Crow Butte Resources, Inc., 83289-83291 [2016-27946]

Download as PDF Federal Register / Vol. 81, No. 224 / Monday, November 21, 2016 / Notices asabaliauskas on DSK3SPTVN1PROD with NOTICES The NRC does not routinely edit comment submissions to remove identifying or contact information. If you are requesting or aggregating comments from other persons for submission to the NRC, then you should inform those persons not to include identifying or contact information that they do not want to be publicly disclosed in their comment submission. Your request should state that the NRC does not routinely edit comment submissions to remove such information before making the comment submissions available to the public or entering the comment submissions into ADAMS. II. Additional Information The NRC is issuing for public comment a DG in the NRC’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public information regarding methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific issues or postulated events, and data that the staff needs in its review of applications for permits and licenses. The DG, entitled ‘‘Pressurized Water Reactor Control Rod Ejection and Boiling Water Reactor Control Rod Drop Accidents,’’ is a proposed new guide temporarily identified by its task number, DG–1327. DG–1327 proposes new guidance for analyzing reactivityinitiated accidents such as control rod ejection for pressurized water reactors and control rod drop for boiling-water reactors. It defines fuel cladding failure thresholds for ductile failure, brittle failure, and pellet-clad mechanical interaction and provides radionuclide release reactions for use in assessing radiological consequences. It also describes analytical limits and guidance for demonstrating compliance with regulations governing reactivity limits. The draft guide also incorporates new empirical data from in-pile, prompt power pulse test programs and analyses from several international publications on fuel rod performance under reactivity initiated accident conditions to provide guidance on acceptable analytical methods, assumptions, and limits for evaluating a pressurized water reactor control rod ejection accident. The draft guide expands the existing guidance for control rod ejection accidents in Regulatory Guide (RG) 1.77, ‘‘Assumptions Used for Evaluation a Control Rod Ejection Accident for Pressurized Water Reactors.’’ However, the NRC intends to maintain RG 1.77 for existing licensees who do not make any VerDate Sep<11>2014 18:09 Nov 18, 2016 Jkt 241001 design changes within the scope of RG 1.77. III. Backfitting and Issue Finality Draft regulatory guide DG–1327 describes one acceptable method for demonstrating compliance with Appendix A of part 50 of title 10 of the Code of Federal Regulations (10 CFR), ‘‘General Design Criteria 28, Reactivity Limit,’’ with respect to control rod ejection (CRE) for pressurized-water reactors (PWRs) and a control rod drop (CRD) for boiling-water reactors (BWRs). It addresses fuel cladding failure thresholds for ductile failure, brittle failure, and pellet-clad mechanical interaction (PCMI), provides radionuclide release fractions for use in assessing radiological consequences, and describes analytical limits and guidance for demonstrating compliance with GDC 28 governing reactivity limits. This draft regulatory guide, if finalized, would not constitute backfitting as defined in 10 CFR 50.109 (the Backfit Rule) and is not otherwise inconsistent with the issue finality provisions in 10 CFR part 52, ‘‘Licenses, Certifications and Approvals for Nuclear Power Plants.’’ Existing licensees and applicants of final design certification rules will not be required to comply with the positions set forth in this draft regulatory guide, unless the licensee or design certification rule applicant seeks a voluntary change to its licensing basis with respect to CRE for PWRs or CRD for BWRs, and where the NRC determines that the safety review must include consideration of these events. Further information on the staff’s use of the draft regulatory guide, if finalized, is contained in the draft regulatory guide under Section D. Implementation. Applicants and potential applicants are not, with certain exceptions, protected by either the Backfit Rule or any issue finality provisions under part 52. Neither the Backfit Rule nor the issue finality provisions under part 52— with certain exclusions discussed below—were intended to apply to every NRC action which substantially changes the expectations of current and future applicants. Therefore, the positions in any final draft regulatory guide, if imposed on applicants, would not represent backfitting (except as discussed below). The exceptions to the general principle are applicable whenever a combined license applicant references a part 52 license (i.e., an early site permit or a manufacturing license) and/or part 52 regulatory approval (i.e., a design certification rule or design approval. The staff does not, at this time, intend to impose the positions represented in PO 00000 Frm 00094 Fmt 4703 Sfmt 4703 83289 the draft regulatory guide in a manner that is inconsistent with any issue finality provisions in these part 52 licenses and regulatory approvals. If, in the future, the staff seeks to impose a position in this regulatory guide in a manner which does not provide issue finality as described in the applicable issue finality provision, then the staff will address the criteria for avoiding issue finality as described in the applicable issue finality provision. Dated at Rockville, Maryland, this 10th day of November 2016. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guidance and Generic Issues Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. 2016–27903 Filed 11–18–16; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 040–08943; NRC–2008–0208] Crow Butte Resources, Inc. Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption to Crow Butte Resources, Inc. (CBR) for the purpose of complying with occupational dose limits in response to a request from CBR dated September 21, 2015. Issuance of this exemption will allow CBR to disregard certain radionuclides that contribute to the total activity of a mixture when determining internal dose to assess compliance with occupational dose equivalent limits at its in situ uranium recovery (ISR) facility in Crawford, Nebraska. ADDRESSES: Please refer to Docket ID NRC–2008–0208 when contacting the NRC about the availability of information regarding this document. You may obtain publicly-available information related to this document using any of the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2008–0208. Address questions about NRC dockets to Carol Gallagher; telephone: 301–415–3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable documents online in the SUMMARY: E:\FR\FM\21NON1.SGM 21NON1 83290 Federal Register / Vol. 81, No. 224 / Monday, November 21, 2016 / Notices ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced (if that document is available in ADAMS) is provided the first time that a document is referenced. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Ronald A. Burrows, Office of Nuclear Material Safety and Safeguards; U.S. Nuclear Regulatory Commission, Washington DC 20555–0001; telephone: 301–415–6443; email: Ronald.Burrows@ nrc.gov. SUPPLEMENTARY INFORMATION: asabaliauskas on DSK3SPTVN1PROD with NOTICES I. Background Crow Butte Resources, Inc. operates the Crow Butte ISR facility in Crawford, Nebraska (the Crow Butte Project) under NRC source materials license SUA–1534 (ADAMS Accession No. ML13324A101). At the Crow Butte Project, CBR performs airborne uranium particulate monitoring in the plant in accordance with Section 5.8.3.1 of its Technical Report (ADAMS Accession No. ML091470116). As described in its Technical Report, CBR measures airborne uranium by taking samples of particulate matter in air at locations within the plant using glass fiber filters and air pumps. The measurement of airborne uranium is performed by gross alpha counting of air filters. In Section 5.7.4.3.1, ‘‘Airborne Particulate Uranium Monitoring,’’ of the NRC staff’s 2014 Safety Evaluation Report (SER) for the renewal of CBR’s license for the Crow Butte Project (ADAMS Accession No. ML14149A433), the NRC staff stated that CBR did not demonstrate that gross alpha counting would differentiate all airborne radioactivity in air samples, including radionuclides that are not uranium, some of which may not emit alpha particles and, therefore, will not be detected. As a result, the NRC staff imposed license condition 10.8 in CBR’s license SUA–1534, which states that the licensee shall conduct isotopic analyses for alpha- and beta-emitting radionuclides on airborne samples at each in-plant air particulate sampling location at a frequency of once every 6 VerDate Sep<11>2014 18:09 Nov 18, 2016 Jkt 241001 months for the first 2 years and annually thereafter to ensure compliance with section 20.1204(g) of title 10 of the Code of Federal Regulations (10 CFR). The license condition also states that for any changes to operations, the licensee shall conduct an evaluation to determine if more frequent isotopic analyses are required for compliance with 10 CFR 20.1204(g). In its September 21, 2015, response to NRC staff requests for additional information (RAIs), CBR clarified its approach to determining internal dose by air sampling, including an analysis of how CBR meets the requirement in 10 CFR 20.1204(g) for disregarding certain radionuclides contained in mixtures of radionuclides in air (ADAMS Accession No. ML15310A373). As part of its analysis, CBR stated that it accounts for all of the alpha-emitting radioactive material in air when measuring uranium, as described in its Technical Report, but it does not account for total activity (i.e., the sum of all alphaemitting and beta-emitting radioactive material in air) when determining internal dose. In accordance with 10 CFR 20.1204(g)(1), a licensee may only disregard certain radionuclides in a mixture if it uses the total activity of the mixture, which includes both alphaemitting and beta-emitting radionuclides, to demonstrate compliance with the dose limits in 10 CFR 20.1201 and to comply with the monitoring requirements in 10 CFR 20.1502(b). In addition to meeting the condition of 10 CFR 20.1204(g)(1), a licensee must also show that the concentration of any radionuclide disregarded is less than 10 percent of its derived air concentration (DAC), and the sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent, in accordance with 10 CFR 20.1204(g)(2) and 10 CFR 20.1204(g)(3), respectively, in order to disregard certain radionuclides in a mixture. In its September 21, 2015, RAI response, CBR requested an exemption from including the internal dose from beta-emitting radionuclides in occupational dose calculations. In support of this request, CBR provided the following information: (1) CBR accounts for all alpha activity on the sample filters used in its air sampling program, which accounts for nearly all of the internal dose received from airborne radionuclides typically present at an in-situ recovery facility other than radon-222 (radon) and its short-lived progeny; (2) the contribution to occupational dose from internal exposure to airborne beta-emitting radionuclides (other than radon-222 and PO 00000 Frm 00095 Fmt 4703 Sfmt 4703 its short-lived progeny) is very small relative to other sources of occupational dose (such as external dose and internal dose from inhalation of radon-222 and its short-lived progeny, which are accounted for separately); and (3) it would be administratively complex to attempt to track, and account for, a comparatively small internal dose from airborne non-radon beta-emitting radionuclides at the Crow Butte Project. II. Description of Action The NRC may, under 10 CFR 20.2301, upon application by a licensee or upon its own initiative, grant an exemption from the requirements of the regulations in 10 CFR part 20, if the NRC determines the exemption is authorized by law and would not result in undue hazard to life or property. As described in the NRC staff’s safety evaluation report for this exemption request (ADAMS Accession No. ML16078A238), the NRC staff found that this exemption is authorized by law and will not result in undue hazard to life or property. Therefore, the NRC is granting CBR an exemption from the requirement in 10 CFR 20.1204(g)(1) to use the total activity of the mixture in demonstrating compliance with the dose limits specified in § 20.1201. The licensee must still consider all radionuclides in demonstrating compliance with the requirements in § 20.1502(b). In conjunction with granting this exemption, the NRC is revising license condition 10.8 of CBR’s license SUA– 1534 to reflect the terms of the exemption. III. Discussion A. The Exemption Is Authorized by Law The NRC staff concluded that the exemption is authorized by law as 10 CFR 20.2301 expressly allows for an exemption to the requirements in 10 CFR part 20, and the exemption will not be contrary to any provision of the Atomic Energy Act of 1954, as amended. B. The Exemption Presents No Undue Hazard to Life or Property The exemption is related to the requirement in 10 CFR 20.1501(a) for licensees to make, or cause to be made, appropriate surveys. In accordance with 10 CFR 20.1204(g), when concentrations of radioactive material in air are relied upon to determine internal dose, a licensee may disregard certain radionuclides contained in a mixture of radionuclides in air if the following three conditions are met: (1) the licensee uses the total activity of the mixture in demonstrating compliance with the dose limits in § 20.1201 and in E:\FR\FM\21NON1.SGM 21NON1 83291 Federal Register / Vol. 81, No. 224 / Monday, November 21, 2016 / Notices complying with the monitoring requirements in § 20.1502(b); (2) the concentration of any radionuclide disregarded is less than 10 percent of its DAC; and (3) the sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent. CBR has demonstrated, and the NRC staff has verified, that its surveys under § 20.1501(a) and its method of determination under § 20.1204 account for nearly all of the occupational dose and that any additional contribution to occupational dose from internal exposure to airborne non-radon betaemitting radionuclides is very small. Furthermore, in conjunction with granting this exemption, the NRC staff is revising CBR license condition 10.8 to require CBR to periodically assess the mixture of airborne radionuclides present at its facility against a specific regulatory limit. This will ensure that CBR will be aware of changes in the mixture of airborne radionuclides at the Crow Butte Project and that the contribution to occupational dose from internal exposure to beta-emitting radionuclides will remain small. Therefore, granting this exemption presents no undue hazard to life or property. C. Environmental Considerations The NRC staff has determined that granting of an exemption from the requirements of 10 CFR 20.1204(g)(1) belongs to a category of regulatory actions which the NRC, by regulation, has determined do not individually or cumulatively have a significant effect on the environment, and as such do not require an environmental assessment or environmental impact statement. Specifically, the exemption from the requirement to include all radionuclides that contribute to total activity under 10 CFR 20.1204(g)(1) is eligible for categorical exclusion under 10 CFR 51.22(c)(25) based on the NRC staff’s determinations that requirements from which exemption is sought involve inspection or surveillance requirements (a survey under 10 CFR 20.1501(a)), and that the exemption will result in no significant change in the types or significant increase the amount of any offsite effluents; no significant increase to individual or cumulative public or occupational radiation exposure; no significant construction impact; and no significant increase to the potential for, or consequence from, radiological accidents. Section 7 of the Endangered Species Act (the Act) [16 U.S.C. 1531 et seq.] outlines the procedures for Federal interagency cooperation to conserve Federally-listed species and designated critical habitats. Section 7(a)(2) of the Act states that each Federal agency shall, in consultation with the Secretary, insure that any action they authorize, fund, or carry out is not likely to jeopardize the continued existence of a listed species or result in the destruction or adverse modification of designated critical habitat. The NRC staff has determined that a Section 7 consultation is not required because the proposed action is administrative/ procedural in nature and will not affect listed species or critical habitat. The NRC staff has also determined that the proposed action is not a type of activity that has potential to cause effects on historic properties because it is an administrative/procedural action. Therefore, no further consultation is required under Section 106 of the National Historic Preservation Act [54 U.S.C. 300101 et seq.]. IV. Conclusion Accordingly, the NRC has determined that, pursuant to 10 CFR 20.2301, the exemption is authorized by law and will not present an undue hazard to life or property. The NRC hereby grants CBR an exemption from the requirement in 10 CFR 20.1204(g)(1) to use the total activity of the mixture in demonstrating compliance with the dose limits in § 20.1201. Dated at Rockville, Maryland, this 14th day of November 2016. For the Nuclear Regulatory Commission. Andrea Kock, Deputy Director, Division of Decommissioning, Uranium Recovery and Environmental Programs, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2016–27946 Filed 11–18–16; 8:45 am] BILLING CODE 7590–01–P OFFICE OF PERSONNEL MANAGEMENT Excepted Service U.S. Office of Personnel Management (OPM). ACTION: Notice. AGENCY: This notice identifies Schedule A, B, and C appointing authorities applicable to a single agency that were established or revoked from March 1, 2016, to March 31, 2016. FOR FURTHER INFORMATION CONTACT: Senior Executive Resources Services, Senior Executive Services and Performance Management, Employee Services, 202–606–2246. SUPPLEMENTARY INFORMATION: In accordance with 5 CFR 213.103, Schedule A, B, and C appointing authorities available for use by all agencies are codified in the Code of Federal Regulations (CFR). Schedule A, B, and C appointing authorities applicable to a single agency are not codified in the CFR, but the Office of Personnel Management (OPM) publishes a notice of agency-specific authorities established or revoked each month in the Federal Register at www.gpo.gov/fdsys/. OPM also publishes an annual notice of the consolidated listing of all Schedule A, B, and C appointing authorities, current as of June 30, in the Federal Register. Schedule A No Schedule A Authorities to report during March 2016. Schedule B No Schedule B Authorities to report during March 2016. Schedule C The following Schedule C appointing authorities were approved during March 2016. SUMMARY: Authorization No. asabaliauskas on DSK3SPTVN1PROD with NOTICES Agency name Organization name Position title Department of Agriculture .............. Farm Service Agency .................... State Executive Director—Rhode Island. State Executive Director ................ Senior Advisor ................................ State Director ................................. Senior Advisor for Strategic Communications. Rural Housing Service ................... Office of Communications .............. VerDate Sep<11>2014 18:09 Nov 18, 2016 Jkt 241001 PO 00000 Frm 00096 Fmt 4703 Sfmt 4703 E:\FR\FM\21NON1.SGM Effective date DA160077 3/4/2016 DA160091 DA160081 DA160090 DA160083 3/30/2016 3/17/2016 3/30/2016 3/17/2016 21NON1

Agencies

[Federal Register Volume 81, Number 224 (Monday, November 21, 2016)]
[Notices]
[Pages 83289-83291]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-27946]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket No. 040-08943; NRC-2008-0208]


Crow Butte Resources, Inc.

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an 
exemption to Crow Butte Resources, Inc. (CBR) for the purpose of 
complying with occupational dose limits in response to a request from 
CBR dated September 21, 2015. Issuance of this exemption will allow CBR 
to disregard certain radionuclides that contribute to the total 
activity of a mixture when determining internal dose to assess 
compliance with occupational dose equivalent limits at its in situ 
uranium recovery (ISR) facility in Crawford, Nebraska.

ADDRESSES: Please refer to Docket ID NRC-2008-0208 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2008-0208. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov. For technical questions, contact 
the individual listed in the FOR FURTHER INFORMATION CONTACT section of 
this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the

[[Page 83290]]

ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. The 
ADAMS accession number for each document referenced (if that document 
is available in ADAMS) is provided the first time that a document is 
referenced.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Ronald A. Burrows, Office of Nuclear 
Material Safety and Safeguards; U.S. Nuclear Regulatory Commission, 
Washington DC 20555-0001; telephone: 301-415-6443; email: 
Ronald.Burrows@nrc.gov.

SUPPLEMENTARY INFORMATION: 

I. Background

    Crow Butte Resources, Inc. operates the Crow Butte ISR facility in 
Crawford, Nebraska (the Crow Butte Project) under NRC source materials 
license SUA-1534 (ADAMS Accession No. ML13324A101). At the Crow Butte 
Project, CBR performs airborne uranium particulate monitoring in the 
plant in accordance with Section 5.8.3.1 of its Technical Report (ADAMS 
Accession No. ML091470116). As described in its Technical Report, CBR 
measures airborne uranium by taking samples of particulate matter in 
air at locations within the plant using glass fiber filters and air 
pumps. The measurement of airborne uranium is performed by gross alpha 
counting of air filters.
    In Section 5.7.4.3.1, ``Airborne Particulate Uranium Monitoring,'' 
of the NRC staff's 2014 Safety Evaluation Report (SER) for the renewal 
of CBR's license for the Crow Butte Project (ADAMS Accession No. 
ML14149A433), the NRC staff stated that CBR did not demonstrate that 
gross alpha counting would differentiate all airborne radioactivity in 
air samples, including radionuclides that are not uranium, some of 
which may not emit alpha particles and, therefore, will not be 
detected. As a result, the NRC staff imposed license condition 10.8 in 
CBR's license SUA-1534, which states that the licensee shall conduct 
isotopic analyses for alpha- and beta-emitting radionuclides on 
airborne samples at each in-plant air particulate sampling location at 
a frequency of once every 6 months for the first 2 years and annually 
thereafter to ensure compliance with section 20.1204(g) of title 10 of 
the Code of Federal Regulations (10 CFR). The license condition also 
states that for any changes to operations, the licensee shall conduct 
an evaluation to determine if more frequent isotopic analyses are 
required for compliance with 10 CFR 20.1204(g).
    In its September 21, 2015, response to NRC staff requests for 
additional information (RAIs), CBR clarified its approach to 
determining internal dose by air sampling, including an analysis of how 
CBR meets the requirement in 10 CFR 20.1204(g) for disregarding certain 
radionuclides contained in mixtures of radionuclides in air (ADAMS 
Accession No. ML15310A373). As part of its analysis, CBR stated that it 
accounts for all of the alpha-emitting radioactive material in air when 
measuring uranium, as described in its Technical Report, but it does 
not account for total activity (i.e., the sum of all alpha-emitting and 
beta-emitting radioactive material in air) when determining internal 
dose. In accordance with 10 CFR 20.1204(g)(1), a licensee may only 
disregard certain radionuclides in a mixture if it uses the total 
activity of the mixture, which includes both alpha-emitting and beta-
emitting radionuclides, to demonstrate compliance with the dose limits 
in 10 CFR 20.1201 and to comply with the monitoring requirements in 10 
CFR 20.1502(b). In addition to meeting the condition of 10 CFR 
20.1204(g)(1), a licensee must also show that the concentration of any 
radionuclide disregarded is less than 10 percent of its derived air 
concentration (DAC), and the sum of these percentages for all of the 
radionuclides disregarded in the mixture does not exceed 30 percent, in 
accordance with 10 CFR 20.1204(g)(2) and 10 CFR 20.1204(g)(3), 
respectively, in order to disregard certain radionuclides in a mixture.
    In its September 21, 2015, RAI response, CBR requested an exemption 
from including the internal dose from beta-emitting radionuclides in 
occupational dose calculations. In support of this request, CBR 
provided the following information: (1) CBR accounts for all alpha 
activity on the sample filters used in its air sampling program, which 
accounts for nearly all of the internal dose received from airborne 
radionuclides typically present at an in-situ recovery facility other 
than radon-222 (radon) and its short-lived progeny; (2) the 
contribution to occupational dose from internal exposure to airborne 
beta-emitting radionuclides (other than radon-222 and its short-lived 
progeny) is very small relative to other sources of occupational dose 
(such as external dose and internal dose from inhalation of radon-222 
and its short-lived progeny, which are accounted for separately); and 
(3) it would be administratively complex to attempt to track, and 
account for, a comparatively small internal dose from airborne non-
radon beta-emitting radionuclides at the Crow Butte Project.

II. Description of Action

    The NRC may, under 10 CFR 20.2301, upon application by a licensee 
or upon its own initiative, grant an exemption from the requirements of 
the regulations in 10 CFR part 20, if the NRC determines the exemption 
is authorized by law and would not result in undue hazard to life or 
property. As described in the NRC staff's safety evaluation report for 
this exemption request (ADAMS Accession No. ML16078A238), the NRC staff 
found that this exemption is authorized by law and will not result in 
undue hazard to life or property. Therefore, the NRC is granting CBR an 
exemption from the requirement in 10 CFR 20.1204(g)(1) to use the total 
activity of the mixture in demonstrating compliance with the dose 
limits specified in Sec.  20.1201. The licensee must still consider all 
radionuclides in demonstrating compliance with the requirements in 
Sec.  20.1502(b). In conjunction with granting this exemption, the NRC 
is revising license condition 10.8 of CBR's license SUA-1534 to reflect 
the terms of the exemption.

III. Discussion

A. The Exemption Is Authorized by Law

    The NRC staff concluded that the exemption is authorized by law as 
10 CFR 20.2301 expressly allows for an exemption to the requirements in 
10 CFR part 20, and the exemption will not be contrary to any provision 
of the Atomic Energy Act of 1954, as amended.

B. The Exemption Presents No Undue Hazard to Life or Property

    The exemption is related to the requirement in 10 CFR 20.1501(a) 
for licensees to make, or cause to be made, appropriate surveys. In 
accordance with 10 CFR 20.1204(g), when concentrations of radioactive 
material in air are relied upon to determine internal dose, a licensee 
may disregard certain radionuclides contained in a mixture of 
radionuclides in air if the following three conditions are met: (1) the 
licensee uses the total activity of the mixture in demonstrating 
compliance with the dose limits in Sec.  20.1201 and in

[[Page 83291]]

complying with the monitoring requirements in Sec.  20.1502(b); (2) the 
concentration of any radionuclide disregarded is less than 10 percent 
of its DAC; and (3) the sum of these percentages for all of the 
radionuclides disregarded in the mixture does not exceed 30 percent.
    CBR has demonstrated, and the NRC staff has verified, that its 
surveys under Sec.  20.1501(a) and its method of determination under 
Sec.  20.1204 account for nearly all of the occupational dose and that 
any additional contribution to occupational dose from internal exposure 
to airborne non-radon beta-emitting radionuclides is very small. 
Furthermore, in conjunction with granting this exemption, the NRC staff 
is revising CBR license condition 10.8 to require CBR to periodically 
assess the mixture of airborne radionuclides present at its facility 
against a specific regulatory limit. This will ensure that CBR will be 
aware of changes in the mixture of airborne radionuclides at the Crow 
Butte Project and that the contribution to occupational dose from 
internal exposure to beta-emitting radionuclides will remain small. 
Therefore, granting this exemption presents no undue hazard to life or 
property.

C. Environmental Considerations

    The NRC staff has determined that granting of an exemption from the 
requirements of 10 CFR 20.1204(g)(1) belongs to a category of 
regulatory actions which the NRC, by regulation, has determined do not 
individually or cumulatively have a significant effect on the 
environment, and as such do not require an environmental assessment or 
environmental impact statement. Specifically, the exemption from the 
requirement to include all radionuclides that contribute to total 
activity under 10 CFR 20.1204(g)(1) is eligible for categorical 
exclusion under 10 CFR 51.22(c)(25) based on the NRC staff's 
determinations that requirements from which exemption is sought involve 
inspection or surveillance requirements (a survey under 10 CFR 
20.1501(a)), and that the exemption will result in no significant 
change in the types or significant increase the amount of any offsite 
effluents; no significant increase to individual or cumulative public 
or occupational radiation exposure; no significant construction impact; 
and no significant increase to the potential for, or consequence from, 
radiological accidents.
    Section 7 of the Endangered Species Act (the Act) [16 U.S.C. 1531 
et seq.] outlines the procedures for Federal interagency cooperation to 
conserve Federally-listed species and designated critical habitats. 
Section 7(a)(2) of the Act states that each Federal agency shall, in 
consultation with the Secretary, insure that any action they authorize, 
fund, or carry out is not likely to jeopardize the continued existence 
of a listed species or result in the destruction or adverse 
modification of designated critical habitat. The NRC staff has 
determined that a Section 7 consultation is not required because the 
proposed action is administrative/procedural in nature and will not 
affect listed species or critical habitat. The NRC staff has also 
determined that the proposed action is not a type of activity that has 
potential to cause effects on historic properties because it is an 
administrative/procedural action. Therefore, no further consultation is 
required under Section 106 of the National Historic Preservation Act 
[54 U.S.C. 300101 et seq.].

IV. Conclusion

    Accordingly, the NRC has determined that, pursuant to 10 CFR 
20.2301, the exemption is authorized by law and will not present an 
undue hazard to life or property. The NRC hereby grants CBR an 
exemption from the requirement in 10 CFR 20.1204(g)(1) to use the total 
activity of the mixture in demonstrating compliance with the dose 
limits in Sec.  20.1201.

    Dated at Rockville, Maryland, this 14th day of November 2016.

    For the Nuclear Regulatory Commission.
Andrea Kock,
Deputy Director, Division of Decommissioning, Uranium Recovery and 
Environmental Programs, Office of Nuclear Material Safety and 
Safeguards.
[FR Doc. 2016-27946 Filed 11-18-16; 8:45 am]
 BILLING CODE 7590-01-P
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