ML20140C002

Forwards Corrected Page for Rept Submitted on 840417 Re Soil & Liquid Sampling Data for Energy Sys Group.Page Corrects First Paragraph of Rept Which Should Have Been 10CFR20, App B,Table II Values

ML20140C002
Person / Time
Site:	07000025
Issue date:	06/01/1984
From:	Thomas R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
To:	Crow W NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
References
23741, NUDOCS 8406180116
Download: ML20140C002 (2)

Text

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E aj g NUCLEAR REGULATORY COMMISSION REGION V

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}% 33 0.S. NUCLEAR REGULATORY COMMISSION NMS3 09 Mail Section MEMORANDUM FOR: W. T. Crow, Section Leader N m Uranium Fuel Licensing Branch Division of Fuel Cycle and Materials Safety, NMSS FROM: R. D. Thomas, Chief Materials Radiation Protection Inspection and Licensing Section Radiological Sa'.ety Branch

SUBJECT:

CORRECTED PAGE FOR THE REPORT OF SCIL AND LIQUID SAMPLING DATA FOR ENERGY SYSTEMS GROUP, BUILDING 001 Enclosed is a corrected page for the report sent to you on April 17, 1984.

This page corrects values in the first paragraph of the report which should have been the 10 CFR Part 20 Appendix B Table II values. The measurement results included in the report remain unchanged.

Please replace the affected page with enclosed corrected page.

//cd R. D. Thomas, Chief Materials Radiation Protection Inspection and Licensing Section

Enclosure:

As stated

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. DETAILS

, A. Persons Contacted F. W. Feiler, Vice President and Controller, Finance and Administration M. E.LRemley, Director, Health Safety and Radiation Services D. Speed, Health and Safety Specialist R. J. .Tuttle, Manager, Radiation and Nuclear Safety Unit

,B. Sampling' Oak' Rid'ge' Associated Universities (ORAU) under contract to the NRC

-performed the overcheck of the Energy System Group's survey of Building 001 scheduled for removal from the licensee's NRC license (SNM-21). The NRC

- submitted 113 soil samples and 2. liquid samples for independent analyses

- at the' Radiological and Environmental Sciences Laboratory of the 'daho 5 ~

' Nuclear Engineering Laboratory (INEL) to determine if NRCirelcar a limits s' , were being met'(30 pCi/g soil and'3E-5 uCi/ml water for enriched uranium, as g.

.1E-4 uCi/ml water for Mn-54, and 3E-5 uCi/ml water for Co-60). The results 3'? ,

of the analyses were shared with the liceusee.

3 CT , - 1. ' Soil Samples. ~

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t . j The soil samples collected were subsampled (split) for analysis af ter~

pre-treatment. The pre-treatment included drying, (heating in a

~. ' , microwave oven and heating on a hot plate) ball milling, and

- screening to -9 mesh. The screened mat'erial (about 2 pounds) was a '

,.' ', then riffle split to a sample size of about 200' grams. The NRC samples

. were shipped to INEL for uranium analyses by gamma spectrometry.

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Alpha spectrometry was 'used for samples exceeding a uranium content 3- - i . of 25 pCi/g. The licensee retained a fraction of the material NRC s sampled in the event of"a significant discrepancy. The licensee J; appropriately cleaned up areas _where the INEL soil analyses indicated:

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- .NRC release limits were exceeded. Samples from two trenches and one pile of soil exceeded,the release limit. The licensee removed the

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contaminated soil from the trenches and shipped it to burial along-with the' pile of contaminated soil already, separated. Five additional' samples ~from the first trench and three from the second 4

7 trench confirmed that both trenches now contained soil contamination less than the NRC' release limit.

2. Liquid Samples. \ ,:

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. A separate item needing attention involved a drain pipe with elevated readings that was identified by ORAU during the confirmatory survey. The drain pipe contained sludge contaminated with an estimated 18 uCi of HEU (about 0.3g of 93 percent enriched

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