IR 05000482/1986027
| ML20215D672 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/01/1986 |
| From: | Gilbert L, Ireland R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20215D665 | List: |
| References | |
| 50-482-86-27, NUDOCS 8612160446 | |
| Download: ML20215D672 (5) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
NRC Inspection Report:
50-482/86-27 License /CP:
' Docket:
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:
November 3-6, 1986 f
Inspector:
- /'/O L. D. Gilbert, Reactor Inspector, Engineering Date Section, Reactor Safety' Branch Approved:
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R. E. Ireland, Chief, Engineering Section Dat6
Reactor Safety Branch Inspection Summary Inspection Conducted November 3-6, 1986 (Report 50-482/86-27)
Areas Inspected:
Routine, unannounced inspection of inservice inspection activities.
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Results: Within the one area inspected, no violations or deviations were identified.
8612160446 861204 PDR ADOCK 05000482:
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- G. D. Boyer, Deputy Plant Manager
- C. M. Estes, Superintendent of Operations
- M. G. Williams, Superintendent of Regulatory, Quality and Administrative Services
- J. W. Johnson', Chief of Security
- V. J. Mactaggart, Results Engineering Supervisor
- J. L. Blackwell, Fire Protection Coordinator
- T. L. O'Hearn, Lead Engineer, Nuclear Plant Engineering
- W. M. Lindsay, Supervisor, Quality Systems
- C. J. Hoch, QA Technologist
- G. J. Pendergrass, Licensing Engineer-S. W. Lucas, Results Engineering J. T. Holland, Senior Engineer, Nuclear Plant Engineering B. Collier, ISI Engineer J. Mah, Results Engineer J. C. Goode, Licensing Engineer Other Personnel M. Shallis, ISI Supervisor, NDE Level III, Nuclear Energy Services, Inc.
J. A. Winkel, Authorized Nuclear Inservice Inspector, Kemper Group The NRC inspector also interviewed other licensee and contractor personnel.
- Denotes those attending the exit interview.
2.
Inservice Inspection a.
Review of Program The NRC inspector selectively reviewed the KG&E inservice inspection program for volumetric and surface examinations of ASME Class 1, 2, and 3 systems and components.
The following documents were included in the review:
o Procedure ADM 05-107, Revision 0, "ASME Section XI Inservice Inspection."
o Program Plan 83A1710, Revision 1, " Reactor Pressure Vessel."
o Program Plan 83A1708, Revision 2, " Steam Generator."
o Procedure ADM 07-407-9, Revision 9, "WCGS Document Control."
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o Program Plan 83A1709, Revision 1, " Pressurizer."
o Program Plan 83A1700, Revision 1, " Reactor Coolant System."
In the areas reviewed, the inservice inspection program was consistent with the regulatory requirements of 10 CFR 50.55a.
b.
Review of Procedures The NRC inspector reviewed the following nondestructive examination (NDE) procedures used by Nuclear Engineering Services (NES) for performing inservice inspections.
o Procedure 83A1721, Revision 4, " Liquid Penetrant Examination Procedure."
o Procedure 83A1728, Revision 1, " Ultrasonic Examination Procedure for Studs and Bolts."
o Procedure 80A9068, Revision 3, " Procedure for Certifying Nondestructive Examination Personnel."
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Procedure 83A1722, Revision 4, " Procedure for Magnetic Particle Examination."
o Procedure 83A1725, Revision 1, " Ultrasonic Examination Procedure for Pressurizer and Steam Generator Nozzle Inner Radius Areas."
o Procedure 83A1717, Revision 2, " Ultrasonic Examination Procedure General Requirements."
In the areas reviewed, the above procedures were consistent with requirements of Section XI of the ASME Boiler and Pressure Vessel Code 1980 Edition, through.the Winter 1981 addenda.
c.
Observation of Work The NRC inspector observed the following inservice inspection examinations:
o Ultrasonic examination of the primary inlet nozzle inner radius for "B" steam generator.
o Ultrasonic examination of the primary outlet nozzle inner radius for "B" steam generator.
o Magnetic particle examination of the reactor vessel head closure nuts.
o Ultrasonic examination of the support pad bolts for "A" steam generato _-
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In the areas inspected, the examinations were performe'd in accordance
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with the examination procedure using NES personnel certified as a
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Level II and examination materials certified'for maximum content of
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' contaminants.
d.
Review of Records The NRC inspector reviewed the following inservice inspection examination reports:
o Data Sheet No. 1721-14 for liquid penetrant examination of
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welds 1-RV-301-121A and 1-BB-01-F103 on reactor vessel outlet nozzle "A."
o-Data Sheet No. 1721-13 for liquid penetration examination of welds 1-RV-301-121-D and 1-BB-01-F403 on reactor vessel outlet nozzle "H."
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. Data Sheet No. 1721-12 for liquid penetrant examination of
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welds 1-RV-301-121-C and.1-BB-01-F303 on reactor vessel outlet nozzle "E."
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o Data Sheet No. 1721-22 for liquid penetrant examination of welds-1-RV-301-121-B and 1-BB-01-F203 on reactor vessel outlet nozzle "D."
o Data Sheet No. 1728-2 for ultrasonic examination of 24 support pad bolts on steam generator "A."
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o Data Sheet No. 1725-2 for ultrasonic examination of the primary inlet and outlet inner radius areas on steam generator "B."
o Data Sheet No. 1718-1 through 1718-4 for ultrasonic examination of welds 1-BB-01-F001,1-BB-01-F002,1-BB-01-F004B on the
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reactor coolant system surge line.
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Data Sheet No. 1719-14 for ultrasonic examination of
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welds 1-AB-01-F006 and 1-AB-01-F097 on the main steam line.
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Data Sheet No. 1722-2 through 1722-4 for magnetic examination of i
24 reactor vessel head closure nuts.
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o Results of the eddy current testing of steam generators "B" and
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"C."
Approximately 7 percent of the tubes in the two generators were inspected.
No tubes were required to be plugged.
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In'the areas inspected, the records were complete, the data was
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within the previously' established acceptance criteria, and the licensee was utilizing the services of a third party inspection agency in the inservice inspection program.
No violations or deviations were identified.
3.
Exit Interview
,The NRC inspector met with licensee representatives (denoted in paragraph 1) and B. L. Bartlett, NRC resident inspector, on November 6, 1986, and. summarized the scope and findings of the inspection.
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