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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20056G0041993-06-25025 June 1993
Submits Info Re Implementation of Training Rule 10CFR50.120 for Licensees of Plant in Decommissioning Process
ML20107M8001984-10-29029 October 1984
Requests Addl Info on Decommissioning & Decontamination of Tuskegee Inst AGN-201 Reactor
ML20098D9311984-09-17017 September 1984
Requests Permission to Move Reactor Outside Engineering Bldg & to Remove Stacked Concrete Wall Dividing Reactor Area from Rest of Facility in Advance of Termination of License R-122.Space Needed for Const of Wind Tunnel
ML20080D6801983-08-0909 August 1983
Requests Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20080D6681983-08-0909 August 1983
Forwards Request for Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20063K8141982-08-31031 August 1982
Requests Authorization to Dismantle AGN-201 Reactor, Terminate License,Dispose of Remaining Reactor Components & Retain Fission Plate for Possible Use W/Neutron Generator. Fuel Shipped to Oak Ridge,Tn on 820701
ML20054L3881982-06-16016 June 1982
Ltr to All Research & Test Reactor Licensees Requesting That Reg Guide 2.6 (for Comment) & ANSI/ANS-15.16 (Draft II Dtd 811129) Be Used to Meet Requirement of Final Amend to 10CFR50.54(r) Re Emergency Planning.Fr Notice Encl
ML20149K1911980-05-0707 May 1980
Generic Ltr 80-38 to All Nonpower Reactor Licensees Re NPR Physical Protection Requirements.Summary of Certain NPR Physical Protection Requirements Encl & Should Aid in Determining Safeguards Requirements Applicable to Facility
ML19210E3931979-11-19019 November 1979
Notifies of Typographical Error on Page 4 of App A,Tech Specs Re Safety Limits.Should Read Reactor Power Level Should Not Exceed 100 Milliwatts
ML19254D8831979-10-25025 October 1979
Forwards Executed Amend 6 to Indemnity Agreement E-57
ML19261C7251979-03-21021 March 1979
Forwards Revised Physical Security Plan for Approval.Encl Withheld (Ref 10CFR2.790)
1993-06-25
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Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20098D9311984-09-17017 September 1984
Requests Permission to Move Reactor Outside Engineering Bldg & to Remove Stacked Concrete Wall Dividing Reactor Area from Rest of Facility in Advance of Termination of License R-122.Space Needed for Const of Wind Tunnel
ML20080D6801983-08-0909 August 1983
Requests Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20080D6681983-08-0909 August 1983
Forwards Request for Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20063K8141982-08-31031 August 1982
Requests Authorization to Dismantle AGN-201 Reactor, Terminate License,Dispose of Remaining Reactor Components & Retain Fission Plate for Possible Use W/Neutron Generator. Fuel Shipped to Oak Ridge,Tn on 820701
ML19210E3931979-11-19019 November 1979
Notifies of Typographical Error on Page 4 of App A,Tech Specs Re Safety Limits.Should Read Reactor Power Level Should Not Exceed 100 Milliwatts
ML19254D8831979-10-25025 October 1979
Forwards Executed Amend 6 to Indemnity Agreement E-57
ML19261C7251979-03-21021 March 1979
Forwards Revised Physical Security Plan for Approval.Encl Withheld (Ref 10CFR2.790)
1984-09-17
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Category:INCOMING CORRESPONDENCE
MONTHYEARML20107M8001984-10-29029 October 1984
Requests Addl Info on Decommissioning & Decontamination of Tuskegee Inst AGN-201 Reactor
ML20098D9311984-09-17017 September 1984
Requests Permission to Move Reactor Outside Engineering Bldg & to Remove Stacked Concrete Wall Dividing Reactor Area from Rest of Facility in Advance of Termination of License R-122.Space Needed for Const of Wind Tunnel
ML20080D6801983-08-0909 August 1983
Requests Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20080D6681983-08-0909 August 1983
Forwards Request for Authorization to Dismantle & Dispose of Reactor Components & Terminate License R-122
ML20063K8141982-08-31031 August 1982
Requests Authorization to Dismantle AGN-201 Reactor, Terminate License,Dispose of Remaining Reactor Components & Retain Fission Plate for Possible Use W/Neutron Generator. Fuel Shipped to Oak Ridge,Tn on 820701
ML19210E3931979-11-19019 November 1979
Notifies of Typographical Error on Page 4 of App A,Tech Specs Re Safety Limits.Should Read Reactor Power Level Should Not Exceed 100 Milliwatts
ML19254D8831979-10-25025 October 1979
Forwards Executed Amend 6 to Indemnity Agreement E-57
ML19261C7251979-03-21021 March 1979
Forwards Revised Physical Security Plan for Approval.Encl Withheld (Ref 10CFR2.790)
1984-09-17
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Euskegec3ttstitute FOUNDED BY BOOKER T. WASHINGTON,1881 School of Engineering and Architecture Tusnegeeinstitute ALABAMA 36088 OFFICE OF THE DEAN TELEPHONE: (205) 727-8355 l
August 9, 1983 l
Mr. Darrell G. Eisenhut Director of Licensing
- U.S. Nuclear Regulatory Commission l h'ashington, D. C. 20545 I l l
Dear Mr. Eisenhut:
RE: Docket 50-406 Enclosed are three signed and notarized originals of a joint request to the R:cicar Regulatory Commission (NRC) for authorization to both dismantic and dispose of our AGN-201 reactor components and also for termination of our operating license R-122. President Payton has signed these requests as the duly authorized officer (President) of Tuskegee Institute. {
You correctly note in your 1ctter of January 28, 1983, that the reactor never operated here at Tuskegee Institute and its fuel ins never loaded. As you further note, the fuel was shipped back to its owner, the U.S. Department of Energy, last year. The fission plate which was to be I used when the reactor became operational has recained here at the Institute for possible use in the nuclearIrogram. It consists of 20% enriched uranite with a total of 28 grams of U-235. This fission plate is now carried under our Alabama License S21-228, A?.endment No. 6 (see copy enclosed) as per our request of February ll, 1983. Contract No. DE-AC05-76ER04244 (Modification No. M004) between Tuskegee Institute and the U.S. Department of Energy covers the use of this plate. <
A complete report of the results of measurements of surface contamination I of residual radioactivity on the AGN-201 is included for your perusal. The l information provided covers the requirements of Regulatory Guide 1.86 as well as nonnal radiation safety exposure requirements as perfonned with a suney meter. All the results for all the components are considered no greater than background since they fall within statistical accuracy limitations of that measurement.
8308300540 830809 gW PDR ADOCK 05000406 W jgl I l pg l
Mr. Darrell G. Eisenhut Page 2' August 9, 1983 Since the measured radiation icvels for each of the reactor components indicates negligibic surface contamination, we request authorization to
. dispose of these components as we see fit. We however, have no plans to l use this as a reactor again nor do we plan to ship it to any other site for use as a reactor. We trust this covers the intent of 10CFR 50.82.
l If you have any questions concerning our requests, please feel free to contact me (205) 727-8355 or Phil loretan (205) 727-8458 in our Radiation Safety Office.
Sincerely yours, tw -
Vascar . Harris Dean VGI:mhp Enclosures
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