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9 Authorized use: For use in'accordance with the statements, Representations, and [ | 9 Authorized use: For use in'accordance with the statements, Representations, and [ | ||
condition specified in'the licensee's. application' transmitted by letter dated January 16, 1986; and s'upplement dated March 7, 1989. ,U | condition specified in'the licensee's. application' transmitted by {{letter dated|date=January 16, 1986|text=letter dated January 16, 1986}}; and s'upplement dated March 7, 1989. ,U | ||
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: 10. Authorized place of use: The Nuclear Engineering; Laboratories located in Taylor Hall, Room 32N of the Engineering' Science Building, and Balcones Research Center. 1 g n , | : 10. Authorized place of use: The Nuclear Engineering; Laboratories located in Taylor Hall, Room 32N of the Engineering' Science Building, and Balcones Research Center. 1 g n , |
Revision as of 22:51, 8 March 2021
ML20246P466 | |
Person / Time | |
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Site: | 07000157 |
Issue date: | 05/08/1989 |
From: | Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
To: | |
Shared Package | |
ML20246P442 | List: |
References | |
NUDOCS 8905220200 | |
Download: ML20246P466 (3) | |
Text
_ _ _ _ _ _ _ _ _ _ _ _ _ _ - - - . _
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N'.C Form 374 .
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U.S. NUCLEAR RE2ULATORY COMMISSION PAGE 1 OF- 2 PACES l MATERIALS LICENSE I Pursuant to the Atomic Energy Act of 1954, as amended, the Ener,y Reorganization Act of 1974 (Public Law 93-438), and Title 10, I g
Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations ,
heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, t
- source, and special nuclear material designated below; to use such material for the purpose (s) and at the place (s) designated below; to I
deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This I license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is I .
subject to all applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.
g Licensee -
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- 2. ,
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.J'> 4. Expiration date May 31, 1992 Li l
- 5. Docket or t.70-157 [-
Reference No. t
- 6. ByproducUcurce,and/or - 7. Chemical and/or physical ,, 8. Maximum amount that licensee !
form -may possess at any one time L
_ under this license
'y ( , t A. Uranium enriched 1 A.1Uraniumidioxfde% A; T470 grams U-235 L in the U-235 isotope , f in polyethylene J . enriched to 20% f a i m /> -in the U ,35 isotope f
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B. Plutonium ~> ' Bi ,Sealediplutoniuiri- B.n 128 grams ot
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~/ berylljum neutron ' plutonium -
-i sources 5l$;' ;
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9 Authorized use: For use in'accordance with the statements, Representations, and [
condition specified in'the licensee's. application' transmitted by letter dated January 16, 1986; and s'upplement dated March 7, 1989. ,U
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- 10. Authorized place of use: The Nuclear Engineering; Laboratories located in Taylor Hall, Room 32N of the Engineering' Science Building, and Balcones Research Center. 1 g n ,
- 11. The licensee shall establish, maintain, and follow written health and safety j procedures for health physics surveys, personnel monitoring, laboratory operations, p and calibration activities. The procedures shall be reviewed and approved in writing H by the Reactor Committee. This condition is effective for all activities conducted i
90 days from the date of this license renewal.
I
' 12. Prior to working with or handling licensed special nuclear material, all personnel shall receive training or shall be under the supervision of persons who have received l training in the formal radiation safety program.
l 13. The licensee shall read and evaluate the personnel film badges at intervals not to exceed 1 month.
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m - - - - - - - m m mmmuy NAC f orm 374 A U.S. NUCLEAR REGULATORY COMMISSION PAGE 2 or 2 pnots I
.(5 34) '
License number I MATERIALS LICENSE SNM-180 Amendment No. 1 '
pocg,, ,1 Reference number SUPPLEMENTARY SHEET 70-157 l
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MAY 0 81889 i
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- 14. The licensee shall leak test the polyethylene-encapsulated-uranium fuel in accordance with the enclosed " License Condition for Leak Testing Sealed Uranium Sources," August [g 1987.
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IL. (he licensee shall calibrate the radiation detection instruments at intervals not to exceed 8 months.
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- 16. The licensee is exempted from the requirements of 10 CFR 70.24 insofar as this section y applied to the materials covered by this license, r L
- 17. The licensee shall decontaminate facilities,' surfaces, and equipment in accordance I with the enclosed " Guidelines for Decontamination' of Facilities and Equipment Prior to Release for Unrestricted'Use or Termination of Licenses for Byproduct, Source, or ft Special Nuclear Material, " August 1987.
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Enclosures:
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t I FOR THE NUCLEAR REGULATORY COMMISSION t ;
i CriglIialSigtej hy i E
i Date: W 08 m By: Leland C. Rouse
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yr Division of Industrial and P p \f\ Medical Nuclear Safety CF M'S(fp M ONA\ ,W hington, DC 20355 fg M Y 46
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LICENSE CONDITION FOR LEAR TESTING SEALED URANIUM SOURCES AUGUST 1987 A. Each uranium source shall be tested for. leakage at intervals not to exceed 6 months. In the absence of a~ certificate from a transferor indicating that a test has been made within 6 months prior to the transfer, the sealed source-shall not be put:into use until tested.
B. The test shall be capable of. detecting the presence of 0.005 microcurie of alpha contamination on the test sample. The test sample shall be taken from the source or from a'ppropriate accessible surfaces of the device in which the sealed source is permanently or semipermanently mounted or stored.
Records of leak test results shall ba kept in units of microcuries and-maintained for inspection by the Comission.
C. If the test reveals the presence o'f 0.005 microcurie or more of removable alpha contamination, the licensee-shall imediately withdraw the~ sealcd' source from use and shall cause it to be decontaminated and repaired-by
.a person appropriately licensed to make such' repairs or to be disposed
~o f in accordance with the Comission's regulations. Within 5 days after
- determining that any' source has leaked, the licensee shall file a report with the' Division of Industrial and Medical Nuclear Safety, U.S. Nuclear Regulatory Comission, Washington, DC 20555, describing the source, test ;
results, exten,t of contamination,' apparent or suspected cause of sJurce failure, and the corrective action taken. A copy of the report shall be sent to the Administrator of the nearest NRC Regional Office listed in r
Appendix D of Title 10, Code of Federal Regulations, Part 20.
D. The periodic leak test required by this condition does not apply to sealed sources that are stored and not being used. The sources excepted from this test shall be tested for leakage prior to any use or transfer to another person unless they have been leak tested within 6 months prior to the date of use or transfer.
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l; 1 i GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR-TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR EYPRODUCT, SOURCE, OR SF'ECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Comission Division of Industrial and Medical Nuclear Safety i Washington, DC 20555
.l August 1987 N
~. .
The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should be used "
decontamination and survey of surfaces or premises and equipment prior to abandonment or release for unrestricted use. The limits in Table 1 do not apply to premises, equipment, or scrap containing induced radioactivity for which the radiological considerations pertinent to their use may be different.
The release of such facilities or items from regulatory control is considered on a case-by-case basis.
- 1. The licensee shall make a reasonable effort to eliminate residual contamination.
- 2. Radioactivity on equipment or surfaces shall not be covered by paint, plating, or other covering material unless contamination levels, as determined by a survey and documented, are below the limits specified in Table 1 prior to the ap)11 cation of the covering. A reasonable effort must be made to minimize tie contamination prior to use of any covering.
- 3. The radioactivity on the interior surfaces of pipes, drain lines, or ductwork shall be determined by making measurements at all traps, and other appropriate access points, provided that contamination at these . ,
locations is likely to be representative of contamination on the interior !
of the pipes, drain lines, or ductwork. Surfaces of premises, equipment, or scrap which are likely to be contaminated but are of such size, construction, or location as to make the surface inaccessible for purposes i of measurement shall be presumed to be contaminated in excess of the limits.
- 4. Upon request, the Commission may authorize a licensee to relinquish I possession or control of premises, equipment, or scrap having surfaces contaminated with materials in excess of the limits specified. This may include, but would not be limited to, special circumstances such as razing of buildings, transfer of premises to another organization continuing work with radioactive materials, or conversion of facilities to a long-term storage or standby status. Such requests must:
- a. Provide detailed, specific information describing the premises, equipment or sc~ rap, radioactive contaminants, and the nature, axtent, and degree of residual surface contamination. .
- b. Provide a detailed health and safety analysis which reflects that the residual amounts of materials on surface areas, together with other considerations such as prospective use of the premises, equipment, or scrap, are unlikely to result in an unreasonable risk to the health and safety of the public.
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- 5. Prior to. release of premises for unrestricted use, the licensee shall make a comprehensive radiation survey which establishes that contamination is within the limits specified in Table 1. A copy of the survey report shall be filed with the Division of Industrial and Medical Nuclear Safety, U. S. Nuclear Regulatory Commission, Washington, DC 20555, and also the Administrator of the NRC Regional Office having jurisdiction. The report should be filed at least 30 days prior to the planned date of abandonment.
The survey report shall:
- a. Identify the premises.
- b. Show that reasonable effort has been made to eliminate residual contamination.
- c. Describe the scope of the survey and general procedures followed.
- d. State the findings of the survey in units specified in the instruction. >
Following review of the report, the NRC will consider visiting the facilities to confinn the survey. .
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