IR 05000482/1980021
| ML19345F099 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/23/1980 |
| From: | Crossman W, Vandell T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19345F096 | List: |
| References | |
| 50-482-80-21, NUDOCS 8102060710 | |
| Download: ML19345F099 (6) | |
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. STN 50-482/80-21 Docket No. STN 50-482 Category A2
Licensee:
Kansas Gas and Electric Company Post Office Box 208
,
Wichita, Kansas 67201 Facility Name:
Wolf Creek Generating Station Inspection at:
Wolf Creek Site, Coffey County, Kansas Inspection Conducted:
November 1980 Inspector-
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. E. Vandel, Resident Reactor Inspector Date Projects Sectica
/E/2f/J:6 Approved:
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W. A. Crossman, Chief, Projects Section Date Inspection Summary:
Inspection of November 1980 (Recort No. STN 50-482/80-21)
Areas Inspected:
Routine, announced inspection by the Resident Reactor Inspector
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(RRI) including observations of containment liner installation and safety-related piping installation; record review and observations of reactor pressure vessel protection and maintenance; review of procedures, installation, and records for RPV internals.
The inspection involved thirty-one inspector-hours by one NRC inspector.
Results:
No violations or deviations were identified.
81020607/4,
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CETAILS 1.
Persons Contacted Principal Licensee Emoloyees
- M. E. Clark, QA Manager, Site
- J. L. Stokes, Project Support Supervisor
- N. Criss, Audit Response Coordinator, Daniel International (DI)
- L. Bryant, Project Quality Manager, DI
- D. Dennison, Assistant QC Manager, DI
- L. Easterwood, Acting QC Manager, DI W. Wise, Assistant Engineering h nager, DI
- V. Turner, Project QA Manager, DI D. Peterson, CNQA, Chicago Bridge & Iron T. Groves, Quality Assurance, Westinghouse R. Hopkins, Welding Engineer, Westinghouse W. Sovak, Mechanical Engineer, Westinghouse T. Salcido, QC Inspector, Westinghouse Other licensee and construction personnel were contacted during the inspec-tion period.
- Denotes those attending at least one of the exit meetings.
2.
Plant Tours One or more plant areas were toured several times during the reporting period to observe general construction practices, area
- leanliness and storage condition of plant equipment.
No violations or deviations were identified.
3.
Fabrication of Safety-Related Piping Systems During the reporting period, the RRI observed welding work as well as handling, protection and inspection of safety-related piping and piping penetrations.
a.
Westinghouse Incore Instrumentation Piping:
The Bottom (of Reactor) Mounted Instruraentation-(BMI) piping welding activity of welder (symool 018) was observed.
Related documents were review F, including:
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(1) Westinghouse drawings
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BMI Field Assembly 1209 E10 Sheets 1 & 2, Rev. 5
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RPV General Arrangement 1223 E04, Rev. 2 (2) Westinghouse Works Sheets (No. SAP-WC-009)
Fabrication sequenct
'a'-
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Weld Status Log
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Rod Issue Slips
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(3) Related Welding Procedures
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UPS 8-43-GT-1, Rev. 1
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WPS 8-8-GT-1, Rev. 2 (4) Welder qualification-certification records for welder 018
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who was qualified for
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8-8-GT-1 8-8-GT-5
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8 e- "T-1
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b.
Piping Penetrations Reactor Building Area 4, Elevation 2026:
Observed joints, ID-FW597 and FW596, shown on ISO Col-2916-(Q)02 for completed weld, cover pass grinding and tags for NDE inspec-tion required (MT).
c.
Floor drain piping in Reactor Building, 2" stainless steel-drain to incore instrumentation tunnel sump (1-LF-S014): -The RRI observed one weld fit up and one completed weld of a tee joint above the sump.
No violations or deviations were identified.
4.
Reactor Pressure Vessel (RPV) Internals Assembly i
During the reporting period, the RRI observed assembly and welding activities of the lower. core support barrel and other general activities such as handling, protection, and inspection activities i
of.the RPV internals. ' Observations -included:
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Lower core. barrel. assembly activities.
base plate and energy absorbers
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upper guide plate with 28 instrumentation guide tubes
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torqued final lower guide plate ready for assembly
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welding of energy absorbers to base plate including preheat temperature checks, tacking of weld joint, ameter measurement of weld current (128 amps. with 130 amp max allowed)
b.
Related documents review including
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WPS 8-8-GT-2
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Fabrication sequency sheets (No. SAP-WC-006)
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Procedure W-001, Rev. 1
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Weld Status Log Instrumentation and-Secondary Core Support Assembly drawing
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6124ESS, Revision 2, Sheets 1, 2 & 3 c.
Welders 017 and 015 performing TIG welding and completed fillet weld.
d.
NDE examination reports (LI-1-EA and LI-2-EA) of root pass of welds.
(It is noted that the final weld LP inspection is an ANI hold point to be performed later.)
No violations or deviations were identified.
5.
Reactor Vessel Protection The RRI reviewed records regarding maintenance and storage protection during the inspection period. Procedure review along with visual inspection of the vessel condition and review of the maintenance history records were performed by the inspector. The review included:
l a.
Review of Daniel International procedures as follows:
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QCP-I-01, Rev.10, " Receipt, Storage, and Preservation of l
Safety-Related Material ~and Items"
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WP-I-01, Rev. 7, " Receipt, Storage, and Preservation of'
Safety-Related Material and Items" l
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b.
Review of Reactor Maintenance Instructions No. RMI-W-105 for the RPV received under P.O. 207952 on January 15, 1979 (MRR 24889, Rev. 3).
c.
Maintenance log history review conducted with the following information learned:
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Preventive maintenance on vessel started March 13, 1979.
Last entry in the log was made November 13, 1980.
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Memo from DI Mechanical Engineer stating that maintenance which was suspended while Westinghouse retained control of the vessel is to be resumed.
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The vessel was adeclately protected during the stored and installed condition up to the time of turnover to Westinghouse, with replacement of desiccant and air filters as needed.
Vessel observed to be completely open under the control
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of Westinghouse in preparation for the internals trial fit in the vessel.
No violations or deviations were identified.
6.
Containment Liner Plate Installation The RRI observed the installation of the containment liner plate at the construction opening by Chicago Bridge and Iron (CB&I) during the reporting period. Activities observed included fit-up (to the existing installed liner plate), weldino, and weld rod control.
Completed welds appeared good.
No violations or deviations were identified.
7.
Document Control Check During a tour of the plant site, the RRI telected a construction drawing observed to be in use by construction craft personnel in the Reactor Building (elevation 2047'). The drawing selected was a Paper Calmenson and Company Drawing No. R-0262-287, Revision 2 issued by the A/E with No. 10466-C-111-0275-04 stamped on it for control. This was a rebar
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installation drawing entitled " Reactor Building Slab at E1.2068-8 Top and Bottom Bars."
The RRI was informed by DI document control personnel that the drawing is of the current revision issued for construction.
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The IE inspector had no further questions.
8.
Exit Meetings The RRI met with licensee representatives (denoted in paragraph 1 on November-13, 1980, and November'26, 1980. The RRI summarized the scope and findings of the inspections performed.
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