ML20057E289
| ML20057E289 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/04/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20057E288 | List: |
| References | |
| 50-482-93-21, NUDOCS 9310080288 | |
| Download: ML20057E289 (3) | |
Text
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1 APPENDIX A NOTICE OF VIOLATION i
i Wolf Creek Nuclear Operating Corporation Docket:
50-482 Burlington, Kansas License:
NPF-42 1
During an NRC inspection conducted August 9-27, 1993, three violations of NRC requirements were identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:
A.
Criterion XVI, Corrective Action, of Appendix B to 10 CFR Part 50 st ates that " measures shall be established to assure that conditions adverse to i
quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.
In the case of significant conditions adverse to quality, the measures shall assure that the cause of the condition is determined to preclude repetition. The identification of the significant ccndition adverse to quality, the cause of the condition, i
and the corrective action taken shall be documented and reported to l
appropriate levels of management."
Contrary to the above, the following violations of those corrective action provisions were identified:
1.
There had been seven failures of the bellows in Residual Heat Removal Relief Valves EJ8856A and -B since 1984. The licensee failed to promptly resolve these repetitive failures and had i
failed to perform a thorough evaluation of the causes of the
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problem.
2.
The licensee failed to determine the correct model number for j
component cooling water flow transmitters in a timely manner. The drawing discrepancy for the reactor coolant pump thermal barrier
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cooler flow transmitters was identified on August 1, 1992, but no l
action had been initiated until the time of this inspection.
3.
Performance Improvement Request 91-0398 indicated that bends in safety-related tubing installed in the plant could not be verified to meet ovality requirements of the applicable American Society of
)
Mechanical Engineers Code.
This condition was reported on i
July 10, 1991, and evaluated to be significant on September 23, 1991.
There was no additional effort to determine, plan, or initiate corrective action until June 3, 1993.
These violations represent a Severity Level IV problem (482/9321-02)
(Supplement 1).
9310080288 931004 PDR ADOCK 05000482 G
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4 B.
Technical Specification 6.8.1.a states that written ocedures shall be i
established, implemented, and maintained covering tf applicable i
procedures recommended in Appendix A'of Regulator.)
1.33, l
Revision 2, dated February 1978.
Regulatory Guide 1.33, Appendix A, Item 9a, recommends, in part, that maintenance that can affect the performance of safety-related equipment l
should be properly pre-planned and performed in accordance with written procedures appropriate to the circumstances.
Contrary to the above, on July 23, 1993, maintenance workers failed to l
generate a corrective work request as required by Step 2.4 of Work l
Request 4595-93, after critical tolerances measured internal to i
Valve EF-V046 were not within the acceptance criteria.
l This is a Severity Level IV violation (482/9321-03) (Supplement I).
C.
Technical Specification 6.8.1.a states that written procedures shall be established, implemented, and maintained covering the applicable procedures recommended in Appendix A of Regulatory Guide 1. 33, Revision 2, dated February 1978.
Regulatory Guide 1.33, Appendix A, Item 3.m, requires procedures for startup, operation, and shutdown of safety-related systems. This is i
accomplished, in part, by Procedure STN GP-001, " Plant Winterization,"
l Revision 9, which is implemented when the outside temperature has t
remained less than 35o F for one week or as directed by the operations manager.
Procedure SIN GP-001, Step 5.6.4.1 directs operators to open Essential Service Water Warming Line Valve EF-V263.
Procedure STN GP-001, Step 6.3.3.1 subsequently directs that when the outside temperature remains greater than 40o F for one week, the system be restored by closing Valve EF-V0263.
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Contrary to the above, on Notember 10, 1991, and November 28, 1992, operators failed to open Valve EF-V0263 as required by Step 5.6.4.1 of
]
Procedure STN GP-001; and on April 13, 1992, and April 29, 1993, 1
operators failed to shut Valve EF-V0263 as required by Step 6.3.3.1 of i
Procedare STN GP-001. Operators failed to properly position Valve EF-V0263 because the valve actuator was damaged and manipuhtion of the manual operator did not change the position of the valve, een though the actuator's indication of valve position did change.
(The failure of the valve mechanism was documented on April 30, 1991.)
This is a Severity Level IV violation (482/9321-05) (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Wolf Creek Nuclear Operating Corporation is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, 611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC l
t I
Resident inspector at the facility that is-the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation.
This reply should be clearly marked as a " Reply to a Notice of Violation" and i
should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the j
time specified in this Notice, an order or a Demand for Information may be 1
issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.
Dated agArlington, Tpxas I
this //
day of OCtobM>l993 i
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