ML18183A476

Enclosure 1 - Amendment 9 - Public - Corrected - SNM-362

ML18183A476
Person / Time
Site:	07000398
Issue date:	07/13/2018
From:	Ty Naquin Fuel Manufacturing Branch
To:	US Dept of Commerce, National Institute of Standards & Technology (NIST)
Naquin T
Shared Package
ML18183A474	List: ML18183A476 ML18183A477
References
CAC 000222
Download: ML18183A476 (12)

Text

Page 1 of 7 NRC FORM 374 U.S. NUCLEAR REGULATORY COMMISSION 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, Code of Federal Regulations, Chapter I, Parts 30, 31, 32, 33, 34, 35, 36, 39, 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, source, and special nuclear material designated below; to use such material for the purpose(s) and at the place(s) designated below; to deliver or transfer such material to persons authorized to receive it in accordance with the regulations of the applicable Part(s). This 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 all applicable rules, regulations, and orders of the U.S. Nuclear Regulatory Commission now or hereafter in effect and to any conditions specified below.

Licensee

1. U.S. DEPARTMENT OF COMMERCE NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY

2. 100 Bureau Drive, Stop 1731 3. License Number: SNM-362, Amendment 9 Room C-125, Building 245 4. Expiration Date: September 9, 2023 Gaithersburg, MD 20899-1731 5. Docket No.70-398

6. Byproduct, Source and/or 7. Chemical and/or Physical 8. Maximum that Licensee May Special Nuclear Material Form Possess at Any One time Under This License A. Uranium enriched to less than 20 A. Any form except UF6 A.

wt % in the U-235 isotope B. Uranium enriched to or greater B. Any form except UF6 B.

than 20 wt % in the U-235 isotope C. Uranium-233 C. Any form except UF6 C.

D. Natural Uranium D.1 Any soluble form except D.1.

UF6 D.2. Any insoluble form D.2.

except UF6 E. Uranium Depleted in U-235 E.1. Any soluble form except E.1.

(Primarily U-238) UF6 E.2. Any insoluble form E.2.

except UF6 Enclosure 1

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 7 License No. SNM-362 MATERIALS LICENSE Amendment No. 9 SUPPLEMENTARY SHEET Docket: 70-398 F. Any separated Uranium isotope F.1 Any form except UF6 F.1 other than U-233, U-235, or U-238 U-232 F.2 Any form except UF6 F.2 G.Uranium G. As UF6 G.

H. Any isotope of Plutonium, except H. Any form H.

Pu-238 H.1 H.1 Pu-236 H.2 H.2 Pu-239 H.3 H.3 Pu-240 H.4 H.4 Pu-241 H.5 H.5 Pu-242 H.6 H.6 Pu-244 I. Plutonium I. Sealed sources(e.g. PuBe) I.

J. Plutonium enriched to more than J. Any form J.

80% in the Pu-238 isotope K. Th-228 K. Any form K.

L. Th-229 L. Any form L.

M. Th-230 M. Any form M.

N. Th-232 N. Any form N.

O. Natural Thorium O. Any form O.

P. Any Thorium other than P. Any form P.

Th-228, Th-229, Th-230, or Th-232

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 7 License No. SNM-362 MATERIALS LICENSE Amendment No. 9 SUPPLEMENTARY SHEET Docket: 70-398 Q. Radium Q. Any form Q.

R. Radium R. Sealed sources (includes R.

RaBe sources)

S. Co-60 S. Sealed sources (e.g., S.

irradiators)

T. Cs-137 T. Sealed sources (e.g., T.

irradiators)

U. Po-210 U. Sealed sources U.

V. Am-241 V. Sealed sources (e.g., V.

AmBe)

W. Cf-252 W. Sealed sources W.

X. Sr-90 X. Sealed sources X.

Y. Pm-147 Y. Sealed Sources Y.

Z. I-125 Z. Sources sealed in titanium Z.

or stainless steel AA. Byproduct material AA. Any form AA.

Any nuclide of half-life less than 30 days, except the following:

Au-198 Mo-99, Tc-99m, and Xe-133 Rn-220, Rn-222 I-120m Pa-230

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 7 License No. SNM-362 MATERIALS LICENSE Amendment No. 9 SUPPLEMENTARY SHEET Docket: 70-398 AA. Byproduct material AA. Any form AA.

I-124, I-126 Gd-149 Any nuclide of half-life more than 30 days except for the following nuclides:

H-3 Kr-85 Cs-137 C-14, Co-60 In-115 I-129 Pb-210 Ac-227 Am-241 Am-242m, Am-243 Bk-247. Es-254 Cf-248, 249. 250, 251, 252, and 254

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 5 of 7 License No. SNM-362 Amendment No. 9 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket: 70-398 Cm-242, 243, 244, 245, 246, 247, 248 Np-236, Np-237 Sm-146, Sm-147 Gd-152, Pa-231, Cm-250 BB. Any byproduct material with BB. Any form- Neutron BB.

Atomic Number 3 to 83 except activated materials (e.g.,

for the following nuclides: research sample or sample container)

I-129, Sm-146, Bi-210m CC. Irradiated Fuel U-235 CC. Pellets DD. Cm-244, Cm-248 DD. Sealed Sources

9. Authorized place of use: The licensees existing facilities at Gaithersburg, Maryland, and offsite locations that are under NRC jurisdiction and that are subject to the provisions listed in NISTs license renewal application in Item 3, Offsite Locations.

10. Authorized Use: For use in accordance with statements, representations, and conditions of the licensees renewal application dated June 29, 2007; and revised on June 24, 2010; March 23, 2011; June 5, 2013; October 31, 2013; December 27, 2013; November 14, 2016; January 5, 2017; January 11, 2017; March 31, 2017; and October 7, 2017.

11. Deleted.

12. Notwithstanding the requirements of 10 CFR 36.23(b), the licensee is exempt from the requirements that: (1) detection of entry, by an independent backup access control, while the sources are exposed must cause the sources to return to their fully shielded position and must also activate a visible and audible alarm to make the individual entering the room aware of the hazard, and (2) the alarm must alert at least one other individual who is onsite of the entry. When an operator is not present the licensee shall arm the independent backup access control system identified in the licensees letter dated March 5, 2013.

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 6 of 7 License No. SNM-362 MATERIALS LICENSE Amendment No. 9 SUPPLEMENTARY SHEET Docket: 70-398

13. Notwithstanding the requirements of 10 CFR 36.23(c), the licensee is exempt from the requirements that attempted personnel entry while the monitor measures high radiation levels, must activate the alarm described in 10 CFR 36.23(b). The licensee shall comply with 10 CFR 35.615(b).

14. Deleted.

15. Notwithstanding the requirements of 10CFR36.27(a), the licensee is exempt from the requirement that the sources must automatically become fully shielded if a fire is detected.

16. Notwithstanding the requirements of 10 CFR 36.27(b) the licensee is exempt from the requirement that the radiation room must be equipped with a fire extinguishing system capable of extinguishing a fire without the entry of personnel into the room.

17. Notwithstanding the requirements of 10 CFR 36.31(a), the licensee is exempt from the requirements that (1) the console key must be attached to a portable radiation survey meter by a chain or cable, and (2) the door to the radiation room must require the same key used for source movement (i.e.,

control console key).

18. Deleted.

19. The Ionizing Radiation Safety Committee (IRSC) shall meet the requirements of 10 CFR 33.13(c) including the review, approval, and recording of safety evaluations of all proposed new uses of byproduct material prior to use of the byproduct material.

20. No sealed source shall be stored for a period of more than 10 years without being tested for leakage and/or contamination.

21. The applicant is granted an exemption to the requirements of 10 CFR 70.24 to maintain a CAAS.

NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 7 of 7 License No. SNM-362 MATERIALS LICENSE Amendment No. 9 SUPPLEMENTARY SHEET Docket: 70-398 FOR THE U. S. NUCLEAR REGULATORY COMMISSION Date: July 13, 2018 By: _ /RA/________

Robert K. Johnson, Chief Fuel Manufacturing Branch Division of Fuel Cycle Safety, Safeguards, and Environmental Review Office of Nuclear Materials Safety and Safeguards