[Federal Register Volume 61, Number 14 (Monday, January 22, 1996)]
[Notices]
[Pages 1606-1607]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-702]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-213]
Connecticut Yankee Atomic Power Company; Haddam Neck Plant;
Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of an amendment to Facility Operating License No.
DPR-61, issued to Connecticut Yankee Atomic Power Company (CYAPCO, the
licensee), for operation of the Haddam Neck Plant, located in Middlesex
County, Connecticut.
Environmental Assessment
Identification of the Proposed Action
The proposed amendment will revise the Haddam Neck Technical
Specifications (TS) to delete TS Sections 1.38 and 1.39, ``Definitions,
Fuel Assembly Types,'' revise TS Sections 3/4.9.3, ``Refueling
Operations, Decay Time'' and 3/4.9.14, ``Refueling Operations, Spent
Fuel Pool--Reactivity Condition,'' replace TS Sections 5.6.1.1, ``Spent
Fuel,'' and 5.6.3, ``Capacity,'' and add a new TS Section 3/4.9.15,
``Refueling Operations, Spent Fuel Pool Cooling.'' The proposed action
is in accordance with the licensee's amendment request dated March 31,
1995, as supplemented November 14, 1995.
The Need for the Proposed Action
The proposed TS changes support a rerack of the spent fuel pool to
expand the spent fuel pool's storage capacity from 1168 assemblies to
1480 assemblies so as to accommodate a full-core-discharge through the
current validity date of the Haddam Neck Operating License (2007). The
Haddam Neck Plant received its provisional Operating License in June
1967. The original spent fuel pool capacity was 336 fuel assemblies. In
1975-1976, CYAPCO performed a rerack to increase the capacity of the
spent fuel pool from 368 to 1172 fuel assemblies. The licensee
believed, at that time, that the increase to 1172 fuel assemblies would
provide sufficient space until the mid-1990's, at which time a fuel
reprocessing facility would be in operation. At the present time,
CYAPCO has contracted with the U.S. Department of Energy (DOE) to begin
taking delivery of its spent fuel in 1998. However, DOE has indicated
that all of CYAPCO's spent fuel may remain at the site until a
repository is operational or until some other facility is constructed
under the Nuclear Waste Policy Act. CYAPCO does not believe that such a
facility will be operational in time for the Haddam
[[Page 1607]]
Neck Plant to avoid loss of full-core-discharge capability. CYAPCO
evaluated spent fuel storage alternatives that have been licensed by
the NRC and that are currently feasible for use at the Haddam Neck
site. The result of this evaluation is that a rerack of the spent fuel
pool is the most cost-effective alternative. This TS change is
necessary for support of the rerack of the Haddam Neck spent fuel pool.
Environmental Impacts of the Proposed Action
The Commission has completed its evaluation of the proposed
revision to the TS. The staff has concluded the following for the
various design considerations of the rerack of the Haddam Neck spent
fuel pool (SFP):
1. The staff finds the criticality aspects of the proposed increase
in the storage capacity of the Haddam Neck spent fuel pool storage
racks are acceptable and meet the requirements of General Design
Criterion 62 for the prevention of criticality in fuel storage and
handling.
2. The staff has reviewed the licensee's rationale for SPF cooling,
performed confirmatory decay heat load calculations, reviewed the
effects of SFP boiling, and the heavy load capability of the SFP
building cranes, and concludes that the above issues relating to the
increase in the SFP storage capacity from 1168 to 1480 fuel assemblies
are acceptable.
3. The staff concludes that the materials selected for the Haddam
Neck Plant spent fuel rack modifications have been carefully and
satisfactorily thought out and no occurrence of degradation of the
material selected for the rack modification is expected. The racks are
constructed from a type 304 stainless steel and fabricated according to
an approved ASME specification. The choice of Boral as a poison
material will ensure reliable criticality control. The design of the
fuel racks accounts for the possibility of hydrogen production by
corrosion of Boral and provides ventilation outlets that would relieve
hydrogen pressure which otherwise could cause deformation of the rack
cells.
4. The Boral Surveillance Program will provide a reliable method of
assessing the potential degradation of Boral panels which are exposed
to radiation in the spent fuel area over time. The staff concludes that
the licensee's selection of structural, welding and poison materials
meets current industry and regulatory standards. These materials are
acceptable for construction of the new rack modules because they meet
the requirements of General Design Criterion 62, as it applies to
providing physical systems for prevention of criticality in fuel
storage.
5. The staff concludes that CYAPCO's structural analysis and design
of the spent fuel rack modules and the spent fuel pool structure are
adequate to withstand the effects of the required loads. The analysis
and design are in compliance with the current licensing basis set forth
in the Updated Final Safety Analysis Report and applicable provisions
of the Standard Review Plan, and are therefore acceptable.
The TS change will not increase the probability or consequences of
accidents, no changes are being made in the types of any effluents that
may be released offsite, and there is no significant increase in the
allowable individual or cumulative occupational radiation exposure.
Therefore, the Commission concludes that there are no significant
radiological environmental impacts associated with this proposed TS
amendment.
With regard to potential nonradiological impacts, the proposed
amendment involves 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. Therefore, the
Commission concludes that there are no significant nonradiological
environmental impacts associated with the proposed amendment.
Alternatives to the Proposed Action
Since the Commission has concluded there is no measurable
environmental impact associated with the proposed amendment, any
alternatives with equal or greater environmental impact need not be
evaluated. The principal alternative to the amendment would be to deny
the amendment request. Such action would not enhance the protection of
the environment and would result in unjustified cost to the licensee.
Alternative Use of Resources
This action does not involve the use of resources not considered
previously in the Final Environmental Statement for the Haddam Neck
Plant.
Agencies and Persons Consulted
In accordance with its stated policy, on January 5, 1996, the staff
consulted with the Connecticut State official, Alan B. Wang of the U.
S. Nuclear Regulatory Commission, 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 amendment.
For further details with respect to this proposed action, see the
licensee's letter dated March 31, 1995, as supplemented by letter dated
November 14, 1995, 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 Russell Library, 123 Broad Street, Middletown Connecticut.
Dated at Rockville, Maryland, this 11th day of January 1996.
For the Nuclear Regulatory Commission.
Phillip McKee,
Director, Project Directorate I-3, Division of Reactor Projects--I/II,
Office of Nuclear Reactor Regulation.
[FR Doc. 96-702 Filed 1-19-96; 8:45 am]
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