ML20210C884
| ML20210C884 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/06/1987 |
| From: | Rice P GEORGIA POWER CO. |
| To: | Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| GN-1294, NUDOCS 8702090471 | |
| Download: ML20210C884 (2) | |
Text
'
' Georgia Power Cornpany Al[
h Post Ottce Box 282 U
Waynettoro, Georgza 30830 Telephone 404 554-9961. Ext. 3360
=,
404 724-8114. Ext. 336o U
Ofe'e"I* Lent "7 g n P 4: Q Georgia Power
,,,mn,rm/wtre s>wn Vogtte Project January 6, 1987 United States Nuclear _ Regulatory Commission Region II File: X78G10 Suite 2900 Log:
GN-1294 101 Marietta Street, Northwest Atlanta, Georgia 30323
Reference:
50-424/86-74, 50-425/86-35 Attention:
Mr. Roger D. Walker The Georgia Power Company wishes to submit the following information con-cerning the. violations identified in your inspection report 50-424/86-74 and 50-425/86-35:
Violation 50-424/86-74-01, " Failure to Achieve Appropriate Corrective Action on the Implementation of a Formalized / Controlled Training and -Qualification i
Crane Operator Program for Operations Personnel per QA Audit Report No.
OP11/16-86/17, dated July 9, 1986" - Severity Level IV.
Georgia Power Company (GPC) acknowledges _ the violation as identified in i
the USNRC inspection report.
As indicated in the USNRC inspection report, training was conducted for spent - fuel cask crane operators by the Operations Department.
The training was conducted in accordance with a checklist which covered classroom technical lectures and equipment operational qualification and proficiency.
The train-ing consisted of crane operation, a walkdown of crane components, and a demon-L stration in the proper removal of a dummy fuel assembly from a shipping con-l tainer and in the loading of the assembly into the fuel storage area using the spent fuel cask bridge crane.
The training was completed for each operator prior to allowing them to handle fuel.
The training checklist was reviewed and deemed adequate by the QA Site Manager and training activities were moni-tored by QA personnel to ensure that the checklist was properly followed and that the training was adequately documented.
GPC QA audit personnel identified the lack of formal procedura1' control of the spent fuel cask crane operator training program during QA audit OP11/16-86/17 (report issued July 9,1986).
The violation is attributed to a failure by auditors to issue an Audit Finding Report (AFR) to identify this weakness as required by QA Department Procedure QA-05-01.
Issuance of an AFR would have resulted in a documented corrective action requiring QA verifica-i tion for closure.
Plant Procedure 11951-C, " Fuel Handling Operator and Fuel Handling Super-visor Qualification Checklist," was revised and approved for use on October 15, 1986 (Revision 3) to include spent fuel cask crane operator training requirements.
This action was verified by GPC QA in audit OP16-86/43 (report issued November 3, 1986).
e70209o471 870106
- DR ADOCK 050 4
gg xEe
__ J
1
- To prevent recurrence, Operations QA audit personnel have been retrained in the requirements of procedure QA-05-01 for the issuance of AFR's and in the followup process for items tracked through the QA Audit Checklist Item Card file mentioned in the USNRC inspection report.
Corrective actions relative to this violation have been completed.
Violation 50-424/86-74-02, " Inadequate Procedure for Testing Air-Operated Valves With Bailey Controllers" - Severity Level IV.
Georgia Power Company (GPC) acknowledges the violation as identified in the USNRC inspection report.
The violation is attributed to a failure to include provisions in Con-struction Acceptance Testing (CAT) procedure CAT-M-04 for the fast closure of air-operated valves with positioners/ controllers, i
An evaluation by the GPC Nuclear Operations Department identified nineteen safety-related air-operated valves with positioners/ controllers that required testing for a sudden loss of instrument air.
Each of these valves was tested in accordance with revised procedure CAT-M-04.
All test results were accept-able.
To prevent recurrence, procedure CAT-M-04 was revised on October 27, 1986, to include testing for a sudden loss of instrument air to safety-related air-operated valves with positioners/ controllers.
Corrective actions relative to this violation have been completed.
These responses contain no proprietary information and may be placed in the USNRC Public Document Room.
i Yours truly, P. D. Rice CWH/PDR/jl xc:
U. S. Nuclear Regulatory Conunission Document Control Desk Washington, D. C. 20555 H. G. Baker D. R. Altman L. T. Gucwa J. P. O'Reilly J. A. Bailey C. W. Hayes G. F. Head G.
Bockhold G. A. McCarley R. E. Conway J. F. D'Amico R. W. McManus l
R. H. Pinson W. D. Drinkard Sr. Resident (NRC) l B. M. Guthrie C. C. Garrett (OPC)
J. E. Joiner (TSLA)
R. A. Thomas D.
Feig (GANE)
NORMS I