IR 05000482/1982016
| ML20028C421 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/07/1982 |
| From: | Johnson W, Vandel T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028C417 | List: |
| References | |
| 50-482-82-16, NUDOCS 8301100102 | |
| Download: ML20028C421 (6) | |
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APPENDIX B U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report:
STN 50-482/82-16 Docket:
STN 50-482 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek Generating Station Inspection At: Wolf Creek Site, Coffey County, Burlington, Kansas Inspection Conducted: October 1 - November 15, 1982 Inspector:
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Date fj-J-b
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T. E' En~deT, Senior Resident Inspector, Reactor Project Section C Approved:
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/a/ 7/6' 2 W. D. Q#hnson, Chief, Reactor Project Section C Date Inspection Summary Inspection During October 1-November 15, 1982 (Report STN 50-482/82-16)
Areas Inspected:
Routine, announced inspection by the Senior Resident Reactor Inspector (SRI) covering general plant tours; observation of installation activities for safety-related piping systems; safety-related structures installation and welding activities; and electrical cable installation activ-l ities. The inspection activity involved 71 inspector-hours by the SRI.
Results: Within the five areas inspected, one violation was identified in one area (violation - failure to follow procedures - paragraph 2).
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DETAILS i
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Persons Contacted
i Principal Licensee Personnel
- J. V. Palermo, Assistant Construction Manager, Kansas City Power and Light Company
- C. E. Parry, QA Systems Supervisor, KG&E
- J. G. Nelson, Project Quality Supervisor Construction, KG&E
- R. W. Holloway, Project Construction Supervisor, KG&E
- J. Fletcher, Quality Control, KG&E
- D. W. Prigel, QA Manager, Wolf Creek Generating Station, KG&E
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- R. L. Donohoe, QA Technologist, KG&E
- D. L. Thero, QA Surveillance Supervisor, KG&E Other Personnel
- J. D. Grill, Project Piping Engineer, Daniel International Corp. (DIC)
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- C. D. Mauldin, Project Quality Engineer, DIC
- J. J. Grabusky, Piping / Welding Manager, DIC i
Other licensee and contrat. tor personnel were also contacted during the.
course of inspection activity.
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- The above listed personnel attended one or more of the exit meetings held on October 8 and November 10, 1982.
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2.
Piping Systems
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Piping system installation activities observed by the NRC inspector during the inspection period on the Chemical and Volume Control (BG)
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l System included the following:
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Weld out of Weld ID No. F002A shown on Piping Drawing IM03BGil (Q)
was observed.
The following attributes were observed and reviewed.
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Welder D-294 was qualified to Weld Procedure N-8-8-B-2.
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Stainless rod 3/32-inch was issued with the W-100 form dated
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November 3, 1982.
Completed weld appearance was good.
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b.
Welding activities on spool S0ll of Piping Drawing IM03BG01 (Q)
related to Field Weld FW320 were observed as follows:
Welder D-302 is qualified for Procedure N-8-8-B-2.
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NDE tag hung for 100 per cent RT inspection dated November 1,1982.
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Pipe cleanliness and protection of stainless pipe from carbon
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steel was checked. The NRC inspector observed that the pipe spool was placed on two support stands.
One stand, nearest the weld being performed (FW320), had carbon steel rollers in contact with the stainless pipe.
DIC Procedure WP-VII-200, Revision 7, paragraph 3.10, requires that stainless steel piping shall be handled in a manner which prevents direct contact with carbon steel and other metal. This is an apparent violation of 10 CFR Part 50, Appendix B, Criteria V.
(8216-01)
The radiographic film (RT) of the above mentioned Field Weld
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FW320 was reviewed by the NRC inspector. The film quality was very good and the weld in question was observed to be free of any inclusions or porosity that might have been caused by carbon steel particles in the weld.
3.
Electrical Cables a.
Installation activities regarding 5 kv cable terminations were ob-served by the NRC inspector.
The following terminations were observed:
250 MCM cable three phase 5 kv terminations to motor leads for
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auxiliary feedwater pump motor DPAL01A.
250 MCM cable three phase 5 kv terminations to motor leads for
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auxiliary feedwater pump motor DPAL018.
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250 MCM cable three phase 5 kv terminations to 4160 volt Class
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lE switchgear bus in Cubicle NB0105 for auxiliary feedwater j
pt lip motor DPAL01B feeder.
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The results of the observations are as follows:
l Cable termination cards and quality cable termination check-
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list were in use.
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Termination instruction, Ferite print 1T/0T-5NS-NVC for 5 kv
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single conductor nonshielded cable, was available to the termination crew.
Kerite termination kits (DT-8019) were being used for the
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termination installations.
The cable terminators were qualified for 5 kv termination
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installation.
Craft terminations iooked good with stress cone build up
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utilized at both cable end terminations.
The termination kits contained the appropriate specified
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materials.
b.
The electrical cable pulls, observed by the NRC inspector, were as follows:
Auxiliary building elevation 2026' at North spreading room,
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cable (lEFG09CV) pull from NG01BFF2 to ZNE278.
Reactor building, the first cable pull inside containment, a
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collection of ten cables were pulled from EGHV130 to ZNI277.
The results of the cable pull observations are as follows:
Quality checklist preinstallation inspection items had been
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completed and checked off prior to cable pull.
Cable routing had been checked and planned by the construction
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supervisor.
Cable pulling crew was adequate and adequately trained.
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Cables had identification tags on both ends, were pre-cut to
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length, and had been rolled on reels for installation.
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Protection of cables during pulling was good and the installed
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protection afforded the cables was very good.
The NRC inspector also reviewed the completed and signed quality cable installation checklists for the cable pulls inside the reactor containment.
No problems were identified.
No violations or deviations were identified.
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4.
Safety-Related Structures Completion of safety-related structures in the auxiliary building adja-cent to and around the containment buttress C area were reviewed and/or observed by the NRC inspector. Listed below are the areas of interest reviewed by the inspector and the results of the inspection, a.
Procedures Review Work and inspection procedures related to safety-related structures installation activities were reviewed by the NRC inspector as follows:
WP-IV-100, Revision 1, " Reinforcing Steel Field Fabrication"
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WP-IV-101, Revision 3, " Reinforcing Steel Placement"
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WP-IV-102, Revision 7, " Mechanical Splicing of Reinforcing Steel"
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WP-IV-111, Revision 7, " Structural Steel and Pipe Whip
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Restraint Erection" WP-IV-112, Revision 6, " Miscellaneous Steel and Embedments
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Fabrication" QCP-IV-102, Revision 9, " Mechanical Splicing of Reinforcing
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Steel" QCP-IV-lll, Revision 10, " Erection of Structural Steel and
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Pipe Whip Restraints" QCP-IV-ll2, Revision 9, " Miscellaneous Steel and Embedments
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Fabrication" QCP-IV-200, Revision 14, " Inspection of Welding Process"
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b.
Installation Activities Review Work and inspection activities related to safety-related structures installation were selectively reviewed by the NRC inspector as follows:
Structural column A-7, AJ.1 erection bolting activities at
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elevation 2026' of the auxiliary building were observed for completion and inspection.
Nelson stud-welded embedment studs were observed on the cross
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member between columns A-6, WAJ, and AK at elevation 2026' of the auxiliary buildin _
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Evidence of QC inspection activity was observed with QC hold
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tag 4774, listing NCR 1SN 6809C for studs bent greater than 45 degrees, attached to studs near column A-7, AJ.l.
No violations or deviations were identified.
5.
Plant Tours Plant areas were toured several times during the reporting period to observe general construction practices, area' cleanliness, and storage conditions of plant equipment.
Following is an observed instance of plant equipment protection:
RHR pump motor P2J01A located at 1974' elevation of auxiliary building
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was observed covered with plastic sheeting for protection and with motor heaters energized.
It is further noted that a QC hold tag was attached citing hold for IEEE-323, Class 1 approval.
No violations or deviations were identified.
6.
Exit Interviews The NRC Senior Resident Reactor Inspector (SRI) met with licensee represen-tatives denoted in paragraph 1 and with regional based reactor inspectors-during exit meetings as follows:
October 8,1982, SRI meeting along with the exit meeting of Mr. L.
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Gilbert.
Octot,er 22, 1982, exit meeting for Messrs. D. Hunnicutt, R. Mullikin,
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and C. Johnson.
November 10, 1982, the SRI exit meeting.
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The scope and results of the inspection activity were discussed with the licensee representatives.