IR 05000482/1980003
| ML19316A945 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 02/25/1980 |
| From: | Crossman W, Randy Hall, Oberg C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19316A932 | List: |
| References | |
| 50-482-80-03, 50-482-80-3, NUDOCS 8005280087 | |
| Download: ML19316A945 (6) | |
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U. S. NUCLEAR REGJLAYORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
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REGION IV
Report No. STN 50-482/80-03 Docket No. STN 50-482 Category A2 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 07201 Facility Name:
Wolf Creek, Unit No. 1 Inspection at: Wolf Creek Site, Coffey County, Burlington, Kansas Inspection conducted:
February 11-14, 1980 3!2-
Inspectors:
w
. E. Martin, Reactor Inspector, Projects Section Date (Paragraphs 1, 2, 3, 5 & 6)
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- /35lS D L. D. Gilbert, Reactor Inspector, Engineering Support bate'
Section (Paragraph 4)
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Reviewed:
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C. R. Oberg, Reactor Inspector, Projects Section Date'
Approved:
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W. A. Crossman, Chief, Proj ects Section D' ate LS'
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R. E.' Hall, Chief, Engineering Support Section batd 8005280 O[f
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Inspection Summary:
Inspection on February 11-14, 1980 (Report No. STN 50-482/80-03)'*
Areas Inspected:
Licensee action on a previously identified item of noncompliance; safety-related piping; review of records and observation of work for safety-related steel supports; and site tour. The inspection involved forty-eight inspector-hours on site by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS
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1.
Persons Contacted Jyincipal Licensee Personnel
- M. E. Clark, Manager, Quality Assurance, Site
- D. W. Prigel, Assistant Manager, Quality Assurance, Site
- S. J. Walmsley, QA Technician
- G. L. Fouts, Construction Manager, Site Daniel International
- W.
E. Hitt, Project Manager
- R. D. Scott, Construction Manager
- V. J. Turner, Project Quality Assurance Manager
- D. L. Jones, Quality Control Manager
- D. J. Dennison, Assistant QC Manager B. G. Bullard, Project Welding Engineer
- T. R. Barber, Assistant Welding Engineer P. C. Schaffer, Supervisor-Mechanical Welding QC G. Martin, General Foreman, Welder Qualification D. C. Bondurant, Mechanical Engineer D. J. Harris, Area Civil Engineer Others
- R. D. Brown, Site Representative, SNUPPS
- W. R. Seiple, Resident Geotech, Dames & Moore
- E. Glasbergen, Site Manager, Westinghouse
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The IE inspectors also interviewed other licensee and contractor personnel
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including members of the QA/QC and engineering staffs.
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- Denotes those attending the exit interview.
2.
Licensee Action on Previous Inspection Finding (Closed) Item of Noncompliance (STN 50-482/79-17): Failure to Follow Procedures for Blasting Operations.
The IE inspector reviewed the Dames & Moore records for the blasting performed on September 15, 1979, and the subsequent Daniel approved qualifications of Mr. R. D. Blake. Clarkson Blasting Procedure (B-1),
Revision 2 now includes the Daniel approved blasting specialist'.s qualifications as an enclosure and requires the blasting specialist's name to appear on the cover sheet of the blasting plan.
This item is considered closed.
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3.
Site Tour The IE inspectors made a tour of the Reactor Building, Auxiliary Building, and other general plant areas to observe construction activities in progress and to inspect housekeeping.
The IE inspectors advised the licensee representative of two areas (one inside containment around the base of the accumulators and one ares in the cable spread room) which needed attention with regard to housekeeping.
These two areas were cleaned the next morning.
No' items of noncompliance or deviations were identified.
4.
Safety-Related Piping The IE inspector observed the various phases of welding safety-related piping which included fit-up of an insert r'ng for field weld F-001 on the Containment Spray System drawing I-M03EN02(Q); automatic gas tungsten-arc welding of field weld F-049 on the Boron Refueling Water Storage System drawing I-M03BN01(Q); gas tungsten-are welding of shop weld W-823 on the Chemical and Volume Control System drawing P-M03BG09(Q); and tack welding
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of shop weld W-501 on the Chemical and Volume Control System drawing
P-M03BG15(Q).
In the areas inspected, no discrepancies from the require-j ments of welding procedure CWP-507 were noted.
f The automatic gas tungsten-arc welding procedure specification NM-8-8-B-2 for stainless steel pipe and supporting procedure qualification test reports PQT-109, 111 and 180 were reviewed by the IE inspector.
In the areas reviewed, no discrepancies from the requirements of ASME B&PV Code,Section III or IX, 1974 Edition through Summer 1975 Addenda were noted.
Welding filler materials were observed to be controlled and stored as required by procedure CWP-503. The traceability and certification of three filler material heat numbers used for welding safety-related piping were confirmed by the IE inspector to be in compliance with procedure CWP-503. The heat numbers checked were 462570, 464176 and C3547R308.
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Three welders were observed taking performance qualification tests.
The
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pipe position, material and welding processes being used were consistent
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j with the requirements specified in welder qualification procedure CWP-502 j
for qualifying to ASME Code,Section IX.
No items of noncompliance or deviations were identified.
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5.
Safety-Related Steel Supports a.
Records Review The IE inspector reviewed the following procedures, drawings, travelers and records for compliance with FSAR, 10 CFR 50 Appendix B and manu-facturer's instructions for the installation of the below indicated steel supports.
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QCP-I-01, Rev. 8, " Receipt Storage & Preservation of Safety-Related Material"
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AP-VI-08, Rev. 6, " Identification & Status of Material, Parts,
& Components" AP-IV-02, Rev. 2, "Nonconformance Control and Reporting" QCP-IV-509, Rev. 1, " Inspection of Stud Welding" CWP-509, Rev. 1, " Stud Welding" MRR 9198 (P.O. 10466 C 134A) Steam Generator Anchor Bolts MRR 30576 (P.O. 546 CVW 263752) Steam Generator Base Assemblies MRR 31507 (P.O. 546 CVW 263752) Steam Generator Vertical Column Dwg. M-717-008, Rev. 6 Dwg. M-717-002, Rev. 6 Dwg. M-717-007, Rev. 5 Dwg. M-717-003, Rev. 7 Traveler I-PBB01-VC, Rev. 1 for Reactor Coolant Pumps A-D Vertical Supports Traveler I-PBB01-TR, Rev. O for Reactor Coolant Pumps A-D Tie-Rod Supports Traveler I-EBB 01-VC, Rev. 2 for Steam Generator Vertical Supports Traveler I-TBB03, Rev. O for Pressurizer to Pressurizer Base Attachment NCR ISN 1485 MR NCR ISN 0898 M NCR ISN 1727 M NCR 2SN 00915 M (Callaway)
Request for Storage-In-Place (SIP) 1485 KG&E QA Surveillance Report SOS of April 21, 1978 No items of noncompliance or deviations were identified.
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b.
Observation of Work The IE inspector observed the in-process-vork and status of vertical supports for all four steam generators, all four reactor coolant pumps, and the pressurizer lower support. All four reactor coolant pump casings are in-place on the vertical supports, and three steam gener-ators are in-place.
The IE inspector observed the assembling of two of the vertical columns for the fourth steam generator and inspected two vertical columns to determine that the correct parts were used in assembly and properly documented as required by the associated traveler.
During the assembly of one of the steam generator vertical assemblies, the craft experienced considerable alignment difficulties.
In the process of assembling the upper forging to the vertical column, the bearing was displaced approximately one inch from center as the pin was driven through.
The Westinghouse Site Manager advised the IE inspector that this was not a significant problem.
The IE inspector reviewed an NCR 2SN 00915 M from the Callaway project where the same situation had previously been experienced.
The bearing was subsequently centered in the vertical column.
The IE inspector observed the status of the setting of the pressurizer.
During this observation and review, the IE inspector noticed that the heat numbers for the shims between the pressurizer support skirt and the support had not been recorded.
The presssurizer is just sitting on the support; the leveling and torquing has not been done.
These shims can easily be removed to facilitate recording the numbers as required by the traveler. The licensee representative stated that this will be accomplished prior to torquing the hold-down bolts.
Also during the observation of the status of the pressurizer, the Mechanical Engineer who was accompanying the IE inspector noticed some cracked tack welds on a ring inside the pressurizer support skirt.
Subsequent discussions with the Westinghouse Site Manager indicated that this ring and the associated welds were used only for sealing the pressurizer during shipping and storage.
The Daniel engineer initiated NCR 1SN 1727 M to insure follow up and disposition j
of the cracked tack welds.
i No items of noncompliance or deviations were identified.
6.
Exit Interview The IE inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on February 14, 1980.
The IE inspectors summarized the scope and findings of the inspection.
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