17512 Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices 

memorandum, on the National 

Archives’ Records Express blog. 

Dated: March 24, 2015. 

Paul M. Wester, Jr., 

Chief Records Officer for the U.S. 

Government. 

[FR Doc. 2015–07184 Filed 3–31–15; 8:45 am] 

BILLING CODE 7515–01–P 

NATIONAL LABOR RELATIONS 

BOARD 

Sunshine Act Meetings 

April 2015. 

TIME AND DATES: All meetings are held at 

2:00 p.m. 

Wednesday, April 1; 

Thursday, April 2; 

Tuesday, April 7; 

Wednesday, April 8; 

Thursday, April 9; 

Tuesday, April 14; 

Wednesday, April 15; 

Thursday, April 16; 

Tuesday, April 21; 

Wednesday, April 22; 

Thursday, April 23; 

Tuesday, April 28; 

Wednesday, April 29; 

Thursday, April 30. 

PLACE: Board Agenda Room, No. 11820, 

1099 14th St. NW., Washington, DC 

20570. 

STATUS: Closed. 

MATTERS TO BE CONSIDERED: Pursuant to 

§ 102.139(a) of the Board’s Rules and 

Regulations, the Board or a panel 

thereof will consider ‘‘the issuance of a 

subpoena, the Board’s participation in a 

civil action or proceeding or an 

arbitration, or the initiation, conduct, or 

disposition . . . of particular 

representation or unfair labor practice 

proceedings under section 8, 9, or 10 of 

the [National Labor Relations] Act, or 

any court proceedings collateral or 

ancillary thereto.’’ See also 5 U.S.C. 

552b(c)(10). 

CONTACT PERSON FOR MORE INFORMATION: 

Henry Breiteneicher, Associate 

Executive Secretary, (202) 273–2917. 

Dated: March 30, 2015. 

William B. Cowen, 

Solicitor. 

[FR Doc. 2015–07565 Filed 3–30–15; 4:15 pm] 

BILLING CODE 7545–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 52–027 and 52–028; NRC– 

2015–0072] 

South Carolina Electric and Gas 

Company 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Exemption; issuance. 

SUMMARY: The U.S. Nuclear Regulatory 

Commission (NRC) is granting a onetime exemption to South Carolina 

Electric and Gas Company (the licensee) 

from NRC regulations that require that 

a licensee must use the criteria in 

NUREG–1021, ‘‘Operator Licensing 

Examination Standards for Power 

Reactors,’’ in effect six months before 

the examination date to prepare the 

written examinations and the operating 

tests. NUREG–1021, Revision 10, which 

was published on January 2, 2015, adds 

guidance for licensing operators of new 

reactors and includes NUREG–2103, 

‘‘Knowledge and Abilities Catalog for 

Nuclear Power Plant Operators: 

Pressurized-Water Reactors, 

Westinghouse AP1000,’’ dated October 

2011, but does not go into effect until 

July 2, 2015. The exemption allows the 

licensee to use NUREG–1021, Revision 

10, prior to July 2, 2015, to prepare, 

proctor, and grade the written 

examinations and to prepare the 

operating tests required by NRC 

regulations. 

ADDRESSES: Please refer to Docket ID 

NRC–2015–0072 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–2015–0072. 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 

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 (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: 

Denise McGovern, Office of New 

Reactors, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone: 301–415–0681, email: 

Denise.McGovern@nrc.gov 

SUPPLEMENTARY INFORMATION: The 

following sections include the text of 

the exemption in its entirety as issued 

to South Carolina Electric and Gas 

Company (the licensee). 

I. Background 

South Carolina Electric and Gas 

Company (the licensee) is the holder of 

Combined Licenses No. NPF–93 and No. 

NPF–94, issued March 30, 2012, which 

authorize construction and operation of 

the Virgil C. Summer Nuclear Station, 

Units 2 and 3 (VCSNS). The licenses 

provide, among other things, that the 

licenses are subject to, and the licensee 

shall comply with, all applicable 

provisions of the Atomic Energy Act of 

1954, as amended, and the rules, 

regulations, and orders of the U.S. 

Nuclear Regulatory Commission (NRC, 

the Commission) now or hereafter in 

effect. 

The facility consists of two 

Westinghouse AP1000 pressurizedwater reactors located in Fairfield 

County, South Carolina, which are 

currently under construction. 

II. Request/Action 

Title 10 of the Code of Federal 

Regulations (10 CFR) part 55, 

‘‘Operators’ Licenses,’’ § 55.40, 

‘‘Implementation,’’ paragraph (a) states 

in part, ‘‘The Commission shall use the 

criteria in NUREG–1021, ‘‘Operator 

Licensing Examination Standards for 

Power Reactors,’’ in effect six months 

before the examination date to prepare 

the written examinations required by 10 

CFR 55.41 and 55.43 and the operating 

tests required by 10 CFR 55.45. The 

Commission shall also use the criteria in 

NUREG–1021 to evaluate the written 

examinations and operating tests 

prepared by power reactor facility 

licensees pursuant to paragraph (b) of 

this section.’’ 10 CFR 55.40(b)(1) 

requires licensees to prepare and 

evaluate written examinations and 

operating tests in accordance with 

mstockstill on DSK4VPTVN1PROD with NOTICES

Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices 17513 

NUREG–1021 as described in 10 CFR 

55.40(a). NUREG–1021 explains the 

policies, procedures, and practices for a 

particular aspect of the operator testing 

program. 

NUREG–1021, Revision 9, 

Supplement 1, establishes the policies, 

procedures, and practices for 

administering the required initial 

written examinations and operating 

tests, and is appropriate to use for 

currently operating pressurized water 

reactors (PWR) and boiling water 

reactors (BWR). NUREG–1021, Revision 

10, allows for the preparation, 

administration, and evaluation of initial 

operator licensing examinations for the 

currently operating PWRs, BWRs, as 

well as the Westinghouse AP1000 

reactors (AP1000), and the General 

Electric Advanced Boiling Water 

Reactor (ABWR). NUREG–1021, 

Revision 10, also contains a new 

examination standard, ES–401N, 

‘‘Preparing Initial Site-Specific Written 

Examinations,’’ which ensures the 

equitable and consistent administration 

and evaluation of examinations for all 

applicants. 

Under 10 CFR 55.40(b)(1), the 

licensee is required, as described in 10 

CFR 55.40(a), to use NUREG–1021, 

Revision 9, Supplement 1, to prepare 

the AP1000 operator licensing written 

examinations and operator testing for 

the initial licensing examination of 

reactor operators and senior reactor 

operators (applicants) because NUREG– 

1021, Revision 10, which was published 

on January 2, 2015, will not be in effect 

for six months, or until July 2, 2015. 

This limited, one-time exemption would 

allow the licensee to use NUREG–1021, 

Revision 10, for the preparation and 

administration of the VCSNS initial 

operator licensing written examinations 

and operator testing prior to July 2, 

2015. 

III. Discussion 

Pursuant to 10 CFR 55.11, the 

Commission may, upon application by 

an interested person, or upon its own 

initiative, grant exemptions from the 

requirements of 10 CFR part 55 when 

the exemptions are authorized by law 

and will not endanger life or property 

and are otherwise in the public interest. 

A. Authorized by Law 

This exemption would allow the 

licensee to develop, prepare, and 

evaluate initial operator licensing 

written examinations and operator 

testing for the AP1000 reactors under 

construction at its Fairfield County, 

South Carolina site prior to July 2, 2015. 

Under 10 CFR 55.11, the Commission’s 

regulations allow the Commission to 

grant exemptions from the regulations 

in 10 CFR part 55 as the Commission 

determines are authorized by law and 

will not endanger life or property and 

are otherwise in the public interest. The 

NRC staff has determined that granting 

of this limited, one-time exemption will 

not result in a violation of the Atomic 

Energy Act of 1954, as amended, or 

other laws, and will not endanger life or 

property and is otherwise in the public 

interest. Therefore, the exemption is 

authorized by law. 

B. No Endangerment of Life or Property 

The purpose of 10 CFR part 55 is to 

establish the procedures and criteria for 

the issuance of licenses to reactor 

operators and senior reactor operators, 

provide the terms and conditions upon 

which the Commission will issue or 

modify those licenses, and provide the 

terms and conditions to maintain and 

renew those licenses. Specifically, 10 

CFR 55.40(b) establishes the criteria 

licensees must use for the preparation 

and evaluation of the written 

examinations required by 10 CFR 55.41 

and 10 CFR 55.43, and the operating 

tests required by 10 CFR 55.45. 10 CFR 

55.40(b)(1) requires licensees to prepare 

these written examinations and 

operating tests in accordance with the 

criteria in NUREG–1021, ‘‘Operator 

Licensing Examination Standards for 

Power Reactors,’’ as described in 10 CFR 

55.40(a), which requires the use of the 

version of NUREG–1021 in effect six 

months before the examination date. 

NUREG–1021, Revision 9, Supplement 

1, which does not address examination 

standards for the AP1000 reactor, is 

currently in effect. NUREG–1021, 

Revision 9 requires the use of NUREG– 

1122, ‘‘Knowledge and Abilities Catalog 

for Nuclear Power Plant Operators: 

Pressurized-Water Reactors.’’ NUREG– 

1122 provides the basis for developing 

content-valid PWR licensing 

examinations and, in conjunction to the 

instructions in NUREG–1021, will 

ensure that the initial licensing 

examination includes a representative 

sample of the items specified in the 

regulations. 

VCSNS will include two new 

Westinghouse AP1000 pressurizedwater reactors, which are currently 

under construction at the site. The most 

significant new features in the AP1000 

design involve the increased use of 

passive safety systems for accident 

prevention and mitigation that rely on 

passive means, such as gravity, natural 

circulation, condensation and 

evaporation, and stored energy. As a 

result, the AP1000 design includes 

many features that are not found in the 

designs of currently operating reactors, 

and certain systems, components, and 

processes that are part of the currently 

operating pressurized-water reactors are 

not a part of the AP1000 design. The 

AP1000 has numerous systems, 

including safety systems, not covered in 

NUREG–1122 that should be tested as 

part of a comprehensive operator 

licensing examination. Similarly, the 

knowledge, skills, and abilities of 

current PWR licensed operators are 

somewhat different from those of the 

future AP1000 licensed operators. 

NUREG–1021, Revision 10, which 

addresses the AP1000 reactor, was 

issued on January 2, 2015, and does not 

go into effect until July 2, 2015. 

NUREG–1021, Revision 10, in addition 

to providing guidance for currently 

operating PWRs and BWRs, contains a 

new examination standard, ES–401N, 

‘‘Preparing Initial Site-Specific Written 

Examinations.’’ ES–401N will provide 

guidance for the preparation and 

evaluation of the AP1000 design and 

site specific examinations. ES–401N 

provides for the use of NUREG–2103, 

‘‘Knowledge and Abilities Catalog for 

Nuclear Power Plant Operators: 

Westinghouse AP1000 PressurizedWater Reactors.’’ NUREG–2103 provides 

the basis for developing content-valid 

AP1000 licensing examinations and, in 

conjunction with the instructions in 

NUREG–1021, will ensure that the 

initial licensing examination includes a 

representative sample of the items 

specified in the regulations and improve 

the comprehensiveness of the 

examination over an examination 

developed using NUREG–1021, 

Revision 9. Accordingly, the NRC staff 

has determined that granting of the 

exemption will not endanger life or 

property. 

C. Otherwise in the Public Interest 

The purpose of 10 CFR part 55 is to 

establish the procedures and criteria for 

the issuance of licenses to reactor 

operators and senior reactor operators, 

provide the terms and conditions upon 

which the Commission will issue or 

modify those licenses, and provide the 

terms and conditions to maintain and 

renew those licenses. Specifically, 10 

CFR 55.40(b)(1) establishes the criteria 

licensees are required to use for the 

preparation and evaluation of the 

written examinations required by 10 

CFR 55.41 and 10 CFR 55.43, and the 

operating tests required by 10 CFR 

55.45. 10 CFR 55.40(b)(1) requires 

licensees to prepare these written 

examinations and operating tests in 

accordance with the criteria in NUREG– 

1021, ‘‘Operator Licensing Examination 

Standards for Power Reactors,’’ as 

described in 10 CFR 55.40(a), which 

mstockstill on DSK4VPTVN1PROD with NOTICES

17514 Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices 

requires the use of the version of 

NUREG–1021 in effect six months 

before the examination date. 

NUREG–1021, Revision 9, 

Supplement 1, which does not address 

AP1000, is currently in effect, while 

NUREG–1021, Revision 10, which does 

address AP1000, was issued on January 

2, 2015, does not go into effect until July 

2, 2015. Because the exemption enables 

the use of guidance specific to the new 

AP1000 reactors that was not available 

in the previous revision of NUREG– 

1021, and will allow the licensee to 

utilize the appropriate criteria to 

prepare and evaluate operator licensing 

written examinations and operating 

tests, the NRC staff determined that the 

exemption is otherwise in the public 

interest. 

IV. Eligibility for Categorical Exclusion 

From Environmental Review 

With respect to the exemption’s 

impact on the quality of the human 

environment, the NRC has determined 

that this specific exemption request is 

eligible for categorical exclusion as 

identified in 10 CFR 51.22(c)(25) and 

justified by the NRC staff as discussed 

below. 

10 CFR 51.22(c)(25)(i): The criteria for 

determining whether there is no 

significant hazards consideration are 

found in 10 CFR 50.92(c)(1) through (3): 

(1) The proposed exemption is 

administrative in nature and is limited 

to allowing the licensee to use NUREG– 

1021, Revision 10, to prepare and 

evaluate operator licensing written 

examinations and operating tests prior 

to July 2, 2015. The proposed exemption 

does not make any changes to the 

facility or operating procedures and 

does not alter the design, function or 

operation of any plant equipment. 

Therefore, issuance of this exemption 

does not increase the probability or 

consequences of an accident previously 

evaluated. 

(2) The proposed exemption is 

administrative in nature and is limited 

to allowing the licensee to use NUREG– 

1021, Revision 10, to prepare and 

evaluate operator licensing written 

examinations and operating tests prior 

to July 2, 2015. The proposed exemption 

does not make any changes to the 

facility or operating procedures and 

would not create any new accident 

initiators. The proposed exemption does 

not alter the design, function, or 

operation of any plant equipment. 

Therefore, this exemption does not 

create the possibility of a new or 

different kind of accident from any 

accident previously evaluated. 

(3) The proposed exemption is 

administrative in nature and is limited 

to allowing the licensee to use NUREG– 

1021, Revision 10, to prepare and 

evaluate operator licensing written 

examinations and operating tests prior 

to July 2, 2015. The proposed exemption 

does not alter the design, function, or 

operation of any plant equipment. 

Therefore, this exemption does not 

involve a significant reduction in the 

margin of safety. 

The NRC staff has also determined 

that the exemption involves no 

significant change in the types or 

significant increase in the amounts of 

any effluents that may be released 

offsite; that there is no significant 

increase in individual or cumulative 

occupational radiation exposure; that 

there is no significant construction 

impact; and there is no significant 

increase in the potential for or 

consequences from radiological 

accidents. The requirement from which 

an exemption is sought involves 

education, training, experience, 

qualification, requalification or other 

employment suitability requirements. 

Accordingly, the exemption meets the 

eligibility criteria for categorical 

exclusion set forth in 10 CFR 

51.22(c)(25). Pursuant to 10 CFR 

51.22(b), no environmental impact 

statement or environmental assessment 

need be prepared in connection with the 

issuance of the exemption. 

V. Conclusion 

Accordingly, the Commission has 

determined that, pursuant to 10 CFR 

55.11, granting a limited, one-time 

exemption to the licensee from the 

requirements in 10 CFR 55.40(b)(1), 

allowing the use of NUREG–1021, 

Revision 10, for the preparation and 

evaluation of operator licensing written 

examinations and operator testing for 

the AP1000 reactors under construction 

at VCSNS, prior to July 2, 2015, is 

authorized by law and will not endanger 

life or property and is otherwise in the 

public interest. Therefore, the 

Commission hereby grants South 

Carolina Electric and Gas Company an 

exemption from the requirement of 10 

CFR 55.40(b)(1), to allow the use of 

NUREG–1021, Revision 10, for the 

preparation and evaluation of operator 

licensing written examinations and 

operator testing for the AP1000 reactors 

under construction at the VCSNS, prior 

to July 2, 2015. 

Pursuant to 10 CFR 51.22, the 

Commission has determined that the 

exemption request meets the applicable 

categorical exclusion criteria set forth in 

10 CFR 51.22(c)(25), and the granting of 

this exemption will not have a 

significant effect on the quality of the 

human environment. 

This exemption is effective upon 

issuance. 

Dated at Rockville, Maryland, this 19th day 

of March 2015. 

For The Nuclear Regulatory Commission. 

Frank Akstulewicz, 

Director, Division of New Reactor Licensing, 

Office of New Reactors. 

[FR Doc. 2015–07473 Filed 3–31–15; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS) Meeting of the 

ACRS Subcommittee on Reliability & 

PRA; Notice of Meeting 

The ACRS Subcommittee on 

Reliability & PRA will hold a meeting 

on April 24, 2015, Room T–2B1, 11545 

Rockville Pike, Rockville, Maryland. 

The meeting will be open to public 

attendance. 

The agenda for the subject meeting 

shall be as follows: 

Friday, April 24, 2015—1:00 p.m. Until 

5:00 p.m. 

The Subcommittee will discuss the 

Human Reliability Analysis 

Development and Progress. The 

Subcommittee will hear presentations 

by and hold discussions with the NRC 

staff and other interested persons 

regarding this matter. The 

Subcommittee will gather information, 

analyze relevant issues and facts, and 

formulate proposed positions and 

actions, as appropriate, for deliberation 

by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), John Lai 

(Telephone 301–415–5197 or Email: 

John.Lai@nrc.gov) five days prior to the 

meeting, if possible, so that appropriate 

arrangements can be made. Thirty-five 

hard copies of each presentation or 

handout should be provided to the DFO 

thirty minutes before the meeting. In 

addition, one electronic copy of each 

presentation should be emailed to the 

DFO one day before the meeting. If an 

electronic copy cannot be provided 

within this timeframe, presenters 

should provide the DFO with a CD 

containing each presentation at least 

thirty minutes before the meeting. 

Electronic recordings will be permitted 

only during those portions of the 

meeting that are open to the public. 

Detailed procedures for the conduct of 

and participation in ACRS meetings 

were published in the Federal Register 

on October 13, 2014 (79 FR 59307). 

mstockstill on DSK4VPTVN1PROD with NOTICES