IR 05000482/1980016
| ML19343A425 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 07/16/1980 |
| From: | Crossman W, Gilbert L, Randy Hall NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19343A423 | List: |
| References | |
| 50-482-80-16, NUDOCS 8009170387 | |
| Download: ML19343A425 (3) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. STN 50-482/80-16 Docket No. STN 50-482 Category A2 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name:
Wolf Creek, Unit No.1 Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas Inspection conducted: July 8-11, 1980 Inspector:
7/68
.pl.D. Gilbert,ReactorInspector,EngineeringSupport D' ate '
Section 7 4/70 Reviewed:
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C. R. Oberg, React 6r Inspector, Projects Section D(te '
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Approved:
e 7 [ 88 W. A. Crossman, Chief, Projects Section Date f
7 6 R. E.' Hall, Chief, Erigineering Support Section Ddte Inspection Sunnary:
Inspection on July 8-11, 1980 (Report No. 3TN 50-482/80-16)
hreasInspected:
Licensee action on previous inspection findings; site tour; and review of pmcedures and records for welding of safety-related tanks.
The
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inspection invoived twenty-three inspector-hUurs by one NRC inspector.
Results:
No itt.ms of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- M. E. Clark, QA Manager Site
- S. D. Bostom, QA Auditor
- D. W. Prigel, Assistant QA Manager
- G. L. Fouts, Construction Manager G. W. Reeves, QA Engineer J. Bailey, Supervisor Mechanical Engineer - Corporate E. Creel, Manager Quality Assurance - Corporate Daniel International (Daniel) Personnel
- W. E. Hitt, Project Manager
- V. J. Turner, Project QA Manager
- D. Dennison, Assistant QC Manager
- R. Schofield, Assistant Project Welding Engineer
- C. L. Phillips, Assistant Engineer Manager SNUPPS
- R. D. Brown, Site Representative Richmond Engineering Company (RECO)
M. Riles, QC Inspector
- Denotes those present at the exit interview.
The IE inspector also interviewed other licensee and contractor personnel during the course of the inspection.
2.
Licensee Action on Previous Inspection Findings (Closed) Deviation (STN 50-482/79-08):
Improper Penetrameter Size Specifi-cation.
The radiographic examination requirements for the containment liner welds have been clarified in Appendix 3A to the FSAR and are now consistent with the requirements of the Bechtel Specification No.10466-C151(Q) for fabricating and inspecting the reactor containment liner.
The IE inspector had no further questions regarding this matter.
3.
Site Tour The IE inspector walked through the Reactor Building and Auxiliary Building to observe construction activities in progress and housekeeping practices.
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No items of noncompliance or deviations were identified.
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4.
Safety-Related Tank Welding a.
Review of 0A Program
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The IE inspector reviewed the REC 0 Quality Assurance program which included the following documents:
(1)
QA Manual, Revision 11 and site addenda for Wolf Creek, Revision 0 (2)
Procedure Pl/MMA-1, Revision 0, " Shielded Metal-Arc Welding of Carbon Steel Materials," and the supporting procedure qualification report
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(3)
Procedure P8/TIG/GBU, Revision 1, " Gas Tungsten-Arc Welding With Gas Back Up of Stainless Steel Material," and the supporting procedure qualification report I
(4)
Procedure ES-134, Revision 0, " Visual Inspection" b.
Review of Records
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The IE inspector reviewed the traveler and documentation for site erection of a 66-inch diameter Residual Heat Removal (RHR) isolation valve encapsulation tank detailed on RECO Drawing 0-78-063, Revision 8 under Bechtel Contract Numbe.- 10466-M-109A.
The weld in the carbon steel (SA 285C) support, field weld 32, was welded using Weid Procedure Pl/MMA and electrode type E7018 of heat No. 79M.
The welds in the stainless steel (SA 240-304) tank, field welds 39, 40, 41 and 42, were welded using Weld Procedure P8/TIG/GBU and weld rod type ER 308 of heats No. C4402R308 and D4404T308.
In the areas inspected, the procedures, welder qualifications and weld metals were consistent with requirements of Bechtel Specification No. 10466-M-109A.
The welding material certifications were inspected and found consistent with the requirements of ASME Section IIC, Specification SFA-5.1 for E7018 electrode and SFA-5.9 for ER 308 weld rod.
No items of noncompliance or deviations were identified.
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Exit Interview The IE inspector met with licensee representatives (denoted in paragrah 1) and the acting NRC Resident Reactor Inspector (Mr. C. R. Oberg) on July 10, 1980.
The IE ir.spector summarized the scope and findings of the inspection.
No additional findings resulted from inspection activities continued on July 11, 1980.
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