17156 were each signed by one of the three TUGC0 source inspectors as having been inspected and that the welding did comply with AWS D1.1 requirements.
As was stated earlier, this item is directly related to the potential source l inspection program Dreakdown discussed in paragraph 1 of this report.
Pending completion of the TUGC0 engineering analysis and disposition of the weld discrepancies, this will remain an unresolved item.
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4.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, violations, or deviations.
An unresolved item related to potential cource inspection program breakdown is discussed in paragraph 2.
A second unresolved item , related to a potentially reportable item is discussed in paragraph 3.
5.
Exit Interview The NRC inspectors met with licensee representatives (denoted in paragraph 1) and R. G. Taylor (NRC Resident Reactor Inspector) on October 20, 1982, and summarized the scope and findings of the inspection.
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