IR 05000482/1980011
| ML19329A034 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/13/1980 |
| From: | Gilbert R, Randy Hall, Martin I NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19329A032 | List: |
| References | |
| 50-482-80-11, NUDOCS 8007280730 | |
| Download: ML19329A034 (7) | |
Text
U.'S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. STN 50-482/80-11 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: May 27-30, 1980 Inspectors:
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L. E. Martin, Reactor Ins 1ector, Projects Section Date (Paragraphs 1, 2, 3, 6, 7 & 8)
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g. D. Gilbert,' Reacto/ Inspector, Engineering
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Support Section (Paragraphs 4 & 5)
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Reviewed:
C. R. Oberg, Reactor Inspector, Projects Section Date
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Approved:
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8N W. A. Crossman, Chief, Projects Section
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& Wa R. E. Hall, Chief, Engineering Support Section
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80072807pg
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Inspection Summary:
Inspe'; tion on May 27-30, 1980, (Report No. STN 50-482/80-11)
Areas Inspected: Licensee action on previous inspection findings; safety-related pipe welding; containment penetration welding; electrical raceway and equipment installation; and IE follow up on licensee identified deficiencies. The inspection involved forty-eight inspector-hours by two NRC inspectors.
Results: Of the five areas inspected, one item of noncompliance was identified in one area (infraction - failure to specify appropriate acceptance criteria -
paragraph 5).
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- D. G. Plasce, QA Technical Auditor
- J. L. Stokes, Assistant Construction Manager Daniel International (Daniel) Personnel
- T. Damashek, QC Engineer, Civil
- C. E. Hackney, QA Engineer, Welding M. Dugan, Electrical QC Inspector D. C. McBee, Welding General Foreman C. Light, Pipe Department General Foreman M. G. Wiggins, Pipefitter Foreman B. G. Bullard, Project Welding Engineer D. J. Dennison, Assistant QC Manager SNUPPS
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R. D. Brown, Site Representative Kansas Eleccric Power Cooperative A. Mee, Engineer
- Denotes those present at the exit interview The IE inspectors also interviewed other licensee and contractor personnel during the coerse of the inspection.
2.
Licensee Action on Previous Inspection Findings (Closed) Infraction (50-482/80-05): Failure to Provide Appropriate and Prompt Corrective Action.
The reactor vessel internals have been relocated to in place storage inside containment and the reactor head has been relocated to a new sheet metal storage building in an area that is not susceptible to flooding. These actions should preclude water ingress into the storage areas for these components.
This item is consiaered closed.
(Open) Unresolved Item (50-482/80-05):
Concrete Expansion Anchors.
Daniel had initiated a Request for Clarification of Information (RCI No. 7153) to determine if there were criteria for the minimum distance that a replacement anchor can be located from an abandoned anchor. The respocae on the RCI from Bechtel Site Liasion Engineer stated that there were no criteria.
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The IE inspector asked the responsible individual if this statement meont that there was not a requirement for criteria or if he could not fied the criteria. The individual stated that he was not able to identify ir locr.te any criteria for the minimum spacing from abandoned anchors.
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This item will remain open until Bechtel can furnish data substantir. ting that the repair and installation methods that have been used for concrete
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expansion anchors meet the requirements for loading plus safety factor of the original design.
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(0 pen) Unresolved Item (50-482/79-07):
II/I Problem with Electrical Pro-cedures.
Interim Change (ICP) No. 156 to QCP-X-302 now includes within l
its scope II/I and indicates that the inspection requirements are the same as Class IE.
The craft procedures are now undergoing revision to include the II/I requirements.
This item will remain open pending revision of all pertinent procedures.
3.
Site Tour The IE inspectors walked through the Reactor Building, Auxiliary Building Control Building, and various outside storage areas to observe construction activities in progress and housekeeping practices.
No items of noncompliance or deviations were identified.
4.
Safety-Related Piping The IE inspector observed welding of safety-related piping in the following systems:
Boron Refueling Water Steam (Dras ing I-M-03BN01(Q))
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Field Weld Activity
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F 40 Fit Up Inspection and Root Welding FW 901 Interpass temperature Monitoring F 014 Fill Welding F 016R-2 Final Visual Inspection b.
Chemical and Volume Control System (Drawing I-M-03BG01(Q))
Field Weld Activity F 025 Fit Up Inspection, Root and Fill Welding F 022 Final Visual Inspection
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In the areas inspected, no discrepancies from the requirements of welding procedure CWP-507 and visual inspection procedure QCP-VII-200 were noted.
Welding filler materials were observed to be controlled and traceable to certified material test reports as required by the procedure for Control of Welding Consumables (CWP-503).
The Material Receiving Reports (MRR) for the following filler material heat numbers were inspected:
Heat Number MRR Number 7D21B Mix 12 3435 411J4141 41727 462571 30669 No items-of noncompliance or deviations were identified.
5.
Penetration Assemblies The IE inspector observed welding being accomplished on Field Weld FW 537 using the Gas Tungsten-Arc Welding process and welding procedure technique sheet N-1-1-BA-1, Revision 4.
FW 537 is identified on sheet D-2 of Drawing C-OL-2916(Q)01 as a Class MC butt welding in penetration E-283 with Bechtel Specification 10466-M-204 as the control document.
Specification 10466-M-204, paragraph 5.6.1 specifies requirements for making penetration welds in accordance with NE-4000, Class MC.
In addition to technique sheet N-1-1-BA-1; technique sheet d-1-8-BA-24, Revision 0, a procedure specifically issued j
for welding ca.rbon steel to stainless steel for NE-4000 applications; and QCP-VII-200, Revision 5, the visual inspection procedures were selectively
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reviewed for compliance with NE-4000.
The IE inspector determined that these procedures are not in compliance a
with NE-4000, in that the limits for maximum reinforcement of butt welds
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specified in N-1-1-BA-1, N-1-8-BA-24 and QCP-VII-200 are less restrictive than required in NE-4000, paragraph NE-4426 of ASME Code,Section III, 1974 i
Edition through Summer 1975 Addenda. For example, NE-4426 limits maximum
reinforcement to 3/32 inch for a material thickness of one inch, whereas,
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the welding technique sheets and Quality Control procedure permit a maxir ?
reinforcement of 3/16 inch for a material thickness of one inch. For all j
nominal material thicknesses greater than 1/8 inch, the procedural allowance i
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t This is an apparent item of noncompliance with Criterion V of 10 CFR 50, Appendix B, in that these procedures did not specify appropriate acceptance criteria.
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6.
Electrical Systems and Components The IE inspector observed the partial installation of one 480 volt motor control center (NG02A) and one cable tray support (331-08). Neither installation was complete, but the IE inspector inspected the partial
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installation for compliance with the following engineering and construction documents:
480 Volt MCC NG021 Manufacturer's I.B. 10466-E-018-0190-06 Bechtel Specification 10466-E-018 Daniel Work Assignment WA-EI-331-03 Design Change Notice DCN C-003-Rev. 8 Deficicency Report DR ISD3516EW Bechtel Drawing EOR 3311, Rev. 14 Bechtel Drawing C-00331, Rev. 9 Bechtel Drawing E-018-0043-04 Cable Tray Support 331-08 Bechtel Drawing EOR-3311, Rev. 14 Bechtel Drawing C-0401(Q), Rev. 8 Bechtel Drawing C-0402(Q), Rev. 7 Bechtel Drawing C-0403(Q), Rev. 9
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i Bechtel Drawir.g C-0404(Q), Rev. 9 i
Daniel Field Sketch FSK-E-331, Rev. 11
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Danie' Work Assignment WA-EI-331-01
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QC Raceway Support Checklists Dated April 9, April 5, March 1, and March 8,1979 for support 0331-08 The 1E inspector also reviewed the certification records for two Level II and one Level I Electrical QC inspectors for compliance with ANSI N45.2.6.
No items of noncompliance or deviations were identified.
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7.
Follos Up on Licensee Identified Deficiencies The IE inspector discussed the potential 50.55(e) item concerning Rockbestos cable jacket extrusion defects reported to NRC on April 3,1980, and KC&E's letter of May 8,1930, informing the NRC, that based on testing by Rockbestos, that the jacket defects do not constitute a 10 CFR 50.55(e) deficiency. The Rockbestos testing, according to KG&E, shows that the cable still meets the specification requirements and the original IEEE-323 test requirements.
The test documentation was not available on site, but KG&E advised the IE inspector that it would be on site for review during a subsequent inspection.
The IE inspector observed the termination problems with Bunker-Ramo electrical penetrations. The licensee had identified improper crimps on lugs, undersized lugs, and improper insulation stripping.
Bunker-Ramo representatives were on site to determine corrective actions. This problem was reported to NRC on May 19, 1980, and was KG&E's response to investigating a SNUPPS 50.55(e)
of March 14, 1980, at Callaway.
These items will remain open until the licensee submits his report as required by 10 CFR 50.55(e).
8.
Exit Interview The IE inspectors met with licensee representatives (denoted in para-graph 1) at the conclusion of the inspection on May 30, 1980. The IE inspector summarized the scope and findings of the inspection.
The item of noncompliance was acknowledged by the licensee representatives.
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