[Federal Register Volume 60, Number 176 (Tuesday, September 12, 1995)]
[Notices]
[Pages 47402-47403]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-22613]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-287 and 50-388]
Pennsylvania Power & Light Company, Susquehanna Steam Electric
Station, Units 1 and 2; Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuing an amendment to Susquehanna Steam Electric Station,
Units 1 and 2, Technical Specifications to permit the implementation of
an increase in the allowable exposure of Siemens' 9 x 9-2 fuel from 40
GWD/MTU to 45 GWD/MTU. Pennsylvania Power and Light Company (PP&L) (the
licensee), on May 31, 1994, submitted to the Commission for review,
Topical Report PL-NF-94-005-P, ``Technical Basis for SPC 9 x 9-2
Extended Fuel Exposure at Susquehanna SES.'' This report provided a
technical justification for the increased fuel burnup and the staff
subsequently approved the report as indicated in its letter to PP&L
dated December 15, 1994.
Environmental Assessment
Identification of the Proposed Action
The proposed action would amend the Susquehanna Steam Electric
Station (SSES), Units 1 and 2, Technical Specifications (TS) to permit
the implementation of an increase in the allowable exposure of Siemens'
9 x 9-2 fuel from 40 GWD/MTU to 45 GWD/
[[Page 47403]]
MTU. The proposed action is in accordance with the licensee's
application for amendment dated February 2, 1995.
The Need for the Proposed Action
NRC approval of this TS change, as applied to the Unit 1, Cycle 9,
and Unit 2, Cycle 8, will establish a new, higher fuel burnup rod-
average limit of 45 MWD/MTU and will permit the licensee to continue to
operate the plant through the end of each of these specified cycles,
exceeding the current fuel burnup limit of 40 GWD/MTU, without
affecting the safe operation of each reactor.
Environmental Impacts of the Proposed Action
The Commission completed its evaluation of the proposed action and
the above referenced topical report and found it to be acceptable. In
addition the TS changes implementing the higher fuel burnup limit have
also been found to be acceptable. The safety considerations associated
with extended irradiation of nuclear fuel have been evaluated by the
NRC staff and the staff has concluded that such changes would not
adversely affect plant safety. The proposed changes have no adverse
affect on the probability of any accident. The increased burnup may
slightly change the mix of fission products that might be released in
the event of a serious accident, but such changes would not
significantly affect the consequences of serious accidents. Routine
radiological effluents are not affected. As a result, there is no
increase in individual or cumulative radiation exposure.
The environmental impacts of transportation resulting from the use
of higher enrichment and extended irradiation are discussed in the
staff assessment entitled, ``NRC Assessment of the Environmental
Effects of Transportation Resulting from Extended Fuel Enrichment and
Irradiation.'' This assessment was published in the Federal Register on
August 11, 1988 (53 FR 30355), as corrected on August 24, 1988 (53 FR
32322), in connection with the Shearon Harris Nuclear Power Plant, Unit
1: Environmental Assessment and Finding of No Significant Impact. As
indicated therein, the environmental cost contribution of an increase
in fuel enrichment of up to 5 weight percent U-235 and irradiation
limits of up to 60 Gigawatt Days per Metric Ton (GWD/MT) are either
unchanged, or may in fact be reduced from those summarized in Table S-4
as set forth in 10 CRF 51.52(c). These findings are applicable to the
proposed increase in the increase in the allowable exposure of Siemens'
9 x 9-2 fuel for the Susquehanna units. Accordingly, the Commission
concludes that this proposed action would result in no significant
radiological environmental impact.
With regard to potential nonradiological impacts, the proposed
change will in no way affect environs located outside 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 change in the fuel
exposure limit.
Alternatives to the Proposed Action
Since the Commission has concluded there is no measurable
environmental impact 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 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
This action does not involve the use of any resources not
previously considered in the Final Environmental Statement for the
Susquehanna Steam Electric Station, Units 1 and 2.
Agencies and Persons Consulted
In accordance with its stated policy, on July 7, 1995, the staff
consulted with the Pennsylvania State official, David Ney of the
Department of Radiation Protection, 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 February 2, 1995, 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 Osterhout Free Library, Reference
Department, 71 South Franklin Street, Wilkes Barre, Pennsylvania 18701.
Dated at Rockville, Maryland, this 5th day of September 1995.
For the Nuclear Regulatory Commission.
John Stolz,
Director, Project Directorate I-2, Division of Reactor Projects--I/II,
Office of Nuclear Reactor Regulation.
[FR Doc. 95-22613 Filed 9-11-95; 8:45 am]
BILLING CODE 7590-01-P
