ML20237G562

Renewal of License SNM-0561 for Dept of Army,Authorizing Use of Pu-239,Pu-238 & Np-237 Sealed Sources & Enriched U Sealed MTR-type Fuel Elements as Specified in Licensee 840822 Application

ML20237G562
Person / Time
Site:	07000622
Issue date:	08/18/1987
From:	Rouse L NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
To:
Shared Package
ML20237G516	List: ML20237G512 ML20237G562 ML20237G600 ML20237G630 ML20237G660
References
NUDOCS 8708240125
Download: ML20237G562 (4)

Text

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• PAGE OF PAGES g tS 80 U.S. NUCLEAR REGULATORY COMMISSION i

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• j MATERIALS LICENSE Pursuant to the Atomic Energy Act of 1954, as amended, the Energy Reorganization Act of 1974 (Public Law 93-438), and Title 10, g

y Code of Federal Regulations, Chapter I, Parts 30,31,32,33,34,35,40 and 70, and in reliance on statements and representations g heretofore made by the licensee, a license is hereby issued authorizing the licensee to receive, acquire, possess, and transfer byproduct, source, and special nuclear rnaterial designated below; to use such material for the purpose (s) and at the place (s) designated below; to j% deliver or transfer such material to persont authorized to receive it in accordance with the regulations of the applicable Part(s). This N license shall be deemed to contain the conditions specified in Section 183 of the Atomic Energy Act of 1954, as amended, and is subject to al'. applicable rules, regulations and orders of the Nuclear Regulatory Commission now or hereafter in effect and to any

conditions specified below.

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! 1. 3. License number P Department of the Army SNM-561, as renewed I

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y U.S. Army Armament Research 4. Expiration date

, and Development Command . ,- Angust 31,_1992

m 5. Docket or Reference No. '70-622

6. Byproduct, source, and/or ., 7. Chemical and/or physical 8. Maximum amount that licensee special nuclear material s form may possess at any one time under this license f ,

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A. Plutonium-239 s A. Sealed Pu-Be neutron sources

& A. Sources not to exceed a total 1._

of 100 grams l

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-c y B. Plutonium-239 B. Sealed sources B. 2 milligrams W -

total C. Plutonium-238 C. NeutrongeneratoYs C. 4.8 grams (batteries) y D. Plutonium-238 - - D. Sealed sources D. 1 microgram N E. Neptunium-237 E. Sealed sources i E. 15 milligrams F. Uranium enriched F. Sealed MTR-type F. 1,716 grams to 193.27 wt percent fuel elements of U-235 in the U-235 isotope 1

9. Authorized Use: For use in accordance with the statements, representations, i and conditions specified in the licensee's application dated August 22, 1984, j and supplement dated August 6, 1987.

l 10. Authorized Place of Use: The licensee's existing facilities at Dover, New Jersey.

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11. The minimum technical qualifications for the position of Radiation Protection Officer l shall be a bachelor's degree in health physics, physical / life science, or engineering I and 2 years of experience in applied radiation safety.  !

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l rum mm mmmmm === mmm mm= = ==== mm amm = = mmm m m - m m am m mammma gang l NHC Form 374A U.S. NUCLEAR REGULATORY COMMISSION , 2 y 2 ,e I License number SNM-561, as renewed

! MATERIALS LICENSE Dockem Referenn mmkr I SUPPLEMENTARY SHEET i 70-622 I

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I i 12. The minimum technical qualifications for three of the Ionizing Radiation Control I Committee members shall be a bachelor's degree in health physics, physical / life I

science, or engineering and 2 years of experience in radiation and/or nuclear i

safety programs.

I I 13. Notwithstanding the provision of paragraph b on page 167 of the application, the I licensee shall maintain personnel exposures in accordance with 10 CFR 20.101.

l l 14. Sealed in the plutonium sources shall be subject to the leak testing and actions specified attached Annex, " License Condition for_ Leak Testing Sealed Plutonium Sources,"

i i August 1987.  ; 3,, a n C QJ /,

I , v i 15. Plutonium alpha sources shall, bs subject to the leak testing and actions specified in j the attached Annex, " License Condition for Plutonium Alpha Sources," August 1987.

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Y 'h y 16. The possession and use of'ii-235 in MTR-type fuel elements 5 hall ~

,be limited to storage i only in the shipping. container in Building 3030 4 f R%

l t. ,~ n / ::.:. R 1 17. The licensee is hereb'y erempted from the'~ provisions'.of.10 CFR 70.24 insofar as this l sectionappliestomaterialsheldjunder,th,e,1,1 cense.{T t) j l w y, .=.m 3 'sc> ~;

y y 18. Upon termination of operations or'~ prior _to the release of equipment for unrestricted i use, the facility and equipment shall .be' decontaminated in'accordance with the attached i Annex, " Guidelines for Decontamination"of: Facilities and Equipment Prior to Release

! for Unrestricted Use or Termination.of License.s for By product,' Source, or Special i- Nuclear Material," August 1987..47 'g(T j ,- )

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I FOR THE NUCLEAR REf0LATORY COMMISSION i

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! Date: N8 By: Leland C. Rouse Division of Industrial and Medical Nuclear Safety, NMSS lg ggovfl%7 /Y"g 7 aI Washington, DC 20555 l

LICENSE CONDITION FOR PLUT0NIUM ALPHA SOURCES AUGUST 1987 A. Sources when not in use shall be stored in a closed container adequately designed and constructed to contain plutonium which might otherwise be released during storage.

B. At least once every 3 months, the 11censeo shall test the source for loss of plutonium in one of the following ways using radiation detection instrumentation capable of detecting 0.005 microcurie of alpha contamination:

(1) By measurement of the source of potential alpha contamination through surveys of the storage container and areas in which the source is used; or (2) By wiping thoroughly the external surfaces of the source mount, other than the radioactive surface of the source, with a piece of filter paper of high wet strength and low porosity moistened with a solution which will not attack the mount and, after the paper is allowed to dry, measuring the radioactivity on the paper.

C. If any survey or measurement performed as required by B.(1) or B.(2) above discloses the loss of more than 0.005 microcurie of plutonium from '

the source or if a source has been damaged or broken, the source shall be deemed to be Tosing plutonium. The licensee shall immediately withdraw i it from use, and cause the source to be decontaminated and repaired, or disposed of in accordance with the Commission's regulations. Within 5 days after determining that any' source has lost plutonium, the licensee shall file a report with the Division of Industrial and Medical Nuclear Safety, U. S. Nuclear Regulatory Commission, Washington, DC 20555, describing the source, test results, extent of contamination, and corrective action taken.

A copy of the report shall be sent to the Administrator of the nearest NRC Regional Office listed in Appendix D of Title 10, Code of Federal Regulations, Part 20.

D. Records of test results shall be kept in units of microcuries and maintained for inspection by the Commission.

E. Notwithstanding the periodic test required by Paragraph B, any plutonium alpha source containing not more than 0.1 microcurie of plutonium is exempted from the above requirements.

L LICENSE CONDITION FOR LEAK TESTING SEALED PLUT0NIUM SOURCES AUGUST 1987

A. ' Each plutonium 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 appropriate accessible surfaces of the device'in which the sealed source is pennanently or semipermanently mounted or stored.

Records of leak test results shall be kept in units of microcuries_and maintained for inspection by the Comission.

C. .If the test reveals the presence 'of 0.005 microcurie or more of removable alpha contamination, the licensee shall imediately withdraw the sealed 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 of 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 end Medical Nuclear Safety, U.S. Nuclear Regulatory Comission, Washingtca, DC 20555, describing the source, test results, extent of contamination, apparent or suspected cause of source failure, and , corrective action taken. A copy of the report shall be sent to the Administrator of 'che nearest NRC Regional Office listed in Appendix D  ;

of Title 10, Code of Feder.a1 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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u 1 GUIDELINES FOR DECONTAMINATION OF FACILITIES AND EQUIPMENT PRIOR TO RELEASE FOR UNRESTRICTED USE OR TERMINATION OF LICENSES FOR BYPRODUCT, SOURCE, OR SPECIAL NUCLEAR MATERIAL U.S. Nuclear Regulatory Comission Division of Industrial and Medical Nuclear Safety

. Washington, DC 20555 August 1987

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The instructions in this guide, in conjunction with Table 1, specify the radionuclides and radiation exposure rate limits which should be used in 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 l 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 application of the covering. A reasonable effort i must be made to minimize the contamination prior to use of any covering. l l

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 of measurement shall be presumed to be contaminated in excess of the limits.

4. Upon request, the Commission may authorize a licensee to relinquish l 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 l storage or standby status. Such requests must: l

a. Provide detailed, specific information describing the premises, equipment or scrap, radioactive contaminants, and the nature, extent, 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 l safety of the public.

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5. Prior to release of premises for unrestricted use, the licensee shall j make a comprehensive radiation survey which establishes that contamination

- is within the limits specified in Table 1. A copy of the survey report J 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 D should be filed at'least-30-days-prior to the planned date of abandonment. -i 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 confirm the survey.

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