[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