[Federal Register Volume 81, Number 51 (Wednesday, March 16, 2016)]
[Notices]
[Pages 14135-14139]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-05955]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-010, 50-237, 50-249, and 72-37; NRC-2016-0046]
Exelon Generation Company, LLC; Dresden Nuclear Power Station,
Units 1, 2, and 3; Independent Spent Fuel Storage Installation
AGENCY: Nuclear Regulatory Commission.
ACTION: Exemption; issuance.
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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an
exemption from certain requirements regarding the storage of a thoria
rod canister in response to a request submitted by Exelon Generation
Company, LLC (EGC) on January 29, 2015, for its general license to
operate an independent spent fuel storage installation (ISFSI) at the
Dresden Nuclear Power Station (DNPS). This exemption would permit EGC
to load and store the DNPS Unit 1 thoria rod canister containing 18
DNPS Unit 1 thoria rods in a Holtec International, Inc., HI-STORM 100
multi-purpose canister (MPC)-68M using Certificate of Compliance (CoC)
No. 1014, Amendment No. 8, Rev. 1.\1\
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\1\ The licensee's application referred to Amendment 8; since
that time, Amendment 8 has been revised. (On February 16, 2016,
Amendment 8, Rev. 1 to CoC 1014 became effective.) The revision does
not impact the exemption request that is the subject of this
exemption because none of the changes in the revision revised the
thoria contents or the physical characteristics of the storage cask.
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DATES: March 16, 2016.
ADDRESSES: Please refer to Docket ID NRC-2016-0046 when contacting the
NRC about the availability of information regarding this document. You
may obtain publicly-available information related to this document
using any of the following methods:
Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0046. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. For
the convenience of the reader, the ADAMS accession numbers are provided
in a table in the ``Availability of Documents'' section of this
document.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Bernard White, Office of Nuclear
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission,
Washington DC 20555-0001; telephone: 301-415-6577; email:
[email protected].
SUPPLEMENTARY INFORMATION:
I. Background
Dresden Unit 1 produced power commercially from 1960 to October 31,
1978. The plant shut down in October 1978 and is currently in SAFSTOR.
The decommissioning plan was approved in September 1993. No significant
dismantlement activities are underway. Isolation of Units 1, 2, and 3
is complete.
Consistent with subpart K of part 72 of title 10 of the Code of
Federal Regulations (10 CFR), a general license is issued for the
storage of spent fuel in an ISFSI at power reactor sites to persons
authorized to possess or operate nuclear power reactors under 10 CFR
part 50. EGC is currently authorized to store spent fuel at the DNPS
ISFSI under the 10 CFR part 72 general license provisions. The DNPS
ISFSI is currently loading and storing spent fuel in Holtec HI-STORM
100 storage casks, approved by the NRC under CoC No. 1014.
II. Request/Action
By letter dated January 29, 2015, as supplemented on June 8, 2015,
EGC submitted a request for an exemption from 10 CFR 72.212(b)(3) and
the portion of 10 CFR 72.212(b)(11) that requires compliance with the
terms, conditions, and specifications of CoC No. 1014, Amendment No. 8,
for the Holtec HI-STORM 100 with the MPC-68M, to the extent necessary
for EGC to load and store one DNPS Unit 1 thoria rod canister
containing 18 DNPS Unit 1 thoria rods. Upon review, the NRC added the
following requirements for the proposed action pursuant to its
authority under 10 CFR 72.7: 10 CFR 72.212(a)(2), which limits storage
of spent fuel in casks approved under part 72; 72.212(b)(5)(i), which
states a ``cask, once loaded with spent fuel . . . will conform to the
terms, conditions and specifications of a CoC or an amended CoC listed
in Sec. 72.214''; and 10 CFR 72.214, ``List of approved spent fuel
storage casks.''
III. Discussion
Pursuant to 10 CFR 72.7, the Commission may, upon application by
any interested person or upon its own initiative, grant such exemptions
from the requirements of the regulations of 10 CFR part 72 as it
determines are authorized by law and will not endanger life or property
or the common defense and security, and are otherwise in the public
interest.
A. Authorized by Law
This exemption would permit the applicant to load and store the
DNPS Unit 1 thoria rod canister containing 18 DNPS Unit 1 thoria rods
in the HI-STORM 100 MPC-68M CoC 1014, Amendment No. 8, Rev. 1, which
otherwise would not permit the storage of thoria rods. The provisions
from which the NRC is granting the exemption require the licensee to
comply with the terms, conditions, and specifications of the CoCs for
the approved cask model it uses. Section 72.7 allows the Commission to
grant exemptions from the requirements of 10 CFR part 72 if the
exemption is authorized by law, will not endanger life or property or
the common defense
[[Page 14136]]
and security, and is otherwise in the public interest. As explained in
the following discussion, the proposed exemption will not endanger life
or property, or the common defense and security, and is otherwise in
the public interest. Issuance of this exemption is consistent with the
Atomic Energy Act of 1954, as amended, and not otherwise inconsistent
with NRC's regulations or other applicable laws. Therefore, issuance of
the exemption is authorized by law.
B. Will Not Endanger Life or Property or the Common Defense and
Security
Approval of this exemption request will allow EGC to load and store
the 18 thoria rods in the DNPS Unit 1 thoria rod canister within a
Holtec HI-STORM 100 MPC-68M. As discussed in the following section, the
NRC staff finds that EGC's proposal to load and store thoria rods is
acceptable and will not endanger life or property or common defense and
security.
Review of the Requested Exemption
The addition of the MPC-68M to the list of approved storage cask
designs for the Holtec HI-STORM 100 system was reviewed previously and
approved by the NRC. The CoC and safety evaluation report (SER) for
Amendment 8 were issued on May 10, 2012, corrected on November 12,
2012, and revised on February 16, 2016. Amendment No. 8 added the MPC-
68M canister, two new boiling water reactor (BWR) fuel assembly/array
classes, a new pressurized-water reactor fuel assembly/array class, and
revised Condition No. 3 in the certificate to include leak testing of
the confinement boundary base material in addition to confinement
welds. Amendment 8 also made other administrative changes. Thoria rods/
assemblies were not considered in Amendment No. 8 for the MPC-68M,
however they have been approved for storage in the MPC-68, MPC-68F and
MPC-68FF in Amendment No. 1.
The applicant stated that the design characteristics of the thoria
rods in the exemption request are the same as those approved for
storage in the MPC-68, MPC-68F and MPC-68FF. The characteristics of
these rods are specified in CoC No. 1014, Amendment No. 8, Revision No.
1, Appendix B, Table 2.1-1, Section II, ``MPC MODEL: MPC-68F,'' Item
A.7 and Section III, ``MPC MODEL: MPC-68 and MPC-68FF,'' Item A.3. In
addition, the applicant cited the Safety Analysis Report (SAR) for CoC
No. 1014, Amendment No. 8, and the NRC staff's corresponding SER dated
May 10, 2012, which documented the NRC staff's basis for approval of
Amendment No. 8, to support the exemption request.
The NRC staff reviewed the requested exemption and determined that
it does not change the fundamental design, components, or safety
features of the storage system. The NRC staff evaluated the applicable
potential safety impacts of granting the exemption to assess the
potential for any danger to life or property or the common defense and
security. Specifically, the NRC staff reviewed the applicant's
structural integrity, thermal, confinement, shielding, and criticality
evaluations for the proposed exemption.
Structural Review for the Requested Exemption: The NRC staff
reviewed the exemption request including the documents referenced by
the applicant. Specifically, the NRC staff reviewed the design
characteristics of thoria rods and canister limits provided by the
applicant in its June 8, 2015, response to NRC's request for additional
information (RAI) dated May 8, 2015, and verified that the thoria rods
and canister limits are the same as those previously approved in
Amendment No. 1 to CoC 1014. In its review of Amendment No. 8, the NRC
staff determined that the structural analysis presented in ``HI-STORM
Topical Safety Analysis Report (TSAR),'' Holtec Report HI-951312, Rev.
11, as supplemented on July 3, 2001, August 13 and 17, and October 5,
12, and 19, 2001, demonstrated that the thoria rod canister was
structurally adequate to support the loads during normal lifting
operations, normal and off-normal conditions, as well as during
postulated-accident conditions.
Based on the NRC staff's review of the physical characteristics of
the thoria rods, thoria canister and MPC-68M canister, the NRC staff
concludes that the proposed storage of thoria rods in an MPC-68M will
be bounded by the previously approved structural analysis for MPC-68M
because the thoria rods and canister limits are the same as those
previously approved in Amendment No. 1 to CoC 1014. Therefore, the NRC
staff has reasonable assurance that the structural adequacy of the MPC-
68M for the intended purpose will be maintained, as documented in the
NRC staff's SER for Amendment No. 8 to CoC 1014.
Thermal Review for the Requested Exemption: The decay heat per DNPS
Unit 1 thoria rod canister is less than or equal to 115 watts, which is
significantly lower than the maximum allowable decay heat limit of 393
watts per fuel storage location for damaged fuel and fuel debris, as
specified in Amendment No. 8 to CoC 1014. In addition, the exemption,
does not change the cask decay heat distribution due to the lower decay
heat of the DNPS Unit 1 thoria rod canister. Accordingly, the decay
heat analyses reviewed and approved by the NRC staff in Amendment 8 are
bounding.
The applicant referenced the previous Holtec thermal evaluation of
the MPC-68M for Amendment No. 8 to CoC 1014 to show that it has lower
maximum temperatures (i.e., fuel cladding, basket, and MPC shell) than
the maximum temperatures of Holtec's thermal evaluation for the MPC-68
canister. Holtec stated that this is due to the higher thermal
conductivity of the Metamic-HT basket material, the use of full length
aluminum basket shims, and the higher emissivities of the basket and
basket shims. Based on the NRC staff's review of the exemption request
and the references cited therein, the NRC staff finds acceptable the
small decay heat contribution of the thoria rods, when compared with
the design basis-heat load for failed fuel. In addition, the NRC staff
finds that the thermal effects of an MPC-68M basket design loaded with
one DNPS Unit 1 thoria rod canister is bounded by previous thermal
analysis. Therefore, if one DNPS Unit 1 thoria rod canister is included
in an MPC-68M, the NRC staff concludes that the fuel cladding
temperature of the MPC-68M and its contents are bounded by those NRC
reviewed and approved for CoC 1014, Amendment No. 8.
The applicant stated that the cladding hoop stress for the thoria
rods, during vacuum drying, is similar to the stresses expected in
uranium dioxide (UO2) rods stored in an MPC-68M. The
applicant also stated it does not plan to load high burnup fuel, i.e.,
fuel with an average burnup exceeding 45,000 MWD/MTU, in the MPC-68M
that contains the thoria rod canister. The applicant stated that this
would result in a decay heat below the design basis decay heat and,
therefore a lower design basis fuel temperature compared to the value
reported in Table 4.III.5 of the HI-STORM 100 FSAR, Revision 11, during
vacuum drying operations. Based on the lower decay heat and similar
expected cladding hoop stress for the thoria rods during vacuum drying,
the NRC staff finds that the vacuum drying time limits in CoC 1014,
Amendment No. 8, Revision No. 1, Technical Specifications, which were
not necessary for the MPC-68M in CoC 1014, Amendment No. 8, Revision
No. 1, are also not necessary for the MPC-68M with the inclusion of the
DNPS Unit 1 thoria rod canister. Consistent with EGC's request, this
exemption does not authorize the loading and storage of
[[Page 14137]]
high burnup fuel in the MPC-68M if the DNPS Unit 1 thoria rod canister
is loaded in the MPC-68M. Accordingly, the NRC staff finds that the
cask loaded with 1 thoria rod canister will continue to meet applicable
thermal requirements.
Confinement Review for the Requested Exemption: EGC stated that the
design of the MPC-68M confinement boundary, which includes the vent and
drain ports, is unchanged by the exemption request. In addition, EGC
stated that the exemption would not change the short-term cask
operations, including draining of the MPC, welding of the lid, drying
and backfilling with inert gas, and handling of the MPC that were
approved in Amendment No. 8 to CoC No. 1014. Since this exemption would
not change the design aspects, including a leak tight confinement
boundary (leak tight is defined as <=1 x 1-\7\ ref-cc/sec,
as defined by American National Standards Institute (ANSI) N14.5,
``Radioactive Materials--Leakage Tests on Packages for Shipment''),
from those previously reviewed and approved by the NRC, the confinement
characteristics will continue to be adequately maintained.
Shielding Review for the Requested Exemption: The NRC staff
reviewed the exemption request and the applicant's RAI response. EGC is
relying on NRC's previous approval of Amendment Nos. 1 and 8 to CoC No.
1014 to conclude that offsite doses from a storage cask containing a
single thoria rod canister along with 67design basis 6x6 Dresden Unit 1
fuel assemblies are is the same as or bounded by previous analyses and
did not perform any additional analysis for this exemption. The
applicant cites the shielding analysis of the thoria rods as previously
documented in ``HI-STORM TSAR,'' HOLTEC Report HI-951312, Rev. 11, and
approved by the NRC staff in CoC 1014, Amendment No. 1 and documented
in the NRC staff's SER dated July 18, 2002. Sections 5.2.6 and 5.4.8 of
the Holtec TSAR includes Holtec's analysis of the thoria rods, and
presents a summary of the neutron and photon sources in Tables 5.2-7,
5.2-19, 5.2-37, and 5.2-38. EGC stated that the neutron source for the
thoria rods remains below that of the design basis fuel assembly. EGC
also stated that the photon source for the thoria rods is bounded by
the design basis fuel assembly except in the 2.5-3.0 MeV energy range.
To demonstrate that the gamma dose rate from the thoria rods is bounded
by the design-basis BWR fuel, EGC referred to Holtec's TSAR for
Amendment No. 1, which, according to Holtec, conservatively assumed 68
thoria rod canisters were present in the MPC, even though only one
thoria rod canister exists on the DNPS site. Holtec's dose rate
evaluation showed that the external dose rate for a HI-STORM 100 cask
loaded with 68 thoria rod canisters, each with 18 Thoria rods, was 17
percent higher than a canister filled with design-basis fuel. In its
SER for approval of Amendment No. 1, the NRC staff considered the
conservatisms built into Holtec's dose rate analysis and concluded that
a single thoria rod canister would not likely result in a dose rate
increase for a MPC-68M canister loaded with 67 BWR spent fuel
assemblies and a single thoria rod canister containing up to 18 thoria
rods.
Subsequently, in its review of Amendment 8, the NRC staff reviewed
the impact from the MPC-68M basket on external dose rates compared to
the borated baskets for the other MPC-68 canisters. Considering that
the outer loaded assemblies provide significant shielding of the
innermost assemblies, the NRC staff determined that the dose rate is
dominated by the peripherally loaded assemblies. The NRC staff, using
MicroShield[supreg], calculated dose rates with the two
different basket materials. Based on the results of this calculation,
the NRC staff found that the canister and overpack were the components
most critical to shielding. Additionally, in the SER for Amendment No.
8, NRC staff concluded that Holtec showed that the shielding provided
by the MPC-68M did not significantly change from the MPC-68 canister,
since neither the canister shell nor the overpack changed and the
Metamic-HT basket would have negligible impact on external dose rates.
In prior NRC staff reviews of Amendment Nos. 1 and 8, the NRC staff
concluded that the Metamic-HT basket in the MPC-68M has very little
effect on the external dose rate; and a single thoria rod canister,
while unbounded in the 2.5-3.0 MeV energy range, will not impact cask
external dose rates. Accordingly, NRC staff has reasonable assurance
that off-site doses from the presence of a single, thoria rod canister
in an MPC-68M loaded with design-basis fuel with the same
characteristics as those approved for the MPC-68, MPC-68F and MPC-68FF
will not increase when compared to a canister loaded with 68 design-
basis fuel assemblies. Therefore, such a canister will continue to meet
applicable offsite dose requirements.
Criticality Review for the Requested Exemption: The NRC staff
reviewed the exemption request and the applicant's RAI response. The
applicant initially only cited the criticality analysis of the thoria
rods previously documented in ``HI-STORM TSAR'', Holtec Report HI-
951312, Rev. 11, and documented in the NRC staff's SER dated July 18,
2002, which was the basis for approval of Amendment No. 1 to CoC No.
1014. In Section 6.4.6 of the TSAR, Holtec shows that the reactivity of
the thoria rods remains below that of the design-basis fuel assembly
reactivity, which is summarized in Holtec TSAR Tables 6.1.7 and 6.1.8.
The NRC staff did not analyze any impact the thoria rods might have on
criticality during its review of the Holtec TSAR as the components
important to criticality control in the MPC-68 and MPC-68FF remained
unchanged from its prior review of the HI-STAR Amendment No. 1. This is
not the case with the MPC-68M.
In its June 8, 2015 response to additional information, the
applicant cited the NRC staff's basis for approval of CoC 1014,
Amendment No. 8 in its SER dated May 10, 2012, to support this
exemption request. The applicant noted several advantages that Metamic-
HT has over older basket designs. Among them are the inability of the
neutron absorber material to detach or relocate, and the presence of
absorber material along the entire length of the basket, rather than a
fixed, discrete section. During its review of Amendment No. 8, NRC
staff noted that the applicant's analysis resulted in a large margin to
criticality and concluded that the use of the existing fuel assemblies
authorized in the CoC within the Metamic-HT basket in the MPC-68M would
remain subcritical.
Two prior NRC staff reviews of amendments (HI-STORM Amendment Nos.
1 and 8) have found the Metamic-HT basket in the MPC-68M to be at least
as effective as those in the MPC-68 and MPC-68FF. In addition, these
reviews found that a thoria rod canister is less reactive than the
spent fuel assemblies currently authorized in CoC 1014. Based on its
consideration of these previous approvals, NRC staff concludes that the
presence of a single, thoria rod canister in an MPC-68M is bounded by
prior analyses of existing, authorized contents.
Review of Common Defense and Security: The NRC staff also
considered potential impacts of granting the exemption on the common
defense and security. The requested exemption is not related to any
security or common defense aspect of the DNPS ISFSI, therefore granting
the exemption would not result in any potential impacts to common
defense and security.
Based on its review, the NRC staff has reasonable assurance that in
granting the exemption, the storage system will
[[Page 14138]]
continue to meet the requirements of 10 CFR part 72 and the offsite
dose limits of 10 CFR part 20 and, therefore, will not endanger life or
property. The NRC staff also finds that the exemption would not
endanger common defense and security.
C. Otherwise in the Public Interest
In considering whether granting the exemption is in the public
interest, the NRC staff considered the alternative of not granting the
exemption. If the exemption was not granted, in order to comply with
the CoC, the DNPS Unit 1 thoria rod canister containing the 18 thoria
rods would not be loaded during the 2016 spent fuel loading campaign
(SFLC). The applicant maintains that loading the thoria rod canister
during the 2016 DNPS SFLC is part of a program to ensure full core
discharge capability.
EGC stated that granting the exemption is in the public interest
since it will permit storage of the thoria rods in an inherently safe
and passive system. Additionally, EGC stated that granting the
exemption would permit this storage without the burden and impact of
requesting an amendment to the CoC. Not granting the exemption would
require Holtec to submit an amendment to the CoC, which would delay the
DNPS program to ensure full core discharge capability and impact future
loadings. In addition to allowing DNPS to continue with its program to
ensure full core discharge capability on schedule, based on its review
of EGC's request, the NRC staff concludes that allowing thoria rods
with the same characteristics as those approved for the MPC-68, MPC-68F
and MPC-68FF as an approved content in the MPC-68M would continue to
provide adequate protection of public health and safety. Therefore,
granting the exemption is otherwise in the public interest.
D. Environmental Considerations
The NRC staff also considered whether there would be any
significant environmental impacts associated with the exemption. For
this proposed action, the NRC staff performed an environmental
assessment pursuant to 10 CFR 51.30. The environmental assessment
concluded that the proposed action would not significantly impact the
quality of the human environment. The NRC staff concluded that the
proposed action would not result in any changes in the types or amounts
of any radiological or non-radiological effluents that may be released
offsite, and there is no significant increase in occupational or public
radiation exposure because of the proposed action. The Environmental
Assessment and the Finding of No Significant Impact was published on
March 4, 2016 (81 FR 11603).
IV. Conclusions
Accordingly, the Commission has determined that, pursuant to 10 CFR
72.7, this exemption is authorized by law, will not endanger life or
property or the common defense and security, and is otherwise in the
public interest. Therefore, the Commission hereby grants EGC an
exemption from 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR
72.212(b)(5)(i), 10 CFR 72.214, and the portion of 10 CFR 72.212(b)(11)
that requires compliance with terms, conditions, and specifications of
the CoC only with regard to storage of DNPS Unit 1 thoria rods with the
same characteristics as those specified for storage in the MPC-68, MPC-
68F and MPC-68FF in CoC No. 1014, Amendment No. 8, Revision No. 1,
Appendix B, Table 2.1-1, Section II, ``MPC MODEL: MPC-68F,'' Item A.7
and Section III, ``MPC MODEL: MPC-68 and MPC-68FF,'' Item A.3 in the
MPC-68M using the Holtec[supreg] CoC No. 1014, Amendment No.
8, Revision No. 1. This exemption does not authorize loading in a
canister with other spent fuel which has an average burnup exceeding
45,000 MWD/MTU.
V. Availability of Documents
The documents identified in the following table are available to
interested persons through one or more of the methods indicated in the
ADDRESSES section.
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Document ADAMS Accession No.
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Exelon Generation Company (EGC) ML15029A334.
application dated January 29,
2015.
EGC supplement dated June 8, 2015 ML15159A745.
CoC 1014 Amendment 8, Revision 1. ML16041A233.
Amendment No. 8 CoC and SER ML12132A028.
issued on May 10, 2012.
Amendment No 8 correction (CoC ML12213A203.
and SER) issued on November 12,
2012.
Amendment No. 8, Revision No. 1 ML16041A233.
issued on February 10, 2016.
``HI-STORM Topical Safety ML003748149, ML072420266,
Analysis Report (TSAR),'' Holtec ML003748010, ML003747975, and
Report HI-951312, Rev. 11 ML003747995.
(Holtec amendment 1 request)
dated August 31, 2000.
July 3, 2001 supplement to Holtec ML011900259.
amendment 1 request.
August 13, 2001 supplement to ML012260436.
Holtec amendment 1 request.
August 17, 2001 supplement to ML012330523.
Holtec amendment 1 request.
October 5, 2001, supplement to ML012830522.
Holtec amendment 1 request.
October 12, 2001, supplement to ML012900007.
Holtec amendment 1 request.
October 19, 2001, supplement to ML020150094.
Holtec amendment 1 request.
NRC's request for additional ML15128A088.
information dated May 8, 2015.
Amendment No. 1 to CoC 1014...... ML022000176.
HI-STORM 100 FSAR, Revision 11... ML13246A040.
ANSI N14.5, ``Radioactive Accessible from American National
Materials--Leakage Tests on Standards Institute.
Packages for Shipment''.
HI-STAR Amendment No. 1.......... ML003780760.
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[[Page 14139]]
The exemption is effective upon issuance.
Dated at Rockville, Maryland, this 8th day of March, 2016.
For the Nuclear Regulatory Commission.
Steve Ruffin,
Acting Branch Chief, Spent Fuel Licensing Branch, Division of Spent
Fuel Management, Office of Nuclear Material Safetyand Safeguards.
[FR Doc. 2016-05955 Filed 3-15-16; 8:45 am]
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