ML20127L346

Advises That Implementation of Corrective Actions Re 850315 Response to 850213 Notice of Violation Inadequate. Supplemental Response to Notice of Violation Incorporating Listed Addl Info Requested within 30 Days

ML20127L346
Person / Time
Site:	Browns Ferry
Issue date:	05/21/1985
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Parris H TENNESSEE VALLEY AUTHORITY
References
NUDOCS 8506270890
Download: ML20127L346 (2)

Text

I g/{W May 21,1985 Tennessee Valley Authority ATTN: Mr. H. G. Parris Manager of Power and Engineering 500A Chestnut Street Tower II Chattanooga, TN 37401 Gentlemen:

SUBJECT:

REPORT NOS. 50-259/84-52, 50-260/84-52, AND 50-296/84-52 This refers to your March 15, 1985 response to our Notice of Violation, dated February 13, 1985, concerning activities conducted at your Browns Ferry facility.

Actions described in your response appear to be adequate to resolve the identi-fied deficiency. The implementation of these actions, however, appears to have been inadequate. On March 14, 1985, the Limitorque operator pinion gear on RHR torus suction valve FCV3-74-12 was found reversed after having been verified in the correct position by two individuals specifically trained to perform a sample inspection of Limitorque operators on all three units at the NRC's request.

As a result, we question the validity of the inspections performed to verify correct orientation of Limitorque pinion gears.

Please submit a supplemental response to this Notice of Violation within 30 days with the additiunal information pertaining to the following areas:

1. How did the incorrect verification of pinicn gear installation occur, and was it attributable to inadequate training or procedures?

2. Are all Limitorque valve operators inspected by these two individuals in response to the NRC request being reinspected?

3. What additional corrective actions will be, or have been taken to ensure that your initial response to the Notice of Violation is adequately implemented?

In addition, during an inspection in this area conducted December 3-6, 1984, the maintenance staff indicated to the inspector that a valve could not fail to operate electrically due to a loose pinion gear set screw in the Limitorque operator. It was maintained that the pinion gear could not travel far enough to disengage from the shaft gear. A Browns Ferry maintenance order dated August 2, 1982, indicated valve FCV 3-73-3 had failed to operate electrically due to a loose set screw on the pinion gear. Also, on March 17, 1985, valve 3-74-12 failed to close due to a loose pinion gear set screw in the Limitorque operator.

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%- 4 Tennessee Valley Authority 2 May 21, 1985 Please explain this apparent discrepancy and what corrective actions will be taken to prevent further safety-related valve failures due to loose pinion gear set screws in the Limitorque operators.

Sincerely, (Original signed by VLBrownlee for/)

Roger D. Walker, Director Division of Reactor Projects cc: J. A. Coffey, Browns Ferry Nuclear Plant Site Director G. T. Jones, Plant Manager J. W. Anderson, Manager Office of Quality Assurance K. W. Whitt, Chief, Nuclear Safety Staff D. L. Williams, Jr., Supervisor Licensing Section R. E. Rogers, Project Engineer bec: NRC Resident Inspector Document Control Desk R. J. Clark, Licensing Project Manager, NRR State of Alabama RII RII RI

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