ML20211M906

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Partially Withheld Insp Rept 70-1113/86-11 on 860602-06 (Ref 10CFR2.790(d) & 73.21).No Violations or Deviations Noted.Major Areas Inspected:Measurements,Export Shipment & Followup on Previous Insp Findings
ML20211M906
Person / Time
Site: 07001113
Issue date: 06/17/1986
From: Bates J, Mcalpine E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211M455 List:
References
FOIA-86-704 70-1113-86-11, 70-1113-86-11-0, NUDOCS 8612180078
Download: ML20211M906 (8)
v • d • e


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.g .f JUN 17 G86 Recort No.: 70-1113/86-11 L':ensee: General Electric Company Wilmington, NC 28401 C::ket No.: 70-1113 License No.: SNM-1097 Fa:ility Name: General Electric Company

-spection Conducted: June 2-6, 1986

-spector: h bM J. W. Bates, ' Safeguards Cthmist 657 b 6 Date Signed A: proved by: NDMW E. J. McAlpine', Chief, Matirial Control and 6/87 /8 6 Date Signed Accountability Section, Nuclear Materials Safety and Safeguards Branch Division of Radiation Safety and Safeguards

SUMMARY

! 5: ope: This routine, unannounced inspection was performed by one inspector in

! the area of measurements, export shipment, and followup on previous inspection f'ndings.

Results: No violations or deviations were identified.

861218o078 861205 PDR FOIA RATNER 86-704 PDR

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REPORT DETAILS I

1 Report No. 70-1113/86-11 l

1. Persons Contacted Licensee Employees
  • C. M. Vaughan, Manager, Regulatory Compliance l
  • T. O. Brechtlein, Manager, Fuel Chemical and Quality Control l
  • R. K. Stewart, Manager, Material Planning and Control 1
  • L. E. Short, Project Manager, Uranium Process Management Project
  • 0. L. pensinger, Manager, Chem-Met Laboratory
  • 0 W. Brown, Acting Manager, Acting Manager, Uranium Recycle Unit

! *T. P. Winslow, Manager, Licensing and Nuclear Materials Management ,

  • W. J. Kemp, Manager, Shop Support l

The inspector also interviewed several other licensee employees.

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  • Denotes those present at the exit interview.
2. Exit Interview The inspection scope and findings were summarized on June 6,1986, with those persons indicated in paragraph 1 above. The licensee acknowledged the

( inspection findings and took no exceptions.

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, 3. Licensee Action on Previous Inspection Findings -

l (Closed) Inspector Followup Item (84-08-02) Followup on nonsymmetrical control chart limits. An examination revealed that this anomaly was due to a software problem and was corrected during April 1986. A review of the control chart data for June 2-6, 1986, revealed that the control chart limits were symmetrical.

4. Export Verification (85301)

The licensee was granted an export license (XSNM0226) by the Export / Import and International Safeguards Off rnational Pro rams on October 10, 1985 to export u An inspection was conducted '

the General Electric Company during The period June 2-6, 1986, to examine the licensee's requirements and procedures for exporting special nuclear material ( to inde endently verify by random sa lin content i e overseas shipment is scheduled to depart the licensee's fa ity or Oakland,

3 California, on or about Au 15, and includes the following enrichments:

The low enriched UO2 powder was produced and packaged in both three and five gallon metal containers in preparation for shipment. The material type and enrichment determines the size of the c'ontainer to be used. The tare weight of a container was measured prior to packaging and included the weight of the lid, ring, liner, type E seal, wire and the lid securing metal bolt.

Based upon the NRC sampling plan, ontainers were randomly selected for sampling. The samples selected were prorated over each quantity and enrichment associated with the population being examined. Sample sizes and the licensee's sample data are presented in Tables I and II. The identity of the containers sampled, the container gross weights, the drums the containers were packaged in for shipment, the blend numbers and the drum seal numbers are presented in Table III. The samples are being forwarded to the New Brunswick Laboratory under NRC Form-741, transfer series YLJ-CBJ No. 26, dated June 5, 1986. The samples will be analyzed for percent uranium and weight percent uranium-235. This is an inspector followup item (86-11-01) and will be examined during subsequent inspections.

An examination was performed of the sampling frequencies and quality requirements for blends of low enriched 002 powder produced for overseas shipment. It was determined that the sampling frequencies and quality requirements were in accordance with the QC inspector instructions, No. 2.5.2.1, Rev. 22, entitled Acceptance of GE-Wilmington Produced UO2 powder For Sale, dated May 15, 1984.

5. Measurements (85207)

The licensee's program for monitoring and controlling the performance of standard measurements for' analytical methods used for accountability purposes was examined. The analytical methods for uranium and U-235 have warning and control limits determined by statistical techniques using data based upon historical performance of the method. Each measur ystem has warning and control limits that are re-evaluated at leas each material balance period as required. The measurement systems ex ined, the number of out-of-warning conditions and the standard measurements performed during the periods examined are presented in Table IV. It was determined that when the 0.05 out-of-warning limits were exceeded, the investigation, the probable cause of the occurrence and corrective actions taken were documented as required by Section 4.5 of the licensee's FNMC Plan.

The percent uranium in uranium hexaflouride (UF6) was determined gravi-metrically by ledou Company who al erforms a total metallic impurity in UF6 on at least The spectrographic analysis for impurities Inc ifferent eleme s. Once a year, at least such determinations, re esentative of the past year's withdrawals, are se to calculate the gravimetric nonvolatile impurities correction factor. The

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impurity data was averaged to obtain a milligram oxide equivalent. These averages were summed to obtain a total average milligram oxide equivalent which was used to convert the theoretical uranium factor to a corrected uranium factor. The uranium values for UF6 received under NRC Form-741, transfer series BXA-YLJ No. 1322, dated January 3, 1986, was verified by the inspector.

An examination uranium factors andwas performed included a review ofofthe theoxygen licensee's program to uranium ratio for updatin %(0 and metallic impurity analyses that are performed routine ormal rations for various material cate ries. These were ,

A tio was used to determine an 0/U ratio that was correc r meta ic impurities (TMI) and converted to cent uranium i

e in accor ance wtt m ection .. icensee s FNMC Plan. The data the require %

supporting factor updates for several material categories generated during April 1986 were ex mine . The inspector determined that the uranium factors were being updated and in accordance with the sampling frequencies of the QC procedures.

A tour was made of GE's newly constructed LEU Uranium Process Management Pro UPMP). The purpose of the UPMP i recover and recycle LEU from t The UPM udes an' er .

anium f rom various residues and s es orm

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j product suitable for conver'sion to an acceptable grade U02.

Six annular vessels that could contain uranium bearing solutions at inventory shutdown were calibrated using an NBS traceable flow totalizer.

The process is controlled and monitored using PROV0X computer systems.

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TABLE I SAMPLE SIZE DATA Sample No. Gross Wt. Tare Wt. Net Wt.

0.719MP1125 12.9 2.9 10'0 2.909MP0107 13.0 2.9 10'1 2.909MP0132 12.9 2'9 10'O 2.909MP0240 12.9 2.8 2.909MP0196 13.0 2.9 10l1 10 1 3.400MLO241 12.9 2.9 10'0 3.400MLO370 12.9 2.9 10'0 3.400ML0183 12.9 2.9 10'O 3.400MLO322 12.9 2.9 10'0 3.400MLO442 12.9 2.9 10.O 3.900ML4929 12.9 2.9 10 0 3.900ML5088 13.0 2.9 10.1 1

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l TABLE II LICENSEE CONTAINER ANO SAMPLE DATA Blend No. -Factor Isotopic (%)

Sample No.

6789 .8761 0.719MP1125 6539 .8731 2.909MP0107 6707 .8738 2.909MP0132 6579 .8745 2.909MP0240 6541 .8745  ;

2.909MP0196 l

6578 .8781 3.400MLO241 6637 .8780 3.400MLO370  :

6546 .8780 '

! 3.400MLO183

' 6569 .8784 3.400MLO322 I 6728 .8779 3.400MLO442 6570 .8755

! 3.900ML4929 6484 .8737 ,

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I e 7 TABLE !!!

CONTAINER SAMPLE IDENTIFICATION DATA

. l Nominal Cont Drum Cont Gross Cont Drum Enrichtrent ID No. NA Wt. Gms Seal No. Seal No.

9MP1125 K-0101 29730 313825 314617 i 9MP0107 K-2213 30990 313823 314618 i

9MP0132 K-7274 30870 313822 314619 9MP0240 K-3296 29920 313821 314620 9MP0196 K-0143 22650 313824 314621 OHLO241 K-1598 32450 313828 314622 OMLO370 K-0516 32160 313827 314623 OML-0183 K-1934 22820 313826 314624 OHL-0322 K-6288 31500 313830 314625 OML-0442 K-1389 32180 313829 314626  ;

i l OML4929 K-2864 27350 313831 314627 l OML5088 K-3331 21970 313832 314628 i

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