ML19282B355
| ML19282B355 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 02/13/1979 |
| From: | Todd G, Gerald Williams NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19282B349 | List: |
| References | |
| 70-1113-79-02, 70-1113-79-2, NUDOCS 7903130237 | |
| Download: ML19282B355 (3) | |
Text
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FE B 131979 Report No.:
70-1113/79-02 Licensee:
General Electric Company P. O. Box 783 Wilmington, North Carolina 28401 Facility Name: Wilmington Manufacturing Department Docket No.:
70-1113 License No.:
SNM-1 97 Safeguards Group N 7:
III Inspector:
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Y # 77 G. A.,1 Date Signed
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Approved by:
<w G. H. Williams, Section Chief, Safeguards Branch D[te[igned SufY1ARY Inspection on January 15-18, 1979 Areas Inspected:
This routine, unannounced inspection involved 30 inspector-hours onsite in the area of verification of export shipment of special nuclear material (SNM) includirg:
license revieu; packaging and tamper-safing; and SNM verification.
Resul t.s : Of the one ar ea inspected, no apparent items of noncompliance or deviations were identified.
7003130 73 7
4 DETAILS 1.
Persons Contacted Licensee Employees
- B. F. Bentley, Manager, Fuel Chemical Operation
- R. L. Church, Supervisor, Manufacturing Systems
- C. E. Cliche, Manager Fuel Fabrication Operation
- G. F. Finders, Compliance Auditor
- W. J. Hendry, Manager, Regulatory Compliance
- A. L. Kaplan, Manager, Licensing and Compliance Audits
- T. E. Shultz, Manufacturing Systems Specialist
- C. M. Vaughan, Manager, Nuclear Materials Management M. A. Smedley, Auditor, Nuclear Materials Management
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 18, 1979, with those persons indicated in Paragraph 1, above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
a.
License Review The licensee informed the inspector that export license number XSNM-1365 designated for project Tokai 2 Reload 1B has been sub-mitted to the Division of Licensing for review. However, license approval was still pending at the time of inspection.
Conditions of the aforementioned license will limit the export quantities to:
54,300 maximum kilograms UO Powder, 47,860 maximum kilograms 2
uranium and 1,375 maximum kilograms U235 at 3.65% maximum enrich-ment.
The holder of record to this export license is designated as the General Electric Company exporting to the Japan Atomic Power Company through Japan Nuclear Fuel.
The NRC will release this material for shipment only after noti-fication of export license approval.
4 4
2 b.
Packaging and Tamper-Safing Each container of UO, powder contained in this project is tamper-safed with a type-E seal prior to packaging. Tamper-safing is accomplished by interfacing the seal wire with the lid bolt on the lid ring of each container prior to placement inside a ship-ping container. Tamper-safing device control, authorized appli-cation and records documentation appear to have been performed in accordance with approved procedures.
The inspector observed the tamper-safing of thirty-seven 5 gallon buckets and noted no irregularities.
Tamper-safed containers are placed, two each, into type BU-7 shipping containers and are immediately sealed for tamper-indicating purpose in accordance with 49 CFR (Department of Transportation regulations).
The inspector observed the applica-tion of tamper-indicating devices to sampled shipping containers and examined the containers for damage andfe geometric anomilies.
No discrepancies were noted.
c.
Special Nuclear Material Verification The special nuclear material (SNM) verification of the Tokai 2 Reload IB encompassed obtaining random selected samples from a predetermined population of 5-gallon containers in the shipment, check-weighing selected containers, and analyzing sample quan-tities from these containers using a passive nondestructive tech-nique in the RIl measurements van.
A total of thirty-seven con-tainers were selected for verification.
Should a significant difference between licensee and NRC analysis be detected at the time of measurement verification, a supplemen-tal report will be issued.