Exelon Generation Company, LLC; Three Mile Island Nuclear Station, Unit 1; Environmental Assessment and Finding of No Significant Impact, 36700-36701 [2010-15626]
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Federal Register / Vol. 75, No. 123 / Monday, June 28, 2010 / Notices
connection with items for inclusion in
guides currently being developed or
improvements in all published guides
are encouraged at any time. Requests for
technical information about DG–1216
may be directed to the NRC contact:
Robert L. Tregoning, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: (301) 251–
7662, e-mail Robert.Tregoning@nrc.gov,
or, Richard Jervey, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: (301) 251–
7404, e-mail Richard.Jervey@nrc.gov.
Electronic copies of DG–1216 are
available through the NRC’s public Web
site under Draft Regulatory Guides in
the ‘‘Regulatory Guides’’ collection of
the NRC’s Electronic Reading Room at
https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also
available in ADAMS (https://
www.nrc.gov/reading-rm/adams.html),
under Accession No. ML100430356.
The regulatory analysis may be found in
ADAMS under Accession No.
ML101530472.
In addition, regulatory guides are
available for inspection at the NRC’s
Public Document Room (PDR) located at
11555 Rockville Pike, Rockville,
Maryland. The PDR’s mailing address is
USNRC PDR, Washington, DC 20555–
0001. The PDR can also be reached by
telephone at (301) 415–4737 or (800)
397–4205, by fax at (301) 415–3548, and
by e-mail to pdr.resource@nrc.gov.
Regulatory guides are not
copyrighted, and Commission approval
is not required to reproduce them.
Dated at Rockville, Maryland, June 17,
2010.
For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch,
Division of Engineering, Office of Nuclear
Regulatory Research.
[FR Doc. 2010–15629 Filed 6–25–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–289; NRC–2010–0221]
jlentini on DSKJ8SOYB1PROD with NOTICES
Exelon Generation Company, LLC;
Three Mile Island Nuclear Station, Unit
1; Environmental Assessment and
Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption from Title 10
of the Code of Federal Regulations (10
CFR) part 50, Appendix R, Section III.G,
‘‘Fire Protection of Safe Shutdown
Capability,’’ for the use of an operator
manual action in lieu of the
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21:02 Jun 25, 2010
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requirements specified in Appendix R,
Section III.G.2, for Renewed Facility
Operating License No. DPR–50, issued
to Exelon Generation Company, LLC
(the licensee), for operation of Three
Mile Island Nuclear Station, Unit 1
(TMI–1), located in Dauphin County,
Pennsylvania. Therefore, as required by
10 CFR 51.21, the NRC performed an
environmental assessment. Based on the
results of the environmental assessment,
the NRC is issuing a finding of no
significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would grant an
exemption to the requirements of 10
CFR part 50, appendix R, section III.G.2,
based on an operator manual action
contained in the licensee’s Fire Hazards
Analysis Report (FHAR), which is part
of the TMI–1 Updated Final Safety
Analysis Report. The licensee’s FHAR
requires that the identified operator
manual action be performed outside of
the control room to achieve safe
shutdown following a fire in Fire Zone
AB–FZ–6 (Demineralizer and ‘‘A’’ Motor
Control Center Area). The licensee states
that the manual action was subjected to
a manual action feasibility review for
TMI–1 that determined that the manual
action is feasible and can be reliably
performed.
The proposed action is in accordance
with the licensee’s application dated
March 3, 2009, as supplemented by
letter dated March 15, 2010
(Agencywide Documents Access and
Management System (ADAMS)
Accession Nos. ML090630134 and
ML100750093, respectively).
The Need for the Proposed Action
The proposed exemption modifies an
existing exemption which was granted
by letter dated December 30, 1986
(ADAMS Accession No. 8701090216).
The proposed modified exemption
involves an operator manual action to
open the supply breaker for the motor
control center which powers valve MU–
V–36, and then locally ensure that MU–
V–36 is open. The proposed exemption
specifies a reduced (40 minute) time
frame to perform these actions as
compared to one hour in the original
exemption. The reduced timeframe is
being specified because recent plant
testing has shown that the backup air
supply to seal injection valve MU–V–20
would only allow the valve to stay open
for approximately 75 minutes under the
postulated conditions. With MU–V–20
closed, ensuring that valve MU–V–36 is
open provides a minimum recirculation
flow path for the makeup pumps. By
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Frm 00072
Fmt 4703
Sfmt 4703
maintaining a minimum recirculation
flow path, the makeup pumps will not
be susceptible to pump damage from
operation in a ‘‘deadheaded’’ condition.
The recent test results on MU–V–20
necessitate a time reduction for the
specified operator manual action to
maintain sufficient time margin in order
to prevent potential operation of the
makeup pumps in a ‘‘deadheaded’’
condition.
The proposed exemption is necessary
because the crediting of operator
manual actions to achieve and maintain
hot shutdown is not addressed in 10
CFR part 50 appendix R, section III.G.2,
and an exemption is therefore required
in accordance with 10 CFR 50.12.
Environmental Impacts of the Proposed
Action
The NRC has completed its evaluation
for the proposed action and concludes
that the operator manual action
addressed in the application is feasible
and can be reliably performed. Further,
the NRC concludes that there is
sufficient defense-in-depth within the
fire protection program to ensure that a
redundant train necessary to achieve
and maintain safe shutdown of the plant
will remain free of fire damage in the
event of a fire in the postulated area.
The details of the staff’s safety
evaluation will be provided in the
exemption that will be issued as part of
the letter to the licensee approving the
exemption to 10 CFR part 50, appendix
R, section III.G.2.
As described in the staff’s safety
evaluation that will be provided to the
licensee with the exemption, the
proposed action will not significantly
increase the probability or consequences
of accidents. Since the change being
evaluated in this assessment involves
only a change to the time allotted to
accomplish a previously approved
operator manual action, no changes are
being made in the types of effluents that
may be released off-site. Likewise, there
is no significant increase in the amount
of any effluent released off-site because
the time change has no impact on any
effluent release path or duration. There
is no significant increase in
occupational radiation exposure
because, as described in the staff’s safety
evaluation, the areas of consideration
for the operator manual action are
expected to have dose rates of less than
10 millirem per hour. Since there is no
impact to any radiological effluents or
in-plant dose rates from the operator
manual action time change, there is no
impact to public radiation exposure.
Therefore, there are no significant
radiological environmental impacts
associated with the proposed action.
E:\FR\FM\28JNN1.SGM
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Federal Register / Vol. 75, No. 123 / Monday, June 28, 2010 / Notices
The operator manual action described
in the proposed exemption involves
ensuring recirculation flow within the
plant makeup system such that it
continues to operate as designed. It does
not have any impact to water usage or
impact plant systems that contribute to
non-radiological effluent releases from
the plant. Therefore, the proposed
action does not result in changes to land
use or water use, or result in changes to
the quality or quantity of nonradiological effluents. Likewise, no
changes to the National Pollution
Discharge Elimination System permit
are needed and no effects on the aquatic
or terrestrial habitat in the vicinity or
the plant, or to threatened, endangered,
or protected species under the
Endangered Species Act, or impacts to
essential fish habitat covered by the
Magnuson-Stevens Act are expected.
For the same reasons, there are no
impacts to the air or ambient air quality,
nor are there impacts to historical and
cultural resources. With no impact of
the proposed exemption beyond the site
boundary, there would be no noticeable
effect on socioeconomic conditions in
the region. Therefore, no changes or
different types of non-radiological
environmental impacts are expected as
a result of the proposed action.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the NRC staff considered denial
of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the
application would not result in a
decrease in current environmental
impacts. If the proposed action was
denied, the licensee would have to
perform plant modifications and/or
reroute or wrap cables to achieve
compliance. The environmental impacts
of the proposed action and the
alternative action are similar.
In accordance with its stated policy,
on March 29, 2010, the NRC staff
consulted with the Pennsylvania State
official, Dennis Dyckman, of the
Pennsylvania State Department of
Environmental Protection, regarding the
environmental impact of the proposed
action. The State official had no
comments.
Finding of No Significant Impact
On the basis of the environmental
assessment, the NRC concludes that the
proposed action will not have a
significant effect on the quality of the
human environment. Accordingly, the
NRC has determined not to prepare an
environmental impact statement for the
proposed action.
For further details with respect to the
proposed action, see the licensee’s letter
dated March 3, 2009, as supplemented
on March 15, 2010 (ADAMS Accession
Nos. ML090630134 and ML100750093,
respectively). Documents may be
examined, and/or copied for a fee, at the
NRC’s Public Document Room (PDR),
located at One White Flint North, Room
O1 F21, 11555 Rockville Pike (first
floor), Rockville, Maryland. Publicly
available records will be accessible
electronically from the ADAMS Public
Electronic Reading Room on the Internet
at the NRC Web site, https://
www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to
ADAMS or who encounter problems in
accessing the documents located in
ADAMS should contact the NRC PDR
Reference staff by telephone at 1–800–
397–4209 or 301–415–4737, or send an
e-mail to pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 15th day
of June 2010.
For the Nuclear Regulatory Commission.
Peter Bamford,
Project Manager, Plant Licensing Branch
I–2, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. 2010–15626 Filed 6–25–10; 8:45 am]
BILLING CODE 7590–01–P
Alternative Use of Resources
jlentini on DSKJ8SOYB1PROD with NOTICES
Agencies and Persons Consulted
The action does not involve the use of
any different resources than those
previously considered in the Final
Environmental Statement Related to the
Operation of Three Mile Island Nuclear
Station, Units 1 and 2, NUREG–0552,
dated December 1972, and Generic
Environmental Impact Statement for
License Renewal of Nuclear Plants
(NUREG–1437, Supplement 37), dated
June 2009.
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36701
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0440; Docket No. 40–8989]
Issuance of Environmental
Assessment and Finding of No
Significant Impact for Modification of
Exemption From Certain U.S. Nuclear
Regulatory Commission Licensing
Requirements for Special Nuclear
Material for Energy Solutions LLC,
Clive, UT
AGENCY: Nuclear Regulatory
Commission.
ACTION: Environmental Assessment and
Final Finding of No Significant Impact.
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) has prepared an
Environmental Assessment for the
issuance of an Order as authorized by
Section 274f of the Atomic Energy Act
that would modify an Order issued to
EnergySolutions, LLC (formerly
Envirocare of Utah, Inc.) on May 7, 1999
(64 FR 27826; May 21, 1999). In
accordance with 10 CFR 51.33, the NRC
prepared a draft Finding of No
Significant Impact (FONSI) for this
amendment, which was published for
public review and comment on October
7, 2009 (74 FR 51622). The public
comment period closed on November 6,
2009. NRC received 12 comments from
4 commenters. The Order responds to a
request by EnergySolutions dated
September 26, 2006, to amend the
package mass limits contained in
Condition 4 of their 2006 Order, and to
add or revise other conditions. The May
7, 1999, Order exempted
EnergySolutions from certain NRC
regulations and permitted
EnergySolutions, under specified
conditions, to possess waste containing
special nuclear material (SNM), in
greater quantities than specified in 10
CFR Part 150 at its facility located in
Clive, Utah, without obtaining an NRC
license under 10 CFR Part 70. As
discussed below, the Order has been
amended four times since it was issued
in 1999.
ADDRESSES: You can access publicly
available documents related to this
notice using the following methods:
NRC’s Public Document Room (PDR):
The public may examine and have
copied for a fee publicly available
documents at the NRC’s PDR, Public
File Area O1 F21, One White Flint
North, 11555 Rockville Pike, Rockville,
Maryland 20852.
NRC’s Agencywide Documents Access
and Management System (ADAMS):
Publicly available documents created or
received at the NRC are available
E:\FR\FM\28JNN1.SGM
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]]>Agencies
[Federal Register Volume 75, Number 123 (Monday, June 28, 2010)]
[Notices]
[Pages 36700-36701]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-15626]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-289; NRC-2010-0221]
Exelon Generation Company, LLC; Three Mile Island Nuclear
Station, Unit 1; Environmental Assessment and Finding of No Significant
Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption from Title 10 of the Code of Federal
Regulations (10 CFR) part 50, Appendix R, Section III.G, ``Fire
Protection of Safe Shutdown Capability,'' for the use of an operator
manual action in lieu of the requirements specified in Appendix R,
Section III.G.2, for Renewed Facility Operating License No. DPR-50,
issued to Exelon Generation Company, LLC (the licensee), for operation
of Three Mile Island Nuclear Station, Unit 1 (TMI-1), located in
Dauphin County, Pennsylvania. Therefore, as required by 10 CFR 51.21,
the NRC performed an environmental assessment. Based on the results of
the environmental assessment, the NRC is issuing a finding of no
significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would grant an exemption to the requirements of
10 CFR part 50, appendix R, section III.G.2, based on an operator
manual action contained in the licensee's Fire Hazards Analysis Report
(FHAR), which is part of the TMI-1 Updated Final Safety Analysis
Report. The licensee's FHAR requires that the identified operator
manual action be performed outside of the control room to achieve safe
shutdown following a fire in Fire Zone AB-FZ-6 (Demineralizer and ``A''
Motor Control Center Area). The licensee states that the manual action
was subjected to a manual action feasibility review for TMI-1 that
determined that the manual action is feasible and can be reliably
performed.
The proposed action is in accordance with the licensee's
application dated March 3, 2009, as supplemented by letter dated March
15, 2010 (Agencywide Documents Access and Management System (ADAMS)
Accession Nos. ML090630134 and ML100750093, respectively).
The Need for the Proposed Action
The proposed exemption modifies an existing exemption which was
granted by letter dated December 30, 1986 (ADAMS Accession No.
8701090216). The proposed modified exemption involves an operator
manual action to open the supply breaker for the motor control center
which powers valve MU-V-36, and then locally ensure that MU-V-36 is
open. The proposed exemption specifies a reduced (40 minute) time frame
to perform these actions as compared to one hour in the original
exemption. The reduced timeframe is being specified because recent
plant testing has shown that the backup air supply to seal injection
valve MU-V-20 would only allow the valve to stay open for approximately
75 minutes under the postulated conditions. With MU-V-20 closed,
ensuring that valve MU-V-36 is open provides a minimum recirculation
flow path for the makeup pumps. By maintaining a minimum recirculation
flow path, the makeup pumps will not be susceptible to pump damage from
operation in a ``deadheaded'' condition. The recent test results on MU-
V-20 necessitate a time reduction for the specified operator manual
action to maintain sufficient time margin in order to prevent potential
operation of the makeup pumps in a ``deadheaded'' condition.
The proposed exemption is necessary because the crediting of
operator manual actions to achieve and maintain hot shutdown is not
addressed in 10 CFR part 50 appendix R, section III.G.2, and an
exemption is therefore required in accordance with 10 CFR 50.12.
Environmental Impacts of the Proposed Action
The NRC has completed its evaluation for the proposed action and
concludes that the operator manual action addressed in the application
is feasible and can be reliably performed. Further, the NRC concludes
that there is sufficient defense-in-depth within the fire protection
program to ensure that a redundant train necessary to achieve and
maintain safe shutdown of the plant will remain free of fire damage in
the event of a fire in the postulated area.
The details of the staff's safety evaluation will be provided in
the exemption that will be issued as part of the letter to the licensee
approving the exemption to 10 CFR part 50, appendix R, section III.G.2.
As described in the staff's safety evaluation that will be provided
to the licensee with the exemption, the proposed action will not
significantly increase the probability or consequences of accidents.
Since the change being evaluated in this assessment involves only a
change to the time allotted to accomplish a previously approved
operator manual action, no changes are being made in the types of
effluents that may be released off-site. Likewise, there is no
significant increase in the amount of any effluent released off-site
because the time change has no impact on any effluent release path or
duration. There is no significant increase in occupational radiation
exposure because, as described in the staff's safety evaluation, the
areas of consideration for the operator manual action are expected to
have dose rates of less than 10 millirem per hour. Since there is no
impact to any radiological effluents or in-plant dose rates from the
operator manual action time change, there is no impact to public
radiation exposure. Therefore, there are no significant radiological
environmental impacts associated with the proposed action.
[[Page 36701]]
The operator manual action described in the proposed exemption
involves ensuring recirculation flow within the plant makeup system
such that it continues to operate as designed. It does not have any
impact to water usage or impact plant systems that contribute to non-
radiological effluent releases from the plant. Therefore, the proposed
action does not result in changes to land use or water use, or result
in changes to the quality or quantity of non-radiological effluents.
Likewise, no changes to the National Pollution Discharge Elimination
System permit are needed and no effects on the aquatic or terrestrial
habitat in the vicinity or the plant, or to threatened, endangered, or
protected species under the Endangered Species Act, or impacts to
essential fish habitat covered by the Magnuson-Stevens Act are
expected. For the same reasons, there are no impacts to the air or
ambient air quality, nor are there impacts to historical and cultural
resources. With no impact of the proposed exemption beyond the site
boundary, there would be no noticeable effect on socioeconomic
conditions in the region. Therefore, no changes or different types of
non-radiological environmental impacts are expected as a result of the
proposed action.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the NRC staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the application would not result in a decrease in current
environmental impacts. If the proposed action was denied, the licensee
would have to perform plant modifications and/or reroute or wrap cables
to achieve compliance. The environmental impacts of the proposed action
and the alternative action are similar.
Alternative Use of Resources
The action does not involve the use of any different resources than
those previously considered in the Final Environmental Statement
Related to the Operation of Three Mile Island Nuclear Station, Units 1
and 2, NUREG-0552, dated December 1972, and Generic Environmental
Impact Statement for License Renewal of Nuclear Plants (NUREG-1437,
Supplement 37), dated June 2009.
Agencies and Persons Consulted
In accordance with its stated policy, on March 29, 2010, the NRC
staff consulted with the Pennsylvania State official, Dennis Dyckman,
of the Pennsylvania State Department of Environmental Protection,
regarding the environmental impact of the proposed action. The State
official had no comments.
Finding of No Significant Impact
On the basis of the environmental assessment, the NRC concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the NRC has determined
not to prepare an environmental impact statement for the proposed
action.
For further details with respect to the proposed action, see the
licensee's letter dated March 3, 2009, as supplemented on March 15,
2010 (ADAMS Accession Nos. ML090630134 and ML100750093, respectively).
Documents may be examined, and/or copied for a fee, at the NRC's Public
Document Room (PDR), located at One White Flint North, Room O1 F21,
11555 Rockville Pike (first floor), Rockville, Maryland. Publicly
available records will be accessible electronically from the ADAMS
Public Electronic Reading Room on the Internet at the NRC Web site,
https://www.nrc.gov/reading-rm/adams.html. Persons who do not have
access to ADAMS or who encounter problems in accessing the documents
located in ADAMS should contact the NRC PDR Reference staff by
telephone at 1-800-397-4209 or 301-415-4737, or send an e-mail to
pdr.resource@nrc.gov.
Dated at Rockville, Maryland, this 15th day of June 2010.
For the Nuclear Regulatory Commission.
Peter Bamford,
Project Manager, Plant Licensing Branch I-2, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2010-15626 Filed 6-25-10; 8:45 am]
BILLING CODE 7590-01-P
