ML20127N022
| ML20127N022 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/25/1993 |
| From: | Greenman E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20127M997 | List: |
| References | |
| 50-483-93-02, 50-483-93-2, EA-92-249, NUDOCS 9301290070 | |
| Download: ML20127N022 (2) | |
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NOTICE Of VIOLA 110N Union Electric Company Docket No.-50-483 Callaway Plant
' License ho. NPf-30 EA 92-249 During an NRC inspection conducted on October 1 through December 18, 1992, 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:
Callaway Station Technical Specification 6.8.1 states, in' part, that wri_tten procedures shall be established, implemented, and mainteined covering the applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
A.
Regulatory Guide 1.33, Appendix A, paragraph 9, " Procedures for Performing Maintenance," states, in part, that maintenance affecting the performance of safety-related equipment should be performed in accordance with written procedures appropriate to the circumstances.
Callaway Maintenance Mechanical Procedure, HTM-ZZ-QA006, "Limitorque Actuator Limit Switch and Torque Switch Adjustment, Revision-24, dated March 6, 1992, Attachment 4. "Limitorque MOV Limitswitch Setpoints,"
Note 3 for MOV No. EF-HV-0066, under the setpoint for intermediate rotor No. 2 states, in part, to set the rotors such that the disc will coast into the seat after the close limit switch contacts open.
Contrary to the above, on April 12, 1992, intermediate rotor No. 2, the close limit switch for valve EF HV-0066, was not set in accordance with procedure HTM-ZZ-QA006 in that, during operation of the valve, after the close limit switch contact opened, the disc remained approximately 25 percent open and did not coast into the seat.
This is a Severity Level IV violation (Supplement I).
8, Regulatory Guide 1.33, Appendix A, paragraph 8, " Procedures for Control-of Measuring and Test Equipment and for Surveillance Tests, Procedures,.
and Calibrations," states, in part, that specific ' implementing procedures are required for each surveillance test.
Callaway Operations Surveillance Procedure, OSP-EF-V0018, "ESW Train B Valve Operability," Revision 7, dated October 4,1991, Step 6.l.2.4 states, in part, to determine the position of the valve by local observation and record the full stroke position, 9301290070 930125-PDR ADOCK 05000483 G
Contrary to the above, on April 13, July 29, and October 21, 1992, equipment operators locally observing valve EF-HV-0066 recorded-that__the full stroke position was closed even though the valve had only-gone approximately 75 percent closed.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201,_ Union Electric Company is'hereby-reouired 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 U.S. Nuclear Regulatory Commission, Region III, 799 Roosevelt Road, Glen Ellyn, Illinois 60137, and a copy to the NRC Resident inspector at the Callaway Nuclear Power Station within 30 days of the_date of-the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to the Notice of Violation" and should include for each violation:
(1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps thct have been taken and 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 time specified in this Notice, a demand for information may be 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 at Glen Ellyn, Illinois
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this /49f ay of January 1993 Edward G. Greenman, Director Division of Reactor Projects
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