[Federal Register Volume 76, Number 162 (Monday, August 22, 2011)]
[Notices]
[Pages 52356-52357]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-21340]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0188; Docket No. 50-315]


Indiana Michigan Power Company, Donald C. Cook Nuclear Plant, 
Unit 1; Environmental Assessment and Finding of No Significant Impact

    The U.S. Nuclear Regulatory Commission (NRC or the Commission) is 
considering issuance of an exemption and an amendment to Renewed 
Facility Operating License No. NPF-58 issued to Indiana Michigan Power 
Company (the licensee), for operation of Donald C. Cook Nuclear Plant, 
Unit 1 (DCCNP-1), located in Berrien County, Michigan, in accordance 
with Title 10 of the Code of Federal Regulations (10 CFR) part 50, 
Sec.  50.90. In accordance with 10 CFR 51.21, the NRC performed an 
environmental assessment documenting its findings. The NRC concluded 
that the proposed actions would have no significant environmental 
impact.

Environmental Assessment

Identification of the Proposed Actions

    The proposed actions would issue an exemption from 10 CFR 50.46 
regarding fuel cladding material, and revise the Technical 
Specifications document, which is part of the Renewed Facility 
Operating Licenses, to permit use of Optimized ZIRLO\TM\ fuel to a peak 
road average burnup limit of 62 gigawatt-days per metric ton uranium 
(GWD/MTU).
    The proposed actions are in accordance with the licensee's 
application dated December 16, 2010.

The Need for the Proposed Actions

    The proposed actions to issue an exemption to the fuel cladding 
requirement of 10 CFR 50.46, and to amend the Technical Specifications 
to permit use of Optimized ZIRLO\TM\ fuel to a peak rod average burnup 
limit of 62 GWD/MTU would allow for more effective fuel management. If 
the exemption and amendment are not approved, the licensee will not be 
provided the opportunity to use Optimized ZIRLO\TM\ fuel design with a 
peak rod average burnup as high as 62 GWD/MTU; the licensee would thus 
lose fuel management flexibility.

Environmental Impacts of the Proposed Actions

    In this environmental assessment regarding the impacts of the use 
of Optimized ZIRLO\TM\ fuel with the possible burnup up to 62 GWD/MTU, 
the Commission is relying on the results of the updated study conducted 
for the NRC by the Pacific Northwest National Laboratory (PNNL), 
entitled ``Environmental Effects of Extending Fuel Burnup Above 60 GWD/
MTU'' (NUREG/CR-6703, PNNL-13257, January 2001). Environmental impacts 
of high burnup fuel up to 75 GWD/MTU were evaluated in the study, but 
some aspects of the review were limited to evaluating the impacts of 
the extended burnup up to 62 GWD/MTU, because of the need for 
additional data on the effect of extended burnup on gap release 
fractions. All the aspects of the fuel-cycle were considered during the 
study, from mining, milling, conversion, enrichment and fabrication 
through normal reactor operation, transportation, waste management, and 
storage of spent fuel.
    The amendment and exemption would allow DCCNP-1 to use Optimized 
ZIRLO\TM\ fuel up to a burnup limit of 62 GWD/MTU. The NRC staff has 
completed its evaluation of the proposed actions and concludes that 
such changes would not adversely affect plant safety, and would have no 
adverse effect on the probability of any accident. For the accidents 
that involve damage or melting of the fuel in the reactor core, fuel 
rod integrity has been shown to be unaffected by extended burnup under 
consideration; therefore, the probability of an accident will not be 
affected by fuel burnup to 62 GWD/MTU. For the accidents in which the 
reactor core remains intact, the increased burnup may slightly change 
the mix of fission products that could be released in the event of a 
serious accident, but because the radionuclides contributing most to 
the dose are short-lived, increased burnup would not have an effect on 
the consequences of a serious accident beyond the consequences of 
previously evaluated accident scenarios. Thus, there will be no 
significant increase in projected dose consequences of postulated 
accidents associated with fuel burnup up to 62 GWD/MTU, and doses will 
remain well below regulatory limits.
    Regulatory limits on radiological effluent releases are independent 
of burnup. The requirements of 10 CFR part 20, 10 CFR 50.36a, and 
Appendix I to 10 CFR part 50 ensure that routine releases of gaseous, 
liquid or solid radiological effluents to unrestricted areas is kept 
``As Low As is Reasonably Achievable.'' Therefore, the NRC staff 
concludes that during routine operations, there would be no significant 
increase in the amount of gaseous radiological effluents released into 
the environment as a result of the proposed actions, nor will there be 
a significant increase in the amount of liquid radiological effluents 
or solid radiological effluents released into the environment.
    The proposed actions will not change normal plant operating 
conditions (i.e., no changes are expected in the fuel handling, 
operational, or storing processes). The fuel storage and handling, 
radioactive waste, and other systems which may contain radioactivity 
are designed to assure adequate safety under normal

[[Page 52357]]

conditions. There will be no significant changes in radiation levels 
during these evolutions, and no significant increase in the allowable 
individual or cumulative occupational radiation exposure is expected to 
occur.
    The use of Optimized ZIRLO\TM\ fuel with a burnup limit of 62 GWD/
MTU will not change the potential environmental impacts of incident-
free transportation of spent nuclear fuel or the accident risks 
associated with spent fuel transportation if the fuel is cooled for 5 
years after being discharged from the reactor. A PNNL report for the 
NRC (NUREG/CR-6703, January 2001) concluded that doses associated with 
incident-free transportation of spent fuel with burnup to 75 GWD/MTU 
are bound by the doses given in 10 CFR 51.52, Table S-4 for all regions 
of the country, based on the dose rates from the shipping casks being 
maintained within regulatory limits. Increased fuel burnup will 
decrease the annual discharge of fuel to the spent fuel pool which will 
postpone the need to remove spent fuel from the pool.
    NUREG/CR-6703 determined that no increase in environmental effects 
of spent fuel transportation accidents is expected as a result of 
increasing fuel burnup to 75 GWD/MTU.
    Based on the nature of the amendment, the proposed actions do not 
result in changes to land use or water use, or result in changes to the 
quality or quantity of non-radiological effluents. No changes to the 
National Pollution Discharge Elimination System permit are needed. No 
effects on the aquatic or terrestrial habitat in the vicinity or the 
plant, or to threatened, endangered, or protected species under the 
Endangered Species Act, or impacts to essential fish habitat covered by 
the Magnuson-Stevens Act are expected. There are no impacts to the air 
or ambient air quality. There are no impacts to historic and cultural 
resources. There would be no noticeable effect on socioeconomic 
conditions in the region. Therefore, no changes or different types of 
non-radiological environmental impacts are expected as a result of the 
proposed actions. Accordingly, the NRC concludes that there are no 
significant environmental impacts associated with the proposed actions.
    For more detailed information regarding the environmental impacts 
of extended fuel burnup, please refer to the study conducted by PNNL 
for the NRC, entitled ``Environmental Effects of Extending Fuel Burnup 
Above 60 GWD/MTU'' (NUREG/CR-6073, PNL-13257, January 2001, Agencywide 
Documents Access and Management System (ADAMS) Accession No. 
ML010310298). The details of the NRC staff's Safety Evaluation will be 
issued concurrently with the amendment.

Environmental Impacts of the Alternatives to the Proposed Actions

    As an alternative to the proposed action, the NRC staff considered 
denial of the proposed actions (i.e., the ``no-action'' alternative). 
Denial of the application would result in no change in current 
environmental impacts. Thus, the environmental impacts of the proposed 
actions and the alternative action are similar.

Alternative Use of Resources

    The action does not involve the use of any different resources than 
those previously considered in the Final Environmental Statement for 
Donald C. Cook Nuclear Plant, Unit 1, or the Generic Environmental 
Impact Statement for License Renewal of Nuclear Plants: Regarding 
Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2--Final Report (NUREG-
1437, Supplement 20), dated May 2005.

Agencies and Persons Consulted

    In accordance with its stated policy, on July 14, 2011, the NRC 
staff consulted with the Michigan State official regarding the 
environmental impact of the proposed action. The State officials had no 
comments.

Finding of No Significant Impact

    On the basis of the environmental assessment, the NRC staff 
concludes that the proposed actions will not have a significant effect 
on the quality of the human environment. Accordingly, the NRC staff 
determined not to prepare an environmental impact statement for the 
proposed action.
    For further details with respect to the proposed actions, see the 
licensee's letter dated October 29, 2009 (ADAMS Accession No. 
ML093140092). Documents may be examined, and/or copied for a fee, at 
the NRC's Public Document Room (PDR), located at One White Flint North, 
Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland. Publicly available records will be accessible electronically 
from the ADAMS Public Electronic Reading Room on the Internet at the 
NRC Web site, http://www.nrc.gov/reading-rm/adams.html.
    Persons who do not have access to ADAMS or who encounter problems 
in accessing the documents located in ADAMS should contact the NRC PDR 
Reference staff by telephone at 1-800-397-4209 or 301-415-4737, or send 
an e-mail to <a href="/cdn-cgi/l/email-protection#c8b8acbae6baadbba7bdbaabad88a6baabe6afa7be"><span class="__cf_email__" data-cfemail="08786c7a267a6d7b677d7a6b6d48667a6b266f677e">[email protected]</span></a>.

    Dated at Rockville, Maryland, this 11th day of August, 2011.

    For the Nuclear Regulatory Commission.
Peter S. Tam,
Senior Project Manager, Plant Licensing Branch III-1, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2011-21340 Filed 8-19-11; 8:45 am]
BILLING CODE 7590-01-P


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