ML20101T328
| ML20101T328 | |
| Person / Time | |
|---|---|
| Site: | 05000394 |
| Issue date: | 01/30/1985 |
| From: | Schell T CALIFORNIA POLYTECHNIC STATE UNIV., SAN LUIS OBISPO |
| To: | Erickson P Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20101T330 | List: |
| References | |
| NUDOCS 8502060105 | |
| Download: ML20101T328 (6) | |
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CALIFORNIA POLYTECI4NIC STATE UNIVERSITY SAN LUIS ODISPO, CALIFORNIA 93401 -
(805) 546-0111 -.
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30 January-85 . ;-
Mr. Peter B. Erickson, Proje'ct Manager Operating Reactors Branch #5 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Erickson:
Pursuant'to your letter dated October 6, 1981, Docket No. 50-394, author-izing California Polytechnic State University to dismantle the AGN-201 Training Reactor in accordance with our dismantling plan dated September 8, 1981, and all related correspondence, we request the termination of license number R-121, d.ecomission of the Reactor, and release of the facility for uncontrolled use.
The AGN-201 Reactor has been dismantled . All reactor fuel and components containing ' residual radioactive material have been removed from the facility.
The fuel was shipped to the Department of Energy, Oakridge Y-12 Plant, Oak-ridge Operations, Oakridge, TN. The components containing residual radio-active materials and the RaBe Neutron Sources have been shipped to U.S.
Ecology, Richland, Washington, Low-Level Radioactive Waste Disposal Facility.
(See attached certification and Radioactive Waste Shipment and Disporal Form.)
The final radiation surveys have been performed (for details co'nsult the Final Decommissioning Report for the AGN-201 Reactor submitted on January
, 24-25,1985). It is c'oncluded, after reviewing the data, that there is no adverse impact to the health and safety of the general public, employees, or students at the University.
As specified in the dismantling plan, radiation levels have been reduced to background levels estelishing radiation levels as low as reasonably achievable. .
Thank you for the continuation of good radiation safety.
1 S' rely, Thomas A. Schell do Radiation Safety Officer, Public_ Safety j 3 ohn A. Zwolinskit l .
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CALIFORNIA POLYTECHNIC STATE UNIVERSITY SAN LUIS OBISPO, CALIFORNIA 93407 ,
(805) 546-0111 0ATH OF AFFIRMATION I, Thomas A. Schell, represent California Polytechnic State University's Radiation Safety Office in all matters relating to the submission of documents to the U.S. Nuclear Regulatory Commission referencing Reactor License #R-121; Docket No. 50C-394 and final decommissioning of the AGN-201 Nuclear Reactor. As appointed Radiation Safety Officer for California Polytechnic State University and pursuant to subchapter D-Preparation, Transmittal, and Processing of Documents code of Federal Regulations Title 1, Chapter 1, Part 18.3 submission of documents and letters of transmittal; 18.5 Certified Copies; 18.6 Form of Certification; and 18.7 Signature; I do hereby affirm that each copy of each document is certified to be a true copy of the original on this twenty-fifth day of January in the year of our Lord one thousand nine hundred and eighty five.
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Dated: / - M - -
Thomas A. Schell Radiation Safety Officer lutelbed and n to before me this AB to g
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71-0492
'. l California Polytechnic State University ATTN: Mr. Jeffrey L. Hall Department of Public Safety San Luis Obispo, CA 93407 .
Gentlemen:
Enclosed is Quality Assurance Program Approval No. 0492, Revision No. O.
This approval is applicable to a one-time sh.ipment of enriched uranium-oxide fuel discs from a dismantled AGN-201 reactor.
Please note that pursuant to the general license provisions of 10 CFR 71.12(a), (b) that the proposed shipment must be in a Department c of Transportation specification container or an NRC approved package.
Sincerely,
{
Charles E. MacDonald, Chief Transportation Certification Branch
- Division of Fuel Cycle and J Material Safety, NMSS
Enclosure:
As stated .
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QUALITY ASSURANCE PROGRAM APPROVAL ,y92 , ,9 FOR RADIOACTIVE MATERIAL PACKAGES O
Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974, as amended,,and Title 10,
. Code of Federal Regulations, Chapter 1, Part 71, and in reliance on statements and representations heretofore made in item 5 trir the person named in item 2.the Quality Assurancn Program identified in item 5 is hereby approved. This approval is issued to satisfy the requirements of Section 71.51 of 10 CFR Part 71. This approval is subject to all applicable rules, regulations, and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
- 2. N AME 3. EXPIRATION DATE California Polytechnic State University December 31, 1983
- "'"^l$ep"a'r*tment of Public Safety
- a. oocxEy NvMeER San Luis Obispo !"^lA l2'gjggy 71-0492 6.C.UALITY A55vRANCE PROoRAM APPLICATION DATE(s)
February 4,1983 ,
S. CO NDITIONS The activities -authorized by this approval are procurement of packaging, use, and one-time shipment of polyethylene fuel and control rod fuel discs from a AGN-201 dismantled reactor.
It shall remain the responsibility of the licensee-user to ensure that all transportation activities meet the requirements of Section 71.51 of 10 CFR Part 71.
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Docket No. 50-394 BUSINESS r..-inifiS
- California Polytechnic State University San Luis Obispo, California 93401
% R L.~y 4 A MM Attention: R. W. Adamson ('#g'$.-
gr,4*. s Reactor Administrator '
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y Gentlemen:
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Subject:
NRC Inspection of AGN-201 Reactor This refers to the inspection conducted by Mr. T. Young Jr. of this office on March' 14-16, 1983, of activities authorized by NRC License .
I No. R-121, and to the discussion of our findings held by Mr. Young with
, you and other members of your staff.
- Areas examined during this inspection are described in the enclosed
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inspection report. Within these areas, the inspection consis'ted "of
- selective examinations of procedures and representative records, interviews with personnel *, and observations by the inspector.
No items of noncompliance with NRC requirements were identified within the scope of this inspection.
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure will be placed in the NRC Public Document Room unless you notify this office, by telephone, within ten days of the date of this letter and submit written application to withhold information contained therein within thirty days of the date of this letter. Such application must be consistent with the requirements of 2.790(b)(1). '
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Should you have any questions concerning this inspection, we will be glad to discuss them with you.
Sincerel ,
. D. H. Sternberg, Chi
, Reactor Projects Branch No. 1
Enclosure:
NRC Inspection Report i
No. 50-394/83-01 1
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U. S. NUCLEAR REGULATORY C0tltllSSION REGION V
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I Report No.
50-394/83-01' Docket No. . 50-394
! License No. R-121 Licensee:
Californie Pclytechnic State University -
San Luis Obispo, California 93407 Facility Name:
Research Reactor (AGN-201)
Inspection at:
California Polytechnic State University Inspection conducted: March 14-16, 1983 ll t
i Inspector: k bh ie " ~~
T. Young, Jr., .ef, Reg or rojects Section 2 Date Signed Approved By: *
),28!8 D. M. Sternberg, Chief, Reactc r Projects Branch I DJte Signed Q
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Summary: .
Inspection on'Harch 14-16, 1983 (Report No. 50-394/83-01)
Areas Inspected:
defueling. Routine unannounced inspection of facility one NRC inspector.The inspection involved seven inspector-hours onsite Results:
_ No items of noncompliance or deviations were identified. .
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- 1. Persons Contacted *
( *R. Adamson, Reactor Administrator -
- R. Fisher, Senior Reactor Operator
! *A. Rosen, Nuclear Physicist
- J. Nall, Radiation Safety Of ficer
- T. Nash, Technician '.
J. Neelands, Technician ,
- Denotes those attending the exit interview. ; I
- 2. Reactor Core Disassembly i F
The inspector witnessed the reactor core being disassembled. The 4
procedure used was the one proposed by the licensee in his application for authorization to dismantle the facility and dispose of component parts dated April 30, 1981, and as revised by letter dated September 8, 1981. The application was approved by the NRC on j October 6, 1981.
! The procedure was followed step by step and the fuel handling was. '
supervised by the senior licensed operator. The fuel was then ;
packaged in two Department of Transportation approved shipping t
containers.. The two containers were to be bolted shut, sealed and !
stored in the reactor room until they could be shipped.
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! No items of noncompliance or deviations were identified.
. 3. Exit I'nterview .
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- The inspector met with licensee representatives (denoted in l ,
paragraph 1) at the completion of the inspection. The inspection j
findings were discussed, as set forth in paragraph 2.
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