ML20211F705

Insp Rept 70-1201/99-02 on 990726-27.No Violations Noted. Major Areas Inspected:Decommissioning Activities Associated with Wet Weather Stream

ML20211F705
Person / Time
Site:	07001201
Issue date:	08/19/1999
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211F703	List: ML20211F697 ML20211F705
References
70-1201-99-02, NUDOCS 9908310057
Download: ML20211F705 (6)

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l U. S. NUCLEAR REGULATORY COMMISSION t

REGION ll

. Docket No.

70-1201 I

License No.: SNM-1168 Report No.: 70-1201/99-02 Licensee: Framatome Cogema Fuels l

l Facility: Lynchburg Manufacturing Facility Location: Lynchburg, VA 24506 Dates: July 26 through 27,1999 Inspector: C. Hughey, Sr. Resident inspector Approved By: E. McAlpine, Chief Fuel Facilities Branch Division of Nuclear Materials Safety l

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Enclosure 9908310057 990819 '

PDR ADOCK 07001201 C PDR

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EXECUTIVE

SUMMARY

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Framatome Cogema Fuels NRC Inspection Report 70-1201/99-02 This announced inspection focused on the observation and evaluation of the licensee's decommissioning activities associated with the wet weather stream.

Decommission Activities Contract personnel conducting radiological surveying activities were knowledgeable of the survey methodologies and the proper use of the instrumentation.

Radiological survey instruments were properly calibrated and maintained.

Twelve randomly selected split samples were collected for comparison. The licensee's final report containing survey results and final analyses will be sent to the Office of Nuclear Material Safety and Safeguards for review and approval.

Attachrr/201 List of Persons Contacted Inspection Procedure Used List of item Opened 4

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REPORT DETAILS

1. Wet Weather Stream Decommissionino Activities (88104)

a. Inspection Scope The inspector reviewed documentation and observed activities associated with the survey and remediation of a contaminated wet weather stream. Split soil samples were also collected for analysis and comparison.

b. Observations and Findings As a result of a decommissioning radiological survey of the wet weather stream conducted during March 1998, the licensee identified soil contamination in excess of the applicable limits (See inspection Report 70-1201/98-01). Further significant soil

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remediation was subsequently completed and final surveys of the remediated areas were completed in July 1999. The NRC approved the licensee's " Characterization and Final Status Survey Plan for the Wet Weather Stream," dated November 25,1998.

Upon arrival at the site, the inspector observed that significant excavation activities in and around the stream bed had been completed, including between six to twelve inches of excavation in several grided areas. The removed soil had been placed into numerous 55-gallon drums that were then stored nearby in an unaffected area. The licensee stated that they filled 2680 drums. At the end of the inspection, a disposal plan had not been determined.

Cabrera Services, Inc. of Vemon, Connecticut, conducted the radiological characterization, surveying, and technical support activities. The inspector reviewed the resumes and conducted informal interviews of onsite personnel, and determined that they were knowledgeable of the survey methodologies and the proper use of the instrumentation, as discussed in the approved Final Status Survey Plan.

The inspector reviewed calibration records for the instruments used for the gamma walkover surveys and verified they were properly calibrated. The two instruments used were:

- Eberline SPA-3 (2x2 Sodium lodide crystal)

- Ludlum Model 18 (2x2 Sodium lodide crystal)

The inspector also reviewed calibration records for the gamma spectroscopy counting system used for the high purity germanium In Situ gamma spectroscopy measurements.

Specifically reviewed were results from energy checks, efficiency checks, and full width half maximum determinations. No discrepancies were noted. The inspector also reviewed daily quality control check records and noted no significant instrument drift.

On July 27,1999,12 soil samples were collected and split with the inspector. The inspector randomly picked the sample locations just before beginning sampling activities.

The inspector directly observed the collection of all samples and maintained direct control and custody of the NRC split samples throughout the sampling, labeling, packaging, and shipping process. Proper sampling techniques were consistently used.

The samples were shipped to an NRC contractor for analysis on July 28,1999. An inspector follow-up item (IFI) was opened to compare the licensee's sample analyses results with NRC's results for confirmatory measurement purposes (IFl 70-1201/9-02-01).

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c. Conclusions -

Contract personnel were knowledgeable of the survey methodologies and the proper use of theinstrumentation.

Radiological survey instruments were properly calibrated and maintained.

Twelve split samples were collected for comparison. The licensee will send their final report containing survey results and final analyses to the Office of Nuclear Material Safety and Safeguards for review and approval.

2. Exit Interview The inspection scope and results were summarized on July 27,1999, with those persons indicated in the Attachment. Dissenting comments were not received.

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ATTACHMENT -

l 1. LIST OF PERSONS CONTACTED Licensee T. Allsep, Acting Manager of Safety and Licensing D. Gordon, Senior Health Physicist i

1. J. Matheson, Plant Manager Cabrera Services. Inc.

S. Masciulli, Health Physicist D. Watters, Health Physicist B. Bower, Radiological Engineer

1. Contacted by telephone on August 11,1999

2. INSPECTION PROCEDURE USED IP 88104 Decommissioning inspection Procedure for Fuel Cycle Facilities

3. OPEN ITEM ltem Number Status Descriotion 70-1201/99-02-01 Open Inspector Follow-up Item - Comparison of split sample results.

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