IR 05000482/1990016
| ML20055C994 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 06/26/1990 |
| From: | Collins S NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Withers B WOLF CREEK NUCLEAR OPERATING CORP. |
| References | |
| NUDOCS 9007030053 | |
| Download: ML20055C994 (3) | |
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In Reply Refer To:
Docket: STN 50-480/90-16 Wolf Creek Nuclear Operating Corporation ATTN: Bart D. Withers President and Chief Executive Officer P.O. Box 411 Burlington, Kansa. 66B39 Gentlemen:
Thank you for your letter of June 13, 1990, in response to our letter and
Notice of Violation dated May 14, 1990. We have reviewed your reply and find it responsive to the concerns raised in our Notice of Violation. We will review the implementation of your corrective actions during a future inspection to determine that full compliance has been achieved and will be maintained.
Sincerely, E
Origlar) Signed By:
Samuel J. Collins Samuel J. Collins, Director Division of Reactor Pruiects
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Wolf Creek Nuclear Operating Corp.
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ATTN: Gary Boyer, Flant Manager P.O. Box 411 Burlington, Kansas 66839 Shaw, Pittman, Potts & Trowbridge ATTN: Jay Silberg, Esq.
1800 M Street, NW Washington, D.C.
20036
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Public Service Commission ATTN: Chris R. Rogers, P.E.
Manager, Electric Department P.O. Box 360 Jefferson City, Missouri 65102
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Wolf Creek Nuclear Operating-2-Corporation
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U.S. Nuclear Regulatory Comission ATTN:
Regional Administrator, Region III 799 Roosevelt Road Glen Ellyn Illinois 60137 Wolf Creek Nuclear Operating Corp.
ATTN: Otto Maynard, Manager Regulatory. Services P.O. Box 411 Burlington, Kansas 66839 Kansas Corporation Comission ATTN:
Robert Elliot, Chief Engineer Utilities Division 4th Floor - State 0ffice Building Topeka, Kansas 66612-1571 Office of the Governor State of Kansas Topeka, Kansas 66612 Attorney General 1st Floor - The Statehouse Topeka, Kansas 66612 Chairman, Coffey County Comission Coffey County Courthouse
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Burlington, Kansas 66839 Kansas Department of Health and Environment Bureau of Air Quality & Radiation Control ATTN: Gerald Allen, Public Health Physicist Division of Environment Forbes Field Building 321 Topeka, Kansas 66620 U.S. Nuclear Regulatory Comission ATTN:
Senior Resi t t Inspector P.O.~ Box 311 Burlington, Kansas 66839 U.S. Nuclear Regulatory Comission ATTN:
Regional Administrator, Region IV 611 Ryan Plaza Drive Suite 1000 Arlington, Texas 76011
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R. D. Martin Resident Inspector
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DRP DRSS-FRPS R. Hague, RIII
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RIY File SRI, Callaway, Rill MIS System RSTS Operator Project Engineer (DRP/D)
Lisa Shea, RM/ALF D. V. Pickett, NRR Project Manager (MS:
13-D-18)
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W$LF CREEKm==s NUCLEAR OPERATING CORPORATION s
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June 13,1990 WM 90-0102
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i U. S. Nuclear Regulatory Come.ission ATTN Document Control Desk Mail Station Pl.137
Washington, D. C.
20555 Reference:
Letter dated May 14, 1990 from S. J. Colline, NRC to l
B. D. Withers, WCNOC
Subject:
Docket No. 50-482: Response to Violation 482/9016-01 Centlemen:
Attached is Wolf Creek Nuclear Operating Corporation's (WCNOC) response to l
violation 482/9016 01 which was documented in the Reference.-
Violation 482/9016-01 involved a failure to follow procedure.
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If you have any questions concerning this matter, please contact me or Mr. H. K. Chernoff of my staff.
Very truly yours, 2-v Bart D. Withers President and
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Chief Executive Officer BDW/aem Attachment cca R. D. Martin (NRC), w/a D. V. Pickett (NRC), w/a H. E. Skow (NRC), w/a t. S. Wiebe (NRC), w/a
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PO. Box 411/ Buriengton, KS 66839 / Phone: (316) 364 8631 An Equal Opporuey Employe umcNET
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Attachment to WM 90-0102 Page 1 of 2 i
Violation (482/9016-01): failure to Follow Procedure Finding:
Technical specifications requires that written procedures shall be established, implemented, and maintained covering those activities recommended in Appendix A of Regulatory Cuide (RG)
1.33, Revision 2 February 1978.
RG 1.33 required, in part, that there be procedures covering performing maintenance.
Procedure FHP 03-012 Revision 3. ' Rod cluster Control Change Tool Operating instructions', paragraph 7.2.4,
' Recovery',
specifies the steps tv perform
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to disengage the tool from a rod cluster control assembly (RCCA)
prior to moving the bridge crane.
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Contrary to the above, on March 30, 1990, with the reactor in Mode 6, the operators moved the spent fuel pool bridge crane while the rod cluster control change tool was attached to an RCCA in a test location.
Reason For Violations
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On March 29. -
1990 during performance of eddy _ current testing on the rod cluster control assemblies (RCCAs),
RCCA R-96 had been placed in its final location (DD02) in the spent fuel pool.
A scheduled operator change
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,j ocurred and the oncoming operator raised the RCCA change tool and moved the spent fuel pool bridge crane approximately 20 inches toward location FF06.
The operator did not verify by use of the load cell or movement of the RCCA change tool that the RCCA was disengaged.
Refueling crew personnel then observed that RCCA R-96 had not be disengaged.
Evaluation of this event determined that the reason for the failure to follow procedure FHP 03-012,
' Rod Cluster Control Change Tool Operating instructions' was inattention to detail and inadequate turnover by refueling crew personnel.
Corrective Steps Which Have Been Taken And Results Achieved
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Movement of the spent fuel pool bridge crane toward location FF06 was halted when personnel observed that RCCA R-96 had not been disengaged from the RCCA change tool.
The bridge crane was returned to location DD02 and the RCCA change tool lowered onto the fuel assembly in this grid location.
RCCA R-96 was then raised and reinserted into the sesembly with no visual damage or binding being observed.
Operations management discussed the event with the operators involved and stressed the need for attention to details including the need to monitor disengagement by use of the installed load cell as well as the indicating lights.
The need for complete and thorough turnovers to oncoming personnel was emphasized to the involved operators.
Additionally, one operator was removed from fuel handling activities and letters of reprimand were placed in the involved individuals'
personnel file.
During subsequent eddy current testing a member of the refueling crew was ascigned as a spotter to observe operation and disengagement of the RCCA change tool.
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Attachment to WM 90-0102
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Page 2 of 2 An Operations Event Report was initiated to investigata this event.
RCCA
R-96 was replaced with a new RCCA and a corrective work request was generated to evaluate the condition of RCCA R-96.
Corrective Steos Which Will Be Taken To Avoid Further Violations:
Procedure FHP 03-012 has been revised to require an individual ta observe operation and disengagement of the RCCA change tool.
Additionally, the
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revision requires a refueling Senior Reactor Operator (SRO) to be present j
during use of the RCCA change tool.
Date When Full Compliance Will Be Achievedt Full compliance has been achieved.
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