[Federal Register Volume 63, Number 169 (Tuesday, September 1, 1998)]
[Notices]
[Pages 46491-46493]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-23458]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-260 AND 50-296]
Tennessee Valley Authority Browns Ferry Nuclear Plant, Units 2
and 3; Environmental Assessment and Finding of no Significant Impact
Introduction
The U.S. Nuclear Regulatory Commission (NRC, or the Commission) is
considering issuance of an amendment to Facility Operating License Nos.
DPR-52 and DPR-68 issued to the Tennessee Valley Authority (TVA or the
licensee) for operation of the Browns Ferry Nuclear Plant (BFN) Units 2
and 3, located in Limestone County, Alabama.
Environmental Assessment
Identification of the Proposed Action
The proposed action would allow the licensee to increase allowed
core power level by 5 percent, from 3293 megawatt thermal (MWt) to the
uprated power level of 3458 MWt.
The proposed action is in accordance with the licensee's
application for amendment dated October 1, 1997, as supplemented
October 14, 1997; and March 16 and 20, April 1 and 28, May 1, 20 and
22, June 12, 17 and 26, and July 17, 24, and 31, 1998.
The Need for the Proposed Action
The proposed action is needed to allow the licensee to increase the
licensed core thermal power and the potential electrical output of each
BFN Units 2 and 3 by approximately 55 MWt and thus, providing
additional electric power to service TVA's grid. The proposed thermal
power uprate project is in accordance with the generic boiling water
reactor (BWR) power uprate program established by the General Electric
Company and approved by the NRC in a letter dated September 30, 1991.
Power uprate has been widely recognized by the industry as a safe and
cost-effective method to increase generating capacity. The proposed
power uprate will provide the licensee with additional operational
flexibility.
Environmental Impacts of the Proposed Action
The Commission has completed its evaluation of the proposed action
and concludes that no significant change in the environmental impact
can be expected for the proposed increase in power. On September 1,
1972, TVA issued a Final Environmental Statement (FES) which is based
on a total electrical
[[Page 46492]]
generation name plate rating of 3456 MWt.
Nonradiological Effects
Under normal operation, BFN uses a once-through circulating water
system to dissipate heat from the main turbine condensers. Water is
drawn from the Tennessee River by the plant intake system and is
discharged back to the river. In addition, BFN currently has four
mechanical draft cooling towers which can be operated to assist in heat
dissipation (helper mode) primarily during summer hot weather periods.
BFN has a National Pollutant Discharge Elimination System (NPDES)
permit issued by the State of Alabama that contains specific
requirements applicable to the nonradiological effluents released from
BFN. The licensee has evaluated the impact of power uprate on NPDES
limitations relating to effluent temperatures, cooling tower usages and
effects on biological species. The licensee has evaluated and
determined that post-accident effluent temperature from emergency
equipment cooling water systems and normal operating condition effluent
discharges from other plant systems such as yard drainage, station
sumps, and sewage treatment will not change as a result of the power
uprate. The licensee indicates that the proposed uprated power level
may result in approximately a 1 percent temperature increase of the
circulating water leaving the main condenser, a 5 percent increase in
the heat rejection to the Tennessee River, and may require additional
cooling tower usage during summer periods. The licensee states that as
a result of power uprate, cooling tower use would increase
approximately 12 percent. However, the impacts of the increase would
continue to be bounded by the FES. Based on its evaluation, the
licensee has concluded that the changes in discharges to the river as a
result of the power uprate will remain within the bounding conditions
established in the NPDES permit and no changes to the permit
requirements are needed as a result of the power uprate.
As part of its NPDES permit application in April 1994, the licensee
documented its biological monitoring program and the effect of thermal
discharge limitations on selected biological species. In that report,
the licensee concluded that operation of BFN has not had a significant
impact on the reproductive success of yellow perch and sauger, or the
overall indigenous community in Wheeler Reservoir. This conclusion is
not affected by the power uprate.
The proposed action would not change the method of generating
electricity at BFN Units 2 and 3 nor the methods of handling influents
from the environment or effluents to the environment. The licensee
indicates that power uprate does not require any plant modifications.
Therefore, no changes to land use or impacts to historical areas would
result from lay down areas. Therefore, no new or different types of
nonradiological environmental impacts are expected. The staff considers
that continued compliance with applicable Federal, State, and Local
agency requirements relating to environmental protection will preclude
any significant increase in nonradiological impacts over those
evaluated in the FES.
Radiological Effects
Gaseous and liquid effluents are produced during both normal
operation and abnormal operational events. The licensee has evaluated
the radiological effects of the proposed power uprate during both
normal operation and postulated accident conditions for gaseous and
liquid effluent releases.
The licensee evaluated the offsite radiation exposure to the
maximally exposed individual member of the general public for the
proposed uprate. Section 2.4, Table 2.4.3, of the FES dated September
1, 1972, projected doses due to radioactive materials released to the
environment during routine operations of the BFN units. The estimated
radiation exposure of the maximally exposed individual from radioactive
material in both liquid and gaseous effluents was 2.2 mrem/year total.
The estimated dose based on actual liquid and gaseous effluent releases
for the period 1994-1996 was 0.054 mrem/year. Although a 5 percent
increase in reactor power does not necessarily result in any increase
in effluents, the licensee projected the total body dose would increase
to 0.056 mrem/year. This projected dose is about 2 percent of the
applicable NRC limits in 10 CFR Part 50, Appendix I. Therefore, the
staff concludes that the actual releases at the BFN units will still
remain within the FES estimates and are not significantly above current
levels.
With respect to onsite radiation exposure, the licensee stated that
in-plant radiation levels will generally increase by no more than the
percentage increase in power level. The licensee stated that individual
worker exposures will be maintained within the acceptable limits by the
site as-low-as-reasonably-achievable program, by procedural controls
that compensate for increased radiation levels. The 5-year (1991-1996)
average collective dose at Browns Ferry was 202 person-rem per year per
reactor and 0.5 person-rem per MWe-year. (See NUREG-0713 Volume 18,
Occupational Radiation Exposure at Commercial Nuclear Power Reactors
and Other Facilities, 1996). This compares favorably with the average
collective dose for all BWRs of 306 person-rem per year per reactor and
0.5 person-rem per MWe-year. Considering a potential increase of 5
percent, onsite radiation exposure will not be significantly higher
than the current operation and will remain within the acceptable limits
of 10 CFR 20. Therefore, the staff concludes that operation at the
uprated power level will not significantly impact occupational
exposures.
Regarding radioactive waste production, the licensee stated that
the total volume of processed waste is not expected to increase
appreciably since the only significant increase in processed waste is
due to the slightly more frequent backwashes of the condensate
demineralizers. Based on this, the licensee concluded that the power
uprate would not have an adverse effect on the processing of liquid
radwaste. With regard to gaseous waste production, the licensee stated
that gaseous effluent releases through building vents are not expected
to increase significantly with power uprate, since the releases are
maintained within administratively controlled values that are not a
function of core power. The noncondensable radioactive gases exhausted
from the main condenser and discharged via the off gas system are the
major source of radioactive gases. The licensee stated that the
operation of the off gas equipment will continue to be within the
design parameters for the equipment. The staff concludes that operation
at the uprated power will not significantly affect the licensee's
ability to process radioactive wastes. Therefore, the staff concludes
that operation at the uprated power level will not significantly
increase the allowable occupational exposures.
Technical Specification (TS) 4.3 establishes spent fuel storage
design features to ensure that the fuel array in fully loaded fuel
racks remains subcritical and to prevent inadvertent draining of the
spent fuel pool. No changes to TS 4.3 were necessary for the uprate
condition. The design basis for the SFP system remains unchanged during
power uprate conditions. Therefore, the proposed action will not
significantly increase the probability or consequences of spent fuel
storage criticality accidents.
[[Page 46493]]
As discussed above, the projected dose due to power uprate is about
2 percent of the applicable NRC limits in 10 CFR Part 50, Appendix I
for offsite exposures, and will remain within the acceptable limits of
10 CFR 20 for occupational exposures. The actual releases at the BFN
units will also remain within the FES estimates. Thus, the amendment
does not significantly effect the amount or type of radiological plant
effluents, and has no other environmental impact. Therefore, the staff
concludes that continued compliance with applicable Federal, State, and
Local agency requirements relating to environmental protection will
preclude any significant radiological environmental impacts associated
with the proposed uprate. Accordingly, the Commission concludes that
there are no significant radiological environmental impacts associated
with the proposed action.
Alternatives to the Proposed Action
Since the Commission has concluded there is no significant
environmental impact associated with the proposed action, any
alternatives with equal or greater environmental impact need not be
evaluated. As an alternative to the proposed action, the NRC staff
considered denial of the proposed action (no action alternative).
Denial of the application would result in no change in current
environmental impacts and would reduce operational flexibility.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the FES dated September 1, 1972 for BFN Units
2 and 3.
Agencies and Persons Consulted
In accordance with its stated policy, on August 26, 1998, the NRC
staff consulted with the Alabama State official, Mr. Kirk Whatley of
the State Office of Radiation Control, regarding the environmental
impact of the proposed action. The State official had no comments.
Finding of no Significant Impact
Based upon the environmental assessment, the Commission concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the Commission has
determined not to prepare an environmental impact statement for the
proposed action.
For further details with respect to this action, see the
application for amendment dated October 1, 1997, as supplemented
October 14, 1997; and March 16 and 20, April 1 and 28, May 1, 20 and
22, June 12, 17 and 26, and July 17, 24, and 31, 1998, which are
available for public inspection at the Commission's Public Document
Room, the Gelman Building, 2120 L Street NW., Washington, DC and at the
local public document room located at the Athens Public Library, 405 E.
South Street, Athens, Alabama.
Dated at Rockville, Maryland, this 26th day of August 1998.
For the Nuclear Regulatory Commission.
Frederick J. Hebdon,
Director, Project Directorate II-3, Division of Reactor Projects--I/II,
Office of Nuclear Reactor Regulation.
[FR Doc. 98-23458 Filed 8-31-98; 8:45 am]
BILLING CODE 7590-01-P
