[Federal Register Volume 73, Number 121 (Monday, June 23, 2008)]
[Notices]
[Pages 35419-35421]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E8-14147]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-445 AND 50-446]


Luminant Generation Company, LLC; Comanche Peak Steam Electric 
Station, Units 1 and 2; Final 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).
SUMMARY: As required by Title 10 of the Code of Federal Regulations 10 
CFR part 51, the NRC has prepared a final Environmental Assessment (EA) 
associated with 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. The 
final EA and Finding of No Significant Impact are being published in 
the Federal Register.
    The NRC published a draft EA and finding of no significant impact 
on the proposed action for public comment in the Federal Register on 
April 30, 2008 (73 FR 23503). No comments were received.

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 final 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, November 7, and 
December 3, 2007, January 10, 29, and 31, February 21, 26, and 28, 
March 6, April 17, and May 14, 2008. The letters dated April 17, and 
May 14, 2008, were received after issuance of the Draft EA, provided 
supplemental clarifying information, but did not have any impact on the 
Draft EA.

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. 
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

[[Page 35420]]

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 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 (reactor 
coolant) and 12.6 percent (secondary coolant) for I-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 limiting 
increase 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, 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.

[[Page 35421]]

Agencies and Persons Consulted

    In accordance with its stated policy, on June 11, 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, November 7, and December 3, 2007, January 10, 
29, and 31, February 21, 26, and 28, March 6, April 17, and May 14, 
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: http://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 and e-mail to [email protected].

    Dated at Rockville, Maryland, this 16th day of June, 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. E8-14147 Filed 6-20-08; 8:45 am]
BILLING CODE 7590-01-P