ML19263B404
| ML19263B404 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 12/18/1978 |
| From: | Kaplan A GENERAL ELECTRIC CO. |
| To: | Sutherland J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19263B402 | List: |
| References | |
| NUDOCS 7901180211 | |
| Download: ML19263B404 (3) | |
Text
GENER AL h ELECTRIC NUCLEAR ENERGY PRODUCTS DIVISION WILMINGTON MANUF ACTURING DEPARTM E NT CASTLE H AYNE ROAD. P. O. BOX 780. WILMINGTON, N. C. 28401. (919) 343-5000 Decer:ber 18, 1978 Mr. J. T. Sutherland Fuel Facility & Materials Safety Branc.
U. S. Nuclear Pegulatory OcrTnission, Region II 101 Parietta Street, Suite 3100
~
Atlanta, Georgia 30303
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p n:
Dear Mr. Sutherland:
Referenms:
(1) NFC Inspection Report RII:JBK, 70-1113/78-20, dated 11/28/78 (2) NFC Li nse SNM-1097, Docket #70-1113
'Ihank you for your letter referenced above which reprted the results of the inspection of our fuel fabrication plant by Mr. J. B. Kahle of your offi on October 31 through Naventer 3,1978.
Pertaining to the item of apparent noncn.plian with NFC requirstents in your letter, the reply to this item is given in the attachment to this letter.
We appreciate your inspector's coments and suggestions related to our enployee safety and enviromental protection programs. 'Ihese acrrents and suggestions are helpful to us in cur constant efforts to inprove these programs, ensure the continued health and safety of plant personnel, and ensure our compliance with NFC regulations and license conditions. We also welcone further discussion with your staff on the items in your letter and in our related reply, if necessary, for further clarification of these items.
Your inspection report referred to above cbes not contain information which we believe to be proprietary.
Very truly yours, ELECTRI COMPANT
{/
h Arthur L. Kaplan Manager Licensing & Cmplian Audits M/C J26 AU(:b:w Attach"ent B <
NSD-I 790118can
' r. J. T. Sutherland M
De nber 18,1978 Attachment The information given below refers to the one itan in Appendix A, " Notice of Violation" and the one item in Appendix B, " Noti of Deviation," in the NRC Inspection Report RII:JBK, 70-1113/78-20. The corrective actions detailed below have elready been inplemented or will be inplemented by the dates shown.
I.
Condition 9 of the license requires that licensed material be used in accordance with statements, representations and conditions of Appendix A, as contained in the licensee's application.
Section 4.1 requires that operations and activities shall be directed by the de gnated area manager who shall establish writt. operating procedures incorporating radiati.n and criticality safety control and limits.
Contrary to the above, special nuclear material was placed in locations which did not meet the criticality safety controls.
This is a deficiency.
Operating procedures relative to criticality safety controls were discussed at the next scheduled series of regularly held round-table meetings between fore-men and manufacturing workers. These procedures were also stressed at a series of routinely scheduled neetings bebeen unit managers and forenen.
In order to avoid further noncxrpliance in this area, a series of walk-throuch inspections by nenbers of the Licensing & Cccpliance Audits Unit were initiated on October 31, 1978. 'Ihe purpose of these inspections is as follcus:
e 'Ib identify the type of item described above involving the following of radiatics, and criticality safety controls and limits by plant operations perronnel, e 'Ib correct any such itan thus identified.
'Ib report to management on a periodic basis.
e
'Ihese walk-through inspections are in addition to all other walk-through inspecticris and will be conducted on a weekly basis on the average. The results of these walk-throtrJ s will be reported to operations managerent initially on a nonthly h
basis.
'Ihe weekly walk-throtrJh schedule and nanthly reporting of results will be inplenented by January 30, 1979.
9
- Mr. J. T. Sutherland Decenter 18, 1978
'Attacirrent - Page 2 II.
Based on the results of the NRC inspection conducted on October 31 through November 3, 1978, certain of your activities appear to deviate from your commitments to the Commission, as indicated below.
Section 9.1 of the Demonstration of the License Application states that a photoelectric device is installed in each vaporization chamber to aid in leak detection.
Contrary to the above, operable photoelectric devices were not maintained in the vaporization chambers to pid in leak detection.
Additional manpcuer has already been assigned during the vaporization pro ss, to observe continuously the pro ss equiprent, looking for any signs of irregularities in the process which could lead to a UF6 gas release, as well as looking for any gas release itself. The individual thus assigned also assures that all process equiprent has been properly set up before the vaporization pro ss is begun.
Also, a special stu3y is underway to determine the need for leak detection and the best technical approach to neet these needs. Based upon the results of this study, the appropriate technical appuch or approaches will be inpleented and an inplenentaticri schedule deternunec.. This study is expected to be cmpleted by January 31, 1979.
Contintrus observations of the vaporization pro ss will be maintained at least until the study has been otrpleted.
B A. L. Kaplan EdERAL rifrT11C CINPANY abrw