Entergy Operations, Inc.; Arkansas Nuclear One, Unit 2; Environmental Assessment and Finding of No Significant Impact, 19106-19107 [E5-1675]
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19106
Federal Register / Vol. 70, No. 69 / Tuesday, April 12, 2005 / Notices
underlying purpose of the 10 CFR Part
50, Appendix E and 10 CFR 50.47(b)(3)
is to provide reasonable assurance that
adequate protective measures can and
will be implemented in the event of a
radiological emergency. Specifically,
adequate protective measures are those
that provide effective direction and
control, protective actions for the
public, and coordination of the
emergency response effort with Federal,
State, and local agencies.
The staff relied upon the licensee’s
submittals to evaluate whether the
licensee’s proposal to consolidate the
EOF’s for Hatch, Vogtle, and Farley
meets the underlying purpose of 10 CFR
Part 50, Appendix E and 10 CFR
50.47(b)(3). Advancements in
communications, monitoring
capabilities, computer technology, the
familiarity of the NRC staff with the use
of common EOFs, and the SNC’s
emergency response strategies will
continue to provide reasonable
assurance that adequate protective
measures can and will be implemented
in the event of a radiological emergency.
The common EOF in Birmingham,
AL, meets the functional and
availability characteristics for carrying
out the functions of a ‘‘near-site’’ EOF.
The remote location of the common EOF
could aid in response to a security event
as the licensee can effectively mobilize
and manage its resources and
communicate effectively with the site,
Federal, State, and local emergency
management. However, the former nearsite EOFs or equivalent ‘‘near-site’’
facilities may be needed to
accommodate an NRC site team.
Therefore, as a condition of this
exemption, SNC must provide a
functional working space of
approximately 75 square feet per person
for up to 10 people; including NRC,
State, and FEMA representatives at the
former EOFs or equivalent ‘‘near-site’’
facilities. In addition, the licensee will
maintain telecommunications and
habitability provisions (i.e., standard
office lighting, furniture, heating and
ventilating systems, and electrical
power outlets) at these facilities to
support the 10 people.
The NRC staff observed a dual-site
drill on July 14, 2004, involving Farley
and Hatch. The staff observed the
licensee’s notification process, staffing,
communication, technical support, dose
assessment, protective action
recommendation process, coordination
with offsite officials, and overall
command and control. The licensee
demonstrated the capability to respond
to a dual-site emergency event. EOF
staffing was in accordance with the
SNC’s procedures. The offsite agencies
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16:48 Apr 11, 2005
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received timely and accurate
information, and adequate protective
measures were recommended to protect
the public health and safety.
In summary, the licensee’s proposal to
consolidate the near-site EOFs for
Hatch, Farley, and Vogtle to SNC’s
corporate location in Birmingham,
Alabama meets the underlying purpose
of the rule, see 10 CFR 50.12(a)(2)(ii). As
evinced in SNC’s submittals the new
EOF location can perform all of the
functions of a ‘‘near-site’’ location as
contemplated by the regulations.
Relocation of the EOFs to the proposed
site will continue to provide reasonable
assurance that adequate protective
measures can and will be implemented
in the event of a radiological emergency.
Therefore, SNC has demonstrated that
special circumstances exist such that an
exemption is warranted.
4.0
Conclusion
Accordingly, the Commission has
determined that, pursuant to 10 CFR
50.12(a), the exemption is authorized by
law, will not present an undue risk to
the public health and safety, and is
consistent with the common defense
and security. Also, special
circumstances are present. Therefore, as
specified herein, the Commission
hereby grants Southern Nuclear
Operating Company, Inc., an exemption
from the ‘‘near-site’’ requirements of 10
CFR Part 50, Appendix E, Section E.8.
and 10 CFR 50.47(b)(3), subject to
maintaining the functionality of the
former near-site EOF or equivalent nearsite facilities.
Pursuant to 10 CFR 51.32, the
Commission has determined that the
granting of this exemption will not have
a significant effect on the quality of the
human environment (70 FR 10417).
This exemption is effective upon
issuance.
Dated at Rockville, Maryland, this 6th day
of April 2005.
For the Nuclear Regulatory Commission.
Ledyard B. Marsh,
Director, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–1677 Filed 4–11–05; 8:45 am]
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NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–368]
Entergy Operations, Inc.; Arkansas
Nuclear One, Unit 2; 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 A, ‘‘General
Design Criteria For Nuclear Power
Plants,’’ General Design Criteria (GDC)
57, ‘‘Closed system isolation valves,’’ for
Facility Operating License No. NPF–6,
issued to Entergy Operations, Inc. (the
licensee), for operation of the Arkansas
Nuclear One, Unit 2 (ANO–2), located
in Pope County, Arkansas. Therefore, as
required by 10 CFR 51.21, the NRC is
issuing this environmental assessment
and finding of no significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would provide
an exemption from the requirements of
10 CFR Part 50, Appendix A, GDC 57,
which requires that certain lines that
penetrate containment have at least one
containment isolation valve (CIV) which
shall either be automatic, locked closed,
or capable of remote manual operation.
The licensee requests an exemption in
order to operate at power with certain
valves in the open position.
Specifically, the proposed exemption
would allow ANO–2 to operate at power
with the applicable manual upstream
CIVs associated with the emergency
feedwater (EFW) steam trap and the
atmospheric dump valve (ADV) drain
steam trap (i.e., one applicable CIV per
steam trap) in the open position.
The proposed action is in accordance
with the licensee’s application dated
October 30, 2003, as supplemented by
letters dated July 1, November 15, and
December 3, 2004, and March 3, 2005.
The Need for the Proposed Action
The proposed action is needed to
ensure the operability of the steamdriven EFW pump and to prevent
inoperability due to condensate
buildup, and to ensure that
waterhammer does not damage the
piping associated with the ADV due to
condensate buildup.
GDC 57 states, ‘‘Each line that
penetrates primary reactor containment
and is neither part of the reactor coolant
pressure boundary nor connected
directly to the containment atmosphere
shall have at least one containment
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12APN1
Federal Register / Vol. 70, No. 69 / Tuesday, April 12, 2005 / Notices
isolation valve which shall be either
automatic, or locked closed, or capable
of remote manual operation. This valve
shall be outside containment and
located as close to the containment as
practical. A simple check valve may not
be used as the automatic isolation
valve.’’ However, in the case of ANO–
2, operating with the EFW steam trap
upstream CIV closed and the ADV drain
steam trap upstream CIV closed, could
pose a potential challenge to the
operability of the steam-driven EFW
pump and could damage the piping
associated with the ADV, due to
condensate buildup.
Operating with the EFW steam trap
and ADV drain steam trap upstream
CIVs open results in having only the
secondary system pressure boundary
inside containment as a barrier against
the release of radioactivity to the
environment through the steam trap
piping. However, operating with the
EFW steam trap upstream CIV closed
and the ADV drain steam trap upstream
CIV closed could compromise the
operability of the EFW pump turbine
and could damage the ADV piping, due
to condensate buildup. The licensee has
evaluated the effects of the EFW steam
trap and ADV drain steam trap upstream
CIVs being open during power
operation, and has shown this to have
no impact on the consequences of any
of the events evaluated in the Safety
Analysis Report (SAR). Therefore, the
licensee is requesting an exemption
from the requirements of GDC 57 to
keep these valves open during
operation.
Environmental Impacts of the Proposed
Action
The NRC has completed its safety
evaluation of the proposed action and
concludes that, in this case, it is not
necessary for the subject CIVs to be
locked closed, automatic, or capable of
remote manual operation, as required in
GDC 57, in order to achieve the
underlying purpose of GDC 57. The
effects of these valves being open during
power operation has been evaluated and
shown to have no impact on the
consequence of any of the postulated
events that are evaluated in the SAR.
Thus, the NRC staff finds that the
operation of ANO–2 with the subject
CIVs open is acceptable, and that the
requested exemption from GDC 57 is
justified for ANO–2.
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 the regulation.
The proposed action will not
significantly increase the probability or
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consequences of accidents. No changes
are being made in the types of effluents
that may be released off site. There is no
significant increase in the amount of
any effluent released off site. There is no
significant increase in occupational or
public radiation exposure. Therefore,
there are no significant radiological
environmental impacts associated with
the proposed action.
With regard to potential nonradiological impacts, the proposed
action does not have a potential to affect
any historic sites. It does not affect nonradiological plant effluents and has no
other environmental impact. Therefore,
there are no significant non-radiological
environmental impacts associated with
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 staff considered denial of the
proposed action (i.e., the ‘‘no-action’’
alternative). Denial of the application
would result in no change in current
environmental impacts. Installing
remote manual operators on the CIVs
was considered as an alternative to
bring the CIVs into compliance with
GDC 57. However, the staff believes that
any potential safety benefit derived from
installing remote manual operators on
the subject CIVs would not be
commensurate with the cost associated
with such a modification. 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 Arkansas Nuclear One,
Unit 2, NUREG–0254, dated June 1977.
Agencies and Persons Consulted
In accordance with its stated policy,
on January 13, 2005, the staff consulted
with the Arkansas State official, Dave
Baldwin of the Arkansas Department of
Health, 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
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19107
environmental impact statement for the
proposed action.
For further details with respect to the
proposed action, see the licensee’s letter
dated October 30, 2003, as
supplemented by letters dated July 1,
November 15, and December 3, 2004,
and March 3, 2005. Documents may be
examined, and/or copied for a fee, at the
NRC’s Public Document Room (PDR),
located at One White Flint North, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible electronically from
the Agencywide Documents Access and
Management System (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@nrc.gov.
Dated at Rockville, Maryland, this 6th day
of April 2005.
For the Nuclear Regulatory Commission.
Thomas W. Alexion,
Project Manager, Section 1, Project
Directorate IV, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–1675 Filed 4–11–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–348 and 50–364]
Southern Nuclear Operating Company,
Joseph M. Farley Nuclear Power Plant,
Units 1 and 2; 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 E, Section
IV.F.2.b and c for Facility Operating
License Nos. NPF–2 and NPF–8, issued
to Southern Nuclear Operating
Company (SNC or the licensee), for
operation of the Joseph M. Farley
Nuclear Power Plant (FNP), Units 1 and
2, located in Houston County, Alabama.
Therefore, as required by 10 CFR 51.21,
the NRC is issuing this environmental
assessment and finding of no significant
impact.
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]]>Agencies
[Federal Register Volume 70, Number 69 (Tuesday, April 12, 2005)]
[Notices]
[Pages 19106-19107]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-1675]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-368]
Entergy Operations, Inc.; Arkansas Nuclear One, Unit 2;
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 A, ``General Design Criteria For
Nuclear Power Plants,'' General Design Criteria (GDC) 57, ``Closed
system isolation valves,'' for Facility Operating License No. NPF-6,
issued to Entergy Operations, Inc. (the licensee), for operation of the
Arkansas Nuclear One, Unit 2 (ANO-2), located in Pope County, Arkansas.
Therefore, as required by 10 CFR 51.21, the NRC is issuing this
environmental assessment and finding of no significant impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would provide an exemption from the
requirements of 10 CFR Part 50, Appendix A, GDC 57, which requires that
certain lines that penetrate containment have at least one containment
isolation valve (CIV) which shall either be automatic, locked closed,
or capable of remote manual operation. The licensee requests an
exemption in order to operate at power with certain valves in the open
position. Specifically, the proposed exemption would allow ANO-2 to
operate at power with the applicable manual upstream CIVs associated
with the emergency feedwater (EFW) steam trap and the atmospheric dump
valve (ADV) drain steam trap (i.e., one applicable CIV per steam trap)
in the open position.
The proposed action is in accordance with the licensee's
application dated October 30, 2003, as supplemented by letters dated
July 1, November 15, and December 3, 2004, and March 3, 2005.
The Need for the Proposed Action
The proposed action is needed to ensure the operability of the
steam-driven EFW pump and to prevent inoperability due to condensate
buildup, and to ensure that waterhammer does not damage the piping
associated with the ADV due to condensate buildup.
GDC 57 states, ``Each line that penetrates primary reactor
containment and is neither part of the reactor coolant pressure
boundary nor connected directly to the containment atmosphere shall
have at least one containment
[[Page 19107]]
isolation valve which shall be either automatic, or locked closed, or
capable of remote manual operation. This valve shall be outside
containment and located as close to the containment as practical. A
simple check valve may not be used as the automatic isolation valve.''
However, in the case of ANO-2, operating with the EFW steam trap
upstream CIV closed and the ADV drain steam trap upstream CIV closed,
could pose a potential challenge to the operability of the steam-driven
EFW pump and could damage the piping associated with the ADV, due to
condensate buildup.
Operating with the EFW steam trap and ADV drain steam trap upstream
CIVs open results in having only the secondary system pressure boundary
inside containment as a barrier against the release of radioactivity to
the environment through the steam trap piping. However, operating with
the EFW steam trap upstream CIV closed and the ADV drain steam trap
upstream CIV closed could compromise the operability of the EFW pump
turbine and could damage the ADV piping, due to condensate buildup. The
licensee has evaluated the effects of the EFW steam trap and ADV drain
steam trap upstream CIVs being open during power operation, and has
shown this to have no impact on the consequences of any of the events
evaluated in the Safety Analysis Report (SAR). Therefore, the licensee
is requesting an exemption from the requirements of GDC 57 to keep
these valves open during operation.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
and concludes that, in this case, it is not necessary for the subject
CIVs to be locked closed, automatic, or capable of remote manual
operation, as required in GDC 57, in order to achieve the underlying
purpose of GDC 57. The effects of these valves being open during power
operation has been evaluated and shown to have no impact on the
consequence of any of the postulated events that are evaluated in the
SAR. Thus, the NRC staff finds that the operation of ANO-2 with the
subject CIVs open is acceptable, and that the requested exemption from
GDC 57 is justified for ANO-2.
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 the regulation.
The proposed action will not significantly increase the probability
or consequences of accidents. No changes are being made in the types of
effluents that may be released off site. There is no significant
increase in the amount of any effluent released off site. There is no
significant increase in occupational or public radiation exposure.
Therefore, there are no significant radiological environmental impacts
associated with the proposed action.
With regard to potential non-radiological impacts, the proposed
action does not have a potential to affect any historic sites. It does
not affect non-radiological plant effluents and has no other
environmental impact. Therefore, there are no significant non-
radiological environmental impacts associated with 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 staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the application would result in no change in current
environmental impacts. Installing remote manual operators on the CIVs
was considered as an alternative to bring the CIVs into compliance with
GDC 57. However, the staff believes that any potential safety benefit
derived from installing remote manual operators on the subject CIVs
would not be commensurate with the cost associated with such a
modification. 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 Arkansas Nuclear One, Unit 2, NUREG-0254,
dated June 1977.
Agencies and Persons Consulted
In accordance with its stated policy, on January 13, 2005, the
staff consulted with the Arkansas State official, Dave Baldwin of the
Arkansas Department of Health, 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 October 30, 2003, as supplemented by letters
dated July 1, November 15, and December 3, 2004, and March 3, 2005.
Documents may be examined, and/or copied for a fee, at the NRC's Public
Document Room (PDR), located at One White Flint North, 11555 Rockville
Pike (first floor), Rockville, Maryland. Publicly available records
will be accessible electronically from the Agencywide Documents Access
and Management System (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@nrc.gov.
Dated at Rockville, Maryland, this 6th day of April 2005.
For the Nuclear Regulatory Commission.
Thomas W. Alexion,
Project Manager, Section 1, Project Directorate IV, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-1675 Filed 4-11-05; 8:45 am]
BILLING CODE 7590-01-P
