[Federal Register Volume 65, Number 189 (Thursday, September 28, 2000)]
[Notices]
[Pages 58298-58299]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-24939]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-458]
Entergy Gulf States, Inc. and Entergy Operations, Inc.; River
Bend Station, Unit 1; Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an amendment to Facility Operating License No. NPF-47,
issued to Entergy Gulf States, Inc. and Entergy Operations, Inc. (EOI,
or the licensee) for operation of the River Bend Station, Unit 1 (RBS),
located in Saint Francisville, Louisiana.
Environmental Assessment
Identification of the Proposed Action
The proposed action would allow EOI to increase the maximum reactor
core power level from 2894 megawatts thermal (MWt) to 3039 MWt, which
is an increase of five percent of rated core thermal power for the RBS.
The proposed action is in accordance with EOI's application for
amendment dated July 30, 1999, as supplemented by letters dated April
3, May 9, July 18, and August 24, 2000.
Need for the Proposed Action
The proposed action permits an increase in the licensed core
thermal power from 2894 MWt to 3039 MWt and provides the flexibility to
increase the potential electrical output of RBS.
Environmental Impacts of the Proposed Action
EOI has submitted an environmental evaluation supporting the
proposed power uprate and provided a summary of its conclusions
concerning both the radiological and non-radiological environmental
impacts of the proposed action. Based on the NRC's independent analyses
and the evaluation performed by the licensee, the staff concludes that
the proposed increase in power is not expected to result in a
significant environmental impact.
Radiological Environmental Assessment
Radwaste Systems
The reactor coolant contains activated corrosion products, which
are the result of metallic materials entering the water and being
activated in the reactor region. Under power uprate conditions, the
feedwater flow increases with power and the activation rate in the
reactor region increases with power. The net result may be an increase
in the activated corrosion product production. However, the total
volume of processed waste is not expected to increase appreciably.
Non-condensible radioactive gas from the main condenser, along with
air inleakage, normally contains activation gases (principally N-16, O-
19 and N-13) and fission product radioactive noble gases. This is the
major source of radioactive gas (greater than all other sources
combined). These non-condensible gases, along with non-radioactive air,
are continuously removed from the main condensers which discharge into
the offgas system. The gaseous effluents will remain within the
original limits following implementation of power uprate.
EOI has concluded that the operation of the radwaste systems at RBS
will not be impacted by operation at uprated power conditions and the
slight increase in effluents discharged would continue to meet the
requirements of Part 20 of Title 10 of the Code of Federal Regulations
(10 CFR) and 10 CFR Part 50, Appendix I. Therefore, power uprate will
not appreciably affect the ability to process liquid or gaseous
radioactive effluents and there are no significant environmental
effects from radiological releases.
Dose Consideration
EOI evaluated the effects of power uprate on the radiation sources
within the plant and radiation levels during normal and post-accident
conditions. Post-operation radiation levels in most areas of the plant
are expected to increase by no more than the percentage increase in
power level. In a few areas near the spent fuel pool cooling system
piping and the reactor water piping, where accumulation of corrosion
product crud is expected, as well as near some liquid radwaste
equipment, the increase could be slightly higher. In this regard,
procedural controls are expected to compensate for increased radiation
levels. Occupational doses for normal operations will be maintained
within acceptable limits by the site as-low-as-reasonably-achievable
program.
Power uprate does not involve significant increases in the offsite
doses to the public from noble gases, airborne particulates, iodine,
tritium, or liquid effluents. A review of the normal radiological
effluent doses shows that, at the current power level, doses are less
than one percent of the doses allowed by Technical Specifications
(TSs). Present offsite radiation levels are a negligible portion of
background radiation. Therefore, the normal offsite doses are not
significantly affected by operation at the uprated power level and
remain below the limits of 10 CFR Part 20 and 10 CFR Part 50, Appendix
I.
The change in core inventory resulting from power uprate is
expected to increase post-accident radiation levels by no more than the
percentage increase in power level. The licensee reanalyzed the control
rod drop accident, the loss-of-coolant accident (LOCA), the fuel
handling accident, the instrument line break accident, and the main
steam line break accident for power uprate conditions. The slight
increase in the post-accident radiation levels has no significant
effect on the plant nor on the habitability of the control room
envelope, the Emergency Operations Facility, or the Technical Support
Center. Thus, the licensee has determined that access to areas
requiring post-accident occupancy will not be significantly affected by
power uprate. The licensee evaluated the whole body and thyroid doses
at the exclusion area boundary that might result from the postulated
design basis LOCA and determined that doses remain below established
regulatory limits. Therefore, the results of the radiological analyses
remain below the 10 CFR Part 100 guidelines and all radiological safety
margins are maintained.
[[Page 58299]]
Summary
The proposed power uprate will not significantly increase the
probability or consequences of accidents, will not involve any new
radiological release pathways, will not result in a significant
increase in occupational or public radiation exposure, and will not
result in significant additional fuel cycle environmental impacts.
Accordingly, the NRC staff concludes that there are no significant
radiological environmental impacts associated with the proposed action.
Non-Radiological Environmental Assessment
The licensee reviewed the non-radiological environmental impacts of
power uprate based on information submitted in the Environmental
Report, Operating License Stage, the NRC Final Environmental Statement
(FES), and the requirements of the Environmental Protection Plan. Based
on this review, the licensee concluded that the proposed uprate has no
significant effect on the non-radiological elements of concern and the
plant will be operated in an environmentally acceptable manner as
established by the FES. In addition, the licensee states that existing
Federal, State, and local regulatory permits presently in effect
accommodate power uprate without modification.
The safety-related standby service water (SSW) at RBS is drawn from
the ultimate heatsink (UHS), (e.g., the SSW cooling towers), where the
maximum calculated temperature due to the uprate does not exceed the
original maximum UHS temperature. As a result of power uprate to 105
percent of current licensed core power, there will be a slight increase
in the normal heat loads rejected to the plant service water system.
For normal operation, the maximum service water heat loads occur during
peak summer months. The licensee calculates that the maximum summer
discharge temperature for the service water system will remain below
the current TS limit of 88 deg.F. EOI determined that the effects of
power uprate on air and land resources are negligible. The aesthetics
of the physical plant and plant site, as well as actual land use, are
not changed or increased by power uprate. An increase in operational
consumption of natural resources is negligible and below the levels
previously evaluated for two unit operation. Finally, air quality and
noise levels remain the same as before the power uprate.
With regard to potential non-radiological impacts, the proposed
action does not change the method of operation at RBS or the methods of
handling effluents. No changes to land use would result and the
proposed action does not involve any historic sites. Therefore, no new
or different types of non-radiological environmental impacts are
expected. Accordingly, the NRC concludes that there are no significant
non-radiological environmental impacts associated with the proposed
action.
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 but would reduce the operational flexibility that
would be afforded by the proposed change. The environmental impacts of
the proposed action and the alternative action are not significantly
different.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the FES for RBS.
Agencies and Persons Consulted
In accordance with its stated policy, on August 15, 2000, the staff
consulted with the Louisiana State official, Prosanta Chowdhury,
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 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 July 30, 1999, as supplemented by letters dated
April 3, May 9, July 18, and August 24, 2000, which may be examined,
and/or copied for a fee, at the NRC's Public Document Room, located at
One White Flint North, 11555 Rockville Pike (first floor), Rockville,
Maryland. Publicly available records will be accessible electronically
from the ADAMS Public Library component on the NRC Web site, (the
Electronic Reading Room).
Dated at Rockville, Maryland this 22nd day of September 2000.
For the Nuclear Regulatory Commission.
John A. Nakoski,
Acting Chief, Section 1, Project Directorate IV & Decommissioning
Division of Licensing Project Management, Office of Nuclear Reactor
Regulation.
[FR Doc. 00-24939 Filed 9-27-00; 8:45 am]
BILLING CODE 7590-01-P