IR 05000482/1982015
| ML20028B592 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 11/02/1982 |
| From: | Gilbert L, Hunnicutt D, Johnson W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20028B581 | List: |
| References | |
| 50-482-82-15, NUDOCS 8212030058 | |
| Download: ML20028B592 (5) | |
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APPENDIX U. S. NUCLEAR REGULATORY COMISSION
REGION IV
Report:
STN 50-482/82-15 Docket:
STN 50-482 Category A2 Licensee:
Kansas Gas and Electric Company P. O. Box 208 Wichita, Kansas 67201 Facility Name: Wolf Creek, Unit 1 Inspection at:
Wolf Creek Site, Coffey County, Burlington, Kansas Inspection Conducted:
October 4-8, 1982 s
Inspector:
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L. D. Gilbert, Reactor Inspector, Engineering Section Date Reviewed:
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QW/D.(Jqhnson, Chief,ReactorProjectSectionC Date Approved:
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///M82 D. M. Hunnicutt, Chief, Engineering Section
/ Dat'e Inspection Summary Inspection during October 4-8, 1982 (Report STN 50-482/82-15)
Areas Inspected:
Routine, unannounced inspection of licensee action on previous inspection findings; site tour; observation of work and review of records for welding and nondestructive examination (N9E) of safety-related piping.
The inspection involved 30 inspector-hours onsite by one NRC inspector.
l Results:
In the areas inspected, no violations or deviations were identified.
8212030058 821103 gDRADOCK 05000482 PDR u-
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DETAILS 1.
Persons Contacted Principal Licensee Personnel
- D. W. Prigel, Manager, QA Site
- D. L. Donohoe, QA Technologist
- 0. L. Thero, Supervisor, QA Surveillance
- C. E. Parry, Supervisor, QA Systems
- D. A. Colwell, QA Technologist
- R. W. Holloway, Project Construction Supervisor
- J. Fletcher, Quality Control
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Other Personnel
- J. C. Grill, Project Piping Engineer, Daniel International Corporation (DIC)
C. D. Mauldin, Project Quality Engineer, DIC G. Robertson, NDE Level III, GEO Construction Testing The NRC inspector also interviewed other licensee and contractor employees during the course of the inspection.
- Denotes those attending the exit interview.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (8111-01):
Grounding of welding machine to steam generator support base plate.
The NRC inspector reviewed the actions taken to resolve Deficiency Report No. ISD 7059M, which was issued to assess the potential damage resulting from grounding a welding machine to a steam generator support base plate while welding on the Reactor Coolant Loop piping.
The deficiency report was upgraded to Nonconformance Report No. ISN 3302 MW and work instructions were issued to remove and inspect the steam generator support column for damage to the upper and lower pins and bearing surfaces.
The visual inspection was performed and reported as acceptable.
This item is considered resolved.
3.
Site Tour The NRC inspector toured the reactor building and auxiliary building to observe construction in progress and to inspect housekeeping.
No violations or deviations were identified.
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4.
Safety-Related Pipe Welding and Nondestructive Examination a.
Observation of Welding Activities The NRC inspector observed the welding and quality control activities associated with fabricating the following safety-related piping welds.
Weld Control Drawing System Class F-004 IM138804(Q)
FW-310 IM03BG09(Q)
Chemical & Volume Control
FW-320A IM03BG03(Q)
Chemical & Volume Control
FW-313 IM038G02(Q)
Chemical & Volume Control
F-002 IM038G16(Q)
Chemical & Volume Control
F-013 IM03BG16(Q)
Chemical & Volume Control
FW-315 IM03BG16(Q)
Chemical & Volume Control
FW-521 IM03BG16(Q)
Chemical & Volume Control
F-034A IM03BG03(Q)
Chemical & Volume Control
FW-596 IM03EM03(Q)
High Pressure Core Injection
FW-654 IM03EM03(Q)
High Pressure Core Injection
F-002 IM03EJ05(Q)
F-001 IM03EG01(Q)
Component Cooling Water
In the areas inspected, the entries on the weld control record were consistent with the status of the welds, the filler materials were traceable to certified material test reports, and the welders were qualiffeo to ASME B&PV Code Section IX.
b.
Observation Of Nondestructive Examination Activities The NRC inspector observed the liquid penetrant examination of the following completed welds:
i Weld Control Drawing System Class l
FW-596 IM03EM03(Q)
High Pressure Core Injection
l FW-654 IM03EM03(Q)
High Pressure Core Injection
l FW-306 IM03BM18(Q)
Steam Generator Blowdown
l FW-301 IM03BM20(Q)
Steam Generator Blowdown
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FW-301 IM03BM17(Q)
Steam Generator Blowdown
The examinations were performed consistent with requirements of GE0 I
Procedure IPPT-340, Revision 1701-0 for liquid penetrant examination techniques, materials, and acceptance criteria.
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c.
Observation of Completed Welds The NRC inspector observed the weld surface condition of the following completed welds.
Weld Control Drawing System Class F661 IM13AE04(Q)
FW-302 IM03EP01(Q)
Safety Injection
F-001 IM03BB05(Q)
F-009 IM03EN03(Q)
F-001A IM13BB02(Q)
F-005A IM13BB02(Q)
F-008 IM13BB02(Q)
FW-900 IM13BB02(Q)
F-004 IM13BB04(Q)
FW-503 IM13BB04(Q)
FW-904 IM03EG24(Q)
Component Cooling Water
FW-905 IM03EG24(Q)
Component Cooling Water
FW-906 IM03EG24(Q)
Component Cooling Water
FW-907 IM03EG24(Q)
Component Cooling Water
F-003 IM03EJ05(Q)
F-004 IM03EM03(Q)
High Pressure Core Injection
In the areas inspected, no discrepancies with the requirements of ASME B&PV Code,Section III for completed welds were noted.
d.
Review of Nonconformance Reports The NRC inspector selected for review Nonconformance Report No. ISN5394 on improper radiographic examination by GEO and determined that the recommended disposition had been completed, cause of nonconformance had been established, and action to prevent recurrence had been taken.
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Review of Records l
The NRC inspector reviewed the weld history and nondestructive
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exemination documentation related to the fabrication of the following
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14 completed welds.
Weld Control Drawing System Class F-001 IM03BB05(Q)
F-009 IM03EN03(Q)
F-001A IM13BB02(Q)
F-005A IM13BB02(Q)
F-008 IM13BB02(Q)
FW-900 IM13BB02(Q)
FW-503 IM13BB04(Q)
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FW-500 IM13BB04(Q)
FW-506 IM13BB04(Q)
FW-509 IM13BB04(Q)
FW-904 IM03EG24(Q)
Component Cooling Water
FW-905 IM03EG24(Q)
Component Cooling Water
FW-906 IM03EG24(Q)
Component Cooling Water
FW-907 IM03EG24(Q)
Component Cooling Water
In the areas reviewed, the records indicated that specified inspections were' completed; the records reflected adequate weld quality; and weld history records were adequate.
No violations or deviations were identified.
5.
Exit Interview The NRC inspector met with licensee representatives (denoted in paragraph 1)
and T. E. Vandel (NRC Senior Resident Reactor Inspector) on October 8, 1982, and summarized the scope and findings of the inspection.
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