[Federal Register Volume 80, Number 62 (Wednesday, April 1, 2015)]
[Notices]
[Pages 17512-17514]
From the Federal Register Online via the Government Publishing 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.
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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 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: [email protected]. 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 [email protected]. 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: [email protected]
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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