IR 05000566/1979017
| ML19260D912 | |
| Person / Time | |
|---|---|
| Site: | Yellow Creek  |
| Issue date: | 11/28/1979 |
| From: | Crowley B, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19260D860 | List: |
| References | |
| 50-566-79-17, 50-567-79-17, NUDOCS 8002120591 | |
| Download: ML19260D912 (5) | |
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ATLANTA, G EORGIA 30303 NOV 3 01979 Report Nos.
50-566/79-17 and 50-567/79-17 Licensee: Tennessee Valley Authority 500A Chestnut Street Chattanooga, Tennessee 37401 Facility Name:
Yellow Creek Nuclear Plant Docket Nos.
50-566 and 50-567 License Nos.
CPPR-172 and CPPR-173 Inspection at Yellow Creek site near Iuka, Mississippi Inspector:
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B.'R. Crowley
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Dite Signed'
Approved by:
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A. R. Herdt, Section Chief, RC&ES Branch
'Date' Signed SUMMARY Inspection on November 5-7, 1979 Areas Inspected This routine unannounced inspection involved 18 inspector-hours onsite in the area of containment welding.
Results In the one area inspected, one item of noncompliance was found (infraction -
failure to perform proper chemical analysis on submerged are welding materials, paragraph 8.e. ).
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DETAILS 1.
Persons Contacted Licensee Employees
- H. M. Price, Project Macager L. S. Cox, Construction Engineer
- C G. Wages, Assistant Construction Engineer - QC
- M. F. Steakley, Supervisor Welding QC Unit
- R. D. Briggs, Supervisor Mechanical QC Unit
- L. G. Hebert, OEDC QA Staff M. H. Partes, Associate Engineer - QC Other licensee employees contacted during this inspection included construc-tion craftsmen, technicians, security force members and office personnel.
Other Organizations Chicago Bridge and Iron Company (CB&I)
L. Salvage, QA Technician
- Attenied exit interview.
2.
Exit Interview The inspector met with licensee represen'.atives noted in paragraph 1 at the conclusion of the inspection on November 7, 1979. The scope and findings of the inspection of containment welding were summarized.
The inspector identified to the licensee one unresolved item relative to the chemical analysis for,ubmerged arc welding materials (see paragraph 8.e).
After further review at the RII offices, the unresolved item was upgraded to an item of noncompliance.
This information was transmitted to the licensee by telephone on November 14, 1979.
3.
Licensee Actior on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unrescived items were not identified during this inspection.
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5.
Independent Inspection Effort The following areas of interest were examined by the inspector:
a.
A general plant tour was made and general construction activities and conditions observed in the following areas:
Reactor Building sites (Units 1 and 2);
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QA storage area for piping; and
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CB&I subassembly area.
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b.
Two TVA welders were observed in the process of qualifying; one on test SM-5-B-3-L and the other en ;est SM-3-0-3-L.
At the time of the inspection, welding of the test assemblies had been completed and bend tests were being performed. The qualification activities were compared with requirements of the applicable TVA procedure, process specitication 1.M.2.2(a), " Welder and Welding Operator Performance Qualification".
Within the areas inspected, no items of noncompliance or dcviations were identified.
6.
Steel Structures and Supports - Welding Procedure Specificatiota and Quality Assurance Procedures (Units 1 and 2)
The steel containment structures are being fabricated by CB&I. The inspector reviewed CB&I containment Welding Procedure Specifications (WPS) and qua'.ity assurance procedures to determine whether specifications and procedtres have been established, qualified and controlled in accordance with NRC requirements, SAR commitments, licensee's QA program, and ASME code require-meuts, as applicable. The applicable code for this welding is the ASME Boiler and Pressure Vessel Code,Section III, Subsection NE, 1974 Editian with addenda through the summer of 1976. The-areas reviewed were as follows:
a.
Quality related procedures were reviewed to determine whether the contractor had established procedures for preparation, qualification, approval / certification, distribution and revision of welding procedure specifications. The following procedure was reviewed:
" Nuclear Quality Assurance Manual For ASME Section III Products" Division 4, Section 8.
b.
Welding procedure specifications EH14/860 0.D./74200, E70S-2/E7018/74200, and EH14(AGW)/860 0.D./74200 were reviewed to determine:
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Conformance with control procedure of paragraph b. above.
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Whether essential, supplementary, and nonessential variables are
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defined in accordance with code requirements.
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Whether the selected WPS's have been qualified in accordance with
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code requirements and the supporting procedure qua14fication records (PQR) are adequate and available as req-ired.
Whether the PQr s for the selected procedures lists essential
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variables and che values of these variables are consistent with those permitted by the WPS within the limits of the applicable code.
Whether mechanical tests required by the applicable codes have
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been perfo rmed, properly documented, and meet applicable code requirements.
Whether the PQR's have been approved / certified by the licensee.
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Whether changes in essential and nonessential variables have been properly documented and supported by requalification and/or WPS revision as applicable.
Whether selected WPS's comply with Regulatory Guides committed to
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in the SAR.
Within the areas inspected, no items of noncompliance or deviation were identified.
7.
Steel Structures and Supports - Visual Examination of Welds (Unit 1)
The inspector visually examined and reviewed quality records for completed containment structural field welds as described below to determine if appli-cable code and procedure requirements were being met. See paragraph 6 above for the applicable code.
a.
The following welds were visually examined relative to:
location, length, size and shape; surface finish and appearance including grinding and surface thinning; transition between plates of different thickness; reinforcement; permanent attachments; removal of temporary attachments; and surface defects:
ASSY. B-1:
Seams A-1 and A-2 ASSY. B-4:
Seams A-1 and A-2 Bottom Plate: Seams D-1 and D-4 b.
Quality records for the following welds were reviewed to determine whether:
(1) the records covering visual and dimensional inspections indicated that the specified inspections were completed (2) records reflected adequate weld quality, and (3) weld history records were adequate:
Bottom Plate:
Seam D-4 ASSY. B-4:
Seam A-1 ASSY. B-1:
Seam A-2
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The records reviewed for these welds included " Record Drawing", " Record Drawing Table" and radiographic film.
Within the areas inspected, no items of noncompliance or deviations were identified.
8.
Steel Structures and Supports - Welding Material Control (Units 1 and 2)
The inspector reviewed the CB&I program for control of welding materials to determine whether materials are being purchased, accepted, stored and handled in accordance with QA procedures and ASME code requirements. See paragraph 6 above for the applicable code. The following specific areas were examined:
a.
Purchasing procedures b.
Receiving, storing, distributing and handling procedures c.
Material identification d.
Inspection of welding material issuing stations Welding material purchasing and receiving records for the following e.
materials were reviewed for conformance with applicable procedures and code requirements:
(1) Submerged Arc -
EH14 Wire: Ht. 036057 Flux: Lot Code HH (2) Shielded Metal Arc
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E7018: Ht. 401H0961 During review of material certification records for the above submerged arc material, the inspector noted that a chemical analysis was not performed on a weld deposit of the combination of materials being certified as required by paragraph NE-2432.1(b) of the summer 1975 addenda to subsection NE of Section III of the ASME Boiler and Pressure Vessel Code. This is considered to be noncompliance with paragraph (a)(1) of 10 CFR 50.55a as implemented by paragraph 3.8.2.2 and 3.8.2.6 of the Yellow Creek Nuclear Plant PSAR. This item is identified as item 566/567/79-17-01, Failure to perform proper chemical analysis on submerged arc welding materials.
Within the area: inspected, no item of noncompliance or deviation, except as noted in paragraph e., were identified.
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