ML24152A181
| ML24152A181 | |
| Person / Time | |
|---|---|
| Site: | 07000398 |
| Issue date: | 04/10/2025 |
| From: | Kimyata Morgan-Butler Division of Fuel Management |
| To: | US Dept of Commerce, National Institute of Standards & Technology (NIST) |
| Shared Package | |
| ML24152A178 | List: |
| References | |
| EPID L-2023-RNW-0017 | |
| Download: ML24152A181 (1) | |
Text
NRC FORM 374 Page 1 of 7 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.
- 1. U.S. DEPARTMENT OF COMMERCE NATIONAL INSTITUTE OF STANDARDS AND TECHNOLOGY 2.
100 Bureau Drive, Stop 1731 Gaithersburg, MD 20899-1731
- 3. License Number: SNM-362 Renewed April 10, 2025 - ADAMS Accession No. ML24152A178
- 4. Expiration Date: April 10, 2035
- 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 wt % in the U-235 isotope A. Any form except UF6 A. [Security-Related Information - Withheld Under 10 CFR 2.390]
B. Uranium enriched to or greater than 20 wt % in the U-235 isotope B. Any form except UF6 B. [Security-Related Information - Withheld Under 10 CFR 2.390]
C. Uranium-233 C. Any form except UF6 C. [Security-Related Information - Withheld Under 10 CFR 2.390]
D. Natural Uranium D.1 Any soluble form except UF6 D.2. Any insoluble form except UF6 D.1. [Security-Related Information - Withheld Under 10 CFR 2.390]
D.2. [Security-Related Information - Withheld Under 10 CFR 2.390]
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 2 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License E. Uranium Depleted in U-235 (Primarily U-238)
E.1. Any soluble form except UF6 E.2. Any insoluble form except UF6 E.1. [Security-Related Information - Withheld Under 10 CFR 2.390]
E.2. [Security-Related Information - Withheld Under 10 CFR 2.390]
F. Any separated Uranium isotope other than U-233, U-235, or U-238 U-232 F.1 Any form except UF6 F.2 Any form except UF6 F.1 1 Ci F.2 0.1 Ci H. Any isotope of Plutonium, except Pu-238 H.1 Pu-236 H.2 Pu-239 H.3 Pu-240 H.4 Pu-241 H.5 Pu-242 H.6 Pu-244 H. Any form H. [Security-Related Information - Withheld Under 10 CFR 2.390]
H.1 [Security-Related Information - Withheld Under 10 CFR 2.390]
H.2 [Security-Related Information - Withheld Under 10 CFR 2.390]
H.3 [Security-Related Information - Withheld Under 10 CFR 2.390]
H.4 [Security-Related Information - Withheld Under 10 CFR 2.390]
H.5 [Security-Related Information - Withheld Under 10 CFR 2.390]
H.6 [Security-Related Information - Withheld Under 10 CFR 2.390]
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 3 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License I. Plutonium I. Sealed sources(e.g. PuBe)
I. [Security-Related Information - Withheld Under 10 CFR 2.390]
J. Plutonium enriched to more than 80% in the Pu-238 isotope J. Any form J. [Security-Related Information - Withheld Under 10 CFR 2.390]
K. Th-228 K. Any form K. [Security-Related Information - Withheld Under 10 CFR 2.390]
L. Th-229 L. Any form L. [Security-Related Information - Withheld Under 10 CFR 2.390]
M. Th-230 M. Any form M. [Security-Related Information - Withheld Under 10 CFR 2.390]
N. Th-232 N. Any form N. [Security-Related Information - Withheld Under 10 CFR 2.390]
O. Natural Thorium O. Any form O. [Security-Related Information - Withheld Under 10 CFR 2.390]
P. Any Thorium other than Th-228, Th-229, Th-230, or Th-232 P. Any form P. [Security-Related Information - Withheld Under 10 CFR 2.390]
Q. Radium Q. Any form Q. [Security-Related Information - Withheld Under 10 CFR 2.390]
R. Radium R. Sealed sources (includes RaBe sources)
R. [Security-Related Information - Withheld Under 10 CFR 2.390]
S. Co-60 S. Sealed sources (e.g.,
irradiators)
S. [Security-Related Information - Withheld Under 10 CFR 2.390]
T. Cs-137 T. Sealed sources (e.g.,
irradiators)
T. [Security-Related Information - Withheld Under 10 CFR 2.390]
U. Po-210 U. Sealed sources U. [Security-Related Information - Withheld Under 10 CFR 2.390]
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 4 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License V. Am-241 V. Sealed sources (e.g.,
AmBe)
V. [Security-Related Information - Withheld Under 10 CFR 2.390]
Y. Pm-147 Y. Sealed Sources Y. [Security-Related Information - Withheld Under 10 CFR 2.390]
Z. I-125 Z. Sources sealed in titanium or stainless steel Z. [Security-Related Information - Withheld Under 10 CFR 2.390]
AA. Byproduct material AA. Any form AA. [Security-Related Information - Withheld Under 10 CFR 2.390]
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 120m Pa-230 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
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 5 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License I-129 Pb-210 Ac-227 Am-241 Am-242m, Am-243 Bk-247. Es-254 Cf-248, 249. 250, 251, 252, and 254 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 Atomic Number 3 to 83 except for the following nuclides:
BB. Any form-Neutron activated materials (e.g.,
research sample or sample container)
BB. [Security-Related Information - Withheld Under 10 CFR 2.390]
I-129, Sm-146, Bi-210m CC. Irradiated Fuel U-235 CC. Pellets CC. [Security-Related Information - Withheld Under 10 CFR 2.390]
DD. Cm-244, Cm-248 DD. Sealed Sources DD. [Security-Related Information - Withheld Under 10 CFR 2.390]
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 6 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License 9.
Authorized place of use: The licensees existing facilities at 100 Bureau Drive, 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.
The licensee shall conduct activities in accordance with statements, representations, and conditions as described in the following documents:
a.
License renewal application dated August 8, 2023, and Revision 1 dated March 2024.
b.
Decommissioning funding plan dated September 27, 2022, as supplemented by letters dated January 24, 2023, May 16, 2023, and January 10, 2024.
11.
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 12.
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).
13.
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).
14.
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.
NRC FORM 374A U.S. NUCLEAR REGULATORY COMMISSION Page 7 of 7 License No. SNM-362 MATERIALS LICENSE SUPPLEMENTARY SHEET Docket or Reference Number 70-398 Renewed License 15.
No sealed source shall be stored for a period of more than 10 years without being tested for leakage and/or contamination.
16.
Notwithstanding the requirements in 10 CFR 70.24, Criticality accident requirements, (a), the licensee is exempt from the requirements to maintain a criticality accident alarm system.
17.
The licensee may make changes to its NRC-regulated programs provided that the changes are in accordance with regulatory requirements, will not change license conditions, will not decrease the effectiveness of the program, and the changes are documented.
FOR THE U. S. NUCLEAR REGULATORY COMMISSION Date: April 10, 2025 By:
Kimyata Morgan-Butler, Deputy Director Division of Fuel Management, Office of Nuclear Material Safety and Safeguards Signed by Morgan-Butler, Kimyata on 04/10/25