ML20147E502
| ML20147E502 | |
| Person / Time | |
|---|---|
| Issue date: | 03/11/1997 |
| From: | Gallo R NRC (Affiliation Not Assigned) |
| To: | Wilkinson I LIMITORQUE CORP. |
| Shared Package | |
| ML20147E507 | List: |
| References | |
| REF-QA-99900100 NUDOCS 9703140173 | |
| Download: ML20147E502 (1) | |
Text
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March 11, 1997 Dr. Ivan E. Wilkinson', P. E.
Director, Engineering Limitorque Corporation 5114 Woodall Road P.O. Box 11318 Lynchburg, VA 24506
Dear Dr. Wilkinson:
SUBJECT:
NRC INSPECTION REPORT 99900100/97-01 On February 26, 1997, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Lynchburg facility. The enclosed report presents the i
l results of that inspection.
During this inspection, the NRC team reviewed the root cause analysis you performed on a motor-operated-valve actuator from Oyster Creek Nuclear Generating Plant to determine why it had failed to electrically operate in 1996, and reviewed the corrective actions taken on a violation identified in l
Inspection Report 99900100/93-01 and an unresolved item identified in Inspection Report 99900100/91-01.
The inspectors did not idenkify any instances where your quality assurance program failed to meet NRC requirements for the areas inspected.
Therefore, no response to this letter is required.
The corrective actions taken on violation 99900100/93-01-01 and unresolved item 9900100/91-01-07 were determined to be adequate and are closed, in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of t;.is letter and its enclosures will be placed in the NRC's Public Document Room (PDR).
Sincerely, ORIGINAL SIGNED BY I
Robert M. Gallo 9703140173 970311 Special Inspection Branch PDR GA999 EMVLMIT Division of Inspection and Support Programs 99900100 PDR Office of Nuclear Reactor Regulation Docket No.: 99900100/97-01
Enclosure:
Inspection Report 99900100/97-01 Y
Distribution:
j PSIB R/F Central Files / RIDS IE:09 Docket File 99900100 I
PUBLIC orough 140023 EO IiE2 Id505E NY eV".I JLee
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- Previously concurred DOCVMENT NAME:
G:\\INSP. LIM Ta recolve a copy of this document, indicate in the box: 'C' = Copy without enclosures *E* = Copy with enclosures *N* = No copy
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1.
INSPECTION
SUMMARY
The team reviewed the root cause analysis that Limitorque Corporation i
(Limitorque) performed on a SMB Size 1 motor-operated-valve (MOV) actuator i
from General Public Utilities (GPU) Nuclear Corporation to determine the cause 1
of failure to electrically operate.,The actuator had been installed in a i
nonsafety-related application at Oyster Creek Nuclear Generating Station i
(OysterCreek).
Inspection bases were:
l i
Appendix B, " Quality Assurance Criteria for Nuclear Power Plants
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l and Fuel Processing Plants," to Part 50 of Title 10 of the Code of Federal Reaulations (10 CFR Part 50, Appendix B) l 10 CFR Part 21, " Reporting Defects and Noncompliance" 2.
STATUS OF PREVIOUS INSPECTION FINDINGS j
One violation identified in Inspection Report 99900100/93-01 and one unresolved item identified in Inspection Report 99900100/91-01-07 were t
i reviewed during this inspection. The inspectors did not review information on unresolved items (9990100/91-01-03, 04, and 05) during this inspection.
l Violation 93-01-01 (Closed). A May 10 through 14, 1993, inspection identified that contrary to 10 CFR Part 21.21, Limitorque failed to complete its j
evaluation and did not report a condition associated with the relaxation of i
motor actuator spring packs.
l Limitorque revised Quality Assurance Procedure (QAP) 13.2, " Reporting of Defects for Safety Related Equipment," on May 14, 1993, to require the use of i
Form L-345 to document future evaluations.
i Limitorque Log No. 08 dated June 8, 1993, documented that the effect of spring i
evaluation was insignificant and so advised the industry with its Technical l
Update 93.02 of the same date.
j..
Unresolved Item 99900100-91-01-07 (Closed).
It was identified that Limitorque had committed to, but had not notified NRC or informed its customers by way of i
Maintenance Update as of May 14, 1993, of a possible defect concerning improper machining of actuator limit stop housings for HBC-1 actuators.
[
Limitorque issued "Limitorque Maintenance Update 93-1," on August 31, 1993, to address this subject and inform its customers of the deviation.
l 3.
INSPECTION FINDINGS AND OTHER COMMENTS t
j 3.1 Introduction In a letter dated January 23, 1997, Limitorque Corporation, pursuant to the i
reporting requirements of 10 CFR Part 21, informed the NRC that it had discovered the existence of a " counterfeit" component installed in a Limitorque actuator at a nuclear power plant.
Limitorque discovered the discrepant worm shaft clutch gear in a SMB Size 1 actuator which failed to
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operate in a nonsafety-related application at GPU's Oyster Creek facility.
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