Federal Register / Vol. 79, No. 243 / Thursday, December 18, 2014 / Notices 75597 

staff has concluded that the exemption 

would not reduce security measures 

currently in place to protect against 

radiological sabotage. Therefore, 

removing the requirement for a licensed 

senior operator to approve the 

suspension of security measures in an 

emergency or during severe weather so 

that suspension of security measures 

can be authorized by CFH does not 

adversely affect public health and safety 

issues or the assurance of the common 

defense and security. 

C. Is Otherwise in the Public Interest 

The DEF’s proposed exemption would 

remove the requirement that a licensed 

senior operator approve suspension of 

security measures in an emergency 

when ‘‘immediately needed to protect 

the public health and safety’’ or during 

severe weather when ‘‘immediately 

needed to protect the personal health 

and safety of security force personnel.’’ 

Without the exemption, the licensee 

cannot implement changes to its 

security plan to authorize a CFH to 

approve temporary suspension of 

security regulations during an 

emergency or severe weather 

comparable to the authority given to the 

CFH by the Commission when it 

promulgated § 50.54(y). Instead, the 

regulations would continue to require 

that a licensed senior operator be 

available to make decisions for a 

permanently shutdown plant, even 

though CR3 no longer requires a 

licensed senior operator. It is unclear 

how the licensee would implement 

emergency or severe weather 

suspensions of security measures 

without a licensed senior operator. This 

exemption is in the public interest for 

two reasons. First, without the 

exemption, there is uncertainty on how 

the licensee will invoke temporary 

suspension of security matters that may 

be needed to protect public health and 

safety or the safety of the security forces 

during emergencies and severe weather. 

Additionally, the consistent and 

efficient regulation of nuclear power 

plants serves the public interest by 

assuring consistency between the 

security regulations in 10 CFR part 73 

and the operating reactor regulations in 

10 CFR part 50, and the requirements 

concerning licensed operators in 10 CFR 

part 55. Accordingly, the NRC staff 

concludes that the exemption 

requirements to obtain approval from a 

licensed senior operator, who is not 

otherwise required for a permanently 

shutdown and defueled reactor, before 

taking steps to protect the public health 

and safety, or to protect the safety of the 

security force, is in the public interest. 

D. Environmental Considerations 

The NRC approval of the exemption 

to security requirements belongs to a 

category of actions that the Commission, 

by rule or regulation, has declared to be 

a categorical exclusion, after first 

finding that the category of actions does 

not individually or cumulatively have a 

significant effect on the human 

environment. Specifically, the 

exemption is categorically excluded 

from further analysis under 

§ 51.22(c)(25). 

Under § 51.22(c)(25), granting of an 

exemption from the requirements of any 

regulation of Chapter I to 10 CFR is a 

categorical exclusion provided that (i) 

there is no significant hazards 

consideration; (ii) there is no significant 

change in the types or significant 

increase in the amounts of any effluents 

that may be released offsite; (iii) there is 

no significant increase in individual or 

cumulative public or occupational 

radiation exposure; (iv) there is no 

significant construction impact; (v) 

there is no significant increase in the 

potential for or consequences from 

radiological accidents; and (vi) the 

requirements from which an exemption 

is sought involve: safeguard plans, and 

materials control and accounting 

inventory scheduling requirements; or 

involve other requirements of an 

administrative, managerial, or 

organizational nature. 

The Director, Division of Operating 

Reactor Licensing, Office of Nuclear 

Reactor Regulation, has determined that 

approval of the exemption request 

involves no significant hazards 

consideration because removing the 

requirement to have a licensed senior 

operator approve the security 

suspension at a defueled shutdown 

power plant does not (1) involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated; or (2) create the possibility of 

a new or different kind of accident from 

any accident previously evaluated; or 

(3) involve a significant reduction in a 

margin of safety. The exempted security 

regulation is unrelated to any 

operational restriction. Accordingly, 

there is no significant change in the 

types or significant increase in the 

amounts of any effluents that may be 

released offsite; and no significant 

increase in individual or cumulative 

public or occupational radiation 

exposure. The exempted regulation is 

not associated with construction, so 

there is no significant construction 

impact. The exempted regulation does 

not concern the source term (i.e., 

potential amount of radiation in an 

accident), nor mitigation. Thus, there is 

no significant increase in the potential 

for, or consequences of, a radiological 

accident. The requirement to have a 

licensed senior operator approve 

departure from security actions may be 

viewed as involving either safeguards, 

materials control, or managerial matters. 

Therefore, pursuant to §§ 51.22(b) and 

51.22(c)(25), no environmental impact 

statement or environmental assessment 

need be prepared in connection with the 

approval of this exemption request. 

IV. Conclusions 

Accordingly, the Commission has 

determined that, pursuant to § 73.5, the 

exemption is authorized by law and will 

not endanger life or property or the 

common defense and security, and is 

otherwise in the public interest. 

Therefore, the Commission hereby 

grants DEF exemption from the 

requirements of §§ 73.55(p)(1)(i) and 

73.55(p)(1)(ii), which otherwise would 

require suspension of security measures 

during emergencies and severe weather, 

respectively, to be approved by a 

licensed senior operator. The exemption 

is effective upon issuance. 

Dated at Rockville, Maryland, this 9th day 

of December 2014. 

For the Nuclear Regulatory Commission. 

Michele G. Evans, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. 2014–29656 Filed 12–17–14; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2014–0178] 

Standard Review Plan for Conventional 

Uranium Mills and Heap Leach 

Facilities 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Draft NUREG; request for 

comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment a draft NUREG, NUREG–2126, 

‘‘Standard Review Plan for 

Conventional Uranium Mills and Heap 

Leach Facilities.’’ The NRC has 

developed draft NUREG–2126 to 

provide guidance for NRC staff reviews 

of applications to develop and operate 

conventional uranium mills and heap 

leach facilities and to ensure a 

consistent quality and uniformity of 

staff reviews. 

DATES: Submit comments by March 18, 

2015. Comments received after this date 

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75598 Federal Register / Vol. 79, No. 243 / Thursday, December 18, 2014 / Notices 

will be considered if it is practical to do 

so, but the Commission is able to ensure 

consideration only for comments 

received on or before this date. 

ADDRESSES: You may submit comments 

by any of the following methods (unless 

this document describes a different 

method for submitting comments on a 

specific subject): 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2014–0178. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–287–3422; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individual listed in the FOR FURTHER

INFORMATION CONTACT section of this 

document. 

• Mail comments to: Cindy Bladey, 

Office of Administration, Mail Stop: 

3WFN–06–A44M, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

For additional direction on obtaining 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Douglas T. Mandeville, Office of 

Nuclear Material Safety and Safeguards, 

telephone: 301–415–0724, email: 

douglas.mandeville@nrc.gov, U.S. 

Nuclear Regulatory Commission, 

Washington DC 20555–0001. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2014– 

0178 when contacting the NRC about 

the availability of information for this 

action. You may obtain publiclyavailable information related to this 

action by any of the following methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2014–0178. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may obtain publiclyavailable documents online in the 

ADAMS Public Documents collection at 

http://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. Draft 

NUREG–2126 is available in ADAMS 

under Accession No. ML14325A634. 

• 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. 

B. Submitting Comments 

Please include Docket ID NRC–2014– 

0178 in the subject line of your 

comment submission. 

The NRC cautions you not to include 

identifying or contact information that 

you do not want to be publicly 

disclosed in your comment submission. 

The NRC posts all comment 

submissions at http://

www.regulations.gov as well as entering 

the comment submissions into ADAMS. 

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. Discussion 

Under the provisions of part 40 of 

Title 10 of the Code of Federal 

Regulations, ‘‘Domestic Licensing of 

Source Material,’’ an NRC materials 

license is required to conduct uranium 

recovery by conventional mill or heap 

leach techniques. Applicants for a new 

license and operators seeking an 

amendment or renewal of an existing 

license are required to provide detailed 

information on the facilities, equipment, 

and procedures used in the proposed 

activities. This information is used by 

the NRC staff to determine whether the 

proposed activities will be protective of 

public health and safety and the 

environment. Each section in the Draft 

NUREG–2126 provides guidance on 

what information is to be reviewed, the 

basis for the review, how the NRC staff 

review is to be accomplished, what the 

staff will find acceptable in a 

demonstration of compliance with 

applicable regulations, and the 

evaluation criteria for determining 

compliance with the applicable 

regulations. Draft NUREG–2126 is 

intended to improve the understanding 

of the NRC staff’s review process by 

interested members of the public and 

the uranium recovery industry. Any 

interested party may submit comments 

on draft NUREG–2126 for consideration 

by the NRC staff. 

Dated at Rockville, Maryland, this 8 th day 

of December 2014. 

For the Nuclear Regulatory Commission. 

Andrew Persinko, 

Deputy Director, Division of 

Decommissioning, Uranium Recovery and 

Waste Programs, Office of Nuclear Material 

Safety and Safeguards. 

[FR Doc. 2014–29663 Filed 12–17–14; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–373 and 50–374; NRC– 

2014–0268] 

LaSalle County Station, Units 1 and 2 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: License renewal application; 

receipt. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) has received an 

application for the renewal of operating 

licenses NPF–11 and NPF–18, which 

authorize Exelon Generation Company, 

LLC (the applicant) to operate LaSalle 

County Station (LSCS), Units 1 and 2. 

The renewed licenses would authorize 

the applicant to operate LSCS, Units 1 

and 2, for an additional 20-year period 

beyond the periods specified in each of 

the current licenses. The current 

operating licenses for LSCS, Units 1 and 

2, expire on April 17, 2022, and 

December 16, 2023, respectively. 

DATES: The license renewal application 

referenced in this document is available 

on December 18, 2014. 

ADDRESSES: Please refer to Docket ID 

NRC–2014–0268 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 

http://www.regulations.gov and search 

for Docket ID NRC–2014–0268. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–287–3422; 

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 

ADAMS Public Documents collection at 

http://www.nrc.gov/reading-rm/

adams.html. To begin the search, select 

mstockstill on DSK4VPTVN1PROD with NOTICES