Florida Power Corporation, Crystal River Unit 3 Nuclear Generating Plant; Exemption, 5216-5218 [2011-1911]
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5216
Federal Register / Vol. 76, No. 19 / Friday, January 28, 2011 / Notices
www.nrc.gov/reading-rm/adams.html),
under Accession No. ML101040727.
Regulatory guides are not
copyrighted, and Commission approval
is not required to reproduce them.
Dated at Rockville, Maryland, this 21st day
of January, 2011.
For the Nuclear Regulatory Commission.
Edward O’Donnell,
Acting Chief, Regulatory Guide Development
Branch, Division of Engineering, Office of
Nuclear Regulatory Research.
[FR Doc. 2011–1909 Filed 1–27–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2008–0339]
Notice of Availability of Final
Supplemental Environmental Impact
Statement for the Nichols Ranch Insitu Recovery Project in Campbell and
Johnson Counties, WY; Supplement to
the Generic Environmental Impact
Statement for In-situ Leach Uranium
Milling Facilities
Nuclear Regulatory
Commission.
ACTION: Notice of availability.
AGENCY:
Notice is hereby given that
the U.S. Nuclear Regulatory
Commission (NRC) has published a final
Supplemental Environmental Impact
Statement (SEIS) to the Generic
Environmental Impact Statement (GEIS),
for In-situ Leach Uranium Milling
Facilities (NUREG–1910, Supplement 2)
for the Nichols Ranch In-situ Recovery
Project in Campbell and Johnson
Counties, Wyoming. By letter dated
November 30, 2007, Uranerz Energy
Corporation (Uranerz), submitted an
application to the NRC for a new source
material license for the proposed
Nichols Ranch In-situ Uranium
Recovery Project, located in the
Pumpkin Buttes Uranium Mining
District within the Powder River Basin.
Uranerz is proposing to recover uranium
from the site using an in-situ leach (also
known as an in-situ recovery [ISR])
process. In this final SEIS, the NRC staff
assessed the environmental impacts
from the construction, operation, aquifer
restoration, and decommissioning of the
proposed Nichols Ranch ISR Project.
The proposed Nichols Ranch ISR Project
is comprised of two noncontiguous
units, the Nichols Ranch Unit and the
Hank Unit.
In addition to the proposed action, the
NRC staff assessed two alternatives in
the final SEIS: the No-Action alternative
and an alternative where only the
WReier-Aviles on DSKGBLS3C1PROD with NOTICES
SUMMARY:
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Nichols Ranch Unit would be developed
for ISR operations. Under the No-Action
alternative, NRC would deny Uranerz’s
request to construct, operate, conduct
aquifer restoration, and decommission
an ISR facility at Nichols Ranch.
Alternatives that were considered, but
were eliminated from detailed analysis,
include conventional mining and
conventional milling or heap leach
processing. However, given the
substantial environmental impact from
implementing of these alternatives, they
were not further considered. The NRC
staff also evaluated alternative
lixiviants, alternative wastewater
disposal options, and an alternative
where only the Hank Unit would be
developed ISR operations. For reasons
discussed in the SEIS, these alternatives
were also eliminated from detailed
analysis.
As discussed in Section 2.3 of the
final SEIS, unless safety issues mandate
otherwise, the NRC staff’s
recommendation to the Commission
related to the environmental aspects of
the proposed action is that the source
material license be issued as requested.
This recommendation is based upon: (1)
The license application, including the
environmental and technical report
submitted by Uranerz and the
applicant’s supplemental letters and
responses to the NRC staff’s requests for
additional information; (2) consultation
with Federal, State, Tribal, and local
agencies; (3) the NRC staff’s
independent review; (4) the NRC staff’s
consideration of comments received on
the draft SEIS; and (5) the assessments
summarized in this SEIS.
The final SEIS for the Nichols Ranch
ISR Project may be accessed on the
Internet at https://www.nrc.gov/readingrm/doc-collections/nuregs/staff/sr1910/
s2/. Additionally, the NRC maintains an
Agencywide Documents and
Management System (ADAMS), which
provides text and image files of the
NRC’s public documents. The SEIS may
also be accessed through the NRC’s
Public Electronic Reading Room on the
Internet at: https://www.nrc.gov/readingrm/adams.html. The final
‘‘Environmental Impact Statement for
the Nichols Ranch ISR Project in
Campbell and Johnson Counties,
Wyoming—Supplement to the Generic
Environmental Impact Statement for Insitu Leach Uranium Milling Facilities’’
is available electronically under
ADAMS Accession Number
ML104330120. If you do not have access
to ADAMS or if there is a problem
accessing documents located in
ADAMS, contact the NRC Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
PO 00000
Frm 00087
Fmt 4703
Sfmt 4703
e-mail pdr.resource@nrc.gov.
Information and documents associated
with the final SEIS are also available for
inspection at the NRC’s PDR, NRC’s
Headquarters Building, 11555 Rockville
Pike (first floor), Rockville, Maryland
20852–2738. For those without access to
the Internet, paper copies of any
electronic documents may be obtained
for a fee by contacting the NRC’s PDR
at 1–800–397–4209. The final SEIS and
related documents may also be found at
the following public libraries:
Campbell County Public Library, 2101
South 4J Road, Gillette, Wyoming
82718, 307–687–0009.
Johnson County Library, 171 North
Adams Avenue, Buffalo, Wyoming
82834, 307–684–5546.
FOR FURTHER INFORMATION CONTACT: Ms.
Patricia Swain, Project Manager,
Environmental Review Branch-B,
Division of Waste Management and
Environmental Protection (DWMEP),
Office of Federal and State Materials
and Environmental Management
Programs (FSME), Mail Stop T–8F5,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001.
Telephone: 1 (800) 368–5642, extension
5405; E-mail: Patricia.Swain@nrc.gov.
For general or technical information
associated with the safety and licensing
of uranium milling facilities, please
contact Stephen Cohen, Team Lead,
Uranium Recovery Licensing Branch,
DWMEP, FSME, Mail Stop T–8F5, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
Telephone: 1 (800) 368–5642, extension
7182; E-mail: Stephen.Cohen@nrc.gov.
Dated at Rockville, Maryland, this 20th day
of January, 2011.
For the Nuclear Regulatory Commission.
Gregory Suber,
Acting Deputy Director, Environmental
Protection and Performance Assessment
Directorate, Division of Waste Management
and Environmental Protection, Office of
Federal and State Materials and
Environmental Management Programs.
[FR Doc. 2011–1813 Filed 1–27–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–302; NRC–2011–0024]
Florida Power Corporation, Crystal
River Unit 3 Nuclear Generating Plant;
Exemption
1.0 Background
Florida Power Corporation (the
licensee) is the holder of Facility
Operating License No. DPR–72, which
authorizes operation of the Crystal River
E:\FR\FM\28JAN1.SGM
28JAN1
Federal Register / Vol. 76, No. 19 / Friday, January 28, 2011 / Notices
Unit 3 Nuclear Generating Plant (Crystal
River). The license provides, among
other things, that the facility is subject
to all rules, regulations, and orders of
the U.S. Nuclear Regulatory
Commission (NRC, the Commission)
now or hereafter in effect.
The facility consists of one
pressurized-water reactor located in
Citrus County, Florida.
2.0 Request/Action
Title 10 of the Code of Federal
Regulations (10 CFR) Part 55,
‘‘Operators’ Licenses,’’ Section 55.59,
‘‘Requalification,’’ requires that a
facility’s licensed operator
requalification program be conducted
for a continuous period not to exceed 2
years (24 months) and upon conclusion
must be promptly followed, pursuant to
a continuous schedule, by successive
requalification programs. Each 2-year
requalification program must include a
biennial comprehensive written
examination and annual operating tests.
By letter dated December 2, 2010, as
superseded by letter dated December 13,
2010, the licensee requested a one-time
exemption under 10 CFR 55.11 from the
schedule requirements of 10 CFR 55.59.
Specifically for Crystal River, the
licensee has requested a one-time
extension from February 28, 2011, to
April 30, 2011, for completing the
current licensed operator requalification
program. The next requalification
program period would begin May 1,
2011, and continue for 24 months to
April 30, 2013, with successive periods
running for 24 months. This requested
exemption would allow an extension of
2 months beyond the 24-month
requalification program schedule
required by 10 CFR 55.59.
WReier-Aviles on DSKGBLS3C1PROD with NOTICES
3.0 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.
Authorized by Law
The exemption being requested for
Crystal River would alleviate potential
scheduling difficulties associated with
administering requalification
examinations and completing the
requalification program at the end of an
extended shutdown period. As stated
above, 10 CFR 55.11 allows the NRC to
grant exemptions from the requirements
of 10 CFR Part 55. The NRC staff has
determined that granting of the
licensee’s proposed exemption will not
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result in a violation of the Atomic
Energy Act of 1954, as amended, or the
Commission’s regulations. Therefore,
the exemption is authorized by law.
No Endangerment of Life or Property
and Otherwise in the Public Interest
The underlying purposes of 10 CFR
55 are to establish procedures and
criteria for the issuance of licenses to
operators, provide for the terms and
conditions upon which the Commission
will issue or modify these licenses, and
provide for the terms and conditions to
maintain and renew these licenses.
Specifically, 10 CFR 55.59 establishes
the requirements for operator
requalification programs and requires a
2-year (24-month) requalification
schedule to include a biennial
comprehensive written examination and
annual operating tests.
Crystal River is in the final stages of
an extended outage in which significant
plant modifications have been
completed. Crystal River has requested
a 2-month extension to the requirements
of 10 CFR 55.59 due to the reasonable
probability of activities associated with
plant startup overlapping the biennial
comprehensive written examination and
annual operating examination period.
Although the 24-month schedule
requirement of 10 CFR 55.59 at Crystal
River would be exceeded, Crystal River
has trained the licensed operators on the
plant modifications completed during
the outage and examined operators on
the modified plant configuration with
positive results. During both the
originally scheduled and extended
periods of the outage, Crystal River has
continued the requalification training
cycle in accordance with the Institute of
Nuclear Power Operations (INPO)
accredited training program. All Crystal
River licensed operators are actively
enrolled in the accredited training
program.
Moving the end of the requalification
program, including the biennial
comprehensive written examination and
annual operating test, to April 30, 2011,
would: (1) Allow operators to focus on
preparing for and performing activities
associated with plant startup after an
extended maintenance period with
significant plant modifications; (2)
maximize the number of licensed
operators available to perform licensed
duties during startup; and (3) assist in
managing operator fatigue during
startup activities.
Licensed operator fatigue is of serious
concern to the NRC, and the NRC staff
has concluded that this exemption will
allow the licensee to better manage
licensed operator fatigue during a
period of high workload. Further, the
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5217
NRC staff has concluded that allowing
operators to focus on startup activities
will support safe plant operations
during a series of infrequently
performed evolutions. Based on the
above, the NRC staff has determined
that the exemption will not endanger
life or property and is otherwise in the
public interest.
4.0 Environmental Consideration
This exemption authorizes a one-time
exemption from the requirements of 10
CFR 55.59(c)(1) for Crystal River. The
NRC staff has determined that this
exemption involves no significant
hazards considerations:
(1) The proposed exemption is
administrative in nature and is limited
to extending the current licensed
operator requalification program period
for Crystal River from 24 to 26 months
on a one-time only basis. 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 extending the current licensed
operator requalification program period
for Crystal River from 24 to 26 months
on a one-time only basis. 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 extending the current licensed
operator requalification program period
for Crystal River from 24 to 26 months
on a one-time only basis. 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.
Based on the above, the NRC staff
concludes that the proposed exemption
does not involve a significant hazards
consideration under the standards set
forth in 10 CFR 50.92(c), and
accordingly, a finding of ‘‘no significant
hazards consideration’’ is justified.
The NRC staff has also determined
that the exemption involves no
significant increase in the amounts, and
no significant change in the types, of
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28JAN1
5218
Federal Register / Vol. 76, No. 19 / Friday, January 28, 2011 / Notices
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 a radiological
accident. Furthermore, the requirement
from which the licensee will be
exempted involves scheduling
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.
5.0
Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
55.11, granting an exemption to the
licensee from the schedule requirements
in 10 CFR 55.59, by allowing Crystal
River a one-time extension in the
allowed time for completing the current
licensed operator requalification
program, is authorized by law and will
not endanger life or property and is
otherwise in the public interest.
Therefore, the Commission hereby
grants Florida Power Corporation an
exemption on a one-time only basis
from the schedule requirement of 10
CFR 55.59, to allow the completion date
for the current licensed operator
requalification program for the Crystal
River Unit 3 Nuclear Generating Plant to
be extended from February 28, 2011, to
April 30, 2011. The next requalification
program period would begin May 1,
2011, and continue for 24 months to
April 30, 2013, with successive periods
running for 24 months.
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 20th day
of January 2011.
For the Nuclear Regulatory Commission.
WReier-Aviles on DSKGBLS3C1PROD with NOTICES
Joseph G. Giitter,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2011–1911 Filed 1–27–11; 8:45 am]
BILLING CODE 7590–01–P
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NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on Advanced
Boiling Water Reactor (ABWR); Notice
of Meeting
The ACRS Subcommittee on
Advanced Boiling Water Reactor
(ABWR) will hold a meeting on
February 8, 2011, 11545 Rockville Pike,
Rockville, MD T–2B3.
The entire meeting will be open to
public attendance with the exception of
a portion that may be closed to protect
information that is proprietary to South
Texas Project Nuclear Operating
Company (STPNOC) and its contractors,
pursuant to 5 U.S.C. 552b(c)(4).
The agenda for the subject meeting
shall be as follows:
Wednesday, February 8, 2011—1 p.m.
until 5 p.m.
The purpose of the meeting is for the
Subcommittee to review Chapter 7 of
the Safety Evaluation Report (SER) with
no open items associated with the
Combined License Application (COLA)
for South Texas Project, Units 3 and 4.
The Subcommittee will hear
presentations by and hold discussions
with representatives of the NRC staff,
STPNOC, and other interested persons.
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, Maitri Banerjee
(Telephone 301–415–6973 or E-mail:
Maitri.Banerjee@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 Designated Federal
Official 30 minutes before the meeting.
In addition, one electronic copy of each
presentation should be e-mailed to the
Designated Federal Official 1 day before
meeting. If an electronic copy cannot be
provided within this timeframe,
presenters should provide the
Designated Federal Official with a CD
containing each presentation at least 30
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 21, 2010 (75 FR 65038–65039).
PO 00000
Frm 00089
Fmt 4703
Sfmt 4703
Detailed meeting agendas and meeting
transcripts are available on the NRC
Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information
regarding topics to be discussed,
changes to the agenda, whether the
meeting has been canceled or
rescheduled, and the time allotted to
present oral statements can be obtained
from the Web site cited above or by
contacting the identified DFO.
Moreover, in view of the possibility that
the schedule for ACRS meetings may be
adjusted by the Chairman as necessary
to facilitate the conduct of the meeting,
persons planning to attend should check
with these references if such
rescheduling would result in a major
inconvenience.
Dated: January 24, 2011.
Antonio Dias,
Chief, Reactor Safety Branch B, Advisory
Committee on Reactor Safeguards.
[FR Doc. 2011–1891 Filed 1–27–11; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards
In accordance with the purposes of
Sections 29 and 182b of the Atomic
Energy Act (42 U.S.C. 2039, 2232b), the
Advisory Committee on Reactor
Safeguards (ACRS) will hold a meeting
on February 10–12, 2011, 11545
Rockville Pike, Rockville, Maryland.
The date of this meeting was previously
published in the Federal Register on
Thursday, October 21, 2010 (74 FR
65038–65039).
Thursday, February 10, 2011,
Conference Room T2–B1, 11545
Rockville Pike, Rockville, Maryland
8:30 a.m.—8:35 a.m.: Opening
Remarks by the ACRS Chairman
(Open)—The ACRS Chairman will make
opening remarks regarding the conduct
of the meeting.
8:35 a.m.—10 a.m.: Final Safety
Evaluation Report Associated with the
License Renewal Application for the
Palo Verde Nuclear Generating Station
(Open)—The Committee will hear
presentations by and hold discussions
with representatives of the NRC staff
and Arizona Public Service Company
regarding the final Safety Evaluation
Report associated with the License
Renewal Application for the Palo Verde
Nuclear Generating Station.
10:15 a.m.—12:45 p.m.: Final Safety
Evaluation Report Associated with the
Virgil C. Summer Units 2 and 3
Combined License Application (Open/
E:\FR\FM\28JAN1.SGM
28JAN1
Agencies
[Federal Register Volume 76, Number 19 (Friday, January 28, 2011)]
[Notices]
[Pages 5216-5218]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-1911]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-302; NRC-2011-0024]
Florida Power Corporation, Crystal River Unit 3 Nuclear
Generating Plant; Exemption
1.0 Background
Florida Power Corporation (the licensee) is the holder of Facility
Operating License No. DPR-72, which authorizes operation of the Crystal
River
[[Page 5217]]
Unit 3 Nuclear Generating Plant (Crystal River). The license provides,
among other things, that the facility is subject to all rules,
regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC,
the Commission) now or hereafter in effect.
The facility consists of one pressurized-water reactor located in
Citrus County, Florida.
2.0 Request/Action
Title 10 of the Code of Federal Regulations (10 CFR) Part 55,
``Operators' Licenses,'' Section 55.59, ``Requalification,'' requires
that a facility's licensed operator requalification program be
conducted for a continuous period not to exceed 2 years (24 months) and
upon conclusion must be promptly followed, pursuant to a continuous
schedule, by successive requalification programs. Each 2-year
requalification program must include a biennial comprehensive written
examination and annual operating tests.
By letter dated December 2, 2010, as superseded by letter dated
December 13, 2010, the licensee requested a one-time exemption under 10
CFR 55.11 from the schedule requirements of 10 CFR 55.59. Specifically
for Crystal River, the licensee has requested a one-time extension from
February 28, 2011, to April 30, 2011, for completing the current
licensed operator requalification program. The next requalification
program period would begin May 1, 2011, and continue for 24 months to
April 30, 2013, with successive periods running for 24 months. This
requested exemption would allow an extension of 2 months beyond the 24-
month requalification program schedule required by 10 CFR 55.59.
3.0 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.
Authorized by Law
The exemption being requested for Crystal River would alleviate
potential scheduling difficulties associated with administering
requalification examinations and completing the requalification program
at the end of an extended shutdown period. As stated above, 10 CFR
55.11 allows the NRC to grant exemptions from the requirements of 10
CFR Part 55. The NRC staff has determined that granting of the
licensee's proposed exemption will not result in a violation of the
Atomic Energy Act of 1954, as amended, or the Commission's regulations.
Therefore, the exemption is authorized by law.
No Endangerment of Life or Property and Otherwise in the Public
Interest
The underlying purposes of 10 CFR 55 are to establish procedures
and criteria for the issuance of licenses to operators, provide for the
terms and conditions upon which the Commission will issue or modify
these licenses, and provide for the terms and conditions to maintain
and renew these licenses. Specifically, 10 CFR 55.59 establishes the
requirements for operator requalification programs and requires a 2-
year (24-month) requalification schedule to include a biennial
comprehensive written examination and annual operating tests.
Crystal River is in the final stages of an extended outage in which
significant plant modifications have been completed. Crystal River has
requested a 2-month extension to the requirements of 10 CFR 55.59 due
to the reasonable probability of activities associated with plant
startup overlapping the biennial comprehensive written examination and
annual operating examination period.
Although the 24-month schedule requirement of 10 CFR 55.59 at
Crystal River would be exceeded, Crystal River has trained the licensed
operators on the plant modifications completed during the outage and
examined operators on the modified plant configuration with positive
results. During both the originally scheduled and extended periods of
the outage, Crystal River has continued the requalification training
cycle in accordance with the Institute of Nuclear Power Operations
(INPO) accredited training program. All Crystal River licensed
operators are actively enrolled in the accredited training program.
Moving the end of the requalification program, including the
biennial comprehensive written examination and annual operating test,
to April 30, 2011, would: (1) Allow operators to focus on preparing for
and performing activities associated with plant startup after an
extended maintenance period with significant plant modifications; (2)
maximize the number of licensed operators available to perform licensed
duties during startup; and (3) assist in managing operator fatigue
during startup activities.
Licensed operator fatigue is of serious concern to the NRC, and the
NRC staff has concluded that this exemption will allow the licensee to
better manage licensed operator fatigue during a period of high
workload. Further, the NRC staff has concluded that allowing operators
to focus on startup activities will support safe plant operations
during a series of infrequently performed evolutions. Based on the
above, the NRC staff has determined that the exemption will not
endanger life or property and is otherwise in the public interest.
4.0 Environmental Consideration
This exemption authorizes a one-time exemption from the
requirements of 10 CFR 55.59(c)(1) for Crystal River. The NRC staff has
determined that this exemption involves no significant hazards
considerations:
(1) The proposed exemption is administrative in nature and is
limited to extending the current licensed operator requalification
program period for Crystal River from 24 to 26 months on a one-time
only basis. 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 extending the current licensed operator requalification
program period for Crystal River from 24 to 26 months on a one-time
only basis. 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 extending the current licensed operator requalification
program period for Crystal River from 24 to 26 months on a one-time
only basis. 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.
Based on the above, the NRC staff concludes that the proposed
exemption does not involve a significant hazards consideration under
the standards set forth in 10 CFR 50.92(c), and accordingly, a finding
of ``no significant hazards consideration'' is justified.
The NRC staff has also determined that the exemption involves no
significant increase in the amounts, and no significant change in the
types, of
[[Page 5218]]
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 a
radiological accident. Furthermore, the requirement from which the
licensee will be exempted involves scheduling 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.
5.0 Conclusion
Accordingly, the Commission has determined that, pursuant to 10 CFR
55.11, granting an exemption to the licensee from the schedule
requirements in 10 CFR 55.59, by allowing Crystal River a one-time
extension in the allowed time for completing the current licensed
operator requalification program, is authorized by law and will not
endanger life or property and is otherwise in the public interest.
Therefore, the Commission hereby grants Florida Power Corporation an
exemption on a one-time only basis from the schedule requirement of 10
CFR 55.59, to allow the completion date for the current licensed
operator requalification program for the Crystal River Unit 3 Nuclear
Generating Plant to be extended from February 28, 2011, to April 30,
2011. The next requalification program period would begin May 1, 2011,
and continue for 24 months to April 30, 2013, with successive periods
running for 24 months.
This exemption is effective upon issuance.
Dated at Rockville, Maryland, this 20th day of January 2011.
For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2011-1911 Filed 1-27-11; 8:45 am]
BILLING CODE 7590-01-P