ML20135H693

Matl Control & Accounting Insp Rept 70-0371/85-08 on 850610-14.No Noncompliance Noted.Major Areas Inspected: Measurement Sys & Measurement Control & Statistics

ML20135H693
Person / Time
Site:	07000371
Issue date:	08/23/1985
From:	David Jones, Keimig R, Zibulsky H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20135H688	List: ML20135H687 ML20135H693
References
70-0371-85-08, 70-371-85-8, NUDOCS 8509240135
Download: ML20135H693 (4)

Text

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1 U.S. NUCLEAR REGULATORY COMMISSION REGION I Report.No. 70-371/85-08 Docket No.70-371 License No. SNM-368 SAFEGUARDS GROUP 1 Licensee: UNC Naval Products Division of UNC Resources, Inc. ,

67 Sandy Desert Road Uncasville, Connecticut 06382 Facility Name: UNC Naval Products Inspection At: Uncasville, CT Inspection Conducted: June 10-14, 1985 Date of Last Material Control and Accounting Inspection: May 7-10, 1985 Inspectors: [L e7v . I C H. Zibulsky, Chemist / date ')

b4" & Ff2.1 f D. Jon'es,1 Region II Statistician date Approved by: /4/ d -. -

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R. R. Keimi!g, Chief, Safeguards Section, date Division of Radiation Safety and Safeguards Inspection Summary: Routine, Announced Material-Control and Accounting Inspection on June 10-14, 1985 Report No. (70-371/85-08)

Areas Inspected: Measurement systems and measurement control and statistics.

The inspection involved 63 hours7.291667e-4 days <br />0.0175 hours <br />1.041667e-4 weeks <br />2.39715e-5 months <br /> on site and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> offsite by two NRC inspectors.

l Results: The licensee was in compliance in the areas examined during this inspection.

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DETAILS

1. Persons Contacted T. Collopy, Manager, Nuclear Material Control

• N. Grenon, Supervisor, Nuclear Material Control

• M. Kelly, Statistical Specialist

• S. Ververis, Chemist The inspectors also interviewed other licensee personnel involved in the control and accounting of special nuclear material (SNM) and chemistry.

• Present at exit interview.

2. 30703-Exit Interview The inspectors met with the licensee representatives (denoted in paragraph

1) at the conclusion of the inspection on June 14, 1985, and summarized the scope and findings of the inspection. At no time during this inspec-tion was written material provided to the licensee by the inspectors.

3. 85207-Measurement Systems The licensee analyzed three standards with varying concentrations of uranium provided by the NRC inspector. The liquid standards were prepared with normal uranium and certified by the New Brunswick Laboratory. The uranium concentrations.and matrix were within the normal range of-the material-the licensee routinely analyzed.

The inspector observed two analysts, using the same analytical procedure (spectrophotometric TOPO extraction), perform the tests. This procedure is used on low level uranium concentrations as is found in laboratory waste solutions.

The results of the. test showed that each analyst had a disagreement in one of the standard solutions. The differences are not considered signifi-cant. One disagreement from one analyst was about 1 ppm of uranium and the other ~ disagreement, from the other analyst, was less than 0.5 ppm of uranium.

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4. 85209-MEASUREMENT CONTROL AND STATISTICS

a. The licensee's statistical program for the evaluation.of the biases-and uncertainties associated with the measurement systems utilized to account for special nuclear material was inspected. The inspection consisted of an examination of the licensee's written procedures for performing the statistical calculations, the data base used to evaluate the statistical parameters and the statistical methods applied in the evaluation of the data base. The performance of the program during the January 11 through March 15, 1985, material

2 balance period was inspected. The program data for the following statistical parameters were inspected: the biases, systematic errors and random errors associated with weighing, sampling, and analyzing fuel receipts, elements, element sections, scrap fuel, and sludge.

A review of the licensee's written statistical procedures revealed that they contained narrative descriptions of the statistical calcu-lations rather than the mathematical models and the equations used for evaluating the statistical parameters. However, most of the calculations are performed by a computer using appropriate models.

It was also noted that the procedures were not numbered or dated.

The licensee indicated that, in order to provide further assurance that current procedures were being used, the procedures would be assigned numbers.and dated. (Inspector Followup Item 85-08-01) The procedures were included in a measurement control procedures manual and the manual was approved by the Nuclear Materials Manager.

In general, the biases and systematic errors were determined from i measurcments of standards and'the random errors were determined from replicate measurements of process materials. .The ' random weighing errors were determined from measurements of standards. Current measurement control data were used as the base for the statistical-calculation and the data were generated in accordance with the licensee's FNMC Plan and relevant license conditions. The statis-tical methods used to evaluate the data base were appropriate except as noted below. ,

The measurement uncertainties used by the licensee for fuel receipts were the uncertainties associated with the fuel vendor's measure-ments. Since the licensee books the vendor's values,- this is appro-priate. However, the uncertainties supplied to the licensee by the vendor were determined from data generated over three material balance periods rather than from one period. The licensee indicated that the vendor would be requested to report the uncertainties on a single period basis rather than on a three period basis. (During the inspection, the vendor was contacted and agreed to supply the data as requested.) (Inspector Followup Item 85-08-02)

It was noted that the FNMC Plan contained no commitment to update the uncertainties associated with the volume measuraments used to account for the SNM contained in element sections. During the inspection NMSS was advised of this issue. NMSS indicated that either the licensee would be requested to include such a commitment in the plan or a license condition would be issued to specify the frequency ~ for updating the uncertainties. (Inspector Followup Item 85-08-03)

One unresolved item was disclosed during the_ inspection. In an effort to test the licensee's-computer program for calculating the systematic error associated with sludge, the licensee was requested

- to enter the date from an example contained in a reference text.

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Since the results obtained by the licensee did not totally agree with

the results delineated in the reference text, this issue was deemed unresolved pending demonstration by the licensee that appropriate statistical methods were being used to determine the systematic error associated with the NDA measurements of sludge. This unresolved item requires more information in order to ascertain whether it is.  ;

acceptable, an item of nocompliance or a deviation. (Unreso~1ved item  ;

85-08-04)

b. .The-licensee's program for evaluating shipper-receiver differences was also inspected. The. comments'in paragraph a. above pertaining to.the statistical procedures used to determine the systematic error

• also apply _to the licensee's procedure for evaluating shipper-receiver differences. The program data for a fuel receipt (KAS-KDS-148) was selected for review. .The licensee's calculations of tne shipper-receiver difference and the 95 percent confidence-interval about the shipper-receiver difference were verified to be i

accurate.

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