[Federal Register Volume 63, Number 121 (Wednesday, June 24, 1998)]
[Notices]
[Pages 34491-34493]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-16746]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-424 and 50-425]
Southern Nuclear Operating Company, Inc., et al.; Vogtle Electric
Generating Plant, Units 1 and 2; Environmental Assessment and Finding
of No Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of amendments to Facility Operating License Nos.
NPF-68 and NPF-81 issued to Southern Nuclear Operating Company, Inc.,
et al. (the licensee), for operation of the Vogtle Electric Generating
Plant (VEGP), Units 1 and 2, respectively, located in Burke County,
Georgia.
Environmental Assessment
Identification of the Proposed Action
The proposed action would change the common VEGP Technical
Specifications to allow an increase in the Unit 1 spent fuel storage
capacity from 288 to 1476 fuel assemblies. The increase in spent fuel
storage capacity is achieved by replacing the existing spent fuel
storage racks, a process referred to herein as ``reracking.'' The
proposed action is in accordance with the licensee's application for
license amendments dated September 4, 1997, as supplemented by letters
dated November 20, 1997, May 19 and June 12, 1998.
The Need for the Proposed Action
The VEGP spent fuel pools (SFPs) are operated as a single facility
and accept spent fuel from both Units 1 and 2. The VEGP Unit 2 spent
fuel pool has a storage capacity of 2098 fuel assemblies. Under current
conditions, the SFPs will lose the capacity for a full-core off-load
(193 fuel assemblies) in the year 2005. There are no independent
commercial spent fuel storage facilities operating in the U.S., nor are
there any domestic reprocessing facilities; therefore, the projected
loss of storage capacity in the VEGP SFPs would affect the licensee's
ability to operate VEGP. The proposed amendments are needed to ensure
the capability of full-core off-load until the year 2015.
Environmental Impacts of the Proposed Action
Radiological Impacts
VEGP has waste treatment systems designed to collect and process
waste that may contain radioactive material. The radioactive waste
treatment systems were evaluated in the ``Final Environmental Statement
Related to the Operation of Vogtle Electric Generating Plant,'' NUREG-
1087, March 1985. The SFP cooling and purification system is designed
to remove the decay heat generated by stored spent fuel assemblies and
to clarify and purify the water to permit unencumbered access to the
plant fuel storage area and maintain optical clarity of the SFP water.
Liquid Radioactive Waste
It is not expected that there will be a significant increase in the
liquid release of radionuclides from the plant as a result of the SFP
reracking modifications. The SFP cooling and purification system
operates as a closed system. The SFP demineralizer resin removes
soluble radioactive materials from the SFP water. A small increase in
activity on the filters and demineralizers may occur during the
installation of the new racks because of the more frequent fuel
shuffling and underwater pressure washing of the old racks during
removal. However, the amount of radioactivity released to the
environment as a result of the proposed reracking is expected to be
negligible.
Solid Radioactive Waste
The existing spent fuel racks in the VEGP Unit 1 SFP will be
removed from the site by a salvage company. After usable material has
been salvaged, the remainder will be volume reduced and disposed of at
the Barnwell, South Carolina, facility. In a worst-case scenario, with
no salvageable material and no volume reduction, the resulting material
would represent 44 percent of the expected solid waste volume
associated with VEGP Units 1 and 2 for 1998; however, this volume is
not significant when viewed over the 40-year operational lifetime of
the VEGP facility.
In addition to the spent fuel assemblies themselves, the only other
solid radioactive waste generated by the SFP is the SFP polisher resin,
which is used for water clarity. As indicated in the licensee's
submittal of September 4, 1997, these resins are replaced approximately
once per refueling cycle. No additional spent resins are expected to be
generated by the pool cleanup system as a result of the expanded spent
fuel storage capability; therefore, no significant increase in the
volume of solid radioactive waste associated with these resins is
expected with the proposed amendments.
Radioactive Material Released to the Atmosphere
The only radioactive gas of significance that could be attributable
to storing additional spent fuel assemblies for a longer period of
time, made possible as a result of the proposed reracking, would be the
noble gas radionuclide krypton-85 (Kr-85). Experience has demonstrated
that after spent fuel has decayed 4 to 6 months, there is no longer a
significant release of fission products, including Kr-85, from stored
spent fuel containing cladding defects. The licensee has stated that in
the past 2 years, the Kr-85 concentrations measured from the fuel
storage area ventilation release point have been negligible and the
licensee expects that enlarging the storage capacity of the SFP will
have no effect on the average annual quantities of Kr-85 released to
the atmosphere.
Iodine-131 released from spent fuel assemblies to the SFP water
will not be significantly increased as a result of the expansion of the
fuel storage capacity since the iodine-131 inventory in the fuel will
decay to negligible levels between refuelings.
Most of the tritium in the SFP water results from activation of
boron and lithium in the primary coolant during power operation. A
relatively small amount of tritium is produced during reactor operation
by the fission process within the reactor fuel. The subsequent
diffusion of the tritium through the fuel and cladding represents a
small contribution to the total amount of tritium in the SFP water.
Tritium releases from the fuel assemblies occur mainly during reactor
operation and, to a limited extent, shortly after shutdown. Thus,
expanding the SFP capacity will not increase the tritium concentration
in the SFP.
Most airborne releases of tritium and iodine from nuclear power
plants result during refuelings from evaporation of reactor coolant,
which contains tritium and iodine in higher concentrations than in the
SFP. The storage of additional spent fuel assemblies in the SFP is not
expected to significantly increase the SFP bulk water temperature, and,
therefore, evaporation rates from the SFP are not expected to
significantly increase. Consequently, it is not expected that there
will be any significant change in the annual release of tritium or
iodine as a result of the proposed modifications from that previously
evaluated in NUREG-1087.
[[Page 34492]]
Occupational Doses
The licensee estimates that the increased number of fuel assemblies
stored in the Unit 1 SFP may result in a small increase in doses in the
areas adjacent to the sides of the SFP, although it will not be enough
to change any existing radiation zone designations. To minimize any
potential dose rate increases from the increased storage of spent fuel,
the licensee plans to control the placement of freshly discharged fuel
so that it is not placed in SFP rack positions adjacent to the sides of
the SFP. Dose rates on the fuel pool level are primarily due to
radionuclides in the pool water. During normal operations, dose rates
in this area are generally 2.5 mrem/hr or less. The staff finds these
dose rates to be acceptable and in accordance with SFP dose rates at
other plants.
The licensee will constantly monitor the doses to the workers
during the reracking operation using electronic personnel dosimetry.
Each diver will be monitored using multiple teledosimetry devices.
These teledosimetry devices will transmit diver dose and dose rate data
that will be continuously monitored adjacent to the SFP. Cameras will
be used to monitor the movements of the divers. The licensee will use
continuous air samplers when there is a potential for airborne activity
in the SFP area during the modifications. In addition, the plant
effluent radiation monitoring system will monitor any gaseous releases.
The total occupational dose to plant workers as a result of the
reracking operation is estimated to be approximately 4.3 person-rem.
This dose estimate is based on the licensee's detailed review of the
anticipated work activities, their duration, and expected dose rates
associated with each of the activities related to the SFP reracking.
The upcoming reracking operation at Vogtle Unit 1 will follow detailed
procedures prepared with full consideration of as low as is reasonably
achievable (ALARA) principles. On the basis of its review of the
proposed action, the staff concludes that the Vogtle Unit 1 SFP rerack
modification can be performed in a manner that will ensure that doses
to workers will be maintained ALARA. The estimated dose of 4.3 person-
rem to perform the proposed SFP rerack is a small fraction of the
annual collective dose accrued at Vogtle and, therefore, the staff
finds this dose to be acceptable.
Uranium Fuel Cycle and Transportation
The environmental impacts on the uranium fuel cycle and
transportation resulting from the use of higher enrichment fuel and
extended irradiation were published in NUREG/CR-5009, ``Assessment of
the Use of Extended Burnup Fuels in Light Water Power Reactors,''
February 1988, and discussed in the staff's Environmental Assessment
and Finding of No Significant Impact published in the Federal Register
on February 29, 1988 (53 FR 6040). The staff concluded that no
significant adverse effects will be generated by increasing the burnup
levels as long as the maximum rod-average burnup level of any fuel rod
is no greater than 60 Gwd/MtU. The staff also stated that the
environmental impacts summarized in Tables S-3 and S-4 for a burnup
level of 33 Gwd/MtU are conservative and bound the corresponding
impacts for burnup levels up to 60 Gwd/MtU and uranium-235 enrichments
up to 5 weight percent. Since the proposed amendment does not involve
an increase in the enrichment or burnup of fuel utilized at VEGP, the
staff concludes that there is no significant radiological environmental
impact associated with the proposed expansion of the spent fuel storage
capacity at VEGP Unit 1 or with the uranium fuel cycle or
transportation.
Accident Considerations
In the Vogtle Final Safety Analysis Report, the licensee evaluated
the possible consequences of the following three hypothetical accidents
involving fuel in the SFP: a fuel-handling accident in the fuel-
handling building; a fuel-handling accident in the containment with the
airlock closed; and a fuel-handling accident in the containment with
the airlock open. The licensee reevaluated these hypothetical accidents
to determine the thyroid and whole-body doses at the exclusion area
boundary, in the low-population zone, and in the control room.
On the basis of the review of the licensee's reevaluation, the NRC
staff concludes that the proposed reracking of the Vogtle Unit 1 SFP
will not result in an increase in the doses from any of these
hypothetical accidents.
Nonradiological Impact
The proposed amendments do not modify land use at the site; no new
facilities or laydown areas are needed to support the rerack or
operation after rerack; therefore, the proposed amendments do not
affect land use or land with historical or archeological sites.
The increased spent fuel inventory results in a minor bulk pool
temperature increase. This minor increase in temperature results in a
minor increase in the pool water evaporation rate. The licensee's
submittal of September 4, 1997, indicates that the effects of the
increased temperature and evaporation rates are within the capacity of
the existing fuel-handling building heating, ventilation, and air
conditioning system. The total heat load from spent fuel cooling
dissipated to the environment represents 2.5 percent of the total
rejected plant heat.
The proposed action does not affect nonradiological plant
effluents, and no changes to the National Pollution Discharge
Elimination System permit are needed. The proposed action does not
result in any significant changes to land use or water use, or result
in any significant changes to the quantity or quality of effluents; no
effects on endangered or threatened species or on their habitat are
expected.
The proposed action will not change the method of generating
electricity or the method of handling any influents from the
environment or nonradiological effluents to the environment. Therefore,
no changes or different types of nonradiological environmental impacts
are expected as a result of the amendments.
Summary
The Commission has completed its evaluation of the proposed action.
The proposed action will not increase the probability or consequences
of accidents, no changes are being made in the types of any effluents
that may be released off site, and there is no significant increase in
the allowable individual or cumulative occupational or offsite
radiation exposure. Accordingly, the Commission concludes that there
are no significant radiological environmental impacts associated with
the proposed action.
With regard to potential nonradiological impacts, the proposed
action does involve features located entirely within the restricted
area as defined in 10 CFR Part 20. It does not affect nonradiological
plant effluents and has no other environmental impact. Accordingly, the
Commission concludes that there are no significant nonradiological
environmental impacts associated with the proposed action.
Alternatives to the Proposed Action
Since the Commission has concluded there are no significant
environmental impacts 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 staff
considered denial of the proposed action. Denial of
[[Page 34493]]
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 proposed action does not involve the use of any resources not
previously considered in NUREG-1087.
Agencies and Persons Consulted
In accordance with its stated policy, on May 26, 1998, the staff
consulted with the Georgia State official, Mr. J. Setzer of the Georgia
Department of Natural Resources, 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 the proposed action, see the
licensee's letter dated September 4, 1997, as supplemented by letters
dated November 20, 1997, May 19 and June 12, 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 Burke County Library, 412 Fourth
Street, Waynesboro, Georgia.
Dated at Rockville, Maryland, this 19th day of June 1998.
For the Nuclear Regulatory Commission.
Jacob I. Zimmerman,
Acting Director, Project Directorate II-2, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 98-16746 Filed 6-23-98; 8:45 am]
BILLING CODE 7590-01-P
