10164 Federal Register / Vol. 80, No. 37 / Wednesday, February 25, 2015 / Notices 

application, processing, and disposition 

of petitions for modification. This notice 

is a summary of petitions for 

modification submitted to the Mine 

Safety and Health Administration 

(MSHA) by the parties listed below. 

DATES: All comments on the petitions 

must be received by the Office of 

Standards, Regulations, and Variances 

on or before March 27, 2015. 

ADDRESSES: You may submit your 

comments, identified by ‘‘docket 

number’’ on the subject line, by any of 

the following methods: 

1. Electronic Mail: zzMSHAcomments@dol.gov. Include the docket 

number of the petition in the subject 

line of the message. 

2. Facsimile: 202–693–9441. 

3. Regular Mail or Hand Delivery: 

MSHA, Office of Standards, 

Regulations, and Variances, 1100 

Wilson Boulevard, Room 2350, 

Arlington, Virginia 22209–3939, 

Attention: Sheila McConnell, Acting 

Director, Office of Standards, 

Regulations, and Variances. Persons 

delivering documents are required to 

check in at the receptionist’s desk on 

the 21st floor. Individuals may inspect 

copies of the petitions and comments 

during normal business hours at the 

address listed above. 

MSHA will consider only comments 

postmarked by the U.S. Postal Service or 

proof of delivery from another delivery 

service such as UPS or Federal Express 

on or before the deadline for comments. 

FOR FURTHER INFORMATION CONTACT: 

Barbara Barron, Office of Standards, 

Regulations, and Variances at 202–693– 

9447 (Voice), barron.barbara@dol.gov 

(Email), or 202–693–9441 (Facsimile). 

[These are not toll-free numbers.] 

SUPPLEMENTARY INFORMATION: 

I. Background 

Section 101(c) of the Federal Mine 

Safety and Health Act of 1977 (Mine 

Act) allows the mine operator or 

representative of miners to file a 

petition to modify the application of any 

mandatory safety standard to a coal or 

other mine if the Secretary of Labor 

determines that: 

1. An alternative method of achieving 

the result of such standard exists which 

will at all times guarantee no less than 

the same measure of protection afforded 

the miners of such mine by such 

standard; or 

2. That the application of such 

standard to such mine will result in a 

diminution of safety to the miners in 

such mine. 

In addition, the regulations at 30 CFR 

44.10 and 44.11 establish the 

requirements and procedures for filing 

petitions for modification. 

II. Petitions for Modification 

Docket Numbers: M–2015–001–C and 

M–2015–002–C. 

Petitioner: Sunrise Coal LLC, 12661 

North Agricare Road, Oaktown, Indiana 

47561. 

Mines: Oaktown Fuels No. 1 Mine, 

MSHA I.D. No. 12–02394, and Oaktown 

Fuels No. 2, MSHA I.D. No. 12–02418, 

both located in Knox County, Indiana. 

Regulation Affected: 30 CFR 75.503 

(Permissible electric face equipment; 

maintenance), 30 CFR 18.35(a)(5) 

(Portable (trailing) cables and cords). 

Modification Request: The petitioner 

requests a modification of the existing 

standard to increase the maximum 

length of trailing cables supplying 

power to permissible pumps in the 

mines. The petitioner states that: 

(1) These petitions will apply only to 

trailing cables supplying three-phase, 

480-volt power for permissible pumps. 

(2) The maximum length of the 

trailing cables for a 480-volt permissible 

pump will be 4000 feet. 

(3) The permissible pump will be no 

greater than 6.2 horsepower. 

(4) The 480-volt power for permissible 

pump trailing cables exceeding 500 feet 

will not be smaller than No. 6 AWG. 

(5) All circuit breakers used to protect 

No. 6 AWG trailing cables exceeding 

500 feet in length will have an 

instantaneous trip unit calibrated to trip 

at 60 amperes. These circuit breakers 

will be in the cable coupler and the 

cable coupler will have permanent, 

legible labels. Each label will identify 

the cable coupler as being suitable for 

protecting No. 6 AWG cables. This label 

will be maintained legible. 

(6) Replacement circuit breakers used 

to protect No. 6 AWG trailing cables 

exceeding 500 feet in length will be 

calibrated to trip at 60 amperes. 

(7) All circuit breakers used to protect 

the No. 2 AWG trailing cables exceeding 

500 feet in length will have 

instantaneous trip units calibrated to 

trip at 150 amperes. These circuit 

breakers will be in the cable coupler and 

the cable coupler will have permanent, 

legible labels. Each label will identify 

the cable coupler as being suitable for 

protecting No. 2 AWG cables. The labels 

will be maintained legible. 

(8) Replacement circuit breakers used 

to protect No. 2 AWG trailing cables 

exceeding 500 feet in length will be 

calibrated to trip at 150 amperes. 

(9) The petitioner’s alternative 

method will not be implemented until 

all miners who have been designated to 

examine and verify the short-circuit 

settings and proper procedures for 

examining trailing cables for defects and 

damage have received training. 

(10) Within 60 days after these 

petitions are granted, the petitioner will 

submit proposed revisions for their 

approved 30 CFR part 48 training plans 

to the District Manager for the area in 

which the mine is located. The training 

will include the following: 

(a) Mining methods and operating 

procedures for protecting the trailing 

cables against damage. 

(b) Proper procedures for examining 

the trailing cables to ensure safe 

operating condition. 

(c) The hazards of setting the 

instantaneous circuit breakers too high 

to adequately protect the trailing cables. 

(d) How to verify that the circuit 

interrupting device(s) protecting the 

trailing cable(s) are properly set and 

maintained. 

The petitioner further states that 

procedures specified in 30 CFR 48.3 for 

proposed revisions to approved training 

plans will apply. 

The petitioner asserts that the 

alternative method will guarantee no 

less than the same measure of protection 

for all miners than that of the existing 

standard. 

Dated: February 19, 2015. 

Sheila McConnell, 

Acting Director, Office of Standards, 

Regulations, and Variances. 

[FR Doc. 2015–03835 Filed 2–24–15; 8:45 am] 

BILLING CODE 4510–43–P 

NATIONAL SCIENCE FOUNDATION 

Advisory Committee for 

Cyberinfrastructure; Notice of Meeting 

In accordance with the Federal 

Advisory Committee Act (Pub., L. 92– 

463, as amended), the National Science 

Foundation announces the following 

meeting: 

Name: Advisory Committee for 

Cyberinfrastructure (25150). 

Date and Time: 

April 22, 2015; 09:00 a.m.–5:30 p.m. 

April 23, 2015; 8:30 a.m.–1:00 p.m. 

Place: National Science Foundation, 

4201 Wilson Blvd., Arlington, VA 

22230, Room 1235. 

Type of Meeting: OPEN. 

Contact Person: Mark Suskin, CISE, 

Division of Advanced 

Cyberinfrastructure, National Science 

Foundation, 4201 Wilson Blvd., Suite 

1145, Arlington, VA 22230, Telephone: 

703–292–8970. 

Minutes: May be obtained from the 

contact person listed above. 

Purpose of Meeting: To advise NSF on 

the impact of its policies, programs and 

activities in the ACI community. To 

provide advice to the Director/NSF on 

issues related to long-range planning. 


asabaliauskas on DSK5VPTVN1PROD with NOTICES
Federal Register / Vol. 80, No. 37 / Wednesday, February 25, 2015 / Notices 10165 

Agenda: Updates on NSF wide ACI 

activities. 

Dated: February 19, 2015. 

Suzanne Plimpton, 

Acting, Committee Management Officer. 

[FR Doc. 2015–03869 Filed 2–24–15; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–271–LA–2; ASLBP No. 15– 

937–02–LA–BD01] 

Entergy Nuclear Vermont Yankee, LLC 

and Entergy Nuclear Operations, Inc.; 

Establishment of Atomic Safety and 

Licensing Board 

Pursuant to delegation by the 

Commission, see 37 FR 28,710 (Dec. 29, 

1972), and the Commission’s 

regulations, see, e.g., 10 CFR 2.104, 

2.105, 2.300, 2.309, 2.313, 2.318, 2.321, 

notice is hereby given that an Atomic 

Safety and Licensing Board (Board) is 

being established to preside over the 

following proceeding: Entergy Nuclear 

Vermont Yankee, LLC, And Entergy 

Nuclear Operations, Inc., (Vermont 

Yankee Nuclear Power Station). 

This proceeding involves an 

application by Entergy Nuclear Vermont 

Yankee, LLC and Entergy Nuclear 

Operations, Inc. for a license 

amendment for the Vermont Yankee 

Nuclear Power Station, which is located 

in Vernon, Vermont. In response to a 

notice filed in the Federal Register, see 

79 FR 73,106 (Dec. 9, 2014), a hearing 

request was filed via the Electronic 

Information Exchange on February 9, 

2015 by the State of Vermont through 

the Vermont Department of Public 

Service. 

The Board is comprised of the 

following administrative judges: 

Paul S. Ryerson, Chairman, Atomic 

Safety and Licensing Board Panel, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

Dr. Michael F. Kennedy, Atomic Safety 

and Licensing Board Panel, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

Dr. Richard E. Wardwell, Atomic Safety 

and Licensing Board Panel, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

All correspondence, documents, and 

other materials shall be filed in 

accordance with the NRC E-Filing rule. 

See 10 .FR 2.302. 

Rockville, Maryland February 19, 2015. 

E. Roy Hawkens, 

Chief Administrative Judge, Atomic Safety 

and Licensing Board Panel. 

[FR Doc. 2015–03903 Filed 2–24–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. IA–14–025–EA; ASLBP No. 14– 

932–02–EA–BD01] 

James Chaisson; Notice of Atomic 

Safety and Licensing Board 

Reconstitution 

Pursuant to 10 CFR 2.313(c) and 

2.321(b), the Atomic Safety and 

Licensing Board in the above-captioned 

James Chaisson enforcement action 

proceeding is hereby reconstituted as 

follows: Administrative Judge G. Paul 

Bollwerk, III (who was serving as a 

Licensing Board member in this 

proceeding) is appointed to serve as 

Chairman; and Administrative Judge 

Michael M. Gibson (who was serving as 

Chairman in this proceeding) is 

appointed to serve as a Licensing Board 

member. 

All correspondence, documents, and 

other materials shall continue to be filed 

in accordance with the NRC E-Filing 

rule. See 10 CFR 2.302 et seq. 

Issued at Rockville, Maryland this 19th day 

of February 2015. 

E. Roy Hawkens, 

Chief Administrative Judge, Atomic Safety 

and Licensing Board Panel. 

[FR Doc. 2015–03899 Filed 2–24–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2011–0022] 

Concentration Averaging and 

Encapsulation Branch Technical 

Position 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Branch technical position; 

issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is issuing Revision 1 

of the Branch Technical Position on 

Concentration Averaging and 

Encapsulation (CA BTP). This guidance 

provides acceptable methods that can be 

used to perform concentration averaging 

of low-level radioactive waste (LLW) for 

the purpose of determining its waste 

class for disposal. 

DATES: The Branch Technical Position 

referenced in this document is available 

on February 25, 2015. 

ADDRESSES: Please refer to Docket ID 

NRC–2011–0022 when contacting the 

NRC about the availability of 

information regarding this document. 

You may access 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–2011–0022. Address 

questions about NRC dockets to Carol 

Gallagher; telephone: 301–415–3463; 

email: Carol.Gallagher@nrc.gov. For 

technical questions, contact the 

individual(s) 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 notice (if 

that document is available in ADAMS) 

is provided the first time that a 

document is referenced. The revised 

Branch Technical Position on 

Concentration Averaging and 

Encapsulation consists of two volumes. 

Volume 1 (ADAMS Accession No. 

ML12254B065) contains the staff 

technical positions on averaging and 

certain other information. Volume 2 

(ADAMS Accession No. ML12326A611) 

contains staff responses to stakeholder 

comments on the May 2012 draft 

(ADAMS Accession No. ML121170418) 

and the technical bases for the staff 

positions. 

• 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: 

Maurice Heath, Office of Nuclear 

Material Safety and Safeguards, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001; telephone: 

301–415–3137; email: Maurice.Heath@

nrc.gov. 

SUPPLEMENTARY INFORMATION: 


asabaliauskas on DSK5VPTVN1PROD with NOTICES