ML20248C811
| ML20248C811 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 07/27/1989 |
| From: | Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20248C808 | List: |
| References | |
| 50-348-89-10, 50-364-89-10, NUDOCS 8908100158 | |
| Download: ML20248C811 (2) | |
Text
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ENCLOSURE 1 NOTICE OF VIOLATION Alabama Power Company Docket Nos. 50-348, 50-364 Farley :,uclear Plant License Nos. NPF-2, NPF-8 Unitt 1 and 2 During the Nuclear Regulatory Commission (NRC) inspection conducted on April 24-27 and May 8-12, 1989, a violation of NRC requirements was identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C, 53 Fed. Reg. 40019 (October 13,1988), the violation is listed below:
Technical Specification 6.8.1 requires that applicable written procedures recommended in Appendix A of Regulatory Guide (RG) 1.33, Revision 2, 1978, shall be established, implemented and maintained.
RG 1.33, Appendix A, specifies procedures for 1) Procedure Adherence and Temporary Change Method, and 2) Procedures for Performing Maintenance.
Contrary to the above, NRC identified four examples described below where procedures were not followed or an adequate procedure was not established, a)
On November 7,1987, a Temporary Change Notice (TCN) was processed to Maintenance Procedure FNP-0-MP-28.116 which deleted the requirement to calibrate safety-related 0.C. circuit breakers. As a result, the circuit breakers were not calibrated for several years, some since plant startup.
The change was not properly conducted in compliance with procedure FNP-0-AP-1, Development Review and Approval of Plant Procedures in that the change was an intent change but was not approved by the proper level of management prior to implementation.
b)
On May 10, 1989, NRC observed maintenance work on the Unit 2 turbine driven auxiliary feedwater pump using procedure FNP-0-MP-7.
Two steps were signed off as complete when in fact these steps were not and should not have beer, performed. The erroneous steps should have been deleted by procedure revision, c)
On April 25, 1989, NRC identified that the orfice plate for flow element (FE) 949 was installed backwards.
The licensee subsequently identified four other orfice plates that were installed backwards in other plant systems.
Maintenance procedures were not established to ensure that orfice plates are installed in the correct direction, d)
On May 11, 1989, NRC observed in-shop lding repairs on a fire door.
The welding procedure CSM-10 specified for the job called for too high amperage and hence too high heat for the thin metal being welded.
The welder was using reduced heat and made the repair correctly but r.o effort was made to change the procedure or seek another procedure.
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-Alabama Power' Company 2
Docket Nos. 50-348,.50-364
'Farley License Nos. NPF-2, NPF-8
- These four examples collectively represent a violation for failure to establish and implement procedures.
This,is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR '2.201, Alabama Power Company is hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington,. DC 20555, with a' copy to the _ Regional Administrator, Region II, and a copy to the NRC Resident
. Inspector, within 30 days of the date of the letter transmitting this Notice.
This' reply should be clearly marked as a " Reply to a Notice of Violation" and should include:
(1) admission or' denial of tha violation, (2) the reason for the violation if ' admitted, (3) the. corrective steps which have been taken and the results achieved..-(4) the corrective steps which will be taken to avoid further violations,. and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be' given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, an order 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.
FOR THE NUCLEAR REGULATORY,COMM SSION
/l 65 Albert F. Gibson, Dir. tor Division of Reactor Safety Dated at Atlanta, Georgia this 2~/" day of July 1989 J
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