[Federal Register Volume 61, Number 197 (Wednesday, October 9, 1996)]
[Notices]
[Pages 52959-52960]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-25903]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-317 and 50-318]
Baltimore Gas and Electric Company: Calvert Cliffs Nuclear Power
Plant, Unit Nos. 1 and 2, Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of an exemption from certain requirements of its
regulations for Facility Operating License Nos. DPR-53 and DPR-69,
issued to Baltimore Gas and Electric Company (the licensee), for
operation of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2,
located in Calvert County, Maryland.
Environmental Assessment
Identification of Proposed Action
The proposed action would exempt the licensee from the requirements
of 10 CFR 70.24, which requires a monitoring system that will energize
clearly audible alarms if accidental criticality occurs in each area in
which special nuclear material is handled, used, or stored. The
proposed action would also exempt the licensee from the requirements of
10 CFR 70.24(a)(3) to maintain emergency procedures for each area in
which this licensed special nuclear material is handled, used, or
stored to ensure that all personnel withdraw to an area of safety upon
the sounding of the alarm and to conduct drills and designate
responsible individuals for such emergency procedures.
The proposed action is in accordance with the licensee's
application for exemption dated August 19, 1996.
The Need for the Proposed Action
Power reactor license applicants are evaluated for the safe
handling, use, and storage of special nuclear materials. The proposed
exemption from criticality accident requirements is based on the
original design for radiation monitoring at Calvert Cliffs. Exemptions
from the requirements of 10 CFR 70.24(a) ``Criticality Accident
Requirements'' were granted in the Special Nuclear Material (SNM)
licenses for each unit as part of the 10 CFR Part 70 license. However,
with the issuance of the Part 50 license this exemption expired because
it was inadvertently omitted in that license. Therefore, the exemption
is needed to clearly define the design of the plant as evaluated and
approved for licensing.
Environmental Impacts of the Proposed Action
The NRC staff has completed its evaluation of the proposed action
and
[[Page 52960]]
concludes that there is no significant environmental impact if the
exemption is granted. Inadvertent or accidental criticality will be
precluded through compliance with the Calvert Cliffs Technical
Specifications, the geometric spacing of fuel assemblies in the new
fuel storage facility and spent fuel storage pool, and administrative
controls imposed on fuel handling procedures.
Inadvertent or accidental criticality in the reactor vessel is
prevented through compliance with the facility Technical
Specifications, including reactivity requirements (e.g., shutdown
margin limits and control rod movement limits), instrumentation
requirements (e.g., power and radiation monitors), and control on
refueling operations (e.g., refueling boron concentration and source
range monitor requirements). In addition, the operators' attention is
directed toward instruments monitoring behavior of the nuclear fuel in
the reactor, assuring that the facility is operated in a manner that
precludes inadvertent criticality.
Special nuclear material, as nuclear fuel, is stored in the spent
fuel pool, the new fuel storage racks, and the Independent Spent Fuel
Storage Installation. The spent fuel pool is used to store irradiated
fuel under water after its discharge from the reactor, and new fuel
prior to loading into the reactor. The Independent Spent Fuel Storage
Installation utilizes dry canisters to store spent fuel. Dry fuel
storage facilities are specifically excluded from criticality
monitoring in accordance with 10 CFR 72.124(c).
The spent fuel pool is designed to store the fuel in a geometric
array using a solid neutron absorber that precludes criticality. The
effective neutron multiplication factor, Keff is maintained less
than or equal to 0.95 by the solid neutron absorber. Although soluble
boron is maintained in the spent fuel pool, no credit is taken for it
in determining Keff.
The new fuel storage racks may be used to receive and store new
fuel in a dry condition upon arrival on site and prior to loading in
the reactor or spent fuel pool. The maximum enrichment of 5.0 wt% U-235
for the new fuel assemblies results in a maximum effective
multiplication factor of 0.89 at a water density of 1.0 gm/cc (full
flood), and a multiplication factor of less than 0.89 for aqueous foam.
Nuclear fuel is moved between the new fuel storage racks, the
reactor vessel, the refueling pool, and the spent fuel pool to
accommodate refueling operations. In addition, fuel is moved into the
facility and within the reactor vessel, or within the spent fuel pool.
In all cases, fuel movements are procedurally controlled and designed
to preclude conditions involving criticality concerns. In addition, the
Technical Specifications also preclude certain movements over the spent
fuel pool to prevent an inadvertent criticality. Previous accident
analyses have demonstrated that a fuel handling accident (i.e., a
dropped fuel assembly) will not create conditions which could result in
inadvertent criticality. Additionally, the Emergency Response Plan
contains provisions for coping with unusual events such as a dropped
fuel assembly.
In summary, exemptions from the requirements of 10 CFR Part 70,
Section 70.24 approved by the NRC in connection with the SNM licenses
for Calvert Cliffs Unit Nos. 1 and 2 were based upon NRC's finding that
the inherent features associated with the storage and inspection of
unirradiated fuel established good cause for granting the exemption and
that granting such a exemption at this time will not endanger public
life or property or the common defense and security and is otherwise in
the public interest. The training provided to all personnel involved in
fuel handling operations, the administrative controls, the Technical
Specifications on new and spent fuel handling and storage, and the
design of the new and spent fuel storage racks in place preclude
inadvertent or accidental criticality. Since the facilities, storage,
and inspection and procedures currently in place are consistent with
those in place at the time the exemptions were granted in connection
with the SNM licenses, an exemption from 10 CFR 70.24 is appropriate.
The proposed exemption will not affect radiological plant effuents
nor cause any significant occupational exposures. Only a small amount,
if any, of radioactive waste is generated during the receipt and
handling of new fuel (e.g., smear papers or contaminated packaging
material). The amount of waste would not be changed by the exemption.
With regard to potential nonradiological impacts, the proposed
exemption involves systems located 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 that there is no measurable
environmental impact associated with the proposed action, any
alternatives with equal or greater environmental impact need not be
evaluated. The principal alternative would be to deny the requested
exemption. The environmental impacts of the proposed action and the
alternative action are similar.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement related to
the operation of Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2,
dated April 1973.
Agencies and Persons Consulted
In accordance with its stated policy, on September 18, 1996, the
staff consulted with the Maryland State Official, Mr. Richard I. McLean
of the Maryland 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 August 19, 1996, which is 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 Calvert County Library, Prince Frederick,
Maryland 20678.
Dated at Rockville, Maryland, this 3rd day of October 1996.
For the Nuclear Regulatory Commission.
Alexander W. Dromerick,
Senior Project Manager, Project Directorate I-1, Division of Reactor
Projects-I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 96-25903 Filed 10-8-96; 8:45 am]
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