[Federal Register Volume 74, Number 196 (Tuesday, October 13, 2009)]
[Rules and Regulations]
[Pages 52387-52391]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E9-24561]
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Rules and Regulations
Federal Register
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Federal Register / Vol. 74, No. 196 / Tuesday, October 13, 2009 /
Rules and Regulations
[[Page 52387]]
NUCLEAR REGULATORY COMMISSION
10 CFR Part 72
RIN 3150-AI71
[NRC-2009-0349]
List of Approved Spent Fuel Storage Casks: HI-STORM 100 Revision
7
AGENCY: Nuclear Regulatory Commission.
ACTION: Direct final rule.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is amending its
spent fuel storage regulations by revising the Holtec International
(Holtec) HI-STORM 100 dry cask storage system listing within the ``List
of Approved Spent Fuel Storage Casks'' to include Amendment No. 7 to
Certificate of Compliance (CoC) Number 1014. Amendment No. 7 will
modify the CoC to add the HI-STORM 100U system to the HI-STORM 100 cask
systems. The HI-STORM 100U system allows for the underground storage of
dry spent nuclear fuel (SNF) by utilizing an underground vertical
ventilated module (VVM) that can accept certain Holtec multipurpose
canisters (MPCs) previously certified for storage of SNF in the
aboveground HI-STORM system. The amendment also incorporates a
mandatory radiation protection perimeter around the loaded VVMs. In
addition, the amendment will reinstate the decay heat limits for
damaged fuel and fuel debris in Appendix B, Technical Specification
(TS) 2.4, for the aboveground system that had been inadvertently
deleted from Amendment Nos. 5 and 6; incorporate separate TS Appendices
A and B for the aboveground system (Apps. A and B) and for the HI-STORM
100U system (Apps. A-100U and B-100U); revise Appendix B, TS 3.4.5, to
be consistent with the required system thermal boundary conditions, as
submitted in the applicant's safety analysis report for a fire accident
condition, and with Holtec's original (i.e., initial certificate
application or Amendment 0) submittal and the NRC's original safety
evaluation report; and revise and add certain definitions in Appendix
A, TS 1.1, to include the VVM. The amendment will also incorporate
minor editorial corrections in the TS for the aboveground system.
DATES: The final rule is effective December 28, 2009, unless
significant adverse comments are received by November 12, 2009. A
significant adverse comment is a comment where the commenter explains
why the rule would be inappropriate, including challenges to the rule's
underlying premise or approach, or would be ineffective or unacceptable
without a change. If the rule is withdrawn, timely notice will be
published in the Federal Register.
ADDRESSES: You can access publicly available documents related to this
document using the following methods:
Federal e-Rulemaking Portal: Go to http://www.regulations.gov and
search for documents filed under Docket ID [NRC-2009-0349]. Address
questions about NRC dockets to Carol Gallagher 301-492-3668; e-mail
[email protected].
NRC's Public Document Room (PDR): The public may examine and have
copied for a fee publicly available documents at the NRC's PDR, Public
File Area O-1F21, One White Flint North, 11555 Rockville Pike,
Rockville, Maryland.
NRC's Agencywide Documents Access and Management System (ADAMS):
Publicly available documents created or received at the NRC are
available electronically at the NRC's Electronic Reading Room at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain
entry into ADAMS, which provides text and image files of NRC's public
documents. If you do not have access to ADAMS or if there are problems
in accessing the documents located in ADAMS, contact the NRC's PDR
Reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
[email protected]. An electronic copy of the proposed CoC, TS, and
preliminary safety evaluation report (SER) can be found under ADAMS
Package Number ML091680333.
CoC No. 1014, the TS, the preliminary SER, and the environmental
assessment are available for inspection at the NRC PDR, Public File
Area O-1F21, One White Flint North, 11555 Rockville Pike, Rockville,
MD. Single copies of these documents may be obtained from Neelam
Bhalla, Office of Federal and State Materials and Environmental
Management Programs, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone (301) 415-6843, e-mail [email protected].
FOR FURTHER INFORMATION CONTACT: Neelam Bhalla, Office of Federal and
State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6843, e-mail [email protected].
SUPPLEMENTARY INFORMATION:
Background
Section 218(a) of the Nuclear Waste Policy Act of 1982, as amended
(NWPA), states that ``[t]he Secretary [of the Department of Energy
(DOE)] shall establish a demonstration program, in cooperation with the
private sector, for the dry storage of spent nuclear fuel at civilian
nuclear power reactor sites, with the objective of establishing one or
more technologies that the [Nuclear Regulatory] Commission may, by
rule, approve for use at the sites of civilian nuclear power reactors
without, to the maximum extent practicable, the need for additional
site-specific approvals by the Commission.'' Section 133 of the NWPA
states, in part, that ``[t]he Commission shall, by rule, establish
procedures for the licensing of any technology approved by the
Commission under Section 218(a) for use at the site of any civilian
nuclear power reactor.''
To implement this mandate, the NRC approved dry storage of SNF in
NRC-approved casks under a general license by publishing a final rule
in 10 CFR Part 72, which added a new Subpart K within 10 CFR Part 72,
entitled ``General License for Storage of Spent Fuel at Power Reactor
Sites'' (55 FR 29181; July 18, 1990). This rule also established a new
Subpart L within 10 CFR Part 72, entitled ``Approval of Spent Fuel
Storage Casks,'' which contains procedures and criteria for obtaining
NRC approval of spent fuel storage cask designs. The NRC subsequently
issued a final rule on May 1, 2000 (65 FR 25241),
[[Page 52388]]
that approved the HI-STORM 100 cask design and added it to the list of
NRC-approved cask designs in 10 CFR 72.214 as CoC No. 1014.
Discussion
By letter dated April 27, 2007, and as supplemented on June 5, June
12, July 14, December 19, 2008, January 16, January 21, February 6,
April 6, April 22, May 13, and June 23, 2009, Holtec submitted an
application to the NRC that requested an amendment to CoC No. 1014. The
amendment proposes to add the HI-STORM 100U system to the list of
approved HI-STORM 100 cask systems. The HI-STORM 100U system allows for
the underground storage of dry spent fuel by utilizing an underground
VVM that can accept certain Holtec MPCs previously certified for
storage in the Holtec aboveground overpacks. The fixed structure of the
vertical storage cavity, identified by Holtec as the ``Cavity Enclosure
Container'' (CEC), is made of a cylindrical container shell integrally
welded to both a bottom plate and an upper container flange. A
continuous weld between the container shell and the bottom plate is
done to ensure that the CEC is completely sealed at its base. The
constituent parts of the CEC are fabricated out of approximately 1-inch
thick low-carbon steel plate and are coated with epoxy paint following
fabrication. For installation in highly corrosive soils, the subsurface
outer shell of the VVM would be encased in concrete for additional
protection against corrosion.
As installed in the subsurface, an individual VVM extends
approximately 5.8 meters (19 feet) below the ground surface and rests
in a recess on a concrete support foundation of requisite thickness
(0.61-0.91 meter) (2 to 3 feet). Engineered backfill surrounds the VVM
for most of its subsurface interface. The VVM is capped by a massive
steel and concrete ventilated closure lid that sits above the ground
surface to about 0.74 meters (approximately 29 inches), and prevents
its horizontal shifting during design basis events. Internally, the CEC
is equipped with a removable insulated divider shell and MPC bearing
pads to help meet cask thermal performance requirements. Air inlets and
outlets allow air to circulate naturally through the cavity to cool the
MPC interior. All ventilation openings in the VVM are covered with
stainless steel wire mesh to preclude the entry of small birds and
mammals.
The subterranean steel structure is seal welded to prevent ingress
of any groundwater from the surrounding subgrade, and is mounted on a
stiff foundation. The surrounding subgrade and a top surface pad
provide significant radiation shielding. A loaded MPC is stored within
the HI-STORM 100U storage VVM in the vertical orientation.
For the HI-STORM 100U underground system, the amendment also
incorporates a mandatory radiation protection perimeter around the
loaded VVMs. In Appendix B-100U, TS 3.4.8 requires that prior to an
excavation activity contiguous to a Radiation Protection Space (RPS), a
seismic evaluation of the Independent Spent Fuel Storage Installation
(ISFSI) in the structurally most vulnerable configuration (i.e.,
maximum amount of earth removed) shall be performed to verify that the
stability of the support foundation, the ISFSI pad, and the shielding
material within the RPS is maintained. It requires that excavation can
only occur at a distance from the RPS greater than 10 times the depth
of the planned excavation. The RPS, as defined in TS 5.7.9 of Appendix
A-100U, is intended to ensure that the substrate material (such as
natural subgrade and engineered fill) remains intact under all service
conditions, including during an excavation activity adjacent to the
RPS.
For the HI-STORM 100U underground system, Appendix B-100U TS
3.4.5.a. requires that the support foundation rest directly on a
bedrock unless the shear wave velocity of the substrate on which the
support foundation rests is greater than or equal to 3500 feet/second.
As explained in the SER, item 3.1.7 entitled, ``Evaluation of the HI-
STORM 100U System Structural Design,'' Holtec must submit an amendment
request to CoC No.1014 if there is any deviation from the requirement
set forth in Appendix B-100U TS 3.4.5.a. This requirement will ensure
that the ISFSI can withstand the design basis seismologic events.
For the HI-STORM 100 aboveground system, the amendment will
reinstate the decay heat limits for damaged fuel and fuel debris in TS
Appendix B, Section 2.4. These requirements had been inadvertently
deleted from Amendment Nos. 5 and 6. Amendment No. 7 does not alter the
decay heat limits that were previously approved in the TS Appendix B.
For the aboveground system, the amendment will revise Appendix B,
TS 3.4.5, to be consistent with the required system thermal boundary
conditions as submitted in the applicant's safety analysis report (SAR)
for a fire accident condition. This revision to TS Appendix B does not
add any new requirements but makes it consistent with the intent of
Holtec's original (i.e., initial certificate application or Amendment
0) submittal and NRC's original SER.
For the aboveground system, the amendment will also revise and add
certain definitions in Appendix A, TS 1.1. For example, ``Vertical
Ventilated Module'' has been added and defined in the list of terms
defined in Appendix A. The revisions and additions to the definitions
in Appendix A make these terms usable in Appendices A, B, A-100U, and
B-100U. Finally, the amendment will also incorporate minor editorial
corrections in Appendices A and B for the aboveground system.
This direct final rule revises the HI-STORM 100 dry storage cask
system listing in 10 CFR 72.214 by adding Amendment No. 7 to CoC No.
1014. The amendment consists of the changes described above, as set
forth in the revised CoC and TS. The amendment provides separate TS
Appendices A and B for the aboveground system, and Appendices A-100U
and B-100U for the underground system. As documented in the SER for
Amendment No. 7, the NRC staff performed a detailed safety evaluation
of the proposed CoC amendment request and found that an acceptable
safety margin is maintained. In addition, the NRC staff has determined
that there continues to be reasonable assurance that public health and
safety and the environment will be adequately protected.
The amended HI-STORM 100 cask design, when used under the
conditions specified in the CoC, the TS, and NRC regulations, will meet
the requirements of Part 72; thus, adequate protection of public health
and safety will continue to be ensured. When this direct final rule
becomes effective, entities holding a general license under 10 CFR
72.210 may load SNF into HI-STORM 100 casks that meet the criteria of
Amendment No. 7 to CoC No. 1014 under 10 CFR 72.212.
Discussion of Amendments by Section
Section 72.214 List of Approved Spent Fuel Storage Casks
Certificate No. 1014 is revised by adding the effective date of
Amendment No. 7. This amendment also corrects the CoC expiration date
of June 1, 2020, to May 31, 2020. The CoC No. 1014, Amendment 0 (65 FR
25241; May 1, 2000), incorrectly stated an expiration date of June 1,
2020, instead of May 31, 2020.
Procedural Background
This rule is limited to the changes contained in Amendment No. 7 to
CoC No. 1014 and does not include other
[[Page 52389]]
aspects of the HI-STORM 100 dry storage cask system. The NRC is using
the ``direct final rule procedure'' to issue this amendment because it
represents a limited and routine change to an existing CoC that is
expected to be noncontroversial. Adequate protection of public health
and safety continues to be ensured. The amendment to the rule will
become effective on December 28, 2009. However, if the NRC receives any
significant adverse comments on this direct final rule by November 12,
2009, then the NRC will publish a document that withdraws this action
and will subsequently address any comment received in a final rule as a
response to the companion proposed rule published elsewhere in this
issue of the Federal Register. Absent significant modifications to the
proposed revisions requiring republication, the NRC will not initiate a
second comment period on this action.
A significant adverse comment is a comment where the commenter
explains why the rule would be inappropriate, including challenges to
the rule's underlying premise or approach, or would be ineffective or
unacceptable without a change. A comment is adverse and significant if:
1. The comment opposes the rule and provides a reason sufficient to
require a substantive response in a notice-and-comment process. For
example, a substantive response is required when:
a. The comment causes the NRC staff to reevaluate (or reconsider)
its position or conduct additional analysis;
b. The comment raises an issue serious enough to warrant a
substantive response to clarify or complete the record; or
c. The comment raises a relevant issue that was not previously
addressed or considered by the NRC staff.
2. The comment proposes a change or an addition to the rule, and it
is apparent that the rule would be ineffective or unacceptable without
incorporation of the change or addition.
3. The comment causes the NRC staff to make a change (other than
editorial) to the rule, CoC, or TS.
Voluntary Consensus Standards
The National Technology Transfer and Advancement Act of 1995 (Pub.
L. 104-113) requires that Federal agencies use technical standards that
are developed or adopted by voluntary consensus standards bodies unless
the use of such a standard is inconsistent with applicable law or
otherwise impractical. In this direct final rule, the NRC will revise
the HI-STORM 100 cask design listed in Sec. 72.214 (List of NRC-
approved spent fuel storage cask designs). This action does not
constitute the establishment of a standard that contains generally
applicable requirements.
Agreement State Compatibility
Under the ``Policy Statement on Adequacy and Compatibility of
Agreement State Programs'' approved by the Commission on June 30, 1997,
and published in the Federal Register on September 3, 1997 (62 FR
46517), this rule is classified as Compatibility Category ``NRC.''
Compatibility is not required for Category ``NRC'' regulations. The NRC
program elements in this category are those that relate directly to
areas of regulation reserved to the NRC by the Atomic Energy Act of
1954, as amended (AEA), or the provisions of Title 10 of the Code of
Federal Regulations. Although an Agreement State may not adopt program
elements reserved to NRC, it may wish to inform its licensees of
certain requirements via a mechanism that is consistent with the
particular State's administrative procedure laws but does not confer
regulatory authority on the State.
Plain Language
The Presidential Memorandum, ``Plain Language in Government
Writing,'' published June 10, 1998 (63 FR 31883), directed that the
Government's documents be in clear and accessible language. The NRC
requests comments on this direct final rule specifically with respect
to the clarity and effectiveness of the language used. Comments should
be sent to the address listed under the heading ADDRESSES, above.
Finding of No Significant Environmental Impact: Availability
Under the National Environmental Policy Act of 1969, as amended,
and the NRC regulations in Subpart A of 10 CFR Part 51, the NRC has
determined that this rule, if adopted, would not be a major Federal
action significantly affecting the quality of the human environment,
and therefore, an environmental impact statement is not required. This
rule will amend the CoC for the HI-STORM 100 cask design within the
list of approved spent fuel storage casks that power reactor licensees
can use to store spent fuel at reactor sites under a general license.
The amendment will modify the CoC 1014 to add the HI-STORM 100U
system to the HI-STORM 100 cask systems. The HI-STORM 100U system
allows for the underground storage of dry SNF. The amendment also
incorporates a mandatory radiation protection perimeter around the
loaded VVMs. The environmental impact of interim storage of SNF at an
ISFSI has been evaluated in NUREG-1092, ``Environmental Assessment for
10 CFR 72 Licensing Requirements for the Independent Storage of Spent
Fuel and High-Level Radioactive Waste.'' The environmental assessment
provided the basis for allowing deployment of ISFSIs under general
licenses at nuclear power reactor sites without the need for additional
site-specific approvals, but it did not consider subsurface designs.
Because the HI-STORM 100U is an underground storage system, Holtec,
under the requirements of 10 CFR 51.41, submitted an environmental
report to NRC on June 2, 2008, as a reference document for evaluating
the potential environmental impacts of this subsurface design. Holtec
also provided supplemental information on December 19, 2008, in
response to questions requesting additional information from the NRC
staff.
The environmental impacts of the proposed action have been reviewed
in accordance with the requirements of 10 CFR Part 51. NRC has
determined that the storage of SNF in an underground Holtec HI-STORM
100U cask system array within the controlled area of a licensed reactor
site would not significantly affect the quality of the human
environment, either incrementally or cumulatively. Therefore, an
environmental impact statement is not warranted for the proposed
action, and accordingly, a finding of no significant impact is
appropriate.
NRC has prepared an environmental assessment to evaluate the
potential impacts of construction, operation, and decommissioning of
the subsurface ISFSI arrays under a general license for the HI-STORM
100U underground system. The environmental assessment and finding of no
significant impact on which this determination is based are available
for inspection at the NRC Public Document Room, Public File Area O-
1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD.
Single copies of the environmental assessment and finding of no
significant impact are available from Neelam Bhalla, Office of Federal
and State Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, telephone (301) 415-
6843, e-mail [email protected].
The environmental assessment concludes that there would be no
significant radiological or nonradiological environmental impacts from
routine operation of the ISFSI. The
[[Page 52390]]
ISFSI is a passive facility and no liquid or gaseous effluents would be
released from the storage casks. The dose rates from the spent fuel
would be limited by the design of both the storage casks and the
subsurface VVM. The total occupational dose to workers at any given
reactor site may increase slightly due to work associated with loading,
transferring, and storing the casks, but all occupational doses must be
maintained below the limits specified in 10 CFR Part 20 and must be
kept as low as reasonably achievable in accordance with licensee's
radiation protection programs. The annual dose to the nearest residents
from general license ISFSI activities (which, to date, have utilized
aboveground cask systems) has always been significantly below the
limits specified in 10 CFR 72.104 and 10 CFR 20.1301(a). The shielding
provided by soil is expected to result in a radiation dose from the
Holtec HI-STORM 100U system to be the same or lower than the current
aboveground systems.
For the aboveground system, the amendment would reinstate the decay
heat limits for damaged fuel and fuel debris in Appendix B, TS 2.4,
that had been inadvertently deleted from Amendments 5 and 6, and revise
Appendix B, TS 3.4.5, to be consistent with the required system thermal
boundary conditions as submitted in the applicant's SAR for a fire
accident condition. This revision to TS Appendix B does not add any new
requirements but makes it consistent with the intent of Holtec's
original (i.e., initial certificate application or Amendment 0)
submittal and NRC's original SER.
The amendment will also incorporate separate TS Appendices A and B
for the aboveground system (Apps. A and B) and for the HI-STORM 100U
system (Apps. A-100U and B-100U), and revise and add certain
definitions in Appendix A, TS 1.1, to include the VVM.
As such, Amendment No. 7 does not make any changes to the
previously approved conditions of the HI-STORM 100 aboveground cask
system. The NRC staff believes that the environmental assessments and
findings of no significant impact prepared for earlier HI-STORM 100
system amendments continue to be valid and will bound the revisions to
the TS.
Paperwork Reduction Act Statement
This direct final rule does not contain a new or amended
information collection requirement subject to the Paperwork Reduction
Act of 1995 (44 U.S.C. 3501 et seq.). Existing requirements were
approved by the Office of Management and Budget (OMB), Approval Number
3150-0132.
Public Protection Notification
The NRC may not conduct or sponsor, and a person is not required to
respond to, a request for information or an information collection
requirement unless the requesting document displays a currently valid
OMB control number.
Regulatory Analysis
On July 18, 1990 (55 FR 29181), the NRC issued an amendment to 10
CFR Part 72 to provide for the storage of SNF under a general license
in cask designs approved by the NRC. Any nuclear power reactor licensee
can use NRC-approved cask designs to store SNF if it notifies the NRC
in advance, the spent fuel is stored under the conditions specified in
the cask's CoC, and the conditions of the general license (as set forth
in 10 CFR 72.212) are met. A list of NRC-approved cask designs is
contained in 10 CFR 72.214. On May 1, 2000 (65 FR 25241), the NRC
issued an amendment to Part 72 that approved the HI-STORM 100 cask
design by adding it to the list of NRC-approved cask designs in 10 CFR
72.214. On April 27, 2007, and as supplemented on June 5, June 12, July
14, December 19, 2008, January 16, January 21, February 6, April 6,
April 22, May 13, and June 23, 2009, the certificate holder, Holtec,
submitted an application to the NRC to amend CoC No. 1014 to add the
HI-STORM 100U system to the HI-STORM 100 cask systems. The HI-STORM
100U system allows for the underground storage of dry SNF by utilizing
a VVM that can accept certain MPCs previously certified for storage of
SNF in the Holtec aboveground HI-STORM 100 system. The amendment also
incorporates a mandatory radiation protection perimeter around the
loaded VVMs. In addition, the application requested amending CoC No.
1014 to reinstate the decay heat limits for damaged fuel and fuel
debris in Appendix B, TS 2.4, for the aboveground system that had been
inadvertently deleted from Amendment Nos. 5 and 6, and revise Appendix
B, TS 3.4.5, to be consistent with the required system thermal boundary
conditions as submitted in the applicant's SAR for a fire accident
condition. This revision to TS Appendix B does not add any new
requirements but makes it consistent with the intent of Holtec's
original (i.e., initial certificate application or Amendment 0)
submittal and NRC's original SER.
The amendment will also incorporate separate TS Appendices A and B
for the aboveground system (Apps A and B) and for the HI-STORM 100U
system (Apps. A-100U and B-100U), and revise and add certain
definitions in Appendix A, TS 1.1, to include the VVM. The amendment
will also incorporate minor editorial corrections in the TS for the
aboveground system.
The alternative to this action is to withhold approval of Amendment
No. 7 and to require any Part 72 general licensee, seeking to utilize
the Holtec HI-STORM 100U system, to request an exemption from the
requirements of 10 CFR 72.212 and 72.214. Under this alternative, each
interested Part 72 licensee would have to prepare, and the NRC would
have to review, a separate exemption request, thereby increasing the
administrative burden upon the NRC and the costs to each licensee.
Approval of the direct final rule is consistent with previous NRC
actions. Further, as documented in the SER and the environmental
assessment, the direct final rule will have no adverse effect on public
health and safety. This direct final rule has no significant
identifiable impact or benefit on other government agencies. Based on
this regulatory analysis, the NRC concludes that the requirements of
the direct final rule are commensurate with the NRC's responsibilities
for public health and safety and the common defense and security. No
other available alternative is believed to be as satisfactory, and
thus, this action is recommended.
Regulatory Flexibility Certification
Under the Regulatory Flexibility Act of 1980 (5 U.S.C. 605(b)), the
NRC certifies that this rule will not, if issued, have a significant
economic impact on a substantial number of small entities. This direct
final rule affects only nuclear power plant licensees and Holtec. These
entities do not fall within the scope of the definition of ``small
entities'' set forth in the Regulatory Flexibility Act or the size
standards established by the NRC (10 CFR 2.810).
Backfit Analysis
The NRC has determined that the backfit rule (10 CFR 72.62) does
not apply to this direct final rule because this amendment does not
involve any provisions that would impose backfits as defined in 10 CFR
Chapter I. Therefore, a backfit analysis is not required.
Congressional Review Act
Under the Congressional Review Act of 1996, the NRC has determined
that this action is not a major rule and has verified this
determination with the Office of Information and Regulatory
[[Page 52391]]
Affairs, Office of Management and Budget.
List of Subjects in 10 CFR Part 72
Administrative practice and procedure, Hazardous waste, Nuclear
materials, Occupational safety and health, Radiation protection,
Reporting and recordkeeping requirements, Security measures, Spent
fuel, Whistleblowing.
0
For the reasons set out in the preamble and under the authority of the
Atomic Energy Act of 1954, as amended; the Energy Reorganization Act of
1974, as amended; the Nuclear Waste Policy Act of 1982, as amended; and
5 U.S.C. 552 and 553; the NRC is adopting the following amendments to
10 CFR Part 72.
PART 72--LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF
SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-
RELATED GREATER THAN CLASS C WASTE
0
1. The authority citation for Part 72 continues to read as follows:
Authority: Secs. 51, 53, 57, 62, 63, 65, 69, 81, 161, 182, 183,
184, 186, 187, 189, 68 Stat. 929, 930, 932, 933, 934, 935, 948, 953,
954, 955, as amended, sec. 234, 83 Stat. 444, as amended (42 U.S.C.
2071, 2073, 2077, 2092, 2093, 2095, 2099, 2111, 2201, 2232, 2233,
2234, 2236, 2237, 2238, 2282); sec. 274, Pub. L. 86-373, 73 Stat.
688, as amended (42 U.S.C. 2021); sec. 201, as amended, 202, 206, 88
Stat. 1242, as amended, 1244, 1246 (42 U.S.C. 5841, 5842, 5846);
Pub. L. 95-601, sec. 10, 92 Stat. 2951 as amended by Pub. L. 102-
486, sec. 7902, 106 Stat. 3123 (42 U.S.C. 5851); sec. 102, Pub. L.
91-190, 83 Stat. 853 (42 U.S.C. 4332); secs. 131, 132, 133, 135,
137, 141, Pub. L. 97-425, 96 Stat. 2229, 2230, 2232, 2241, sec. 148,
Pub. L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10151, 10152, 10153,
10155, 10157, 10161, 10168); sec. 1704, 112 Stat. 2750 (44 U.S.C.
3504 note); sec. 651(e), Pub. L. 109-58, 119 Stat. 806-10 (42 U.S.C.
2014, 2021, 2021b, 2111).
Section 72.44(g) also issued under secs. 142(b) and 148(c), (d),
Pub. L. 100-203, 101 Stat. 1330-232, 1330-236 (42 U.S.C. 10162(b),
10168(c),(d)). Section 72.46 also issued under sec. 189, 68 Stat.
955 (42 U.S.C. 2239); sec. 134, Pub. L. 97-425, 96 Stat. 2230 (42
U.S.C. 10154). Section 72.96(d) also issued under sec. 145(g), Pub.
L. 100-203, 101 Stat. 1330-235 (42 U.S.C. 10165(g)). Subpart J also
issued under secs. 2(2), 2(15), 2(19), 117(a), 141(h), Pub. L. 97-
425, 96 Stat. 2202, 2203, 2204, 2222, 2244 (42 U.S.C. 10101,
10137(a), 10161(h)). Subparts K and L are also issued under sec.
133, 98 Stat. 2230 (42 U.S.C. 10153) and sec. 218(a), 96 Stat. 2252
(42 U.S.C. 10198).
0
2. In Sec. 72.214, Certificate of Compliance 1014 is revised to read
as follows:
Sec. 72.214 List of approved spent fuel storage casks.
* * * * *
Certificate Number: 1014.
Initial Certificate Effective Date: May 31, 2000.
Amendment Number 1 Effective Date: July 15, 2002.
Amendment Number 2 Effective Date: June 7, 2005.
Amendment Number 3 Effective Date: May 29, 2007.
Amendment Number 4 Effective Date: January 8, 2008.
Amendment Number 5 Effective Date: July 14, 2008.
Amendment Number 6 Effective Date: August 17, 2009.
Amendment Number 7 Effective Date: December 28, 2009.
SAR Submitted by: Holtec International.
SAR Title: Final Safety Analysis Report for the HI-STORM 100 Cask
System.
Docket Number: 72-1014.
Certificate Expiration Date: May 31, 2020.
Model Number: HI-STORM 100 Systems.
* * * * *
Dated at Rockville, MD, this 24th day of September 2009.
For the Nuclear Regulatory Commission.
R.W. Borchardt,
Executive Director for Operations.
[FR Doc. E9-24561 Filed 10-9-09; 8:45 am]
BILLING CODE 7590-01-P