ML20136H410
| ML20136H410 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 01/26/1982 |
| From: | Macki J, Rampy L DOW CHEMICAL CO. |
| To: | Ridgeway K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20136C633 | List: |
| References | |
| FOIA-85-483 NUDOCS 8508200307 | |
| Download: ML20136H410 (2) | |
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DOW CHEMICAL U.S.A.
MIoLAND. MICH6GAN 48640 knuary 26, 1982 P".T :;IP *.L STe'.7F 7:n i~f3fS 3/D l
r r, Mr. Kenneth Ridgeway 4/n l
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United States Nuclear Regulatory Commission f
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799 Roosevelt Road anTv i
Glen Ellyn, Illinois 60137 g
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Dear Sir:
This refers to your report dated 1-13-82 on your inspection of the Dew TRIGA facility December 7-10, 1981.
We wish to submit the following information and ask that the report be modified before it is placed in the Public Document Room:
- 1. Section 11, Radioactive Effluents, states:
" Solid wastes, mainly decayed sanples, are disposed of under NRC By-Product License No.12(sic)-
0C265-06 which permits incineration.
About one 55-gallon drum of wastes frem the reactor operation is incinerated each year".
Actually, no caterials from the TRIGA are disposed of by incineration under the By-Product License #21-00265-06.
All radioactive wastes from the TRIGA cperation are currently disposed of as solids through burial at Barnwell, South Carolina.
- 2. Section 9 Radiation Control, refers to the Dow Radiation Protection Manual as the source of the statement that " Ionization chamber instruments are calibrated quarterly", and states "the licensee agreed to change the quarterly frequency definition in the manual to agree with the standard quarterly definition of 92 days plus 24 days".
Since your visit here Tracy Parsons has had an NRC inspection, concerned with the by-Product Materials License #21-00265-06, during which the calibratien timirg was discussed.
As a result Tracy is now in the process of rewriting the sectier, on calibration in anticipation of a license renewc1 application due in 1983.
Some meters, based on experience of usage and past calibrations, may go to semi-annual or some other calibration intervals.
In the license renewal application the calibration interval will be defined.
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AN OPtHATWO UNet or THE DoW CHEMsCAL COMPANY FEB 5 T42
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i Mr. Kenneth Ridgeway United States Nuclear Regulatory Commission January 26, 1982 We would appreciate having you de2ete the specific reference to "90 days plus 24 days" and substitute a statement to the effect that the By-Product License is being amended to re-define the calibration periods.
In a telephone conversation on 1-19-82 Mr. Duane Boyd suggested to C. W. Kocher that item 1) above could be satisfactorily modified by removing the paragraph which discusses incineration of wastes. We agree.
The Reacter Suke'rvisor, Dr. Kocher, will be pleased to provide any further information you may require.
Si. erely, J. b1 kiuA '
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<L. W. Rampy, Chairman J. H. Macki, Chairman Radiaticn Safety Committee Reactor Oparations Committee 1803 Building 1602 Building kT j
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g DOW CHEMICAL U.S.A.
MICHIGAN DIVISION March 11, 1985 Mr. George M. McCann U.S.N.R.C.
Region III 799 Roosevelt Road Glen Ellyn, IL 60137
Dear Sirs:
This is notification as to our intent to purchase a 252-Californium neutron source from Amersham Corporation, Arlington Heights, Illinois.
The source is NRC approved, #CVN-CYS, and is covered under our license 21-00265-06.
This neutron source is 50 micrograms, 27 mil 11 curies.
This source will be j
used for research purposes.
Sincerely, i
Ward L. Rigot Assistant Reactor Supervisor
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Dow Triga Research Reactor ne i
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REG 3'LIC30 21-00265-06 PDR
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AN o#EMATING UNIT OF THE DOW CHEM 6 CAL COMPANY ey 4 r
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JUN 17 bd Docket No. 40-17 Dow Chemical Company ATTN:
D r. L. W. Ranpy, Chairman Radiation Safety Committee 1803 Building Midland, MI 48640 Gentlemen:
We have received from our contractor, Oak Ridge Associated Universities (0RAU),
a draft report of ORAU's August 1984, confirmatory survey of the former Dow/Wellman foundry site in Bay City, Michigan.
In a telephone discussion May 24, 1985, M. C. Schumacher of this office informed R. A. Olson of Dow that the report reveals that thorium residues at several locations exceed the guidelines for unrestricted release that were conveyed to you in our letter of September 11, 1984.
This letter is to advise you that the site should be reexamined and decontaminated to acceptable levels.
A copy of the draft ORAU report is enclosed for your use in determining the areas which require further action.
After this work is completed and reported we will schedule another closecut survey.
A representative of this office and of ORAU expect to be in Bay City on another matter during the week of June 24, 1985, and will contact Mr. Olson at that time.
If you have any questions concerning this matter please telephone Mr. Schumacher or myself at (312) 790-5500 Sincerely,
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Carl J. P periello, Chief Emergency Preparedness and Radiological Protection Branch
Enclosure:
As stated cc w/ encl:
DMB/0ccument Control Desk (RIOS)
W. Crow, NHSS i
D. Cool, NMSS J. Berger, ORAU R. A. Olson, Dow I
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