ML20034C874

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Forwards Supplemental Rept Cimarron Facility Closure Responses to NRC Questions
ML20034C874
Person / Time
Site: 07000925
Issue date: 05/15/1990
From: Stauter J
CIMARRON CORP.
To: Haughney C
NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20034C875 List:
References
NUDOCS 9005180036
Download: ML20034C874 (2)


Text

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May 15, 1990 i

i CERTIFIED MAIL RETURN RECEIPT REQUESTED j

Charles Haughney, C' hief Fuel Cycle Safety Branch

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Division of Fuel Cycle, Medical, Academic and Commercial Use Safety l

U.S. Nuclear Regulatory Commission Washington, D.C.

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RE:

License SNM-928; Docket 70-925 Amendment. Request:: On-Site Disposition of Uranium Containing Soils Meeting NRC Branch' Technical Position Option 2 Criteria I

Submittal of Supplemental Material i

Dear Mr. Haughney:

Attached is the supplemental report prepared by James L.

Grant and I

I Associates, Inc. ' addressing NRC's comments relating to the Cimarron

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Site Investigation Report.

This additional information responds to the specific concerns discussed with NRC at the March 1,1990 meeting in your offices in Rockville, Maryland.

In addition to comments on J.L.

Grant's' geohydrological report Cimarron Corporation has included in the report a revised volume i

estimate for the soil to be left at the Cimarron Facility under the provisions of Option 2 of the Branch Technical Position.

Cimarron collected additional soil samples from the uranium plant yard area and, based on the analyses, estimated the volume of soil to~be left on-site at aaproximately 18,500 cubic -yards.

The majority of this 4

soil, approx 1mately 15,000 cubic
yards, will be placed into the designated Option 2 disposal area.

Approximately 3,500 cubic yards of Option 2 level soil will be lef t in-situ within the perimeter of the uranium plant yard area under four feet of clean soil.

These soil volume estimates are based on analysis' of the soil s ampl e s

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using the - Cimarron -Facility Gamma Spec. System.

Ten percent of the samples were submitted to the Kerr-McGee Technical Center for i

radiochemical analysis for comparison against the facility gamma i

spec, results for quality control purposes.

This. data is al s o provided in the supplement submitted with this letter.

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If you have ~any _ questions concerning the information contained in the attached report, please contact me at your earliest convenience.

Sincerely, j

. C. -

J.C. Stauter. Director Environmental Affairs j

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Attachment (4 copies) cc:

P. Brown - OSDH - Radiological Health (1 copy) f

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