Luminant Generation Company LLC; Comanche Peak Steam Electric Station, Units 1 and 2; Draft Environmental Assessment and Finding of No Significant Impact Related to the Proposed License Amendment To Increase the Maximum Reactor Power Level, 23503-23505 [E8-9456]
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Federal Register / Vol. 73, No. 84 / Wednesday, April 30, 2008 / Notices
The NRC Clearance Officer is
Margaret A. Janney, (301) 415–7245.
Dated at Rockville, Maryland, this 23rd day
of April, 2008.
For the Nuclear Regulatory Commission.
Gregory Trussell,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. E8–9449 Filed 4–29–08; 8:45 am]
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SUMMARY: The NRC has recently
submitted to OMB for review the
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The NRC Clearance Officer is
Margaret A. Janney, (301) 415–7245.
Dated at Rockville, Maryland, this 24th day
of April. 2008.
For the Nuclear Regulatory Commission.
Gregory Trussell,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. E8–9452 Filed 4–29–08; 8:45 am]
BILLING CODE 7590–01–P
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23503
NUCLEAR REGULATORY
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[Docket Nos. 50–445 and 50–446]
Luminant Generation Company LLC;
Comanche Peak Steam Electric
Station, Units 1 and 2; Draft
Environmental Assessment and
Finding of No Significant Impact
Related to the Proposed License
Amendment To Increase the Maximum
Reactor Power Level
U.S. Nuclear Regulatory
Commission (NRC).
AGENCY:
Notice of opportunity for public
comment.
ACTION:
SUMMARY: The NRC has prepared a Draft
Environmental Assessment (EA) as its
evaluation of a request by the TXU
Generation Company LP (subsequently
renamed Luminant Generation
Company LLC, the licensee), for a
license amendment to increase the
maximum thermal power at the
Comanche Peak Steam Electric Station
(CPSES), Units 1 and 2, from 3458
megawatts thermal (MWt) to 3612 MWt
at each unit. The NRC staff did not
identify any significant impact from the
information provided in the licensee’s
stretch power uprate (SPU) application
for CPSES, Units 1 and 2 or from the
NRC staff’s independent review;
therefore, the NRC staff is documenting
its environmental review in a draft EA.
The draft EA and Finding of No
Significant Impact are being published
in the Federal Register with a 30-day
public comment period.
Environmental Assessment
The NRC is considering issuance of an
amendment to Facility Operating
License Nos. NPF–87 and NPF–89,
issued to Luminant Generation
Company LLC, for operation of the
CPSES, Units 1 and 2, located in
Somervell County, Texas. Therefore,
consistent with Section 51.21 of Title 10
of the Code of Federal Regulations (10
CFR), the NRC is issuing this draft EA
and finding of no significant impact.
Identification of the Proposed Action
The proposed action would revise the
CPSES, Units 1 and 2 operating licenses
and technical specifications (TSs) to
increase the licensed rated power by 4.5
percent from 3458 MWt to 3612 MWt.
The proposed action is in accordance
with the licensee’s application dated
August 28, 2007, as supplemented by
letters dated October 24, 2007, and
January 10, 29, 31, February 21, 26, 28,
and March 6, 2008.
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23504
Federal Register / Vol. 73, No. 84 / Wednesday, April 30, 2008 / Notices
The Need for the Proposed Action
The proposed action permits an
increase in the licensed core thermal
power from 3458 MWt to 3612 MWt for
the CPSES, Units 1 and 2, providing the
flexibility to obtain a higher electrical
output from the CPSES, Units 1 and 2.
rwilkins on PROD1PC63 with NOTICES
Environmental Impacts of the Proposed
Action
The licensee has submitted an
environmental evaluation supporting
the proposed SPU and provided a
summary of its conclusions concerning
the radiological and non-radiological
environmental impacts of the proposed
action.
Radiological Impacts
The licensee evaluated the impacts of
the proposed SPU on radioactive liquid
waste production, processing, discharge
into the environment, resultant dose to
members of the public, and impact to
Squaw Creek Reservoir (SCR). There
will be an increase (approximately 6.5
percent for long-lived activity) in the
equilibrium radioactivity in the reactor
coolant, which in turn will result in a
maximum increase of 6.5 percent in the
radioactivity content of the liquid
releases since input activities are based
on long-term reactor coolant activity.
Tritium levels are also expected to
increase by 6.5 percent in the
discharged liquid. This will result in
increased aqueous tritium
concentrations in the SCR.
The evaluation shows that even with
the small increase in the radioactivity
being discharged into the environment,
the projected dose to the maximally
exposed member of the public, while
slightly increased, will remain well
below the As Low As Reasonably
Achievable (ALARA) criteria in
Appendix I to 10 CFR Part 50. Also, the
tritium concentration levels in SCR will
remain well below the reporting limits
in the CPSES Offsite Dose Calculation
Manual (ODCM), which is based on
NRC reporting criteria.
The licensee evaluated the impacts of
the proposed SPU on gaseous
radioactive wastes. Gaseous radioactive
wastes are activation gases and fission
product radioactive noble gases, which
come from radioactive system leakage,
process operations including volume
control tank (VCT) venting, gases used
for tank cover gas, and gases generated
in the radiochemistry laboratory. The
evaluation shows that the proposed SPU
will not significantly increase the
inventory of gases normally processed
in the gaseous waste management
system. This is based on there being no
change to plant system functions and no
change to the gas volume inputs.
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17:09 Apr 29, 2008
Jkt 214001
The activity of radioactive gaseous
nuclides present in the waste gas system
will increase as a result of the SPU. This
is due to the increased levels of gases in
the reactor coolant system and the
actions performed in the VCT. However,
the operation of the waste gas system
will not change and will continue to
allow for decay of the short-lived
radionuclides. Tritium will remain the
largest component of the gaseous
effluents, the largest contributor being
from evaporation from the Spent Fuel
Pools. The proposed SPU will result in
an increase (approximately 9.5 percent
for noble gases, 6.6 percent for 1–131,
and 6.5 percent for long-lived activity)
in the equilibrium radioactivity in the
reactor coolant, which in turn increases
the activity in the gaseous waste
disposal systems and the activity
released into the atmosphere (estimated
to increase by 9.5 percent for noble
gases, 6.5 percent for particulates
including Tritium, and 12.6 percent for
iodines).
The evaluation shows that even with
the small increase in the gaseous
radioactivity being discharged into the
environment, the projected dose to the
maximally exposed member of the
public, while slightly increased, will
remain well below the ALARA criteria
in Appendix I to 10 CFR Part 50.
While the SPU will slightly increase
the activity level of radioactive isotopes
in the reactor coolant system and the
volume of radioactive liquid generated
from leakage and planned drainage,
there will only be a minimal effect on
the generation of radioactively
contaminated sludge and resin solids
processed as radwaste. The currently
installed radwaste system and its total
volume capacity for handling solid
radwaste will not be affected.
For the long-term operation of the
plant with the SPU, the dose to an
offsite member of the public from the
onsite storage of solid radwaste was
estimated to increase by approximately
7.2 percent. This is based on several
assumptions: (1) The current radwaste
decays and its dose contribution
decreases; (2) the stored radwaste is
routinely moved offsite for disposal; (3)
the radwaste generated post SPU enters
into storage; and (4) the plant capacity
factor approaches the target of 1.0. The
radiation dose from direct shine is
cumulative based on the waste
generated and stored onsite from all
units over the plant’s lifetime. CPSES
ODCM contains the requirements to
ensure compliance with the radiation
dose limits in 10 CFR Part 20 and the
Environmental Protection Agency’s 40
CFR Part 190. Therefore, while a small
increase in offsite radiation dose is
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expected, it will remain within
regulatory limits.
The radiation exposure to plant
workers from the SPU is expected to be
kept to a minimum based on the design
features at CPSES, Units 1 and 2, and
the Radiation Protection Program. The
design features include: (1) Shielding,
which is provided to reduce levels of
radiation; (2) ventilation, which is
arranged to control the flow of
potentially contaminated air; (3) an
installed radiation monitoring system,
which is used to measure levels of
radiation in potentially occupied areas
and measure airborne radioactivity
throughout the plant; and (4) respiratory
protective equipment, which is used as
prescribed by the Radiation Protection
Program. The Radiation Protection
Program contains procedures for all
radiological work performed at CPSES,
Units 1 and 2 to ensure doses are
maintained ALARA and are in
compliance with regulatory limits in 10
CFR Part 20.
Non-Radiological Impacts
With regard to potential nonradiological impacts of the proposed
SPU, the proposed action does not
result in any significant changes to land
use or water use. The proposed SPU
would increase the temperature of water
discharged from the plant at the
discharge point, Outfall 001, into the
SCR by 1.5 degrees Fahrenheit (°F) and
would increase lake evaporation by
approximately 6 acre-feet per year. The
expected thermal increase would raise
the average daily temperature at Outfall
001 from 95.6 °F to 97.1 °F, which
remains well below the daily average
temperature of 113 °F and daily
maximum temperature of 116 °F
specified in CPSES Texas Pollution
Discharge Elimination System (TPDES)
permit. Because this increase remains
well below the facility’s TPDES permit
limits, the NRC staff determined that
this increase is not significant, and is
bounded by previous analysis of
thermal discharge as documented in the
Final Environmental Statement related
to the operation of CPSES, Units 1 and
2 (September 1981). No effects on the
aquatic or terrestrial habitat in the
vicinity of the plant, or to endangered
or threatened species, or to the habitats
of endangered or threatened species are
expected as a result of the increase in
thermal discharge or change in annual
lake evaporation. The proposed action
does not have a potential to affect any
historical or archaeological sites.
The plant will be modified by
replacing the high-pressure turbines at
both units. All proposed plant changes
will occur within the existing buildings,
E:\FR\FM\30APN1.SGM
30APN1
Federal Register / Vol. 73, No. 84 / Wednesday, April 30, 2008 / Notices
and no proposed equipment upgrades
require any additional equipment that
will be visible from outside the existing
power station. The proposed action will
not change the method of generating
electricity or the method of handling
any influents from the environment or
non-radiological effluents to the
environment. Therefore, no changes or
different types of non-radiological
environmental impacts are expected as
a result of the proposed amendment.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action. The details of the staff’s safety
evaluation will be provided in the
amendment that will be issued as part
of the letter to the licensee approving
the amendment to the facility operating
licenses and technical specifications.
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. 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 CPSES, Units 1 and 2,
dated September 1981.
rwilkins on PROD1PC63 with NOTICES
Agencies and Persons Consulted
In accordance with its stated policy,
on April 22, 2008, the staff consulted
with the Texas State official, Alice
Rogers of the Texas 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
application dated August 28, 2007, as
supplemented by letters dated October
24, 2007, and January 10, 29, 31,
February 21, 26, 28, and March 6, 2008.
Publicly available records are accessible
electronically via the Agencywide
Document Access and Management
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17:09 Apr 29, 2008
Jkt 214001
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. Additionally,
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, Rockville, Maryland 20852.
The comment period expires
May 30, 2008. Comments received after
this date will be considered if it is
practical to do so, but the Commission
is only able to assure consideration of
comments received on or before May 30,
2008.
DATES:
Submit written comments
to Chief, Rules and Directives Branch,
Office of Administration, U.S. Nuclear
Regulatory Commission, Mail Stop T–
6D59, Washington, DC 20555–0001.
Written comments may also be
delivered to 11545 Rockville Pike, Room
T–6D59, Rockville, Maryland 20852
from 7:30 a.m. to 4:15 p.m. on Federal
workdays. Copies of written comments
received will be electronically available
at the NRC’s Public Electronic Reading
Room link, https://www.nrc.gov/readingrm/adams.html, on the NRC Web site or
at the NRC’s PDR located at One White
Flint North, 11555 Rockville Pike (first
floor), Rockville, Maryland 20852.
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 at 1–800–397–4209, or
301–415–4737, or by e-mail to
pdr@nrc.gov.
ADDRESSES:
The NRC
is considering issuance of an
amendment to Facility Operating
License Nos. NPF–87 (Unit 1) and NPF–
89 (Unit 2) issued to Luminant
Generation Company LLC, for the
operation of CPSES, Units 1 and 2,
located in Somervell County, Texas.
SUPPLEMENTARY INFORMATION:
FOR FURTHER INFORMATION CONTACT:
Balwant K. Singal, Office of Nuclear
Reactor Regulation, Mail Stop O–8B1,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001, by
telephone at (301) 415–3016, or by email at Balwant.Singal@nrc.gov.
Dated at Rockville, Maryland, this 24th day
of April 2008.
PO 00000
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Fmt 4703
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23505
For the Nuclear Regulatory Commission
Balwant K. Singal,
Senior Project Manager, Plant Licensing
Branch IV, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E8–9456 Filed 4–29–08; 8:45 am]
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Sunshine Federal Register Notice
AGENCY HOLDING THE MEETINGS: Nuclear
Regulatory Commission.
DATE: Weeks of April 28, May 5, 12, 19,
26, June 2, 2008.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
Week of April 28, 2008
Monday, April 28, 2008
9:30 a.m.
Briefing on Reactor Materials Issues
(Public Meeting). (Contact: Ted
Sullivan, 301 415–2796).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
Tuesday, April 29, 2008
1:25 p.m.
Affirmation Session (Public Meeting)
(Tentative).
a. AmerGen Energy Company, LLC
(License Renewal for Oyster Creek
Nuclear Generating Station), Docket
No. 50–219–LR, Citizens’ Petition
for Review of LBP–07–17 and Other
Interlocutory Decisions in the
Oyster Creek Proceeding
(Tentative).
b. Oyster Creek, Indian Point, Pilgrim,
and Vermont Yankee License
Renewals, Docket Nos. 50–219–LR,
50–247–LR, 50–286–LR, 50–293–
LR, 50–271–LR, Petition to Suspend
Proceedings (Tentative).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
1:30 p.m.
Meeting with Advisory Committee on
the Medical Uses of Isotopes (Public
Meeting). (Contact: Ashley Tull,
918–488–0552.
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
Wednesday, April 30, 2008
9:30 a.m.
Briefing on Materials Licensing and
Security (Public Meeting). (Contact:
Tomas Herrera, 301 415–7138).
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
E:\FR\FM\30APN1.SGM
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]]>Agencies
[Federal Register Volume 73, Number 84 (Wednesday, April 30, 2008)]
[Notices]
[Pages 23503-23505]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-9456]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-445 and 50-446]
Luminant Generation Company LLC; Comanche Peak Steam Electric
Station, Units 1 and 2; Draft Environmental Assessment and Finding of
No Significant Impact Related to the Proposed License Amendment To
Increase the Maximum Reactor Power Level
AGENCY: U.S. Nuclear Regulatory Commission (NRC).
ACTION: Notice of opportunity for public comment.
-----------------------------------------------------------------------
SUMMARY: The NRC has prepared a Draft Environmental Assessment (EA) as
its evaluation of a request by the TXU Generation Company LP
(subsequently renamed Luminant Generation Company LLC, the licensee),
for a license amendment to increase the maximum thermal power at the
Comanche Peak Steam Electric Station (CPSES), Units 1 and 2, from 3458
megawatts thermal (MWt) to 3612 MWt at each unit. The NRC staff did not
identify any significant impact from the information provided in the
licensee's stretch power uprate (SPU) application for CPSES, Units 1
and 2 or from the NRC staff's independent review; therefore, the NRC
staff is documenting its environmental review in a draft EA. The draft
EA and Finding of No Significant Impact are being published in the
Federal Register with a 30-day public comment period.
Environmental Assessment
The NRC is considering issuance of an amendment to Facility
Operating License Nos. NPF-87 and NPF-89, issued to Luminant Generation
Company LLC, for operation of the CPSES, Units 1 and 2, located in
Somervell County, Texas. Therefore, consistent with Section 51.21 of
Title 10 of the Code of Federal Regulations (10 CFR), the NRC is
issuing this draft EA and finding of no significant impact.
Identification of the Proposed Action
The proposed action would revise the CPSES, Units 1 and 2 operating
licenses and technical specifications (TSs) to increase the licensed
rated power by 4.5 percent from 3458 MWt to 3612 MWt. The proposed
action is in accordance with the licensee's application dated August
28, 2007, as supplemented by letters dated October 24, 2007, and
January 10, 29, 31, February 21, 26, 28, and March 6, 2008.
[[Page 23504]]
The Need for the Proposed Action
The proposed action permits an increase in the licensed core
thermal power from 3458 MWt to 3612 MWt for the CPSES, Units 1 and 2,
providing the flexibility to obtain a higher electrical output from the
CPSES, Units 1 and 2.
Environmental Impacts of the Proposed Action
The licensee has submitted an environmental evaluation supporting
the proposed SPU and provided a summary of its conclusions concerning
the radiological and non-radiological environmental impacts of the
proposed action.
Radiological Impacts
The licensee evaluated the impacts of the proposed SPU on
radioactive liquid waste production, processing, discharge into the
environment, resultant dose to members of the public, and impact to
Squaw Creek Reservoir (SCR). There will be an increase (approximately
6.5 percent for long-lived activity) in the equilibrium radioactivity
in the reactor coolant, which in turn will result in a maximum increase
of 6.5 percent in the radioactivity content of the liquid releases
since input activities are based on long-term reactor coolant activity.
Tritium levels are also expected to increase by 6.5 percent in the
discharged liquid. This will result in increased aqueous tritium
concentrations in the SCR.
The evaluation shows that even with the small increase in the
radioactivity being discharged into the environment, the projected dose
to the maximally exposed member of the public, while slightly
increased, will remain well below the As Low As Reasonably Achievable
(ALARA) criteria in Appendix I to 10 CFR Part 50. Also, the tritium
concentration levels in SCR will remain well below the reporting limits
in the CPSES Offsite Dose Calculation Manual (ODCM), which is based on
NRC reporting criteria.
The licensee evaluated the impacts of the proposed SPU on gaseous
radioactive wastes. Gaseous radioactive wastes are activation gases and
fission product radioactive noble gases, which come from radioactive
system leakage, process operations including volume control tank (VCT)
venting, gases used for tank cover gas, and gases generated in the
radiochemistry laboratory. The evaluation shows that the proposed SPU
will not significantly increase the inventory of gases normally
processed in the gaseous waste management system. This is based on
there being no change to plant system functions and no change to the
gas volume inputs.
The activity of radioactive gaseous nuclides present in the waste
gas system will increase as a result of the SPU. This is due to the
increased levels of gases in the reactor coolant system and the actions
performed in the VCT. However, the operation of the waste gas system
will not change and will continue to allow for decay of the short-lived
radionuclides. Tritium will remain the largest component of the gaseous
effluents, the largest contributor being from evaporation from the
Spent Fuel Pools. The proposed SPU will result in an increase
(approximately 9.5 percent for noble gases, 6.6 percent for 1-131, and
6.5 percent for long-lived activity) in the equilibrium radioactivity
in the reactor coolant, which in turn increases the activity in the
gaseous waste disposal systems and the activity released into the
atmosphere (estimated to increase by 9.5 percent for noble gases, 6.5
percent for particulates including Tritium, and 12.6 percent for
iodines).
The evaluation shows that even with the small increase in the
gaseous radioactivity being discharged into the environment, the
projected dose to the maximally exposed member of the public, while
slightly increased, will remain well below the ALARA criteria in
Appendix I to 10 CFR Part 50.
While the SPU will slightly increase the activity level of
radioactive isotopes in the reactor coolant system and the volume of
radioactive liquid generated from leakage and planned drainage, there
will only be a minimal effect on the generation of radioactively
contaminated sludge and resin solids processed as radwaste. The
currently installed radwaste system and its total volume capacity for
handling solid radwaste will not be affected.
For the long-term operation of the plant with the SPU, the dose to
an offsite member of the public from the onsite storage of solid
radwaste was estimated to increase by approximately 7.2 percent. This
is based on several assumptions: (1) The current radwaste decays and
its dose contribution decreases; (2) the stored radwaste is routinely
moved offsite for disposal; (3) the radwaste generated post SPU enters
into storage; and (4) the plant capacity factor approaches the target
of 1.0. The radiation dose from direct shine is cumulative based on the
waste generated and stored onsite from all units over the plant's
lifetime. CPSES ODCM contains the requirements to ensure compliance
with the radiation dose limits in 10 CFR Part 20 and the Environmental
Protection Agency's 40 CFR Part 190. Therefore, while a small increase
in offsite radiation dose is expected, it will remain within regulatory
limits.
The radiation exposure to plant workers from the SPU is expected to
be kept to a minimum based on the design features at CPSES, Units 1 and
2, and the Radiation Protection Program. The design features include:
(1) Shielding, which is provided to reduce levels of radiation; (2)
ventilation, which is arranged to control the flow of potentially
contaminated air; (3) an installed radiation monitoring system, which
is used to measure levels of radiation in potentially occupied areas
and measure airborne radioactivity throughout the plant; and (4)
respiratory protective equipment, which is used as prescribed by the
Radiation Protection Program. The Radiation Protection Program contains
procedures for all radiological work performed at CPSES, Units 1 and 2
to ensure doses are maintained ALARA and are in compliance with
regulatory limits in 10 CFR Part 20.
Non-Radiological Impacts
With regard to potential non-radiological impacts of the proposed
SPU, the proposed action does not result in any significant changes to
land use or water use. The proposed SPU would increase the temperature
of water discharged from the plant at the discharge point, Outfall 001,
into the SCR by 1.5 degrees Fahrenheit ([deg]F) and would increase lake
evaporation by approximately 6 acre-feet per year. The expected thermal
increase would raise the average daily temperature at Outfall 001 from
95.6 [deg]F to 97.1 [deg]F, which remains well below the daily average
temperature of 113 [deg]F and daily maximum temperature of 116 [deg]F
specified in CPSES Texas Pollution Discharge Elimination System (TPDES)
permit. Because this increase remains well below the facility's TPDES
permit limits, the NRC staff determined that this increase is not
significant, and is bounded by previous analysis of thermal discharge
as documented in the Final Environmental Statement related to the
operation of CPSES, Units 1 and 2 (September 1981). No effects on the
aquatic or terrestrial habitat in the vicinity of the plant, or to
endangered or threatened species, or to the habitats of endangered or
threatened species are expected as a result of the increase in thermal
discharge or change in annual lake evaporation. The proposed action
does not have a potential to affect any historical or archaeological
sites.
The plant will be modified by replacing the high-pressure turbines
at both units. All proposed plant changes will occur within the
existing buildings,
[[Page 23505]]
and no proposed equipment upgrades require any additional equipment
that will be visible from outside the existing power station. The
proposed action will not change the method of generating electricity or
the method of handling any influents from the environment or non-
radiological effluents to the environment. Therefore, no changes or
different types of non-radiological environmental impacts are expected
as a result of the proposed amendment.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action. The details
of the staff's safety evaluation will be provided in the amendment that
will be issued as part of the letter to the licensee approving the
amendment to the facility operating licenses and technical
specifications.
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. 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 CPSES, Units 1 and 2, dated September 1981.
Agencies and Persons Consulted
In accordance with its stated policy, on April 22, 2008, the staff
consulted with the Texas State official, Alice Rogers of the Texas
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 application dated August 28, 2007, as supplemented by
letters dated October 24, 2007, and January 10, 29, 31, February 21,
26, 28, and March 6, 2008. Publicly available records are accessible
electronically via the Agencywide Document 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. Additionally, 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, Rockville, Maryland 20852.
DATES: The comment period expires May 30, 2008. Comments received after
this date will be considered if it is practical to do so, but the
Commission is only able to assure consideration of comments received on
or before May 30, 2008.
ADDRESSES: Submit written comments to Chief, Rules and Directives
Branch, Office of Administration, U.S. Nuclear Regulatory Commission,
Mail Stop T-6D59, Washington, DC 20555-0001. Written comments may also
be delivered to 11545 Rockville Pike, Room T-6D59, Rockville, Maryland
20852 from 7:30 a.m. to 4:15 p.m. on Federal workdays. Copies of
written comments received will be electronically available at the NRC's
Public Electronic Reading Room link, https://www.nrc.gov/reading-rm/
adams.html, on the NRC Web site or at the NRC's PDR located at One
White Flint North, 11555 Rockville Pike (first floor), Rockville,
Maryland 20852. 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 at 1-800-397-4209, or 301-415-4737,
or by e-mail to pdr@nrc.gov.
SUPPLEMENTARY INFORMATION: The NRC is considering issuance of an
amendment to Facility Operating License Nos. NPF-87 (Unit 1) and NPF-89
(Unit 2) issued to Luminant Generation Company LLC, for the operation
of CPSES, Units 1 and 2, located in Somervell County, Texas.
FOR FURTHER INFORMATION CONTACT: Balwant K. Singal, Office of Nuclear
Reactor Regulation, Mail Stop O-8B1, U.S. Nuclear Regulatory
Commission, Washington, DC 20555-0001, by telephone at (301) 415-3016,
or by e-mail at Balwant.Singal@nrc.gov.
Dated at Rockville, Maryland, this 24th day of April 2008.
For the Nuclear Regulatory Commission
Balwant K. Singal,
Senior Project Manager, Plant Licensing Branch IV, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E8-9456 Filed 4-29-08; 8:45 am]
BILLING CODE 7590-01-P
