IR 05000458/1981008
| ML20030C108 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/06/1981 |
| From: | Gilbert L, Randy Hall, Whittlesey K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20030C104 | List: |
| References | |
| 50-458-81-08, 50-458-81-8, NUDOCS 8108250401 | |
| Download: ML20030C108 (4) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report:
50-458/81-08 Docket:
50-458 Category A2 Licensee: Gulf States Utilities Post Office Box 2951 Beaumont, Texas 77704 Facility Name:
River Bend, Unit 1 Inspection at:
River Ber.d Site Inspection Conducted:
July 20-24, 1981 lia/6/8/
Inspectors:
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LT D. Gilbe'rt,' Reactor Inspector, Engineering and Materials Section (Paragraphs 1-6)
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<% O f)l K. A. Whittlesey, Reac@r Inspector - Trainee, Engineering Date and Materials Section (Paragraph 3)
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Approved:
R. E. Hall, Acting Chief,/ Engineering and Materials Diter Section Inspection Summary
Inspection on July 20-24, 1981 (Report: 50-458/81-08)
Areas Inspected: Routine, unannounced inspection of licensee action on previous inspection findings; site tour; and observation of work and review of records for welding of reactor containment vessel and safety-related piping. The inspection involved 66 inspector-hours on site by two NRC inspectors:
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Results: No violations or deviations were identified.
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DETAILS 1.
Persons Contacted j
Principal Licensee Employees
- W. J. Cahill, Senior Vice President
- P. D. Graham, Director QA
- G. V. King, Supervisor Quality Engineering
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- T. C. Crouse, Constoction Superintendent
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- H. G. Domschke, QA Engineer
- R. B. Stafford, Supervisor Quality Systems
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j Stone & Webster Employees (S&W)
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- R. L. Spence, Superintendent FQC
- T. L. Vaughn, QA Project Engineer
- C. D. Lundin, Project QA Manager
- W. R. Whitley, Assistant Superintendent FQC
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A. Clawson, Inspection Supervisor J. Green, Inspection Supervisor W. Hathoway, Senior Welding Supervisor Other Personnel L. Sutton, Senior QC Engineer, Graver C. Carr, QA Engineer, Graver
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K. Brawner, Shift QA Superintendent, Chicago Bridge & Iron l
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Licensee Action on Previous Inspection Findings (Clo 'd) Unresolved Item (50-458/80-09-01):
Performance Qualification for Welders and Welding Operators Must be Maintained Separately.
The requirements for maintaining the perfonnance qualification of welders and welding operators have been revised in the Graver Nuclear Quality Assurance Program Manual to be consistent with the ASME Code Interpre-tation IX-79-68.
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l This item is considered resolved.
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(Closed) Unresolved Item (50-458/80-09-02):
Performance Qualification
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Retesting. The requirements for retesting after failure of a performance qualification test have been clarified in S&W Procedure CMP 6.9, j
Revision A, Change 1.
This item is considered resolved.
3.
Reactor Containment Vessel - Welding
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The NRC inspectors observed submerged arc welding of Containment Dome Plate 39-Cl to Dome Plate 37-Cl.
The butt weld joining the two plates-2 i
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was identified as Field Weld C-16 of F# etion Control No. CCDl-016 and was completed using submerged arc wel..
.g wire and flux in accordance with Welding Procedure WPS 332N, Revision 10. The welding wire of heat 040048 and flux of lot 1042 were traceable to test reports conforming to the requirements of SFA 5.23 in ASME B&PV Code,Section II, Part C.
The dome plate material, SA 516 Grade 70, was traceable to certified material test reports for the heat and slab numbers listed below:
Heat _ Numbers Slab Numbers 802W75100 W32883 Y33761 IW1
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802W72300 W32777 Y33761 3W1 The NRC inspectors also observed in-process repairs to the metal contain-ment structure involving rework of containment-to-embedded-plate "T" weld identified by Erection Control No. ECJ1-ll6R3, Revision 5 as Item LEA 31 and repair to Item B-1, Seam lH2 of Erection Control No.
BCS 35-002R4. The NRC inspectors noted that welding activities were in accordance with Procedure Specification WPS 305N, Revision 13.
Electrodes used for welding were consistent with WPS 305N and traceable to certified material test reports conforming to SFA 5.1 in ASME B&PV Code. Weld rod issue and control were consistent with Graver Quality Assurance Manual requirements.
Review of welder qualifications and inspector certifications confirmed compliance with ASME B&PV Code,Section IX and ANSI N45.2.6.
No violations or deviations were identified.
4.
Safety-Related Piping The NRC inspector observed the fitup and root welding of a Class 3 pipe
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butt weld for the Service Water System. The field weld was identified as FW 002 on Drawing 1-SWP-25 for Line. No. 1-SWP-030-25-3.
The welder
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was using the gas tungsten-arc welding process and weld rod type E70S-2 (Heat 065303) in accordance with requirements of Welding Procedure W100B and Weld Technique Sheet W11B, Revision 1.
The NRC inspectors also observed the finished weld surface and reviewed the weld documentation of two Class 2 shop welds. The first weld was a pipe butt joint for the Residual Heat Removal System designated as FW 006A on Drawing 1-RHS-142 for Line No. 1-RHS-018-142-2.
The other
weld was a pipe branch weldolet for the Core Isolation Cooling System designated as FW 007 on Drawing 1-ICS-020 for Line No.1-ICS-006-20-2.
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In the areas of welder qualification, weld and inspection documentation, procedure compliance, inspector certification, and filler material con-trol; no discrepancies were noted. However, some confusion existed concerning the finished weld profile requirements for weldolets which S&W engineering clarified in a memorandum, dated July 24, 1981 A Quality Assurance Finding Report, QAFR No. 81-7-25-B, was issued by GSU in require additional training of piping inspectors and reinspection of previously inspected weldolets.
This item is considered unresolved pendilig review of completed actions required by the above QAFR.
No violations or deviations were identified.
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Unresolved Items Unresolved items are matters about which more information is required in crder to ascertain whether they are acceptable items, violations, or deviations. An unresolved item related to inspection of weldolets is discussed in paragraph 4.
6.
Exit Interview The NRC inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on July 24,1981, and summarized the scope and findings of the inspection, i
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