ML20215D118

Insp Rept 70-0687/86-04 on 860818-22.No Noncompliance Noted. Major Areas Inspected:Nuclear Matl Control & Accounting, Including Facility Operations & Internal Controls, Measurement Sys,Physical Inventory & Records & Repts

ML20215D118
Person / Time
Site:	07000687
Issue date:	09/29/1986
From:	Della Ratta A, Keimig R, Zibulsky H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20215D117	List: ML20215D114 ML20215D118
References
70-0687-86-04, 70-687-86-4, NUDOCS 8610100752
Download: ML20215D118 (5)

Text

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U.S. NUCLEAR REGULATORY COMMISSION REGION I Report No. 70-687/86-04 Docket No.70-687 License No. SNM-639 Safeguards Group I Licensee: Cintichem, Inc.

P.O. Box 816 Tuxedo, New York 10987 Facility Name: Sterling Forest Research Center Inspection At: Tuxedo, New York Inspection Conducted: August 18-22, 1986 Date of Last Material Control and Accounting Inspection: February 10-14, 1986 Type of Inspection: Routine, Unannounced Material Control and Accounting Inspectors: /[ f 9-Ep-fg A. Della Ratt(, Safeguards Auditor date 1 9-29'-74:>

H. Zibulsky, C4 mist \ ciate Approved by- ,- ,

df. R. Keimig, hief, f

eguards Section f.-date 2 [-[d

/ Nuclear Ma eria afety and Safeguards Branch, SS Inspection Summary: Inspection on August 18-22, 1986 (Report No. 70-687/86-04)

Areas Inspected: Routine, unannounced inspection of nuclear material control and accounting including: facility operations and internal controls; measurement systems; measurement control and statistics; physical inventory; and records and reports.

Results: The licensee was in compliance with NRC requirements in the areas examined during the inspection.

8610100752 861002 PDR ADOCK 07000687 C PDR _

DETAILS

1. Key Persons Contacted

• C. Konnerth, Manager, Site Operations

• J. Ditton, Supervisor, Health Physics

• P. O'Callaghan, Supervisor, Quality Control G. Wright, MBA-1 Custodian L. Pitt, MBA-2 Custodian T. English, Reactor Operator and MBA-3 Alternate Custodian G. Richards, MBA-4 Custodian E. Barral, Laboratory Technician A. Dolan, Laboratory Technician .

The inspectors also interviewed other licensee employees associated with plant operations and nuclear material control.

• present at exit interview

2. 30703- Exit Interview The inspectors met with the licensee representatives indicated in para-graph 1 at the conclusion of the inspection on August 22, 1986 and sum-marized the scope and findings of the inspection.

At no time during this inspection was written material provided to the licensee by the inspectors.

3. 85205- Facility Operation and Internal Controls The inspector determined through a review of records, that the licensee maintained procedures to ensure that all receipts of special nuclear material (SNM) were accurately accounted for. The authorized possession and use of SNM were as specified in the facility license.

The inspector determined that the licensee properly prepared and main-tained control of SNM transfer documents. The inspector reviewed all of the transfer documents issued during the period July 1, 1985 -

February 27, 1986 for: number of items; quantity of SNM transferred; signatures of the authorized persons involved in the transfer; and accu-racy of the central record system.

The inspector determined that: the licensee confirmed all receipts of SNM within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, through examination of source documentation and weight verifications; the uranium content of receipts was verified within 5 work-ing days, as required; the licensee had not experienced any significant shipper-receiver differences for the period July 1,1985 - February 27, 1986; and receipts involved only small quantities of uranium (average 610 grams per receipt).

F-3 The inspector reviewed the DOE /NRC Form-741's completed for these transactions, against criteria for: preparing and completing the form; timeliness of issuance; accuracy of data; and authorized signature. No discrepancies were identified.

4. 85207- Measurement Systems The inspector observed licensee personnel analyze the uranium content of three standards that were prepared with normal uranium and certified by the New Brunswick Laboratory (NBL). The matrices and concentrations of the standards were within the licensee's normal operating range. Two ,

analysts, using the gravimetric, Davies and Gray, titration procedure, performed the analyses.

One of the analysts, who was new to the position, obtained results that were significantly biased in two of the three standards and large uncer-tainties in all three. These biases and uncertainties were due to the over-titration of the calibration standards and poor titration technique.

It is expected that with more experience, that analyst's techniques will improve.

Analyst 1 Results -

NBL Standard Relative % Bias Uncertainty 0.005048 gU/ml -0.74 10.39 0.008118 gU/ml -0.33 10.52 0.010253 gU/ml -1.61 0.45 The second analyst had good titration technique, but also had large un-certainties associated with the analyses. Investigation found that this was due to a bad electrode. There were no significant biases because of the large uncertainties.

Analyst 2 Results NBL Standard Relative % Bias Uncertainty 0.005048 gU/ml -0.30 10.44 0.008118 gU/ml 10.31 10.59 0.010258 gU/ml 0.03 10.49 Eight uranyl nitrate solutions of varying concentrations will be sampled for anaylsis. Duplicate samples will be sent to NBL for independent analyses. On completion of the U and U-235 analyses by both laboratories, a statistical evaluation of the results will be made by the NRC Chemist.

(Inspector Followup Item 86-04-01) 1 l'

O 4

~

5. 85209- Measurement Control and Statistics The measurement control program was reviewed by the inspector and compared to the licensee's Fundamental Nuclear Material Control Plan (FNMCP),

Chapters 4.1, 4.2, and 4.5 and License Conditions 4.1, 4.2, and 4.3. The licensee is exempt from determining systematic errors, random errors, and associated limits of error of material unaccounted for (LE1D), if the plant inventory difference is less than 300 grams of U-235. The licensee has not exceeded this limit.

All glassware (volumetric flashes and pipettes) used in the accountability analyses for uranium were calibrated and documented. The uranium cali-bration standard was prepared and certified from NBS-960, uranium metal primary standard. The control standard was prepared and certified from NBS-9508, U 03 8 primary standard. Data were generated from the control standards to develop a control chart with 12 sigma and 3 sigma acceptance criteria.

The licensee's measurement control program identified the problems en-countered by the two analysts (see paragraph 4). The control standards, which were analyzed with NRC standards, resulted in values more than 2 sigma on the control chart. This alerted the analyst that the measurement system was not performing properly. Upon further investigation, a de-fective electrode was found and replaced.

The inspector reviewed the findings of the measurement Quality Assurance Program Audit, dated, October 24, 1985, and the responses by the Nuclear Safeguards Committee.

A finding mentioned in the audit was a small (insignificant), but con-sistent negative bias in the shipper-receiver differences for ~U0.

38 The auditor had compared the split sample analyses with the licensee's labora-tory and with NBL. The comparison indicated no significant measurement differences between the two laboratories. The inspector discussed this problem with licensee management. The inspector questioned whether a positive bias in the measurements of the uranium leaving the plant was being encountered and was told that there was, and that the two biases did cancel each other out. The inspector informed the licensee that the pro-bable cause for the negative bias was that the oxides were absorbing moisture. The inspector advised the licensee to perform the uranium analysis for the U38 0 after calcining the oxide for one hour at about 900 c, to determine whether that was, indeed, the cause. The licensee agreed.

6. 85211- Physical Inventory The inspector reviewed the licensee's supporting records for the physical inventory taken in February 27, 1986 and determined that the inventory was conducted in accordance with approved procedures, based upon measured values, and accurately presented within the SNM inventory report. The master log and MBA logs were reconciled and adjusted for the physical inventory results within 30 days.

0-5 a

The inspector performed a verification of the licensee's SNM inventory on August 21, 1986. Inventory line items were selected at random in Material Balance Areas and compared to book records.

No discrepancies were identified.

7. 85215- Records and Reports The inspector audited the nuclear material control records and reports for the high enriched uranium physical inventory material balance periods ending September 5, 1985, November 5, 1985, January 2, 1986, and February 27, 1986. All line items on the SNM inventory repor+t were traced to source documents and compared with the records maintained by the licensee and the DOE-NMMSS computer tabulations. No discrepancies were identified. The Material Status Reports (DOE /NRC Form 742) for the per-iods ending September 30, 1985 and March 31, 1986 were submitted as re-quired by 10 CFR 70.53.

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