ML20211K291
| ML20211K291 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 06/16/1986 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20211K232 | List: |
| References | |
| 50-321-86-08-01, 50-321-86-8-1, NUDOCS 8606270362 | |
| Download: ML20211K291 (2) | |
Text
ENCLOSURE 1 NOTICE OF VIOLATION Georgia Power Company Docket No. 50-321 Hatch Unit 1 License No. DPR-57 During the Nuclear Regulatory Commission (NRC) inspection conducted on February 24 - March 3,1986, a violation of NRC requirements was identified. The violation involved failure to follow administrative controls and procedural requirements during maintenance activities.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violation is listed below:
10 CFR 50, Appendix B, Criterion XVI states:
The identification of the significant condition adverse to quality, the cause of the condition, and the corrective action taken shall be documented and reported to appropriate levels of management 10 CFR 50, Appendix B, Criterion V states:
Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be at.::omplished in accor-dance with these instructions, procedures, or drawings.
Hatch procedure 10AC-MGR04-0, Deficiency Control System Step 8.2 states:
Significant conditions adverse to quality will normally require initiation of a Deficiency Report (DR).
During the operations phase of plant Hatch, i
the conditions described in Attachment I shall be considered significant conditions adverse to quality.
6 of 10AC-MGR04-0 states: Negligence or disregard of management policy defined in administrative controls or procedural requirements is a significant condition adverse to quality.
Contrary to the above, on January 3,1986, when it was determined that the replacement wedge for valve 1E11-F004A did not fit the original stem, the stem was ground down to make the replacement wedge fit.
This modification of the original stem was accomplished on the verbal authorization of the maintenance supervisor only. No deficiency report was initiated to document that the replacement wedge did not correspond to the as-found condition of the valve or that modification of the original stem had been accomplished by disregarding the administrative controls and procedural requirements of the Hatch maintenance program.
This is a Severity Level IV violation (Supplement I).
I 1
0606070362 860616 DR ADOCK 0D000321 PDR
Georgia Power Company Docket No. 50-321 2
License No. DPR-57 Hatch Unit 1 Pursuant to the provisions of 10 CFR 2.201, Georgia Power Company is hereby required to submit to this Office within 30 days of the date of the letter transmitting this Notice a written statement or explanation in reply including:
(1) admission or denial of the 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 viola-tions, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.
FOR THE NU LEAR REGULATORY COMMISSION in.
I tr
. M is A.
es, Acting Director D vision f Reactor Projects Dated at Atlanta, Georgia this
%% day of luSE 1986 L.
.