Federal Register / Vol. 79, No. 244 / Friday, December 19, 2014 / Notices 75843 

to other NRTLs that operate multiple 

sites. 

C. Supplemental Programs 

OSHA limits QAI’s scope of 

recognition to include the following 

supplemental program: 

Program 9: Acceptance of services 

other than testing or evaluation 

performed by subcontractors or agents 

(for calibration services only). 

A. Conditions 

In addition to those conditions 

already required by 29 CFR 1910.7, QAI 

also must abide by the following 

conditions of the recognition: 

1. QAI must inform OSHA as soon as 

possible, in writing, of any change of 

ownership, facilities, or key personnel, 

and of any major change in its 

operations as an NRTL, and provide 

details of the change(s); 

2. QAI must meet all the terms of its 

recognition and comply with all OSHA 

policies pertaining to this recognition; 

and 

3. QAI must continue to meet the 

requirements for recognition, including 

all previously published conditions on 

QAI’s scope of recognition, in all areas 

for which it has recognition. 

Pursuant to the authority in 29 CFR 

1910.7, OSHA hereby grants recognition 

to QAI as an NRTL, subject to the 

limitations and conditions specified 

above. 

IV. Authority and Signature 

David Michaels, Ph.D., MPH, 

Assistant Secretary of Labor for 

Occupational Safety and Health, 200 

Constitution Avenue NW., Washington, 

DC 20210, authorized the preparation of 

this notice. Accordingly, the Agency is 

issuing this notice pursuant to 29 U.S.C. 

657(g)(2), Secretary of Labor’s Order No. 

1–2012 (77 FR 3912, Jan. 25, 2012), and 

29 CFR 1910.7. 

Signed at Washington, DC, on December 

15, 2014. 

David Michaels, 

Assistant Secretary of Labor for Occupational 

Safety and Health. 

[FR Doc. 2014–29731 Filed 12–18–14; 8:45 am] 

BILLING CODE 4510–26–P 

NATIONAL FOUNDATION ON THE 

ARTS AND THE HUMANITIES 

Institute of Museum and Library 

Services 

Sunshine Act Meeting of the National 

Museum and Library Services Board 

AGENCY: Institute of Museum and 

Library Services (IMLS), NFAH. 

ACTION: Notice of Meeting. 

SUMMARY: The National Museum and 

Library Services Board, which advises 

the Director of the Institute of Museum 

and Library Services in awarding 

national awards and medals, will meet 

by teleconference on February 23, 2015, 

to review nominations for the 2015 

National Medal for Museum and Library 

Service. 

DATE AND TIME: Monday, February 23, 

2015, at 1 p.m. EST. 

PLACE: The meeting will be held by 

teleconference originating at the 

Institute of Museum and Library 

Services. 1800 M Street NW., 9th Floor, 

Washington, DC, 20036. Telephone: 

(202) 653–4676. 

STATUS: Closed. The meeting will be 

closed pursuant to subsections (c)(4) 

and (c)(9) of section 552b of Title 5, 

United States Code because the Board 

will consider information that may 

disclose: Trade secrets and commercial 

or financial information obtained from a 

person and privileged or confidential; 

and information the premature 

disclosure of which would be likely to 

significantly frustrate implementation of 

a proposed agency action. 

FOR FURTHER INFORMATION CONTACT: 

Katherine Maas, Program Specialist, 

Institute of Museum and Library 

Services, 1800 M Street NW., 9th Floor, 

Washington, DC 20036. Telephone: 

(202) 653–4798. 

Signed: December 16, 2014. 

Andrew Christopher, 

Assistant General Counsel. 

[FR Doc. 2014–29797 Filed 12–17–14; 11:15 am] 

BILLING CODE 7036–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–313, 50–368, 72–13, and 

72–1014; NRC–2014–0270] 

Independent Spent Fuel Storage 

Installation, Entergy Operations, Inc.; 

Arkansas Nuclear One, Units 1 and 2 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Environmental assessment and 

finding of no significant impact; 

issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is considering 

issuance of an exemption to Entergy 

Operations, Inc. (Entergy or the 

licensee), for the operation of the 

Arkansas Nuclear One (ANO), Units 1 

and 2, Independent Spent Fuel Storage 

Installation (ISFSI). The request is for an 

exemption from the requirement to 

comply with the terms, conditions, and 

specifications in Section 2.1 of 

Appendix B of Certificate of Compliance 

(CoC) No. 1014, Amendment No. 5, for 

the Holtec International (Holtec) HI– 

STORM 100 dry cask storage system. 

DATES: The environmental assessment 

and finding of no significant impact are 

available as of December 19, 2014. 

ADDRESSES: Please refer to Docket ID 

NRC–2014–0270 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–2014–0270. 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 publicly 

available 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. The 

ADAMS accession number for each 

document referenced in this document 

(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: 

Chris Allen, Office of Nuclear Material 

Safety and Safeguards, telephone: 301– 

287–9225, email: William.Allen@

nrc.gov; U.S. Nuclear Regulatory 

Commission, Washington, DC 20555. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The NRC is considering issuance of an 

exemption to Entergy, for operation of 

the ANO ISFSI, located in Russellville, 

Arkansas. Pursuant to § 72.7 of Title 10 

of the Code of Federal Regulations (10 

CFR), on October 2, 2014, as 

supplemented on October 14 and 

November 7, 2014 (ADAMS Accession 

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75844 Federal Register / Vol. 79, No. 244 / Friday, December 19, 2014 / Notices 

Nos. ML14279A246, ML14289A239, 

and ML14311A121, respectively), 

Entergy submitted its request for 

exemption from the requirements of 10 

CFR 72.212(a)(2) and the portion of 10 

CFR 72.212(b)(11) that requires 

compliance with the terms, conditions, 

and specifications of CoC No. 1014, 

Amendment No. 5, for the HI–STORM 

100 dry cask storage system. In 

evaluating the request, the NRC also 

considered exemption from the 

requirements of 10 CFR 72.212(b)(3), 10 

CFR 72.212(b)(5)(i), and 10 CFR 72.214 

applicable to the request and has 

weighed these regulations in its review. 

Entergy loaded spent nuclear fuel into 

a Model 24 Multi-Purpose Canister 

(MPC–24) under CoC No. 1014, 

Amendment No. 5. While performing 

drying operations on MPC–24–060, a 

radiation alarm actuated. In evaluating 

the cause of the alarm, the licensee 

subsequently determined that a fuel 

assembly loaded into MPC–24–060 may 

contain a fuel rod with cladding damage 

greater than a pinhole leak or hairline 

crack. Section 2.1 of Appendix B of the 

Technical Specifications (TS) for CoC 

No. 1014, Amendment No. 5, only 

authorizes storage of intact fuel 

assemblies, which is defined as fuel 

assemblies without known or suspected 

cladding defects greater than pinhole 

leaks or hairline cracks and which can 

be handled by normal means. Entergy 

requests an exemption to the 10 CFR 

part 72 requirements to store the 

affected MPC in its current condition at 

the ISFSI associated with the operation 

of ANO, Units 1 and 2. 

II. Environmental Assessment (EA) 

Identification of Proposed Action: The 

CoC is the NRC approved design for 

each dry cask storage system. The 

proposed action would grant Entergy an 

exemption from the requirements of 10 

CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 

10 CFR 72.212(b)(5)(i), and the portion 

of 10 CFR 72.212(b)(11) that states the 

licensee shall comply with the terms, 

conditions, and specifications of the 

CoC, and from 10 CFR 72.214 to the 

extent necessary for Entergy to store 

MPC–24–060 in its current condition at 

the ISFSI associated with ANO, Units 1 

and 2. These regulations specifically 

require storage of spent nuclear fuel 

under a general license in dry storage 

casks approved under the provisions of 

10 CFR part 72, and compliance with 

the terms and conditions set forth in the 

CoC for each dry storage spent fuel cask 

used by an ISFSI general licensee. 

Section 2.1 of Appendix B of the TS 

for CoC No. 1014, Amendment No. 5, 

only authorizes storage of intact fuel, 

which is defined as fuel assemblies 

without known or suspected cladding 

defects greater than pinhole leaks or 

hairline cracks and which can be 

handled by normal means. Entergy 

performed tests on the fuel assemblies 

loaded into MPC–24–060 after their 

final operating cycle as well as visual 

examinations prior to loading. 

Nevertheless, a fuel assembly having 

defects greater than pinhole leaks and 

hairline cracks may have been 

inadvertently loaded into MPC–24–060. 

The proposed action would grant 

Entergy an exemption from the 

requirements of 10 CFR 72.212(a)(2), 10 

CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 

and the portion of 10 CFR 72.212(b)(11) 

that states the licensee shall comply 

with the terms, conditions, and 

specifications of the CoC, and from 10 

CFR 72.214, in order to allow storage of 

MPC–24–060 in its current condition. 

This exemption approval would only be 

valid for MPC–24–060 at the ANO 

ISFSI. 

Need for the Proposed Action: The 

proposed action is necessary to avoid 

unloading the MPC. Entergy requested 

this exemption in order to store an MPC 

containing a fuel assembly which may 

have cladding damage greater than a 

pinhole leak or hairline crack. Entergy, 

with the assistance of Holtec, has 

provided an evaluation which shows 

that the affected MPC is bounded by the 

system’s design basis limits and that 

storage of the fuel in the as-loaded 

configuration is safe. 

Entergy has evaluated the 

consequences of not obtaining an 

exemption, which would occur if the 

NRC did not take the proposed action. 

In the absence of an exemption, Entergy 

would be required to correct the 

condition by reloading the affected MPC 

to comply with CoC No. 1014, 

Amendment No. 5. This would involve 

unloading the spent fuel assemblies 

from the MPC, performing inspections 

of various MPC components, reloading 

the spent fuel assemblies into the used 

MPC or a new MPC (if there was damage 

noted on the used MPC) in accordance 

with CoC No. 1014, Amendment No. 5, 

and performing the MPC closing 

procedures. 

Based upon its previous experience 

with the loading process, Entergy 

estimates that unloading and reloading 

the MPC would result in additional 

personnel exposure of 600 mRem. In 

addition, Entergy states unloading and 

reloading the MPC would generate 

radioactive contaminated material and 

waste during loading and unloading 

operations. If the used MPC was 

damaged during the unloading process, 

it would also be disposed as radioactive 

waste. The licensee estimates that 

unloading and reloading operations 

would cost an estimated $300,000. If the 

used MPC was damaged during 

unloading, the licensee estimates an 

additional $750,000 for purchase of a 

new MPC and $200,000 for disposal of 

the used MPC. The licensee also states 

additional opportunities for design basis 

accidents such as a fuel handling 

accident would be introduced if the 

MPC were unloaded and reloaded. 

Environmental Impacts of the 

Proposed Action: The potential impact 

of using the HI–STORM 100 dry cask 

storage system was initially presented in 

the Environmental Assessment (EA) for 

the rulemaking to add the HI–STORM 

100 dry cask storage system for 

irradiated nuclear fuel to the list of 

approved spent fuel storage casks in 10 

CFR 72.214 (64 FR 51271, September 

22, 1999 (Proposed Rule); 65 FR 25241, 

May 1, 2000 (Final Rule)). 

In support of their exemption request, 

the licensee submitted Holtec Report 

No. HI–2146265 which evaluated 

storage of fuel assemblies having greater 

than pinhole leaks and hairline cracks 

in the HI–STORM 100 system (ADAMS 

Accession No. ML14279A246). The 

analysis concluded that the as-loaded 

condition has no impact on internal 

temperature or pressure, that the site 

boundary dose is unaffected (should 

relocation of material occur inside the 

MPC), and that potential reactivity 

effects remain well within acceptable 

margins. The analysis also concluded 

that the damaged fuel rods have no 

impact on the ability either of the MPC, 

the HI–TRAC transfer cask, or the HI– 

STORM storage cask to withstand 

pressure loads due to tornado winds, 

flood, or explosions. 

Based on its review of the licensee’s 

application, the NRC staff concludes 

that there are no changes in either the 

types or the amounts of radiological 

effluents that may be released offsite, 

and there is no significant increase in 

occupational or public radiation 

exposure as a result of the proposed 

activities. Therefore, there are no 

significant radiological environmental 

impacts associated with the proposed 

action. The NRC staff concludes that the 

proposed action only affects the 

requirements associated with the fuel 

assemblies already loaded into the 

canister and does not affect nonradiological plant effluents, or any other 

aspects of the environment. 

Accordingly, the NRC staff concludes 

that there are no significant 

environmental impacts associated with 

the proposed action. 

Alternative to the Proposed Action: 

Because there is no significant 

environmental impact associated with 

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Federal Register / Vol. 79, No. 244 / Friday, December 19, 2014 / Notices 75845 

the proposed action, alternatives with 

equal or greater environmental impact 

were not evaluated. As an alternative to 

the proposed action, the NRC staff 

considered denial of the requested 

exemption, which would require 

unloading and reloading the affected 

MPC as described above. Denying the 

exemption would result in an increase 

in radiological exposure to workers, a 

small increase in the potential for 

radioactive releases to the environment 

due to radioactive material handling 

accidents, and increased cost to the 

licensee. Therefore, the NRC staff has 

determined that approving the proposed 

action has a lesser environmental 

impact than the alternative. 

Agencies and Persons Consulted: The 

environmental assessment associated 

with this exemption request was sent to 

Mr. Bernard Bevill Chief of the 

Radiation Control Section in the 

Arkansas Department of Health, by 

letter dated November 10, 2014. A 

response, which was received by 

electronic mail dated November 21, 

2014 (ADAMS Accession No. 

ML14328A287), states that the Arkansas 

Department of Health has no concerns. 

The NRC staff has determined that a 

consultation under Section 7 of the 

Endangered Species Act is not required 

because the proposed action will not 

affect listed species or a critical habitat. 

The NRC staff has also determined that 

the proposed action is not a type of 

activity having the potential to cause 

effects on historic properties. Therefore, 

no consultation is required under 

Section 106 of the National Historic 

Preservation Act. 

III. Finding of No Significant Impact 

The environmental impacts of the 

proposed action have been reviewed in 

accordance with the requirements set 

forth in 10 CFR part 51. Based upon the 

foregoing Environmental Assessment, 

the Commission finds that the proposed 

action of granting an exemption from 

the requirements of 10 CFR 72.212(a)(2), 

10 CFR 72.212(b)(3), 10 CFR 

72.212(b)(5)(i), and the portion of 10 

CFR 72.212(b)(11) that states the 

licensee shall comply with the terms, 

conditions, and specifications of the 

CoC, and from 10 CFR 72.214 in order 

to allow Entergy to store spent fuel 

assemblies in MPC–24–060 in the asloaded configuration at the ISFSI 

associated with ANO, Units 1 and 2, 

will not significantly impact the quality 

of the human environment. 

Accordingly, the Commission has 

determined that an environmental 

impact statement for the proposed 

exemption is not warranted and that a 

finding of no significant impact is 

appropriate. 

Dated at Rockville, Maryland, this 11th day 

of December, 2014. 

For the Nuclear Regulatory Commission. 

Chris Allen, 

Project Manager, Spent Fuel Licensing 

Branch, Division of Spent Fuel Management, 

Office of Nuclear Material Safety and 

Safeguards. 

[FR Doc. 2014–29750 Filed 12–18–14; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2014–0267] 

Draft Emergency Preparedness 

Frequently Asked Questions 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of availability; request 

for comment. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is seeking public 

comment on emergency preparedness 

(EP) frequently asked question (EPFAQ) 

No. 2014–002, EPFAQ No. 2014–003, 

and EPFAQ No. 2014–007. These 

EPFAQs will be used to provide 

clarification of guidance documents 

related to the development and 

maintenance of EP program elements. 

The NRC is publishing these 

preliminary results to inform the public 

and solicit comments. 

DATES: Submit comments by January 20, 

2015. Comments received after this date 

will be considered if it is practical to do 

so, but the NRC is able to ensure 

consideration only for comments 

received 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–2014–0267. 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, 

Chief, Rules, Announcements, and 

Directives Branch, Office of 

Administration, Mail Stop: 3WFN–06– 

A44M, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001. 

For additional direction on accessing 

information and submitting comments, 

see ‘‘Obtaining Information and 

Submitting Comments’’ in the 

SUPPLEMENTARY INFORMATION section of 

this document. 

FOR FURTHER INFORMATION CONTACT: 

Edward Robinson, Office of Nuclear 

Security and Incident Response, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, telephone: 

301–287–3774, or email at: 

edward.robinson@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and 

Submitting Comments 

A. Obtaining Information 

Please refer to Docket ID NRC–2014– 

0267 when contacting the NRC about 

the availability of information regarding 

this document. You may obtain 

publicly-available information related to 

this document by any of the following 

methods: 

• Federal Rulemaking Web site: Go to 

http://www.regulations.gov and search 

for Docket ID NRC–2014–0267. 

• NRC’s Agencywide Documents 

Access and Management System 

(ADAMS): You may access publicly 

available 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. The draft 

EPFAQs are available electronically in 

ADAMS under Accession No. 

ML14261A054, and are available on the 

NRC’s Web site at http://www.nrc.gov/ 

about-nrc/emerg-preparedness/faq/faqcontactus.html. 

• 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– 

0267 in the subject line of your 

comment submission, in order to ensure 

that the NRC is able to make your 

comment submission available to the 

public in this docket. 

The NRC cautions you not to include 

identifying or contact information in 

comment submissions that you do not 

want to be publicly disclosed. The NRC 

posts all comment submissions at http:// 

www.regulations.gov as well as entering 

the comment submissions into ADAMS, 

and the NRC does not edit comment 

mstockstill on DSK4VPTVN1PROD with NOTICES