South Carolina Electric and Gas Company, 17512-17514 [2015-07473]
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Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices
memorandum, on the National
Archives’ Records Express blog.
NUCLEAR REGULATORY
COMMISSION
Dated: March 24, 2015.
Paul M. Wester, Jr.,
Chief Records Officer for the U.S.
Government.
[Docket Nos. 52–027 and 52–028; NRC–
2015–0072]
South Carolina Electric and Gas
Company
[FR Doc. 2015–07184 Filed 3–31–15; 8:45 am]
Nuclear Regulatory
Commission.
ACTION: Exemption; issuance.
BILLING CODE 7515–01–P
AGENCY:
NATIONAL LABOR RELATIONS
BOARD
SUMMARY:
Sunshine Act Meetings
April 2015.
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.
TIME AND DATES:
Board Agenda Room, No. 11820,
1099 14th St. NW., Washington, DC
20570.
PLACE:
STATUS:
Closed.
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).
MATTERS TO BE CONSIDERED:
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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
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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.
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
https://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
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
ADDRESSES:
PO 00000
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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
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Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices
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.
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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
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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,
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17513
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
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Federal Register / Vol. 80, No. 62 / Wednesday, April 1, 2015 / Notices
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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
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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.
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Fmt 4703
Sfmt 4703
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).
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Agencies
[Federal Register Volume 80, Number 62 (Wednesday, April 1, 2015)]
[Notices]
[Pages 17512-17514]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2015-07473]
=======================================================================
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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
one-time 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 https://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 publicly-available documents online in the
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: 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 pressurized-water
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,'' Sec. 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
[[Page 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 pressurized-water
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 Pressurized-Water 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
[[Page 17514]]
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]
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